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1

Haynes Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

2

Ship Towing Tank | Open Energy Information  

Open Energy Info (EERE)

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

3

Davidson Laboratory Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

4

Ohmsett Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

5

Ice Towing Tank | Open Energy Information  

Open Energy Info (EERE)

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

6

Maine Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

7

Lakefront Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

8

MHL Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

9

Stennis Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

10

Small Towing Tank | Open Energy Information  

Open Energy Info (EERE)

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

11

Alden Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

12

MIT Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

13

Chase Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Chase Tow Tank Chase Tow Tank Jump to: navigation, search Basic Specifications Facility Name Chase Tow Tank Overseeing Organization University of New Hampshire Hydrodynamics Hydrodynamic Testing Facility Type Tow Tank Length(m) 36.6 Beam(m) 3.7 Depth(m) 2.4 Cost(per day) Contact POC Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 2.5 Length of Effective Tow(m) 20.0 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.4 Maximum Wave Height(m) at Wave Period(s) 3.1 Wave Period Range(s) 3.1 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wave Direction Uni-Directional Simulated Beach No Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Description National Instruments LabView-based data acquistion software/components. Optical measurement system for observing kinematics of a model under test in the wave mode.

14

Carderock Tow Tank 3 | Open Energy Information  

Open Energy Info (EERE)

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

15

Carderock Tow Tank 1 | Open Energy Information  

Open Energy Info (EERE)

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

16

Richmond Field Station Tow Tank | Open Energy Information  

Open Energy Info (EERE)

Richmond Field Station Tow Tank Richmond Field Station Tow Tank Jump to: navigation, search Basic Specifications Facility Name Richmond Field Station Tow Tank Overseeing Organization University of California, Berkeley Hydrodynamic Testing Facility Type Tow Tank Length(m) 67.0 Beam(m) 2.4 Depth(m) 1.7 Water Type Freshwater Cost(per day) Contact POC Special Physical Features Glass observation station, suitable for optical access Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 5 Length of Effective Tow(m) 50.0 Wavemaking Capabilities Wavemaking Capabilities Yes Maximum Wave Height(m) 0.3 Maximum Wave Length(m) 2 Wave Period Range(s) 0.0 Current Velocity Range(m/s) 0.0 Programmable Wavemaking Yes Wavemaking Description Waveform can be programmed Wave Direction Both

17

Carderock Rotating Arm Tow Tank | Open Energy Information  

Open Energy Info (EERE)

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

18

Carderock Tow Tank 2 | Open Energy Information  

Open Energy Info (EERE)

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

19

Property:Length of Effective Tow(m) | Open Energy Information  

Open Energy Info (EERE)

of Effective Tow(m) of Effective Tow(m) Jump to: navigation, search Property Name Length of Effective Tow(m) Property Type String Pages using the property "Length of Effective Tow(m)" Showing 20 pages using this property. C Chase Tow Tank + 20.0 + D Davidson Laboratory Tow Tank + 30.5 + H Haynes Tow Tank + 24.4 + I Ice Towing Tank + 15.0 + L Lakefront Tow Tank + 25.9 + M MHL Tow Tank + 103.6 + MIT Tow Tank + 27.4 + Maine Tow Tank + 27.4 + O OTRC Wave Basin + 27.4 + Ohmsett Tow Tank + 155.0 + R Richmond Field Station Tow Tank + 50.0 + S SAFL Channel + 76.0 + Sandia Lake Facility + 45.7 + Scripps Channel 1 + 7.0 + Scripps Channel 2 + 20.0 + Sheets Wave Basin + 25.0 + Ship Towing Tank + 75.0 + Small Towing Tank + 3.0 + Stennis Tow Tank + 114.3 + U University of Iowa Wave Basin + 25.0 +

20

Type I Tanks  

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

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

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


21

Property:Towing Capabilities | Open Energy Information  

Open Energy Info (EERE)

Towing Capabilities Towing Capabilities Jump to: navigation, search Property Name Towing Capabilities Property Type String Pages using the property "Towing Capabilities" Showing 25 pages using this property. (previous 25) (next 25) 1 1.5-ft Wave Flume Facility + None + 10-ft Wave Flume Facility + None + 11-ft Wave Flume Facility + None + 2 2-ft Flume Facility + None + 3 3-ft Wave Flume Facility + None + 5 5-ft Wave Flume Facility + None + 6 6-ft Wave Flume Facility + None + A Alden Large Flume + Yes + Alden Small Flume + None + Alden Tow Tank + Yes + Alden Wave Basin + None + B Breakwater Research Facility + None + Bucknell Hydraulic Flume + Yes + C Carderock 2-ft Variable Pressure Cavitation Water Tunnel + None + Carderock 3-ft Variable Pressure Cavitation Water Tunnel + None +

22

Penn Reverberant Tank | Open Energy Information  

Open Energy Info (EERE)

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

23

Overall plant concept for a tank-type fast reactor  

SciTech Connect

Japanese nuclear industries are expressing interest in the merits of the tank-type FBR as a large plant (demonstration) after JOYO (experimental, in operation) and MONJU (prototype, under construction). In response to this growing interest in a tank-type FBR demonstration plant, Hitachi has initiated a conceptual study of a 1000 MWe tank plant concept in collaboration with GE and Bechtel. Key objectives of this study have been: to select reliable and competitive tank plant concepts, with emphases on a seismic-resistant and compact tank reactor system;to select reliable shutdown heat removal system;and to identify R and D items needed for early 1990s construction. Design goals were defined as follows: capital costs must be less than twice, and as close as practical to 1.5 those of equivalent LWR plants;earthquake resistant structures to meet stringent Japanese seismic conditions must be as simple and reliable as practical;safety must be maintained at LWR-equivalent risks;and R and D needs must be limited to minimum cost for the limited time allowed. This paper summarizes the overall plant concepts with some selected topics, whereas detailed descriptions of the reactor assembly and the layout design are found in separate papers.

Yamaki, Hideo; Davies, S.M.; Goodman, L.

1984-01-01T23:59:59.000Z

24

Applicability of the sludge processing technical standard to type IV waste tanks with high fluoride concentration  

SciTech Connect

Type IV waste tanks at the Savannah River Plant which contain ballast water (tanks 17, 18, 19, 20, and 24) have solution compositions that are generally within the database developed for corrosion protection of the sludge processing tanks. Therefore the technical standard covering tank chemistry limits during sludge processing is applicable to the Type TV tanks. However, Tank 20 contains levels of fluoride higher than those treated in the sludge processing database. To confirm the applicability of the sludge processing technical standard, cyclic potentiodynamic polarization scans for pitting susceptibility were run in a simulant of the Tank 20 contents. The nitrite inhibitor level specified by the standards did inhibit pitting corrosion in the simulant. Pitting was inhibited also at the same nitrite level but with 30 percent higher concentrations of chloride, fluoride, and sulfate. Thus the sludge processing technical standard has been shown to provide corrosion protection to type IV tanks containing ballast water.

Zapp, P.E.

1992-03-31T23:59:59.000Z

25

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

SciTech Connect

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

Wiersma, B

2008-09-18T23:59:59.000Z

26

Prince William Sound disabled tanker towing study. Part 1. Evaluation of existing equipment, personnel and procedures  

Science Conference Proceedings (OSTI)

The study has been undertaken by the Glosten Associates, Inc., to evaluate the existing capability for emergency towing at Prince William Sound and to examine alternatives that could enhance the escort and assist capabilities for disabled tankers within the waterway from the Alyeska Oil Terminal at the Port of Valdez to the Gulf of Alaska outside Hinchinbrook Entrance. Part 1, reported herein, is an objective evaluation by an experienced salvage towing master of the existing tugs, emergency towing equipment, towing practices, and discussion of alternative tug types.

Not Available

1993-08-01T23:59:59.000Z

27

Safety evaluation for packaging 222-S laboratory cargo tank for onetime type B material shipment  

Science Conference Proceedings (OSTI)

The purpose of this Safety Evaluation for Packaging (SEP) is to evaluate and document the safety of the onetime shipment of bulk radioactive liquids in the 222-S Laboratory cargo tank (222-S cargo tank). The 222-S cargo tank is a US Department of Transportation (DOT) MC-312 specification (DOT 1989) cargo tank, vehicle registration number HO-64-04275, approved for low specific activity (LSA) shipments in accordance with the DOT Title 49, Code of Federal Regulations (CFR). In accordance with the US Department of Energy, Richland Operations Office (RL) Order 5480.1A, Chapter III (RL 1988), an equivalent degree of safety shall be provided for onsite shipments as would be afforded by the DOT shipping regulations for a radioactive material package. This document demonstrates that this packaging system meets the onsite transportation safety criteria for a onetime shipment of Type B contents.

Nguyen, P.M.

1994-08-19T23:59:59.000Z

28

An Experimental Study of Turbulence Behind Towed Biplanar Grids in a Salt-Stratified Fluid  

Science Conference Proceedings (OSTI)

Biplanar gods were towed down a 30 m long tank of stratified water at 1060 cm s?1. Stratifications from N=0.2 to 0.5 rad s?1 were used. Single electrode conductivity probes repeatedly profiled the decaying turbulence at selected distance behind ...

R. E. Lange

1982-12-01T23:59:59.000Z

29

Turbulence Measurements from a Towed Body  

Science Conference Proceedings (OSTI)

A towed body suitable for measuring oceanic velocity and temperature microstructure is described. The development was motivated by i) a requirement for long times series to produce statistically reliable estimates of dissipation rates, ii) the ...

Thomas R. Osborn; Rolf G. Lueck

1985-12-01T23:59:59.000Z

30

Comparison of Towed Conductivity Sensor Performance  

Science Conference Proceedings (OSTI)

Electrical conductivity sensors are often used to obtain measurements of small-scale fluctuations, or microstructure, in the ocean. In applications on towed instrument packages, they provide the only way to estimate temperature fluctuations on ...

J. P. Dugan; B. W. Stalcup

1988-02-01T23:59:59.000Z

31

Property:Hydrodynamic Testing Facility Type | Open Energy Information  

Open Energy Info (EERE)

Hydrodynamic Testing Facility Type Hydrodynamic Testing Facility Type Jump to: navigation, search Property Name Hydrodynamic Testing Facility Type Property Type Page Pages using the property "Hydrodynamic Testing Facility Type" Showing 25 pages using this property. (previous 25) (next 25) 1 1.5-ft Wave Flume Facility + Flume + 10-ft Wave Flume Facility + Flume + 11-ft Wave Flume Facility + Flume + 2 2-ft Flume Facility + Flume + 3 3-ft Wave Flume Facility + Flume + 5 5-ft Wave Flume Facility + Flume + 6 6-ft Wave Flume Facility + Flume + A Alden Large Flume + Flume + Alden Small Flume + Flume + Alden Tow Tank + Tow Tank + Alden Wave Basin + Wave Basin + B Breakwater Research Facility + Wave Basin + Bucknell Hydraulic Flume + Flume + C Carderock 2-ft Variable Pressure Cavitation Water Tunnel + Tunnel +

32

Tank Closure  

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

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

33

Microstructure Measurements from a Towed Undulating Platform  

Science Conference Proceedings (OSTI)

MicroSoar, an undulating profiler capable of measuring turbulence parameters such as Thorpe scales and thermal dissipation rate while being towed at speeds of up to 4 m s?1, offers the possibility of obtaining a close-to-synoptic image of mixing ...

Michael W. Ott; John A. Barth; Anatoli Y. Erofeev

2004-10-01T23:59:59.000Z

34

Integrated Short Term Navigation of a Towed Underwater Body*  

E-Print Network (OSTI)

Integrated Short Term Navigation of a Towed Underwater Body* G. Damy' M. Joannides2 F. LeGland3 M. An underwater body, to be called here- after the fish, is towed by a surface ship at the end of a few hundred cannot provide any position estimates of an underwater body such as a towed fish, but only position

LeGland, François

35

Property:Water Type | Open Energy Information  

Open Energy Info (EERE)

Type Type Jump to: navigation, search Property Name Water Type Property Type String Pages using the property "Water Type" Showing 25 pages using this property. (previous 25) (next 25) 1 1.5-ft Wave Flume Facility + Freshwater + 10-ft Wave Flume Facility + Freshwater + 11-ft Wave Flume Facility + Freshwater + 2 2-ft Flume Facility + Freshwater + 3 3-ft Wave Flume Facility + Freshwater + 5 5-ft Wave Flume Facility + Freshwater + 6 6-ft Wave Flume Facility + Freshwater + A Alden Large Flume + Freshwater + Alden Small Flume + Freshwater + Alden Tow Tank + Freshwater + Alden Wave Basin + Freshwater + B Breakwater Research Facility + Freshwater + Bucknell Hydraulic Flume + Freshwater + C Carderock 2-ft Variable Pressure Cavitation Water Tunnel + Freshwater +

36

DETERMINATION OF CORROSION INHIBITOR CRITERIA FOR TYPE III/IIIA TANKS DURING SALT DISSOLUTION OPERATIONS SUMMARY DOCUMENT  

SciTech Connect

Dissolution of salt from Type III/IIIA waste tanks at the Savannah River Site may create solutions with inhibitor concentrations below those currently required (0.6M OH{sup -} and 1.1M OH{sup -} + NO{sub 2}{sup -}) per the Corrosion Control Program for high nitrate salt solutions (5.5 to 8.5M NO{sub 3}{sup -}). An experimental program was conducted to evaluate the corrosion susceptibility of grade A537 carbon steel for waste simulants containing 4.5-8.5M NaNO{sub 3} with maximum inhibitor concentrations of 0.6M NaOH and 0.2M NaNO{sub 2}. These maximum inhibitor concentrations used in this program are at a reduced level from those currently required. Current requirements were initially established for the Types I, II and IV tanks made of A285 carbon steel. The experimental program involved corrosion testing to evaluate the pitting and stress corrosion stress corrosion cracking (SCC) susceptibility of the Type III/IIIA waste tank materials. The program was conducted in two phases; the results of the first phase were reported previously (WSRC-STI-2006-00029). In this second phase, the corrosion specimens were modified to represent the 'as-fabricated' condition of the tank wall, and included specimens with mill scale, ground welds and stress-relief heat treatments. The complete description of the corrosion testing and the results are reported herein. The collective corrosion test results for A537 carbon steel in high nitrate waste simulants (4.5 - 8.5M) with the maximum inhibitor concentrations of 0.6M NaOH and 0.2M NaNO{sub 2} were as follows: (1) In long-term non-polarized U-bend testing, heat treatment, similar to the waste tank stress relief regime, reduced the incidence of cracking over the 18-month test period. Vapor space SCC was found to initiate on non-heat treated U-bend coupons. (2) In polarized U-bend testing, cracking occurred on U-bend coupons that had welds prepared similar to those in the waste tanks, i.e. ground and heat treated. (3) In electrochemical testing, pitting occurred on all coupons independent of heat treatment, inhibitor concentration, temperature, surface preparation, or welding. (4) In slow strain rate testing, cracking occurred on samples tested in solutions containing up to the maximum inhibitor concentration. The primary conclusion derived from this experimental program is that A537 carbon steel exposed to high nitrate (> 5.5M) solutions at inhibitor levels below the current specifications (0.6M OH{sup -} and 1.1M OH{sup -} + NO{sub 2}{sup -}) are susceptible to localized corrosion in the form of pitting and stress corrosion cracking. Long-term storage (e.g., greater than 100 days) of dissolved salt solutions not meeting the current inhibitor specifications for high nitrate salt chemistries in Type III waste tanks shall be avoided. Short term storage (e.g., less than 100 days) at low temperatures (e.g., less than 50 C) in these tanks is permissible for waste removal purposes. The stress relief process reduces the risk of SCC in the Type III waste tanks. On the other hand, the current inhibitor specifications should be strictly followed for the Type I, II and IV waste chemistry to prevent initiation of localized corrosion mechanisms. These tanks were not stress relieved and are more susceptible to SCC.

Mickalonis, J.; Wiersma, B.; Garcia-Diaz, B.

2009-10-01T23:59:59.000Z

37

Performance and Calibration of an Acoustic Doppler Current Profiler Towed below the Surface  

Science Conference Proceedings (OSTI)

A towed acoustic Doppler current profiler (ADCP) system was tested. The instrument was deployed from ships of opportunity and towed at depths between 5 and 25 m. The towed system carries upward- and downward-looking ADCPs. The instrument platform ...

Andreas Mnchow; Charles S. Coughran; Myrl C. Hendershott; Clinton D. Winant

1995-04-01T23:59:59.000Z

38

Property:Maximum Velocity(m/s) | Open Energy Information  

Open Energy Info (EERE)

Velocity(m/s) Velocity(m/s) Jump to: navigation, search Property Name Maximum Velocity(m/s) Property Type String Pages using the property "Maximum Velocity(m/s)" Showing 25 pages using this property. (previous 25) (next 25) A Alden Large Flume + 0.9 + B Bucknell Hydraulic Flume + 2.7 + C Carderock Maneuvering & Seakeeping Basin + 7.2 + Carderock Rotating Arm Tow Tank + 25.8 + Carderock Tow Tank 1 + 9.3 + Carderock Tow Tank 2 + 10.3 + Carderock Tow Tank 3 + 25.8 + Chase Tow Tank + 2.5 + D Davidson Laboratory Tow Tank + 18.3 + H Haynes Tow Tank + 1.8 + I Ice Towing Tank + 0.5 + L Lakefront Tow Tank + 2.7 + M MHL Free Surface Channel + 2 + MHL High Speed Cavitation + 25.9 + MHL Tow Tank + 6.7 + MIT Tow Tank + 1.5 + MMA Tugboat/ Barge/ Vessel + 5.1 + Maine Tow Tank + 3 +

39

TASITATowed AirSea interface Temperature Analyzer  

Science Conference Proceedings (OSTI)

An accurate platinum RTD-based (resistive temperature device) system has been developed to measure the vertical temperature profile in the region of the atmosphere-ocean interface. TASITA, the towed airsea interaction temperature analyzer, ...

R. P. Cechet; J. Bennett; I. Helmond; P. A. Coppin; E. F. Bradley; I. J. Bapton; J. S. Godfrey

1994-06-01T23:59:59.000Z

40

Direct Heat Flux Estimates Using a Towed Vehicle  

Science Conference Proceedings (OSTI)

Direct estimates of vertical heat flux were computed using data collected with a towed vehicle that carried collocated velocity and temperature sensors. Horizontal wavenumbers from about 1 to 40 cpm were resolved, which excludes some potentially ...

M. Fleury; R. G. Lueck

1994-04-01T23:59:59.000Z

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


41

Tank Closure  

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

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

42

Tank 241-S-107 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Jo, J.

1995-04-06T23:59:59.000Z

43

Thermal Testing of Tow-Placed Variable Stiffness Panels  

E-Print Network (OSTI)

Commercial systems for precise placement of pre-preg composite tows are enabling technology that allows fabrication of advanced composite structures in which the tows may be precisely laid down along curvilinear paths within a given ply. For laminates with curvilinear tow paths, the fiber orientation angle varies continuously throughout the laminate, and is not required to be straight and parallel in each ply as in conventional composite laminates. Hence, the stiffness properties vary as a function of location in the laminate, and the associated composite structure is called a variable stiffness composite structure. Previous analytical studies indicate that variable stiffness structures have great potential for improving the structural performance of composite structures. In the present research, an experimental program has been conducted to evaluate the thermal performance of two variable stiffness panels fabricated using the Viper Fiber Placement System developed by Cincinnati Machine. These variable stiffness panels have the same layup, but one panel has overlapping tows and the other panel does not. Results of thermal tests of the variable stiffness panels are presented and com-

K. Chauncey Wu; Zafer Grdal

2001-01-01T23:59:59.000Z

44

Richardson Number and Ocean Mixing: Towed Chain Observations  

Science Conference Proceedings (OSTI)

A 7.2-km tow in the upper seasonal thermocline of the Sargasso Sea with an 80-m aperture thermistor conductivity chain and shipborne 150-kHz ADCP is examined to determine the relationship between patches of scalar activity and buoyancy frequency,...

S. A. Mack; H. C. Schoeberlein

2004-04-01T23:59:59.000Z

45

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

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

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

46

Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for  

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

0: August 4, 0: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks to someone by E-mail Share Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks on Facebook Tweet about Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks on Twitter Bookmark Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks on Google Bookmark Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks on Delicious Rank Vehicle Technologies Office: Fact #530: August 4, 2008 Towing Capacity for Selected 2008 Model Cars and Trucks on Digg Find More places to share Vehicle Technologies Office: Fact #530:

47

Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for  

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

0: May 12, 1997 0: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks to someone by E-mail Share Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks on Facebook Tweet about Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks on Twitter Bookmark Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks on Google Bookmark Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks on Delicious Rank Vehicle Technologies Office: Fact #30: May 12, 1997 Towing Capacity for Selected 1996 Model Cars and Trucks on Digg Find More places to share Vehicle Technologies Office: Fact #30: May

48

Method and apparatus for deregistering multi-filament tow and product thereof  

DOE Patents (OSTI)

A method and apparatus for deregistering drawn crimped nylon multifilament tow includes the steps of stretching the tow under constant controlled tension at a temperature below the glass transition temperature of the nylon. The apparatus includes means for sensing the tension of the tow between the feed and draw sections of a stretching device and producing a signal representative of the tension sensed and a controller for changing the speed of the draw section actuated by said signal.

Lukhard, Craig R. (Newark, DE); Potter, Jerry F. (Seaford, DE); Todd, Maurice C. (Chadds Ford, PA)

1995-01-01T23:59:59.000Z

49

Property:Description of Camera Types | Open Energy Information  

Open Energy Info (EERE)

Camera Types Camera Types Jump to: navigation, search Property Name Description of Camera Types Property Type Text Pages using the property "Description of Camera Types" Showing 25 pages using this property. (previous 25) (next 25) A Alden Large Flume + fully-submersible; multiplexor for four cameras; digital recording from all cameras; digital handheld Alden Small Flume + fully-submersible; multiplexor for four cameras; digital recording from all cameras; digital handheld Alden Tow Tank + Fully-submersible; multiplexor for four cameras; digital recording from all cameras; digital handheld Alden Wave Basin + Fully-submersible; multiplexor for four cameras; digital recording from all cameras; digital handheld C Conte Large Flume + Conventional underwater video, 4; high speed (1000 fps), 1

50

Safety evaluation for packaging (onsite) nitrogen trailers propane tanks  

SciTech Connect

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

Ferrell, P.C.

1998-01-28T23:59:59.000Z

51

Dual Tank Fuel System  

DOE Patents (OSTI)

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

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

1999-11-16T23:59:59.000Z

52

Comparative safety analysis of LNG storage tanks  

Science Conference Proceedings (OSTI)

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

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

1982-07-01T23:59:59.000Z

53

Design, Construction, and Test Results for Three Different Fiber Optic Tow Cables  

Science Conference Proceedings (OSTI)

The design, manufacture, and testing of three armored fiber optic tow cables is discussed. The motivation for these developments was the technical need to have low-loss high-bandwidth transmission lines, that function with negligible crosstalk and absence ...

E. Althouse

2006-09-01T23:59:59.000Z

54

An In Situ Technique for Intercalibrating Temperature or Conductivity Sensors on Towed Arrays  

Science Conference Proceedings (OSTI)

Vertical arrays of temperature and conductivity sensors are towed from research vessels to obtain cross sections of the ocean's internal structure that result from the dynamic finescale and microscale processes. To estimate local water ...

B. W. Stalcup; J. P. Dugan

1990-10-01T23:59:59.000Z

55

eGSE America Electric Baggage Tow Tractor (EBTT) Technical Specificati...  

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

9204 1.0 SCOPE: This document outlines the design and performance requirements for a battery- powered electric tow tractor for the handling of baggage or cargo trailers in...

56

The Impact of Nonsynoptic Sampling on Mesoscale Oceanographic Surveys with Towed Instruments  

Science Conference Proceedings (OSTI)

Mesoscale ocean features, such as eddies and frontal meanders, have temporal and spatial scales that are poorly resolved by conventional surveying methods such as moorings and CTD casts. Towed instruments provide a method of measuring ...

P. A. Matthews

1997-02-01T23:59:59.000Z

57

Hydrogen Tank Testing R&D  

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

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

58

Historical Tank Content Estimate for the Northwest Quandrant of the Hanford 200 East Area  

Science Conference Proceedings (OSTI)

Historical Tank Content Estimate of the Northeast Quadrant provides historical evaluations on a tank by tank basis of the radioactive mixed wastes stored in the underground single-shell tanks of the Hanford 200 East area. This report summaries historical information such at waste history, temperature, tank integrity, inventory estimates and tank level history on a tank by tank basis. Tank Farm aerial photos and in-tank photos of each tank are provided. A brief description of instrumentation methods used for waste tank surveillance, along with the components of the data management effort, such as waste status and Transaction Record Summary, Tank Layering Model, Defined Waste Types, and Inventory Estimates to generate these tank content estimates are also given in this report.

Brevick, C.H.; Gaddis, L.A.; Pickett, W.W.

1994-06-01T23:59:59.000Z

59

A Model for Tow Impregnation and Consolidation for Partially Impregnated Thermoset Prepregs  

Science Conference Proceedings (OSTI)

The formation and transport of voids in composite materials remains a key research area in composite manufacturing science. Knowledge of how voids, resin, and fiber reinforcement propagate throughout a composite material continuum from green state to cured state during an automated tape layup process is key to minimizing defects induced by void-initiated stress concentrations under applied loads for a wide variety of composite applications. This paper focuses on modeling resin flow in a deforming fiber tow during an automated process of partially impregnated thermoset prepreg composite material tapes. In this work, a tow unit cell based model has been presented that determines the consolidation and impregnation of a thermoset prepreg tape under an input pressure profile. A parametric study has been performed to characterize the behavior of varying tow speed and compaction forces on the degree of consolidation. Results indicate that increased tow consolidation is achieved with slower tow speeds and higher compaction forces although the relationship is not linear. The overall modeling of this project is motivated to address optimization of the 'green state' composite properties and processing parameters to reduce or eliminate 'cured state' defects, such as porosity and de-lamination. This work is partially funded by the Department of Energy under Award number DE-EE0001367.

John J. Gangloff Jr; Shatil Sinha; Suresh G. Advani

2011-05-23T23:59:59.000Z

60

AX Tank Farm tank removal study  

Science Conference Proceedings (OSTI)

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

SKELLY, W.A.

1999-02-24T23:59:59.000Z

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


61

First Draft Performance Assessment for the H-Area Tank Farm at...  

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

in a Type III Tank ... 146 Figure 3.2-42: Typical Conical (Umbrella) Type of Deployable Cooling Coil ... 146...

62

Underground Storage Tank Regulations | Department of Energy  

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

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

63

AX Tank Farm tank removal study  

SciTech Connect

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

SKELLY, W.A.

1998-10-14T23:59:59.000Z

64

Storage Tanks (Arkansas) | Department of Energy  

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

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

65

RETRIEVAL & TREATMENT OF HANFORD TANK WASTE  

SciTech Connect

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

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

2006-01-20T23:59:59.000Z

66

HANFORD TANK CLEANUP UPDATE  

SciTech Connect

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

BERRIOCHOA MV

2011-04-07T23:59:59.000Z

67

Tank 241-AW-101 tank characterization plan  

DOE Green Energy (OSTI)

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

Sathyanarayana, P.

1994-11-22T23:59:59.000Z

68

Septic Tanks (Oklahoma)  

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

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

69

Tank 241-U-111 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Carpenter, B.C.

1995-01-24T23:59:59.000Z

70

Tank 241-B-112 tank characterization plan  

Science Conference Proceedings (OSTI)

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

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

1995-02-06T23:59:59.000Z

71

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

SciTech Connect

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

Benar, C.J.

1996-09-26T23:59:59.000Z

72

DIESEL FUEL TANK FOUNDATIONS  

DOE Green Energy (OSTI)

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

M. Gomez

1995-01-18T23:59:59.000Z

73

Tank 241-AZ-102 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Schreiber, R.D.

1995-02-06T23:59:59.000Z

74

Tank 241-AZ-101 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Schreiber, R.D.

1995-02-06T23:59:59.000Z

75

A Deep-Towed ADCP-CTD Instrument Package Developed for Abyssal Overflow Measurements in the Northeastern Caribbean Sea  

Science Conference Proceedings (OSTI)

A deep-towed instrument package has been developed to study the velocity and tracer signature of abyssal overflows in the northeastern Caribbean. Primary package components include a conductivity-temperature-depth (CTD) instrument and an acoustic ...

David M. Fratantoni; William E. Johns

1996-06-01T23:59:59.000Z

76

Tanks Focus Area annual report FY2000  

SciTech Connect

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

None

2000-12-01T23:59:59.000Z

77

Adaption of the Magnetometer Towed Array geophysical system to meet Department of Energy needs for hazardous waste site characterization  

SciTech Connect

This report documents US Department of Energy (DOE)-funded activities that have adapted the US Navy`s Surface Towed Ordnance Locator System (STOLS) to meet DOE needs for a ``... better, faster, safer and cheaper ...`` system for characterizing inactive hazardous waste sites. These activities were undertaken by Sandia National Laboratories (Sandia), the Naval Research Laboratory, Geo-Centers Inc., New Mexico State University and others under the title of the Magnetometer Towed Array (MTA).

Cochran, J.R. [Sandia National Labs., Albuquerque, NM (United States); McDonald, J.R. [Naval Research Lab., Washington, DC (United States); Russell, R.J. [Geo-Centers, Inc., Newton, MA (United States); Robertson, R. [Hughes Associates, Inc., Washington, DC (United States); Hensel, E. [New Mexico State Univ., Las Cruces, NM (United States). Dept. of Mechanical Engineering

1995-10-01T23:59:59.000Z

78

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

SciTech Connect

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

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

1995-02-01T23:59:59.000Z

79

Tank 48 Treatment Process  

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

80

RECOMMENDATIONS FOR SAMPLING OF TANK 19 IN F TANK FARM  

SciTech Connect

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

Harris, S.; Shine, G.

2009-12-14T23:59:59.000Z

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


81

Analyses and characterization of double shell tank  

Science Conference Proceedings (OSTI)

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

Not Available

1994-10-04T23:59:59.000Z

82

Hanford Tank Waste Residuals  

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

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

83

Near Tank Treatment System  

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

84

SRS Tank Closure Regulatory Developments  

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

85

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

SciTech Connect

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

VENETZ TJ; WASHENFELDER D; JOHNSON J; GIRARDOT C

2012-01-25T23:59:59.000Z

86

Tank characterization reference guide  

Science Conference Proceedings (OSTI)

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

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

1994-09-01T23:59:59.000Z

87

Standard Test Methods for Properties of Continuous Filament Carbon and Graphite Fiber Tows  

E-Print Network (OSTI)

1.1 These test methods cover the preparation and tensile testing of resin-impregnated and consolidated test specimens made from continuous filament carbon and graphite yarns, rovings, and tows to determine their tensile properties. 1.2 These test methods also cover the determination of the density and mass per unit length of the yarn, roving, or tow to provide supplementary data for tensile property calculation. 1.3 These test methods include a procedure for sizing removal to provide the preferred desized fiber samples for density measurement. This procedure may also be used to determine the weight percent sizing. 1.4 These test methods include a procedure for determining the weight percent moisture adsorption of carbon or graphite fiber. 1.5 The values stated in SI units are to be regarded as the standard. The values in parentheses are for information only. 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of t...

American Society for Testing and Materials. Philadelphia

1999-01-01T23:59:59.000Z

88

Tank 241-U-202 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Schreiber, R.D.

1995-02-21T23:59:59.000Z

89

Tank 241-BY-106 tank characterization plan  

Science Conference Proceedings (OSTI)

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

Schreiber, R.D.

1995-01-24T23:59:59.000Z

90

Tank 241-C-102 tank characterization plan  

SciTech Connect

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

Schreiber, R.D.

1995-01-01T23:59:59.000Z

91

Pressurizer tank upper support  

DOE Patents (OSTI)

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

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

1994-01-11T23:59:59.000Z

92

Pressurizer tank upper support  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

93

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

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

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

94

Hanford ETR Tank Waste Treatment and Immobilization Plant - Hanford Tank  

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

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

95

Georgia Underground Storage Tank Act (Georgia) | Department of Energy  

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

Underground Storage Tank Act (Georgia) Underground Storage Tank Act (Georgia) Georgia Underground Storage Tank Act (Georgia) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Georgia Program Type Environmental Regulations Siting and Permitting Provider Georgia Department of Natural Resources The Georgia Underground Storage Act (GUST) provides a comprehensive program to prevent, detect, and correct releases from underground storage tanks

96

Underground Storage Tanks (West Virginia) | Department of Energy  

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

Tanks (West Virginia) Tanks (West Virginia) Underground Storage Tanks (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting Provider Department of Environmental Protection This rule governs the construction, installation, upgrading, use, maintenance, testing, and closure of underground storage tanks, including certification requirements for individuals who install, repair, retrofit,

97

Underground Storage Tanks (New Jersey) | Department of Energy  

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

Underground Storage Tanks (New Jersey) Underground Storage Tanks (New Jersey) Underground Storage Tanks (New Jersey) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State New Jersey Program Type Safety and Operational Guidelines This chapter constitutes rules for all underground storage tank facilities- including registration, reporting, permitting, certification, financial responsibility and to protect human health and the environment

98

Onsite Wastewater Treatment Systems: Septic Tank/Soil Absorption Field  

E-Print Network (OSTI)

For septic tank and soil absorption systems to work properly, homeowners must choose the right kind of system for their household size and soil type, and they must maintain them regularly. This publication explains the treatment, design, operation, and maintenance of septic tank and soil absorption systems.

Lesikar, Bruce J.

2008-10-23T23:59:59.000Z

99

Tank 48 - Chemical Destruction  

SciTech Connect

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

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

2013-01-09T23:59:59.000Z

100

Cryogenic Fuel Tank Draining  

E-Print Network (OSTI)

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

Analysis Model Donald; Donald Greer

1999-01-01T23:59:59.000Z

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


101

RECOMMENDATIONS FOR SAMPLING OF TANK 18 IN F TANK FARM  

SciTech Connect

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

Shine, G.

2009-12-14T23:59:59.000Z

102

Tank Stabilization September 30, 1999 Summary  

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

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

103

TRANSIENT HEAT TRANSFER ANALYSIS FOR SRS RADIOACTIVE TANK OPERATION  

SciTech Connect

The primary objective of the present work is to perform a heat balance study for type-I waste tank to assess the impact of using submersible mixer pumps during waste removal. The temperature results calculated by the model will be used to evaluate the temperatures of the slurry waste under various tank operating conditions. A parametric approach was taken to develop a transient model for the heat balance study for type-I waste tanks such as Tank 11, during waste removal by SMP. The tank domain used in the present model consists of two SMP?s for sludge mixing, one STP for the waste removal, cooling coil system with 36 coils, and purge gas system. The sludge waste contained in Tank 11 also has a decay heat load of about 43 W/m{sup 3} mainly due to the emission of radioactive gamma rays. All governing equations were established by an overall energy balance for the tank domain, and they were numerically solved. A transient heat balance model used single waste temperature model, which represents one temperature for the entire waste liquid domain contained in the tank at each transient time.

Lee, S.

2013-06-27T23:59:59.000Z

104

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

SciTech Connect

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

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

1994-08-01T23:59:59.000Z

105

Structural Analysis on Hanford Single Shell Waste Tanks  

Thermal Profile for Type II Tanks 10. Thermal and Operating Loads Analysis ... Ultimate Load Evaluation at 2010 in-situ Conditions Year 64 @ 155 oF (1947 2010)

106

Tank Waste Strategy Update  

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

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

107

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

SciTech Connect

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

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

2012-01-10T23:59:59.000Z

108

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

DOE Green Energy (OSTI)

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

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

2008-10-01T23:59:59.000Z

109

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

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

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

110

A Novel Integration of an Ultraviolet Nitrate Sensor On Board a Towed Vehicle for Mapping Open-Ocean Submesoscale Nitrate Variability  

Science Conference Proceedings (OSTI)

Initial results from a deployment of the SUV-6 ultraviolet spectrophotometer, integrated with the SeaSoar towed vehicle, are presented. The innovative, combined system measures nitrate concentration at high spatial resolution (4 m vertically, 5 ...

Rosalind Pidcock; Meric Srokosz; John Allen; Mark Hartman; Stuart Painter; Matt Mowlem; David Hydes; Adrian Martin

2010-08-01T23:59:59.000Z

111

Tanks focus area. Annual report  

SciTech Connect

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

Frey, J.

1997-12-31T23:59:59.000Z

112

Numerical Analysis of Water Temperature Distribution in the Tank of ASHPWH it ha Cylindrical Condenser  

E-Print Network (OSTI)

Air source heat pump water heaters (ASHPWH) are becoming increasingly popular for saving energy, protecting the environment and security purposes. The water temperature distribution in the tank is an important parameter for an ASHPWH. This paper presented a mathematic model for a cylindrical water tank with a cylindrical condenser as its heat source. The computational fluid dynamics (CFD) software package, FLUENT, was used to study hot water temperature distribution in the tank of the ASHPWH. In addition, the effects of tank dimension and the type of condenser coil on water temperature distribution were discussed. The work of this paper could be used for the optimization of tank and condenser coil designs.

Wang, D.; Shan, S.; Wang, R.

2006-01-01T23:59:59.000Z

113

Tank characterization data report: Tank 241-C-112  

Science Conference Proceedings (OSTI)

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

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

1993-04-01T23:59:59.000Z

114

DEGRADATION EVALUATION OF HEAVY WATER DRUMS AND TANKS  

SciTech Connect

Heavy water with varying chemistries is currently being stored in over 6700 drums in L- and K-areas and in seven tanks in L-, K-, and C-areas. A detailed evaluation of the potential degradation of the drums and tanks, specific to their design and service conditions, has been performed to support the demonstration of their integrity throughout the desired storage period. The 55-gallon drums are of several designs with Type 304 stainless steel as the material of construction. The tanks have capacities ranging from 8000 to 45600 gallons and are made of Type 304 stainless steel. The drums and tanks were designed and fabricated to national regulations, codes and standards per procurement specifications for the Savannah River Site. The drums have had approximately 25 leakage failures over their 50+ years of use with the last drum failure occurring in 2003. The tanks have experienced no leaks to date. The failures in the drums have occurred principally near the bottom weld, which attaches the bottom to the drum sidewall. Failures have occurred by pitting, crevice and stress corrosion cracking and are attributable, in part, to the presence of chloride ions in the heavy water. Probable degradation mechanisms for the continued storage of heavy water were evaluated that could lead to future failures in the drum or tanks. This evaluation will be used to support establishment of an inspection plan which will include susceptible locations, methods, and frequencies for the drums and tanks to avoid future leakage failures.

Mickalonis, J.; Vormelker, P.

2009-07-31T23:59:59.000Z

115

Underground Storage Tank Act (West Virginia) | Department of Energy  

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

Act (West Virginia) Act (West Virginia) Underground Storage Tank Act (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting Provider Department of Environmental Protection New underground storage tank construction standards must include at least the following requirements: (1) That an underground storage tank will prevent releases of regulated substances stored therein, which may occur as

116

Tank safety screening data quality objective. Revision 1  

DOE Green Energy (OSTI)

The Tank Safety Screening Data Quality Objective (DQO) will be used to classify 149 single shell tanks and 28 double shell tanks containing high-level radioactive waste into safety categories for safety issues dealing with the presence of ferrocyanide, organics, flammable gases, and criticality. Decision rules used to classify a tank as ``safe`` or ``not safe`` are presented. Primary and secondary decision variables used for safety status classification are discussed. The number and type of samples required are presented. A tabular identification of each analyte to be measured to support the safety classification, the analytical method to be used, the type of sample, the decision threshold for each analyte that would, if violated, place the tank on the safety issue watch list, and the assumed (desired) analytical uncertainty are provided. This is a living document that should be evaluated for updates on a semiannual basis. Evaluation areas consist of: identification of tanks that have been added or deleted from the specific safety issue watch lists, changes in primary and secondary decision variables, changes in decision rules used for the safety status classification, and changes in analytical requirements. This document directly supports all safety issue specific DQOs and additional characterization DQO efforts associated with pretreatment and retrieval. Additionally, information obtained during implementation can assist in resolving assumptions for revised safety strategies, and in addition, obtaining information which will support the determination of error tolerances, confidence levels, and optimization schemes for later revised safety strategy documentation.

Hunt, J.W.

1995-04-27T23:59:59.000Z

117

Property:Maximum Wave Length(m) | Open Energy Information  

Open Energy Info (EERE)

Wave Length(m) Wave Length(m) Jump to: navigation, search Property Name Maximum Wave Length(m) Property Type String Pages using the property "Maximum Wave Length(m)" Showing 18 pages using this property. A Alden Small Flume + Variable + Alden Wave Basin + 1.8 + C Carderock Maneuvering & Seakeeping Basin + 12.2 + Carderock Tow Tank 2 + 12.2 + Carderock Tow Tank 3 + 12.2 + D Davidson Laboratory Tow Tank + 15.2 + DeFrees Large Wave Basin + 64 + DeFrees Small Wave Basin + 30 + H Haynes Wave Basin + 10.7 + L Lakefront Tow Tank + 22 + M MIT Tow Tank + 4.6 + O OTRC Wave Basin + 25 + Ohmsett Tow Tank + 18 + R Richmond Field Station Tow Tank + 2 + S SAFL Channel + 6.6 + Sandia Lake Facility + 4.57 + Sheets Wave Basin + 10 + Ship Towing Tank + 6 + Retrieved from "http://en.openei.org/w/index.php?title=Property:Maximum_Wave_Length(m)&oldid=597351

118

Property:Number of Color Cameras | Open Energy Information  

Open Energy Info (EERE)

Color Cameras Color Cameras Jump to: navigation, search Property Name Number of Color Cameras Property Type Number Pages using the property "Number of Color Cameras" Showing 25 pages using this property. (previous 25) (next 25) A Alden Large Flume + 2 + Alden Small Flume + 2 + Alden Tow Tank + 2 + Alden Wave Basin + 2 + C Chase Tow Tank + 1 + Conte Large Flume + 5 + Conte Small Flume + 5 + D Davidson Laboratory Tow Tank + 2 + DeFrees Flume 1 + 5 + DeFrees Flume 2 + 5 + DeFrees Flume 3 + 5 + DeFrees Flume 4 + 5 + DeFrees Large Wave Basin + 5 + DeFrees Small Wave Basin + 5 + F Flood Fighting Research Facility + 1 + H Haynes Tow Tank + 6 + Haynes Wave Basin + 6 + Hinsdale Wave Basin 1 + 20 + Hinsdale Wave Basin 2 + 20 + M MIT Tow Tank + 1 + MMA Tugboat/ Barge/ Vessel + 1 +

119

STATUS OF MECHANICAL SLUDGE REMOVAL AND COOLING COILS CLOSURE AT THE SAVANNAH RIVER SITE - F TANK FARM CLOSURE PROJECT - 9225  

SciTech Connect

The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal using the Waste on Wheels (WOW) system within two of its storage tanks. The Waste on Wheels (WOW) system is designed to be relatively mobile with the ability for many components to be redeployed to multiple tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2839 cubic meters (750,000 gallons) each. In addition, Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. DOE intends to remove from service and operationally close Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. After obtaining regulatory approval, the tanks and cooling coils will be isolated and filled with grout for long term stabilization. Mechanical Sludge Removal of the remaining sludge waste within Tank 6 removed {approx} 75% of the original 25,000 gallons in August 2007. Utilizing lessons learned from Tank 6, Tank 5 Mechanical Sludge Removal completed removal of {approx} 90% of the original 125 cubic meters (33,000 gallons) of sludge material in May 2008. The successful removal of sludge material meets the requirement of approximately 19 to 28 cubic meters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. The Chemical Cleaning Process will utilize 8 wt% oxalic acid to dissolve the remaining sludge heel. The flow sheet for Chemical Cleaning planned a 20:1 volume ratio of acid to sludge for the first strike with mixing provided by the submersible mixer pumps. The subsequent strikes will utilize a 13:1 volume ratio of acid to sludge with no mixing. The results of the Chemical Cleaning Process are detailed in the 'Status of Chemical Cleaning of Waste Tanks at the Savannah River Site--F Tank Farm Closure Project--Abstract 9114'. To support Tank 5 and Tank 6 cooling coil closure, cooling coil isolation and full scale cooling coil grout testing was completed to develop a strategy for grouting the horizontal and vertical cooling coils. This paper describes in detail the performance of the Mechanical Sludge Removal activities and SMP operational strategies within Tank 5. In addition, it will discuss the current status of Tank 5 & 6 cooling coil isolation activities and the results from the cooling coil grout fill tests.

Jolly, R

2009-01-06T23:59:59.000Z

120

Estimating Waste Inventory and Waste Tank Characterization |...  

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

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

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


121

ANALYSIS OF THE TANK 5F FINAL CHARATERIZATION SAMPLES-2011  

SciTech Connect

The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the following: Al-26, Sn-126, Sb-126, Sb-126m, Eu-152 and Cf-249. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

2012-01-20T23:59:59.000Z

122

Analysis Of The Tank 5F Final Characterization Samples-2011  

SciTech Connect

The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the following: Al-26, Sn-126, Sb-126, Sb-126m, Eu-152 and Cf-249. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

Oji, L. N.; Diprete, D.; Coleman, C. J.; Hay, M. S.

2012-09-27T23:59:59.000Z

123

ANALYSIS OF THE TANK 5F FINAL CHARACTERIZATION SAMPLES-2011  

SciTech Connect

The Savannah River National Laboratory (SRNL) was requested by SRR to provide sample preparation and analysis of the Tank 5F final characterization samples to determine the residual tank inventory prior to grouting. Two types of samples were collected and delivered to SRNL: floor samples across the tank and subsurface samples from mounds near risers 1 and 5 of Tank 5F. These samples were taken from Tank 5F between January and March 2011. These samples from individual locations in the tank (nine floor samples and six mound Tank 5F samples) were each homogenized and combined in a given proportion into 3 distinct composite samples to mimic the average composition in the entire tank. These Tank 5F composite samples were analyzed for radiological, chemical and elemental components. Additional measurements performed on the Tank 5F composite samples include bulk density and water leaching of the solids to account for water soluble species. With analyses for certain challenging radionuclides as the exception, all composite Tank 5F samples were analyzed and reported in triplicate. The target detection limits for isotopes analyzed were based on customer desired detection limits as specified in the technical task request documents. SRNL developed new methodologies to meet these target detection limits and provide data for the extensive suite of components. While many of the target detection limits were met for the species characterized for Tank 5F, as specified in the technical task request, some were not met. In a few cases, the relatively high levels of radioactive species of the same element or a chemically similar element precluded the ability to measure some isotopes to low levels. The Technical Task Request allows that while the analyses of these isotopes is needed, meeting the detection limits for these isotopes is a lower priority than meeting detection limits for the other specified isotopes. The isotopes whose detection limits were not met in all cases included the following: Al-26, Sn-126, Sb-126, Sb-126m, Eu-152 and Cf-249. SRNL, in conjunction with the plant customer, reviewed all these cases and determined that the impacts were negligible.

Oji, L.; Diprete, D.; Coleman, C.; Hay, M.

2012-08-03T23:59:59.000Z

124

HIGH LEVEL WASTE MECHANCIAL SLUDGE REMOVAL AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT  

SciTech Connect

The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal (MSR) using the Waste on Wheels (WOW) system for the first time within one of its storage tanks. The WOW system is designed to be relatively mobile with the ability for many components to be redeployed to multiple waste tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. In addition, the project is currently preparing another waste tank for MSR utilizing lessons learned from this previous operational activity. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2,840 cubic meters (750,000 gallons) each. The construction of these tanks was completed in 1953, and they were placed into waste storage service in 1959. The tank's primary shell is 23 meters (75 feet) in diameter, and 7.5 meters (24.5 feet) in height. Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. Both Tank 5 and Tank 6 received and stored F-PUREX waste during their operating service time before sludge removal was performed. DOE intends to remove from service and operationally close (fill with grout) Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. Mechanical Sludge Removal, the first step in the tank closure process, will be followed by chemical cleaning. After obtaining regulatory approval, the tanks will be isolated and filled with grout for long-term stabilization. Mechanical Sludge Removal operations within Tank 6 removed approximately 75% of the original 95,000 liters (25,000 gallons). This sludge material was transferred in batches to an interim storage tank to prepare for vitrification. This operation consisted of eleven (11) Submersible Mixer Pump(s) mixing campaigns and multiple intraarea transfers utilizing STPs from July 2006 to August 2007. This operation and successful removal of sludge material meets requirement of approximately 19,000 to 28,000 liters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. Removal of the last 35% of sludge was exponentially more difficult, as less and less sludge was available to mobilize and the lighter sludge particles were likely removed during the early mixing campaigns. The removal of the 72,000 liters (19,000 gallons) of sludge was challenging due to a number factors. One primary factor was the complex internal cooling coil array within Tank 6 that obstructed mixer discharge jets and impacted the Effective Cleaning Radius (ECR) of the Submersible Mixer Pumps. Minimal access locations into the tank through tank openings (risers) presented a challenge because the available options for equipment locations were very limited. Mechanical Sludge Removal activities using SMPs caused the sludge to migrate to areas of the tank that were outside of the SMP ECR. Various SMP operational strategies were used to address the challenge of moving sludge from remote areas of the tank to the transfer pump. This paper describes in detail the Mechanical Sludge Removal activities and mitigative solutions to cooling coil obstructions and other challenges. The performance of the WOW system and SMP operational strategies were evaluated and the resulting lessons learned are described for application to future Mechanical Sludge Removal operations.

Jolly, R; Bruce Martin, B

2008-01-15T23:59:59.000Z

125

Tank Waste Corporate Board | Department of Energy  

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

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

126

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

SciTech Connect

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

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

1993-06-01T23:59:59.000Z

127

FEMA Think Tank Call Meeting  

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

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

128

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

Science Conference Proceedings (OSTI)

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

Homi, C.S.

1995-10-04T23:59:59.000Z

129

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

Science Conference Proceedings (OSTI)

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

Homi, C.S.

1995-10-04T23:59:59.000Z

130

Tank characterization report for single-shell Tank B-201  

Science Conference Proceedings (OSTI)

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

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

1994-09-01T23:59:59.000Z

131

Forms of Al in Hanford Tank Waste  

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

Actual Waste Testing Actual Waste Testing Lanée Snow Sandra Fiskum Rick Shimskey Reid Peterson 4/9/09 2 Tested > 75% of sludge waste types Sludge Sources Bi-Phosphate waste Redox Purex Cladding TBP FeCN sludge Redox Cladding Zirc Cladding Purex waste Misc NA 4/9/09 3 Tested > 75% of saltcake waste types Saltcake fractions Bi-phosphate saltcake S A B R NA Tested 8 groups of tank waste types Group ID Type Al Cr PO 4 3- Oxalate Sulfate Fluoride 1 Bi Phosphate sludge 3% 3% 21% 2% 6% 12% 2 Bi Phosphate saltcake (BY, T) 18% 25% 36% 36% 43% 36% 3 PUREX Cladding Waste sludge 12% 1% 3% 1% 1% 3% 4 REDOX Cladding Waste sludge 8% 1% 0% 0% 0% 2% 5 REDOX sludge 26% 8% 1% 3% 1% 2% 6 S - Saltcake (S) 11% 38% 12% 24% 14% 3% 7 TBP Waste sludge 1% 1% 8% 0% 2% 1% 8 FeCN sludge 2% 1% 4% 1% 1% 1% *Percentages reflect % of total inventory of species in the tank farm. *Discussion will focus on those that make up the largest fraction of the Al

132

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

DOE Green Energy (OSTI)

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

BARKER, S.A.

2006-07-27T23:59:59.000Z

133

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

DOE Green Energy (OSTI)

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

TU, T.A.

2007-01-04T23:59:59.000Z

134

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

DOE Green Energy (OSTI)

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

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

2003-08-28T23:59:59.000Z

135

High-Pressure Hydrogen Tanks  

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

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

136

Hydrogen Storage "Think Tank" Report  

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

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

137

Improvement in LNG storage tanks  

SciTech Connect

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

NONE

1999-11-20T23:59:59.000Z

138

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

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

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

139

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

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

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

140

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

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

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

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


141

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

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

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

142

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

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

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

143

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

Science Conference Proceedings (OSTI)

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

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

2013-11-19T23:59:59.000Z

144

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

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

145

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

Science Conference Proceedings (OSTI)

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

Barnes, Travis J.; Gunter, Jason R.

2013-08-26T23:59:59.000Z

146

Auxiliary resonant DC tank converter  

SciTech Connect

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

Peng, Fang Z. (Knoxville, TN)

2000-01-01T23:59:59.000Z

147

Corrosion and failure processes in high-level waste tanks  

Science Conference Proceedings (OSTI)

A large amount of radioactive waste has been stored safely at the Savannah River and Hanford sites over the past 46 years. The aim of this report is to review the experimental corrosion studies at Savannah River and Hanford with the intention of identifying the types and rates of corrosion encountered and indicate how these data contribute to tank failure predictions. The compositions of the High-Level Wastes, mild steels used in the construction of the waste tanks and degradation-modes particularly stress corrosion cracking and pitting are discussed. Current concerns at the Hanford Site are highlighted.

Mahidhara, R.K.; Elleman, T.S.; Murty, K.L. [North Carolina State Univ., Raleigh, NC (United States)

1992-11-01T23:59:59.000Z

148

TANK48 CFD MODELING ANALYSIS  

SciTech Connect

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

Lee, S.

2011-05-17T23:59:59.000Z

149

Tank Waste Disposal Program redefinition  

SciTech Connect

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

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

1991-10-01T23:59:59.000Z

150

Hanford Tank Farms Waste Certification Flow Loop Test Plan  

Science Conference Proceedings (OSTI)

A future requirement of Hanford Tank Farm operations will involve transfer of wastes from double shell tanks to the Waste Treatment Plant. As the U.S. Department of Energy contractor for Tank Farm Operations, Washington River Protection Solutions anticipates the need to certify that waste transfers comply with contractual requirements. This test plan describes the approach for evaluating several instruments that have potential to detect the onset of flow stratification and critical suspension velocity. The testing will be conducted in an existing pipe loop in Pacific Northwest National Laboratorys facility that is being modified to accommodate the testing of instruments over a range of simulated waste properties and flow conditions. The testing phases, test matrix and types of simulants needed and the range of testing conditions required to evaluate the instruments are described

Bamberger, Judith A.; Meyer, Perry A.; Scott, Paul A.; Adkins, Harold E.; Wells, Beric E.; Blanchard, Jeremy; Denslow, Kayte M.; Greenwood, Margaret S.; Morgen, Gerald P.; Burns, Carolyn A.; Bontha, Jagannadha R.

2010-01-01T23:59:59.000Z

151

Military - Tougher tanks | ornl.gov  

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

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

152

Technical requirements specification for tank waste retrieval  

Science Conference Proceedings (OSTI)

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

Lamberd, D.L.

1996-09-26T23:59:59.000Z

153

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

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

154

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

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

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

155

Tank 241-Z-361 vapor sampling and analysis plan  

Science Conference Proceedings (OSTI)

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

BANNING, D.L.

1999-02-23T23:59:59.000Z

156

Browse wiki | Open Energy Information  

Open Energy Info (EERE)

components. Optical measurement system for observing kinematics of a model under test in the wave mode. Hydrodynamic Testing Facility Type Tow Tank + Length(m) 36.6 + Length...

157

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-05T23:59:59.000Z

158

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-31T23:59:59.000Z

159

Tank 41H bounding uranium enrichment  

Science Conference Proceedings (OSTI)

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

Cavin, W.S.

1994-07-12T23:59:59.000Z

160

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

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

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

Note: This page contains sample records for the topic "type tow tank" from the National Library of EnergyBeta (NLEBeta).
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161

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

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

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

162

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

SciTech Connect

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

Stock, Leon M.; Huckaby, James L.

2000-10-31T23:59:59.000Z

163

Flammable gas tank safety program: Technical basis for gas analysis and monitoring  

DOE Green Energy (OSTI)

Several Hanford waste tanks have been observed to exhibit periodic releases of significant quantities of flammable gases. Because potential safety issues have been identified with this type of waste behavior, applicable tanks were equipped with instrumentation offering the capability to continuously monitor gases released from them. This document was written to cover three primary areas: (1) describe the current technical basis for requiring flammable gas monitoring, (2) update the technical basis to include knowledge gained from monitoring the tanks over the last three years, (3) provide the criteria for removal of Standard Hydrogen Monitoring System(s) (SHMS) from a waste tank or termination of other flammable gas monitoring activities in the Hanford Tank farms.

Estey, S.D.

1998-04-22T23:59:59.000Z

164

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

SciTech Connect

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

Lewis, BE

2003-10-07T23:59:59.000Z

165

Chemical Characterization of an Envelope A Sample from Hanford Tank 241-AN-103  

Science Conference Proceedings (OSTI)

A whole tank composite sample from Hanford waste tank 241-AN-103 was received at the Savannah River Technology Center (SRTC) and chemically characterized. Prior to characterization the sample was diluted to {approximately}5 M sodium concentration. The filtered supernatant liquid, the total dried solids of the diluted sample, and the washed insoluble solids obtained from filtration of the diluted sample were analyzed. A mass balance calculation of the three fractions of the sample analyzed indicate the analytical results appear relatively self-consistent for major components of the sample. However, some inconsistency was observed between results where more than one method of determination was employed and for species present in low concentrations. A direct comparison to previous analyses of material from tank 241-AN-103 was not possible due to unavailability of data for diluted samples of tank 241-AN-103 whole tank composites. However, the analytical data for other types of samples from 241-AN-103 we re mathematically diluted and compare reasonably with the current results. Although the segments of the core samples used to prepare the sample received at SRTC were combined in an attempt to produce a whole tank composite, determination of how well the results of the current analysis represent the actual composition of the Hanford waste tank 241-AN-103 remains problematic due to the small sample size and the large size of the non-homogenized waste tank.

Hay, M.S.

2000-08-23T23:59:59.000Z

166

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

SciTech Connect

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

Wiersma, B; James Elder, J

2008-08-21T23:59:59.000Z

167

ICPP Tank Farm planning through 2012  

SciTech Connect

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

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

1998-04-01T23:59:59.000Z

168

COMPARISON OF EXPERIMENTAL RESULTS TO CFD MODELS FOR BLENDING IN A TANK USING DUAL OPPOSING JETS  

Science Conference Proceedings (OSTI)

Research has been completed in a pilot scale, eight foot diameter tank to investigate blending, using a pump with dual opposing jets. The jets re-circulate fluids in the tank to promote blending when fluids are added to the tank. Different jet diameters and different horizontal and vertical orientations of the jets were investigated. In all, eighty five tests were performed both in a tank without internal obstructions and a tank with vertical obstructions similar to a tube bank in a heat exchanger. These obstructions provided scale models of several miles of two inch diameter, serpentine, vertical cooling coils below the liquid surface for a full scale, 1.3 million gallon, liquid radioactive waste storage tank. Two types of tests were performed. One type of test used a tracer fluid, which was homogeneously blended into solution. Data were statistically evaluated to determine blending times for solutions of different density and viscosity, and the blending times were successfully compared to computational fluid dynamics (CFD) models. The other type of test blended solutions of different viscosity. For example, in one test a half tank of water was added to a half tank of a more viscous, concentrated salt solution. In this case, the fluid mechanics of the blending process was noted to significantly change due to stratification of fluids. CFD models for stratification were not investigated. This paper is the fourth in a series of papers resulting from this research (Leishear, et.al. [1- 4]), and this paper documents final test results, statistical analysis of the data, a comparison of experimental results to CFD models, and scale-up of the results to a full scale tank.

Leishear, R.

2011-08-07T23:59:59.000Z

169

Life Extension of Aging High-Level Waste Tanks  

Science Conference Proceedings (OSTI)

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

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

2002-02-26T23:59:59.000Z

170

Evaluation of 241 AN tank farm flammable gas behavior  

DOE Green Energy (OSTI)

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

Reynolds, D.A.

1994-01-01T23:59:59.000Z

171

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

SciTech Connect

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

Hommel, S.; Fountain, D.

2012-03-28T23:59:59.000Z

172

Enhanced Tank Waste Strategy Update  

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

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

173

High Pressure Hydrogen Tank Manufacturing  

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

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

174

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

SciTech Connect

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

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

2013-07-25T23:59:59.000Z

175

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

SciTech Connect

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

MACKEY, T.C.

2006-03-17T23:59:59.000Z

176

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

SciTech Connect

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

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

2013-07-30T23:59:59.000Z

177

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011  

SciTech Connect

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

West, B.; Waltz, R.

2012-06-21T23:59:59.000Z

178

Review of High Level Waste Tanks Ultrasonic Inspection Data  

SciTech Connect

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

Wiersma, B

2006-03-09T23:59:59.000Z

179

Hydrogen Tank Project Q2 Report - FY 11  

DOE Green Energy (OSTI)

Quarterly report that represents PNNL's results of HDPE, LDPE, and industrial polymer materials testing. ASTM D638 type 3 samples were subjected to a high pressure hydrogen environment between 3000 and 4000 PSI. These samples were tested using an instron load frame and were analyzed using a proprietary set of excel macros to determine trends in data. The development of an in-situ high pressure hydrogen tensile testing apparatus is discussed as is the stress modeling of the carbon fiber tank exterior.

Johnson, Kenneth I.; Alvine, Kyle J.; Skorski, Daniel C.; Nguyen, Ba Nghiep; Kafentzis, Tyler A.; Dahl, Michael E.; Pitman, Stan G.

2011-05-15T23:59:59.000Z

180

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

SciTech Connect

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

Conner, J.M.

1996-06-06T23:59:59.000Z

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


181

ICPP tank farm closure study. Volume 1  

SciTech Connect

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

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

1998-02-01T23:59:59.000Z

182

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect

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

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

183

Deflagration studies on waste Tank 101-SY: Test plan  

DOE Green Energy (OSTI)

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

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

1991-07-01T23:59:59.000Z

184

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

Science Conference Proceedings (OSTI)

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

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

1997-03-06T23:59:59.000Z

185

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

Science Conference Proceedings (OSTI)

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

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

1994-06-01T23:59:59.000Z

186

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

Science Conference Proceedings (OSTI)

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

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

1994-06-01T23:59:59.000Z

187

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

Science Conference Proceedings (OSTI)

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

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

1994-06-01T23:59:59.000Z

188

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

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

189

Property:Bandwidth(kHz) | Open Energy Information  

Open Energy Info (EERE)

Bandwidth(kHz) Bandwidth(kHz) Jump to: navigation, search Property Name Bandwidth(KHz) Property Type String Pages using the property "Bandwidth(kHz)" Showing 25 pages using this property. (previous 25) (next 25) C Conte Large Flume + 44 + Conte Small Flume + 44 + D Davidson Laboratory Tow Tank + .025 typical; can measure at higher frequencies if needed + DeFrees Flume 1 + 1000 + DeFrees Flume 2 + 1000 + DeFrees Flume 4 + 1000 + DeFrees Large Wave Basin + 1000 + DeFrees Small Wave Basin + 1000 + H Hinsdale Wave Basin 1 + Up to 1 MS/s + Hinsdale Wave Basin 2 + Up to 1 MS/s + M MHL 2D Wind/Wave + 20 + MHL Free Surface Channel + 20 + MHL High Speed Cavitation + 20 + MHL Student Tunnel + 20 + MHL Tow Tank + 20 + MIT Tow Tank + +/- 10V + Maine Tow Tank + 10 +

190

Property:Wave Direction | Open Energy Information  

Open Energy Info (EERE)

Direction Direction Jump to: navigation, search Property Name Wave Direction Property Type String Pages using the property "Wave Direction" Showing 25 pages using this property. (previous 25) (next 25) A Alden Small Flume + Uni-Directional + Alden Wave Basin + Both + C Carderock Maneuvering & Seakeeping Basin + Both + Carderock Tow Tank 2 + Uni-Directional + Carderock Tow Tank 3 + Uni-Directional + Chase Tow Tank + Uni-Directional + Coastal Harbors Modeling Facility + Uni-Directional + Coastal Inlet Model Facility + Uni-Directional + Coastal Structures Modeling Complex + Both + D Davidson Laboratory Tow Tank + Uni-Directional + DeFrees Large Wave Basin + Uni-Directional + DeFrees Small Wave Basin + Uni-Directional + H Haynes Wave Basin + Both +

191

Property:Number of channels | Open Energy Information  

Open Energy Info (EERE)

channels channels Jump to: navigation, search Property Name Number of channels Property Type String Pages using the property "Number of channels" Showing 25 pages using this property. (previous 25) (next 25) A Alden Large Flume + Designed as needed + Alden Small Flume + Designed as needed + Alden Tow Tank + Designed as needed + Alden Wave Basin + Designed as needed + C Chase Tow Tank + 8 + Conte Large Flume + 12 + Conte Small Flume + 12 + D Davidson Laboratory Tow Tank + 16 + DeFrees Flume 1 + 64+ + DeFrees Flume 2 + 64+ + DeFrees Flume 3 + 64+ + DeFrees Flume 4 + 64+ + DeFrees Large Wave Basin + 64+ + DeFrees Small Wave Basin + 64+ + H Haynes Tow Tank + 40 + Haynes Wave Basin + 40 + Hinsdale Wave Basin 1 + Up to 192 + Hinsdale Wave Basin 2 + Up to 192 +

192

SINGLE-SHELL TANK INTEGRITY PROJECT ANALYSIS OF RECORD-PRELIMINARY MODELING PLAN FOR THERMAL AND OPERATING LOADS  

SciTech Connect

This document is a Phase I deliverable for the Single-Shell Tank Analysis of Record effort. This document is not the Analysis of Record. The intent of this document is to guide the Phase II detailed modeling effort. Preliminary finite element models for each of the tank types were developed and different case studies were performed on one or more of these tank types. Case studies evaluated include thermal loading, waste level variation, the sensitivity of boundary effects (soil radial extent), excavation slope or run to rise ratio, soil stratigraphic (property and layer thickness) variation at different farm locations, and concrete material property variation and their degradation under thermal loads. The preliminary analysis document reviews and preliminary modeling analysis results are reported herein. In addition, this report provides recommendations for the next phase of the SST AOR project, SST detailed modeling. Efforts and results discussed in this report do not include seismic modeling as seismic modeling is covered by a separate report. The combined results of both static and seismic models are required to complete this effort. The SST AOR project supports the US Department of Energy's (DOE) Office of River Protection (ORP) mission for obtaining a better understanding of the structural integrity of Hanford's SSTs. The 149 SSTs, with six different geometries, have experienced a range of operating histories which would require a large number of unique analyses to fully characterize their individual structural integrity. Preliminary modeling evaluations were conducted to determine the number of analyses required for adequate bounding of each of the SST tank types in the Detailed Modeling Phase of the SST AOR Project. The preliminary modeling was conducted in conjunction with the Evaluation Criteria report, Johnson et al. (2010). Reviews of existing documents were conducted at the initial stage of preliminary modeling. These reviews guided the topics that were explored in the SST preliminary modeling. The reviews determined the level of detail necessary to perform the analyses of the SSTs. To guide the Phase II detailed modeling effort, preliminary finite element models for each of the tank types were developed and different case studies were performed on one or more of these tank types. Case studies evaluated include thermal loading, waste level variation, the sensitivity of boundary effects (soil radial extent), excavation slope or run to rise ratio, soil stratigraphic (property and layer thickness) variation at different farm locations, and concrete material property variation and their degradation under thermal loads. Conclusions were derived from case studies on one of the tank types when no additional runs of similar cases on other types of tanks were found necessary to derive those conclusions. The document reviews provided relatively complete temperature histories for Type IV tanks. The temperature history data for Type I, II, and III tanks was almost nonexistent for years prior to 1975. Document reviews indicate that there might be additional useful data in the US Department of Energy, Richland Operations Office (DOE-RL) records in Seattle, WA, and these records need to be reviewed to extract data that might have been disregarded during previous reviews. Thermal stress analyses were conducted using different temperature distribution scenarios on Type IV tanks. Such studies could not be carried out for other tank types due to lack of temperature history data. The results from Type IV tank analyses indicate that factors such as temperature distribution in the tank waste and rate of rise in waste temperature have a significant impact on the thermal stresses in the tank structures. Overall, the conclusion that can drawn from the thermal stress analyses is that these studies should be carried out for all tank types during the detailed analysis phase with temperature values that are reasonably close to the typical temperature histories of the respective tank types. If and/or when additional waste temperature data

RAST RS; RINKER MW; BAPANAALLI SK; DEIBLER JE; GUZMAN-LEONG CE; JOHNSON KI; KARRI NK; PILLI SP; SANBORN SE

2010-10-22T23:59:59.000Z

193

Tank farms essential drawing plan  

SciTech Connect

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

Domnoske-Rauch, L.A.

1998-08-04T23:59:59.000Z

194

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

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

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

195

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

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

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

196

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

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

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

197

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

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

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

198

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

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

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

199

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

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

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

200

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

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

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

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


201

ANALYSIS OF THE LEACHING EFFICIENCY OF INHIBITED WATER AND TANK SIMULANT IN REMOVING RESIDUES ON THERMOWELL PIPES  

SciTech Connect

A key component for the accelerated implementation and operation of the Salt Waste Processing Facility (SWPF) is the recovery of Tank 48H. Tank 48H is a type IIIA tank with a maximum capacity of 1.3 million gallons. Video inspection of the tank showed that a film of solid material adhered to the tank internal walls and structures between 69 inch and 150 inch levels. From the video inspection, the solid film thickness was estimated to be 1mm, which corresponds to {approx}33 kg of TPB salts (as 20 wt% insoluble solids) (1). This film material is expected to be easily removed by single-rinse, slurry pump operation during Tank 48H TPB disposition via aggregation processing. A similar success was achieved for Tank 49H TPB dispositioning, with slurry pumps operating almost continuously for approximately 6 months, after which time the tank was inspected and the film was found to be removed. The major components of the Tank 49H film were soluble solids - Na{sub 3}H(CO{sub 3}){sub 2} (Hydrated Sodium Carbonate, aka: Trona), Al(OH){sub 3} (Aluminum Hydroxide, aka: Gibbsite), NaTPB (Sodium Tetraphenylborate), NaNO{sub 3} (Sodium Nitrate) and NaNO{sub 2} (Sodium Nitrite) (2). Although the Tank 48H film is expected to be primarily soluble solids, it may not behave the same as the Tank 49H film. There is a risk that material on the internal surfaces of Tank 48H could not be easily removed. As a risk mitigation activity, the chemical composition and leachability of the Tank 48H film are being evaluated prior to initiating tank aggregation. This task investigated the dissolution characteristics of Tank 48H solid film deposits in inhibited water and DWPF recycle. To this end, SRNL received four separate 23-inch long thermowell-conductivity pipe samples which were removed from the tank 48H D2 risers in order to determine: (1) the thickness of the solid film deposit, (2) the chemical composition of the film deposits, and (3) the leaching behavior of the solid film deposit in inhibited water (IW) and in DWPF recycle simulant (3).

Fondeur, F.; White, T.; Oji, L.; Martino, C.; Wilmarth, B.

2011-10-20T23:59:59.000Z

202

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

SciTech Connect

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

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

2013-11-14T23:59:59.000Z

203

Improved method for determining tank heel volumes  

SciTech Connect

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

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

1994-07-01T23:59:59.000Z

204

HANFORD WASTE TANK BUMP ACCIDENT & CONSEQUENCE ANALYSIS  

DOE Green Energy (OSTI)

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

MEACHAM, J.E.

2005-02-22T23:59:59.000Z

205

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007  

SciTech Connect

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

West, B; Ruel Waltz, R

2008-06-05T23:59:59.000Z

206

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

Science Conference Proceedings (OSTI)

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

2013-08-28T23:59:59.000Z

207

Fuel Cell Technologies Office: Onboard Storage Tank Workshop  

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

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

208

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

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

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

209

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

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

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

210

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

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

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

211

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

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

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

212

Hanford Tank Waste Treatment and Immobilization Plan Project...  

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

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

213

Radioactive tank waste remediation focus area  

SciTech Connect

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

1996-08-01T23:59:59.000Z

214

Combustion modeling in waste tanks  

DOE Green Energy (OSTI)

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

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

1997-08-01T23:59:59.000Z

215

Savannah River Tank Waste Residuals  

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

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

216

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

217

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

218

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

Science Conference Proceedings (OSTI)

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

Valenzuela, B.D.; Jensen, L.

1994-09-01T23:59:59.000Z

219

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

Science Conference Proceedings (OSTI)

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

NONE

1997-05-01T23:59:59.000Z

220

TANK 4 CHARACTERIZATION, SETTLING, AND WASHING STUDIES  

SciTech Connect

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

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

2009-09-29T23:59:59.000Z

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


221

Hazard Analysis for In Tank Spray Leaks  

SciTech Connect

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

GRAMS, W.H.

2000-06-13T23:59:59.000Z

222

Data Quality Objectives for Tank Farms Waste Compatibility Program  

SciTech Connect

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 presently 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.

BANNING, D.L.

1999-07-02T23:59:59.000Z

223

Enclosure 1 Additional Information on Hanford Tank Wastes  

E-Print Network (OSTI)

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

224

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

Science Conference Proceedings (OSTI)

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

2013-06-03T23:59:59.000Z

225

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

226

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

Science Conference Proceedings (OSTI)

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

Hay, M; Daniel McCabe, D

2008-05-16T23:59:59.000Z

227

Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

228

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

Science Conference Proceedings (OSTI)

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

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

2012-05-31T23:59:59.000Z

229

Alternative Fuels Data Center: Filling CNG Fuel Tanks  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

230

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

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

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

231

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

Science Conference Proceedings (OSTI)

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

Schreiber, R.D.

1996-09-16T23:59:59.000Z

232

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

SciTech Connect

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

Lewis, BE

2003-10-07T23:59:59.000Z

233

Underground Storage Tank Management (District of Columbia)  

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

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

234

Cryogenic Fuel Tank Draining Analysis Model  

E-Print Network (OSTI)

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

Donald Greer Research; Donald Greer

1999-01-01T23:59:59.000Z

235

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

Science Conference Proceedings (OSTI)

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

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

1993-01-01T23:59:59.000Z

236

RECENT PROGRESS IN DOE WASTE TANK CLOSURE  

SciTech Connect

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

Langton, C

2008-02-01T23:59:59.000Z

237

Analysis of ICPP tank farm infiltration  

SciTech Connect

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

Richards, B.T.

1993-10-01T23:59:59.000Z

238

ANALYSIS OF SAMPLES FROM TANK 6F CHEMICAL CLEANING  

SciTech Connect

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

Poirier, M.; Fink, S.

2010-02-02T23:59:59.000Z

239

Underground storage tank management plan  

Science Conference Proceedings (OSTI)

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

NONE

1994-09-01T23:59:59.000Z

240

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

SciTech Connect

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

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

1994-09-01T23:59:59.000Z

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


241

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

SciTech Connect

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

NONE

1998-02-01T23:59:59.000Z

242

Crude Oil Tank Farms and Pipelines Stocks by Type  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Crude oil stocks in the ...

243

Sloshing response of module-type worm tank - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

244

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

245

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

246

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

247

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

DOE Green Energy (OSTI)

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

Huckaby, J.L.

1995-05-10T23:59:59.000Z

248

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

SciTech Connect

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

Harrington, Stephanie J.; Sams, Terry L.

2013-11-06T23:59:59.000Z

249

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

SciTech Connect

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

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

1994-09-29T23:59:59.000Z

250

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

SciTech Connect

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

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

1994-12-01T23:59:59.000Z

251

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

Science Conference Proceedings (OSTI)

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

TERRI, FELLINGER

2004-12-21T23:59:59.000Z

252

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

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

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

253

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

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

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

254

Independent Oversight Review, Hanford Tank Farms - November 2011 |  

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

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

255

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

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

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

256

System for removing liquid waste from a tank  

DOE Patents (OSTI)

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

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

1994-01-01T23:59:59.000Z

257

System for removing liquid waste from a tank  

DOE Patents (OSTI)

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

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

1994-04-26T23:59:59.000Z

258

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

SciTech Connect

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

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

2012-05-31T23:59:59.000Z

259

Standard Electronic Format Specification for Tank Characterization Data Loader Version 3.5  

Science Conference Proceedings (OSTI)

The purpose of this document is to describe the standard electronic format for data files that will be sent for entry into the Tank Characterization Database (TCD). There are 2 different file types needed for each data load: (1) Analytical Results and (2) Sample Descriptions.

ADAMS, M.R.

2001-01-31T23:59:59.000Z

260

Feasibility study of tank leakage mitigation using subsurface barriers. Revision 1  

SciTech Connect

This document reflects the evaluations and analyses performed in response to Tri-Party Agreement Milestone M-45-07A - {open_quotes}Complete Evaluation of Subsurface Barrier Feasibility{close_quotes} (September 1994). In addition, this feasibility study was revised reflecting ongoing work supporting a pending decision by the DOE Richland Operations Office, the Washington State Department of Ecology, and the US Environmental Protection Agency regarding further development of subsurface barrier options for SSTs and whether to proceed with demonstration plans at the Hanford Site (Tri-Party Agreement Milestone M-45-07B). Analyses of 14 integrated SST tank farm remediation alternatives were conducted in response to the three stated objectives of Tri-Party Agreement Milestone M-45-07A. The alternatives include eight with subsurface barriers and six without. Technologies used in the alternatives include three types of tank waste retrieval, seven types of subsurface barriers, a method of stabilizing the void space of emptied tanks, two types of in situ soil flushing, one type of surface barrier, and a clean-closure method. A no-action alternative and a surface-barrier-only alternative were included as nonviable alternatives for comparison. All other alternatives were designed to result in closure of SST tank farms as landfills or in clean-closure. Revision 1 incorporates additional analyses of worker safety, large leak scenarios, and sensitivity to the leach rates of risk controlling constituents. The additional analyses were conducted to support TPA Milestone M-45-07B.

Treat, R.L.; Peters, B.B.; Cameron, R.J. [Enserch Environmental, Inc., Richland, WA (United States)] [and others

1995-01-01T23:59:59.000Z

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


261

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

SciTech Connect

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

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

1994-07-01T23:59:59.000Z

262

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

SciTech Connect

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

Simpson, B.C.

1997-05-23T23:59:59.000Z

263

Composition and quantities of retained gas measured in Hanford waste tanks 241-U-103, S-106, BY-101, and BY-109  

DOE Green Energy (OSTI)

This report provides the results obtained for the single-shell tanks (SSTs) sampled with the Retained Gas Sampler (RGS) during 1997: Tanks 241-U-103, 241-S-106, 241-BY-101, and 241-BY-109. The RGS is a modified version of the core sampler used at Hanford. It is designed specifically to be used in concert with the gas extraction equipment in the hot cell to capture and extrude a gas-containing waste sample in a hermetically sealed system. The four tanks represent several different types of flammable gas SSTs. Tank U-103 is on the Flammable Gas Watch List (FGWL) and is one of the highest-priority group of SSTs that show evidence of significant gas retention. Tank S-106, though not a FGWL tank, has a uniquely high barometric pressure response and continuing rapid surface level rise, indicating a large and increasing volume of retained gas. Tanks BY-101 and BY-109 are not on the FGWL but were chosen to test the effect of recent salt-well pumping on gas retention. Section 2 of this report provides an overview of the process by which retained gases in the Hanford tanks are sampled and analyzed. A detailed description of the procedure used to reduce and analyze the data is provided in Section 3. Tank-by-tank results are covered in Section 4 (with the data presented in the order in which the tanks were sampled), and an RGS system performance overview is given in Section 5. Section 6 presents conclusions from these analyses and recommendations for further research. The cited references are listed in Section 7. Appendix A describes the procedures used to extract gas and ammonia from the samples, Appendix B contains detailed laboratory data from each of the tanks, and Appendix C gives field sampling data.

Mahoney, L.A.; Antoniak, Z.I.; Bates, J.M.

1997-12-01T23:59:59.000Z

264

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

SciTech Connect

A routine video inspection of the annulus region of double-shell tank 241-A Y-102 in August of 2012 indicated the presence material in the annulus space between the primary and secondary liners. A comparison was made to previous inspections perfom1ed in 2006 and 2007. which indicated that a change had occurred. The material was observed at two locations on the floor of the annulus and one location at the top of the annulus region where the primary and secondary top knuckles meet (RPP-ASMT-53793). Subsequent inspections were performed. leading to additional material observed on the floor of the annulus space in a region that had not previously been inspected (WRPS-PER-2012-1363). The annulus Continuous Air Monitor (CAM) was still operational and was not indicating elevated radiation levels in the annulus region. When the camera from the inspections was recovered. it also did not indicate increased radiation above minimum contamination levels (WRPS-PER-2012-1363). A formal leak assessment team was established August 10, 2012 to review tank 241-AY-102 construction and operating histories and to determine whether the material observed in the annulus had resulted from a leak in the primary tank. The team consisted of individuals from Engineering. Base Operations.and Environmental Protection. As this was a first-of-its-kind task. a method for obtaining a sample of the material in the annulus was needed. The consistency of the material was unknown.and the location of a majority of the material was not conducive to using the sampling devices that were currently available at Hanford. A subcontractor was tasked with the development fabrication.and testing of a sampling device that would be able to obtain multiple samples from the material on the annulus floor. as well as the material originating from a refractory air-slot near the floor of the annulus space. This sampler would need to be able to collect and dispense the material it collected into a sample jar retrieval device for transportation of the material to the 222-S laboratory on the Hanford site for analysis. The subcontractor agency fabricated a remote underground sampler by modifying off-the-shelf robotics and parts. Limited testing of the sampler was conducted using a mock-up of the tank annulus and one simulated material type -a salt block. The mock-up testing indicated that the sampler would be able to maneuver within the confined space and that the device worked with full functionality. A total of six weeks had passed from initiation to implementation of the new sampler in the 241-AY-102 tank annulus. Initial sample material was obtained from the annulus floor using the Off-Riser Sampler System that has been used at Hanford tor years to obtain material from the primary tanks. This could be used at the location near Riser 83 since the material was collected directly from the annulus floor and not from a location on the wall or behind a pipe, as was needed from the two locations near Riser 90. After obtaining a small sample of the material on the annulus floor.this sampler sustained terminal damage due to conduit pipes it had to transverse in order to collect and recover material from this location. Several issues were also encountered during deployment of the new sampler into the annulus near Riser 90. These included: Difficulty fitting the sampler down the 12-inch riser into the annulus due to a small tolerance in the size ofthe sampler Failure of sampler components and functions during deployment including the camera. pneumatics.and bearing seals Delays in the field due to supporting equipment issues including cables. cameras. and scaffolding Low recovery of sample material obtained for analysis The complications that occurred during deployment and use of the new sampler during the sampling event ultimately resulted in lower recovery of material from these locations in the annulus than was obtained using the Off-Riser Sampler System and limited the analyses that could be performed for determining the origin of the material. Following completion of th

Harrington, Stephanie J.; Sams, Terry L.

2013-08-15T23:59:59.000Z

265

Computer modeling of ORNL storage tank sludge mobilization and mixing  

SciTech Connect

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

Terrones, G.; Eyler, L.L.

1993-09-01T23:59:59.000Z

266

Vapor sampling of the headspace of radioactive waste storage tanks  

DOE Green Energy (OSTI)

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

Reynolds, D.A., Westinghouse Hanford

1996-05-22T23:59:59.000Z

267

Ferrocyanide tank waste stability. Supplement 2  

Science Conference Proceedings (OSTI)

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

Fowler, K.D.

1993-01-01T23:59:59.000Z

268

Rethinking the Hanford Tank Waste Program  

Science Conference Proceedings (OSTI)

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

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

2002-02-26T23:59:59.000Z

269

Ferrocyanide safety program: FY 1995 report on Mossbauer spectroscopy tank activities  

Science Conference Proceedings (OSTI)

This report summarizes FY 1995 activities on the Mossbauer Spectroscopy task. The National Aeronautics and Space Administration has developed a miniaturized Mossbauer spectrometer that is small enough to perform elevation scans in the Hanford Site waste tank liquid observation wells. Mossbauer spectroscopy is a sensitive and selective method that can detect and distinguish between different iron-based compounds in many types of chemical environments. Iron is major constituent of ferrocyanide waste and information about its location and composition in the tanks supports interim safe storage of the waste and final resolution of the Ferrocyanide Safety Issue. Results obtained from studies of ferrocyanide waste simulants and those from the first test in a hot cell environment using radioactive tank waste are presented

Riedel, F.R.

1995-10-02T23:59:59.000Z

270

Analysis of seismic sloshing of reactor tanks considering submerged components and seismic isolation  

Science Conference Proceedings (OSTI)

A study of the seismic sloshing response of a large pool-type reactor tank with several deck-mounted components is presented. The main objective of the study is to investigate the effects of internal components on the sloshing response and to determine the sloshing loads on the components. The study shows that the presence of internal components can significantly change the dynamic characteristics of the sloshing motion. The sloshing frequencies of a tank with internal components are considerably higher than those of a tank without internals. The higher sloshing frequencies reduce the sloshing wave height on the free surface but the dynamic pressures of the fluid are increased. The effects of seismic isolation on sloshing response are also presented.

Ma, D.C.; Chang, Y.M.

1985-01-01T23:59:59.000Z

271

Pore-Water Extraction Scale-Up Study for the SX Tank Farm  

SciTech Connect

The phenomena related to pore-water extraction from unsaturated sediments have been previously examined with limited laboratory experiments and numerical modeling. However, key scale-up issues have not yet been addressed. Laboratory experiments and numerical modeling were conducted to specifically examine pore-water extraction for sediment conditions relevant to the vadose zone beneath the SX Tank Farm at Hanford Site in southeastern Washington State. Available SX Tank Farm data were evaluated to generate a conceptual model of the subsurface for a targeted pore-water extraction application in areas with elevated moisture and Tc-99 concentration. The hydraulic properties of the types of porous media representative of the SX Tank Farm target application were determined using sediment mixtures prepared in the laboratory based on available borehole sediment particle size data. Numerical modeling was used as an evaluation tool for scale-up of pore-water extraction for targeted field applications.

Truex, Michael J.; Oostrom, Martinus; Wietsma, Thomas W.; Last, George V.; Lanigan, David C.

2013-01-15T23:59:59.000Z

272

Nested Fixed Depth Fluidic Sampler and At Tank Analysis System Deployment Strategy and Plan  

Science Conference Proceedings (OSTI)

Under the Hanford Site River Protection Project (RPP) privatization strategy, the U.S. Department of Energy (DOE) Office of River Protection (ORP) requires the CH2M Hill Hanford Group, Inc. (CHG) to supply tank waste to the privatization contractor, BNFL Inc. (BNFL), for separation and/or treatment and immobilization (vitrification). Three low-activity waste (LAW) specification envelopes represent the range of liquid waste types in the large, Hanford Site underground waste storage tanks. The CHG also is expected to supply high-level waste (HLW) separation and/or treatment and disposal. The HLW envelope is an aqueous slurry of insoluble suspended solids (sludge). The Phase 1 demonstration will extend over 24 years (1996 through 2019) and will be used to resolve technical uncertainties. About one-tenth of the total Hanford Site tank waste, by mass, will be processed during this period. This document provides a strategy and top-level implementation plan for demonstrating and deploying an alternative sampling technology. The alternative technology is an improvement to the current grab sampling and core sampling approaches that are planned to be used to support the RPP privatization contract. This work also includes adding the capability for some at-tank analysis to enhance the potential of this new technology to meet CHG needs. The first application is to LAW and HLW feed staging for privatization; the next is to support cross-site waste transfer from 200 West Area tanks.

REICH, F.R.

2000-02-01T23:59:59.000Z

273

Tank Waste System Integrated Project Team  

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

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

274

Hanford Single-Shell Tank Integrity Program  

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

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

275

Double Shell Tank (DST) Utilities Specification  

SciTech Connect

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

SUSIENE, W.T.

2000-04-27T23:59:59.000Z

276

Technology development activities supporting tank waste remediation  

Science Conference Proceedings (OSTI)

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

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

1994-06-01T23:59:59.000Z

277

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

SciTech Connect

The US Department of Energy Grand Junction Office (GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the contamination distributed in the vadoze zone sediment beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information about the vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the BY Tank Farm.

Kos, S.E.

1997-02-01T23:59:59.000Z

278

Assessment of Tank 241-S-112 Liquid Waste Mixing in Tank 241-SY-101  

SciTech Connect

The objectives of this study were to evaluate mixing of liquid waste from Tank 241-S-112 with waste in Tank 241-SY-101 and to determine the properties of the resulting waste for the cross-site transfer to avoid potential double-shell tank corrosion and pipeline plugging. We applied the time-varying, three-dimensional computer code TEMPEST to Tank SY-101 as it received the S-112 liquid waste. The model predicts that temperature variations in Tank SY-101 generate a natural convection flow that is very slow, varying from about 7 x 10{sup -5} to 1 x 10{sup -3} ft/sec (0.3 to about 4 ft/hr) in most areas. Thus, natural convection would eventually mix the liquid waste in SY-101 but would be very slow to achieve nearly complete mixing. These simulations indicate that the mixing of S-112 and SY-101 wastes in Tank SY-101 is a very slow process, and the density difference between the two wastes would further limit mixing. It is expected to take days or weeks to achieve relatively complete mixing in Tank SY-101.

Onishi, Yasuo; Trent, Donald S.; Wells, Beric E.; Mahoney, Lenna A.

2003-10-01T23:59:59.000Z

279

Tank characterization report for single-shell tank 241-SX-106  

SciTech Connect

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report. This report and its appendices serve as the tank characterization report for single-shell tank 241-SX-106. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-SX-106 waste and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, Section 4.0 makes recommendations about the safety status of the tank and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Documents developed for 1998.''

FIELD, J.G.

1999-02-24T23:59:59.000Z

280

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

Science Conference Proceedings (OSTI)

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

SASAKI, L.M.

1999-02-24T23:59:59.000Z

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


281

High-Pressure Tube Trailers and Tanks  

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

Berry Berry Salvador M. Aceves Lawrence Livermore National Laboratory (925) 422-0864 saceves@LLNL.GOV DOE Delivery Tech Team Presentation Chicago, Illinois February 8, 2005 Inexpensive delivery of compressed hydrogen with ambient temperature or cryogenic compatible vessels * Pressure vessel research at LLNL Conformable (continuous fiber and replicants) Cryo-compressed * Overview of delivery options * The thermodynamics of compressed and cryo-compressed hydrogen storage * Proposed analysis activities * Conclusions Outline We are investigating two techniques for reduced bending stress: continuous fiber vessels and vessels made of replicants Conformable tanks require internal stiffeners (ribs) to efficiently support the pressure and minimize bending stresses Spherical and cylindrical tanks

282

Alternative Inspection Methods for Single Shell Tanks  

Science Conference Proceedings (OSTI)

This document was prepared to provide evaluations and recommendations regarding nondestructive evaluation methods that might be used to determine cracks and bowing in the ceiling of waste storage tanks on the Hanford site. The goal was to determine cracks as small as 1/16 in. wide in the ceiling, and bowing as small as 0.25 in. This report describes digital video camera methods that can be used to detect a crack in the ceiling of the dome, and methods for determining the surface topography of the ceiling in the waste storage tanks to detect localized movements in the surface. A literature search, combined with laboratory testing, comprised this study.

Peters, Timothy J.; Alzheimer, James M.; Hurley, David E.

2010-01-19T23:59:59.000Z

283

Independent Oversight Activity Report, Hanford Tank Farms - June 2013 |  

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

Oversight Activity Report, Hanford Tank Farms - June Oversight Activity Report, Hanford Tank Farms - June 2013 Independent Oversight Activity Report, Hanford Tank Farms - June 2013 June 2013 Office of River Protection Assessment of Contractor Quality Assurance, Operational Awareness at the Hanford Tank Farms [HIAR NNSS-2012-12-03] The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) Site Lead conducted an operational awareness visit to the ORP Hanford Tank Farms, observed a Tank Farms morning meeting, toured the C Tank Farm, and observed a heavy (34,000 pound) lift. Independent Oversight Activity Report, Hanford Tank Farms - June 2013 More Documents & Publications Independent Activity Report, Office of River Protection Waste Treatment

284

Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Publications » Technology Bulletins Publications » Technology Bulletins Printable Version Share this resource Send a link to Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory to someone by E-mail Share Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Facebook Tweet about Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Twitter Bookmark Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Google Bookmark Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Delicious Rank Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on Digg Find More places to share Alternative Fuels Data Center: Propane Tank Overfill Safety Advisory on AddThis.com... Propane Tank Overfill Safety Advisory

285

High-Level Liquid Waste Tank Integrity Workshop - 2008  

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

Liquid Waste Tank Integrity Liquid Waste Tank Integrity Workshop - 2008 Karthik Subramanian Bruce Wiersma November 2008 High Level Waste Corporate Board Meeting karthik.subramanian@srnl.doe.gov bruce.wiersma@srnl.doe.gov 2 Acknowledgements * Bruce Wiersma (SRNL) * Kayle Boomer (Hanford) * Michael T. Terry (Facilitator) * SRS - Liquid Waste Organization * Hanford Tank Farms * DOE-EM 3 Background * High level radioactive waste (HLW) tanks provide critical interim confinement for waste prior to processing and permanent disposal * Maintaining structural integrity (SI) of the tanks is a critical component of operations 4 Tank Integrity Workshop - 2008 * Discuss the HLW tank integrity technology needs based upon the evolving waste processing and tank closure requirements along with its continued storage mission

286

Savings Project: Insulate Your Water Heater Tank | Department...  

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

Your Water Heater Tank Addthis Project Level medium Energy Savings 20-45 annually Time to Complete 1.5 hours Overall Cost 30 Insulate your hot water tank to save energy and...

287

EIS-0391: Hanford Tank Closure and Waste Management, Richland...  

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

single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal...

288

TANK FARM INTERIM SURFACE BARRIER MATERIALS AND RUNOFF ALTERNATIVES STUDY  

SciTech Connect

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

HOLM MJ

2009-06-25T23:59:59.000Z

289

Authorization basis status report (miscellaneous TWRS facilities, tanks and components)  

SciTech Connect

This report presents the results of a systematic evaluation conducted to identify miscellaneous TWRS facilities, tanks and components with potential needed authorization basis upgrades. It provides the Authorization Basis upgrade plan for those miscellaneous TWRS facilities, tanks and components identified.

Stickney, R.G.

1998-04-29T23:59:59.000Z

290

Tank SY-101 void fraction instrument functional design criteria  

DOE Green Energy (OSTI)

This document presents the functional design criteria for design, analysis, fabrication, testing, and installation of a void fraction instrument for Tank SY-101. This instrument will measure the void fraction in the waste in Tank SY-101 at various elevations.

McWethy, L.M.

1994-10-18T23:59:59.000Z

291

STATUS OF CHEMICAL CLEANING OF WASTE TANKS AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT - 9114  

SciTech Connect

Chemical Cleaning is currently in progress for Tanks 5 and 6 at the Savannah River Site. The Chemical Cleaning process is being utilized to remove the residual waste heel remaining after completion of Mechanical Sludge Removal. This work is required to prepare the tanks for closure. Tanks 5 and 6 are 1950s vintage carbon steel waste tanks that do not meet current containment standards. These tanks are 22.9 meters (75 feet) in diameter, 7.5 meters (24.5 feet) in height, and have a capacity of 2.84E+6 liters (750,000 gallons). Chemical Cleaning adds 8 wt % oxalic acid to the carbon steel tank to dissolve the remaining sludge heel. The resulting acidic waste solution is transferred to Tank 7 where it is pH adjusted to minimize corrosion of the carbon steel tank. The Chemical Cleaning flowsheet includes multiple strikes of acid in each tank. Acid is delivered by tanker truck and is added to the tanks through a hose assembly connected to a pipe penetration through the tank top. The flowsheet also includes spray washing with acid and water. This paper includes an overview of the configuration required for Chemical Cleaning, the planned flowsheet, and an overview of technical concerns associated with the process. In addition, the current status of the Chemical Cleaning process in Tanks 5 and 6, lessons learned from the execution of the process, and the path forward for completion of cleaning in Tanks 5 and 6 will also be discussed.

Thaxton, D; Geoff Clendenen, G; Willie Gordon, W; Samuel Fink, S; Michael Poirier, M

2008-12-31T23:59:59.000Z

292

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

Science Conference Proceedings (OSTI)

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

BAKER, D.M.

2004-08-03T23:59:59.000Z

293

Functional Analysis for Double Shell Tank (DST) Subsystems  

Science Conference Proceedings (OSTI)

This functional analysis identifies the hierarchy and describes the subsystem functions that support the Double-Shell Tank (DST) System described in HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System. Because of the uncertainty associated with the need for upgrades of the existing catch tanks supporting the Waste Feed Delivery (WFD) mission, catch tank functions are not addressed in this document. The functions identified herein are applicable to the Phase 1 WFD mission only.

SMITH, D.F.

2000-08-22T23:59:59.000Z

294

Operational test report for WESF diesel generator diesel tank installation  

Science Conference Proceedings (OSTI)

The WESF Backup Generator Underground Diesel Tank 101 has been replaced with a new above ground 1000 gallon diesel tank. Following the tank installation, inspections and tests specified in the Operational Test Procedure, WHC-SD-WM-OTP-155, were performed. Inspections performed by a Quality Control person indicated the installation was leak free and the diesel generator/engine ran as desired. There were no test and inspection exceptions, therefore, the diesel tank installation is operable.

Schwehr, B.A.

1994-08-02T23:59:59.000Z

295

Sloshing response of a reactor tank with internals  

Science Conference Proceedings (OSTI)

The sloshing response of a large reactor tank with in-tank components is presented. The study indicates that the presence of the internal components can significantly change the dynamic characteristics of the sloshing motion. The sloshing frequency of a tank with internals is considerably higher than that of a tank without internal. The higher sloshing frequency reduces the sloshing wave height on the free-surface but increases the dynamic pressure in the fluid.

Ma, D.C.; Gvildys, J.; Chang, Y.W.

1984-01-01T23:59:59.000Z

296

GEOCHEMICAL TESTING AND MODEL DEVELOPMENT - RESIDUAL TANK WASTE TEST PLAN  

SciTech Connect

This Test Plan describes the testing and chemical analyses release rate studies on tank residual samples collected following the retrieval of waste from the tank. This work will provide the data required to develop a contaminant release model for the tank residuals from both sludge and salt cake single-shell tanks. The data are intended for use in the long-term performance assessment and conceptual model development.

CANTRELL KJ; CONNELLY MP

2010-03-09T23:59:59.000Z

297

Tank Waste Corporate Board Meeting 07/24/08  

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

The following documents are associated with the Tank Waste Corporate Board Meeting held on July 24th, 2008.

298

System Specification for the Double Shell Tank (DST) System  

Science Conference Proceedings (OSTI)

This document establishes the functional, performance, design, development, interface and test requirements for the Double-Shell Tank System.

GRENARD, C.E.

2000-04-21T23:59:59.000Z

299

5th Symposium on Railroad Tank Cars - Programmaster.org  

Science Conference Proceedings (OSTI)

... processing strategies, correlation of material properties with puncture performance, safety and security of tank cars, non destructive testing, maintenance and...

300

Mixer pump test plan for double shell tank AZ-101  

Science Conference Proceedings (OSTI)

Mixer pump systems have been chosen as the method for retrieval of tank wastes contained in double shell tanks at Hanford. This document describes the plan for testing and demonstrating the ability of two 300 hp mixer pumps to mobilize waste in tank AZ-101. The mixer pumps, equipment and instrumentation to monitor the test were installed by Project W-151.

STAEHR, T.W.

1999-05-12T23:59:59.000Z

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


301

Justification for Continued Operation for Tank 241-Z-361  

Science Conference Proceedings (OSTI)

This justification for continued operations (JCO) summarizes analyses performed to better understand and control the potential hazards associated with Tank 241-2-361. This revision to the JCO has been prepared to identify and control the hazards associated with sampling the tank using techniques developed and approved for use in the Tank Waste Remediation System (TWRS) at Hanford.

BOGEN, D.M.

1999-09-01T23:59:59.000Z

302

REMOVING SLUDGE HEELS FROM SAVANNAH RIVER SITE WASTE TANKS BY OXALIC ACID DISSOLUTION  

SciTech Connect

The Savannah River Site (SRS) will remove sludge as part of waste tank closure operations. Typically the bulk sludge is removed by mixing it with supernate to produce a slurry, and transporting the slurry to a downstream tank for processing. Experience shows that a residual heel may remain in the tank that cannot be removed by this conventional technique. In the past, SRS used oxalic acid solutions to disperse or dissolve the sludge heel to complete the waste removal. To better understand the actual conditions of oxalic acid cleaning of waste from carbon steel tanks, the authors developed and conducted an experimental program to determine its effectiveness in dissolving sludge, the hydrogen generation rate, the generation rate of other gases, the carbon steel corrosion rate, the impact of mixing on chemical cleaning, the impact of temperature, and the types of precipitates formed during the neutralization process. The test samples included actual SRS sludge and simulated SRS sludge. The authors performed the simulated waste tests at 25, 50, and 75 C by adding 8 wt % oxalic acid to the sludge over seven days. They conducted the actual waste tests at 50 and 75 C by adding 8 wt % oxalic acid to the sludge as a single batch. Following the testing, SRS conducted chemical cleaning with oxalic acid in two waste tanks. In Tank 5F, the oxalic acid (8 wt %) addition occurred over seven days, followed by inhibited water to ensure the tank contained enough liquid to operate the mixer pumps. The tank temperature during oxalic acid addition and dissolution was approximately 45 C. The authors analyzed samples from the chemical cleaning process and compared it with test data. The conclusions from the work are: (1) Oxalic acid addition proved effective in dissolving sludge heels in the simulant demonstration, the actual waste demonstration, and in SRS Tank 5F. (2) The oxalic acid dissolved {approx} 100% of the uranium, {approx} 100% of the iron, and {approx} 40% of the manganese during a single contact in the simulant demonstration. (The iron dissolution may be high due to corrosion of carbon steel coupons.) (3) The oxalic acid dissolved {approx} 80% of the uranium, {approx} 70% of the iron, {approx} 50% of the manganese, and {approx} 90% of the aluminum in the actual waste demonstration for a single contact. (4) The oxalic acid dissolved {approx} 100% of the uranium, {approx} 15% of the iron, {approx} 40% of the manganese, and {approx} 80% of the aluminum in Tank 5F during the first contact cycle. Except for the iron, these results agree well with the demonstrations. The data suggest that a much larger fraction of the iron in the sludge dissolved, but it re-precipitated with the oxalate added to Tank 5F. (5) The demonstrations produced large volumes (i.e., 2-14 gallons of gas/gallon of oxalic acid) of gas (primarily carbon dioxide) by the reaction of oxalic acid with sludge and carbon steel. (6) The reaction of oxalic acid with carbon steel produced hydrogen in the simulant and actual waste demonstrations. The volume produced varied from 0.00002-0.00100 ft{sup 3} hydrogen/ft{sup 2} carbon steel. The hydrogen production proved higher in unmixed tanks than in mixed tanks.

Poirier, M; David Herman, D; Fernando Fondeur, F; John Pareizs, J; Michael Hay, M; Bruce Wiersma, B; Kim Crapse, K; Thomas Peters, T; Samuel Fink, S; Donald Thaxton, D

2009-03-01T23:59:59.000Z

303

Tank characterization report for single-shell tank 241-BX-111  

Science Conference Proceedings (OSTI)

This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste, stored in Tank 241-BX-111. This report supports the requirements of the Tri-Party Agreement Milestone M-44-ISB.

Anantatmula, R.P.

1998-05-05T23:59:59.000Z

304

Tank characterization report for single-shell tank 241-BY-107  

Science Conference Proceedings (OSTI)

One major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other 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-BY-107. The objectives of this report are (1) to use characterization data in response to technical issues associated with 241-BY-107 waste, and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 provides the best-basis inventory estimate, and Section 4.0 makes recommendations about the safety status and additional sampling needs. The appendices contain supporting data and information.

Mccain, D.J.

1997-04-09T23:59:59.000Z

305

Data Observations on Double Shell Tank (DST) Flammable Gas Watch List Tank Behavior  

DOE Green Energy (OSTI)

This report provides the data from the retained gas sampler, void fraction instrument, ball rheometer, standard hydrogen monitoring system, and other tank data pertinent to gas retention and release behavior in the waste stored in double-shelled Flammable Gas Watch List tanks at Hanford. These include tanks 241-AN-103,241-AN-104, 241-AN-105, 241-AW-101, 241-SY-101, and 241-SY-103. The tanks and the waste they contain are described in terms of fill history and chemistry. The results of mixer pump operation and recent waste transfers and back-dilution in SY-101 are also described. In-situ measurement and monitoring systems are described and the data are summarized under the categories of thermal behavior, waste configuration and properties, gas generation and composition, gas retention and historical gas release behavior.

HEDENGREN, D.C.

2000-09-28T23:59:59.000Z

306

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

307

DEPOSITION TANK CORROSION TESTING FOR ENHANCED CHEMICAL CLEANING POST OXALIC ACID DESTRUCTION  

DOE Green Energy (OSTI)

An Enhanced Chemical Cleaning (ECC) process is being developed to aid in the high level waste tank closure at the Savannah River Site. The ECC process uses an advanced oxidation process (AOP) to destroy the oxalic acid that is used to remove residual sludge from a waste tank prior to closure. The AOP process treats the dissolved sludge with ozone to decompose the oxalic acid through reactions with hydroxyl radicals. The effluent from this oxalic acid decomposition is to be sent to a Type III waste tank and may be corrosive to these tanks. As part of the hazardous simulant testing that was conducted at the ECC vendor location, corrosion testing was conducted to determine the general corrosion rate for the deposition tank and to assess the susceptibility to localized corrosion, especially pitting. Both of these factors impact the calculation of hydrogen gas generation and the structural integrity of the tanks, which are considered safety class functions. The testing consisted of immersion and electrochemical testing of A537 carbon steel, the material of construction of Type III tanks, and 304L stainless steel, the material of construction for transfer piping. Tests were conducted in solutions removed from the destruction loop of the prototype ECC set up. Hazardous simulants, which were manufactured at SRNL, were used as representative sludges for F-area and H-area waste tanks. Oxalic acid concentrations of 1 and 2.5% were used to dissolve the sludge as a feed to the ECC process. Test solutions included the uninhibited effluent, as well as the effluent treated for corrosion control. The corrosion control options included mixing with an inhibited supernate and the addition of hydroxide. Evaporation of the uninhibited effluent was also tested since it may have a positive impact on reducing corrosion. All corrosion testing was conducted at 50 C. The uninhibited effluent was found to increase the corrosion rate by an order of magnitude from less than 1 mil per year (mpy) for an inhibited waste to a range of 5 to 23.4 mpy, depending on sludge chemistry. F-area-based effluents were, in general, more corrosive. Effective corrosion control measures included evaporation, hydroxide additions and mixing with supernates containing a representative supernate chemistry (5 M hydroxide and 1.5 M nitrite). Corrosion rates with these measures were generally 0.2 mpy. The A537 carbon steel was found to be susceptible to pitting when the corrosion control measure involved mixing the ECC effluent with a supernate chemistry having minimal inhibitor concentrations (0.5 M hydroxide and 0.3 M nitrite). Corrosion rates in this case were near 1 mpy.

Mickalonis, J.

2011-08-29T23:59:59.000Z

308

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, B.; Waltz, R.

2009-06-11T23:59:59.000Z

309

Explosion proof vehicle for tank inspection  

Science Conference Proceedings (OSTI)

An Explosion Proof Vehicle (EPV) having an interior substantially filled with an inert fluid creating an interior pressure greater than the exterior pressure. One or more flexible tubes provide the inert fluid and one or more electrical conductors from a control system to the vehicle. The vehicle is preferably used in subsurface tank inspection, whereby the vehicle is submerged in a volatile fluid.

Zollinger, William T. (Idaho Falls, ID); Klingler, Kerry M. (Idaho Falls, ID); Bauer, Scott G. (Idaho Falls, ID)

2012-02-28T23:59:59.000Z

310

Annual Radioactive Waste Tank Inspection Program - 2000  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2000 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, W.R.

2001-04-17T23:59:59.000Z

311

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

Science Conference Proceedings (OSTI)

This report documents a detailed buckling evaluation of the primary tanks in the Hanford double-shell waste tanks (DSTs), which 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 raised by the Office of Environment, Safety, and Health (ES&H) Oversight (EH-22) during a review of work performed on the double-shell tank farms and the operation of the aging waste facility (AWF) primary tank ventilation system. The current buckling review focuses on the following tasks: (1) Evaluate the potential for progressive I-bolt failure and the appropriateness of the safety factors that were used for evaluating local and global buckling. The analysis will specifically answer the following questions: (a) Can the EH-22 scenario develop if the vacuum is limited to -6.6-inch water gage (w.g.) by a relief valve? (b) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario can develop? (c) What is the appropriate factor of safety required to protect against buckling if the EH-22 scenario cannot develop? (2) Develop influence functions to estimate the axial stresses in the primary tanks for all reasonable combinations of tank loads, based on detailed finite element analysis. The analysis must account for the variation in design details and operating conditions between the different DSTs. The analysis must also address the imperfection sensitivity of the primary tank to buckling. (3) Perform a detailed buckling analysis to determine the maximum allowable differential pressure for each of the DST primary tanks at the current specified limits on waste temperature, height, and specific gravity. Based on the I-bolt loads analysis and the small deformations that are predicted at the unfactored limits on vacuum and axial loads, it is very unlikely that the EH-22 scenario (i.e., progressive I-bolt failure leading to global buckling of the tank under increased vacuum) could occur.

MACKEY TC; JOHNSON KI; DEIBLER JE; PILLI SP; RINKER MW; KARRI NK

2007-02-14T23:59:59.000Z

312

Property:Testing Facilities Overseen | Open Energy Information  

Open Energy Info (EERE)

Testing Facilities Overseen Testing Facilities Overseen Jump to: navigation, search This is a property of type Page and uses the Testing Facility form Pages using the property "Testing Facilities Overseen" Showing 25 pages using this property. A Alden Research Laboratory, Inc + Alden Tow Tank +, Alden Wave Basin +, Alden Small Flume +, ... B Bucknell University + Bucknell Hydraulic Flume + C Cornell University Hydrodynamics + DeFrees Flume 1 +, DeFrees Flume 2 +, DeFrees Flume 3 +, ... M Massachusetts Institute of Technology Hydrodynamics + MIT Tow Tank + O Ohmsett + Ohmsett Tow Tank + Oregon State University Hydrodynamics + Hinsdale Wave Basin 1 +, Hinsdale Wave Basin 2 + P Pennsylvania State University Hydrodynamics + Penn Reverberant Tank +, Penn Small Water Tunnel +, Penn Large Water Tunnel +

313

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

SciTech Connect

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

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

1994-03-01T23:59:59.000Z

314

Feasibility study of tank leakage mitigation using subsurface barriers  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has established the Tank Waste Remediation System (TWRS) to satisfy manage and dispose of the waste currently stored in the underground storage tanks. The retrieval element of TWRS includes a work scope to develop subsurface impermeable barriers beneath SSTs. The barriers could serve as a means to contain leakage that may result from waste retrieval operations and could also support site closure activities by facilitating cleanup. Three types of subsurface barrier systems have emerged for further consideration: (1) chemical grout, (2) freeze walls, and (3) desiccant, represented in this feasibility study as a circulating air barrier. This report contains analyses of the costs and relative risks associated with combinations retrieval technologies and barrier technologies that from 14 alternatives. Eight of the alternatives include the use of subsurface barriers; the remaining six nonbarrier alternative are included in order to compare the costs, relative risks and other values of retrieval with subsurface barriers. Each alternative includes various combinations of technologies that can impact the risks associated with future contamination of the groundwater beneath the Hanford Site to varying degrees. Other potential risks associated with these alternatives, such as those related to accidents and airborne contamination resulting from retrieval and barrier emplacement operations, are not quantitatively evaluated in this report.

Treat, R.L.; Peters, B.B.; Cameron, R.J.; McCormak, W.D.; Trenkler, T.; Walters, M.F. [Ensearch Environmental, Inc. (United States); Rouse, J.K.; McLaughlin, T.J. [Bovay Northwest, Inc., Richland, WA (United States); Cruse, J.M. [Westinghouse Hanford Co., Richland, WA (United States)

1994-09-21T23:59:59.000Z

315

Supporting document for the North East Quandrant Historical Tank Content Estimate Report for BX-Tank Farm  

Science Conference Proceedings (OSTI)

This supporting document provides historical in-depth characterization information gathered on BX-Tank Farm, such as historical waste transfer and level data, tank physical information, temperature data, sampling data, and drywell and liquid observation well data for Historical Tank Content Estimate Report of the NE Quandrant and the Hanford 200 East Areas.

Brevick, C.H.

1994-06-01T23:59:59.000Z

316

BLENDING STUDY FOR SRR SALT DISPOSITION INTEGRATION: TANK 50H SCALE-MODELING AND COMPUTER-MODELING FOR BLENDING PUMP DESIGN, PHASE 2  

DOE Green Energy (OSTI)

The Salt Disposition Integration (SDI) portfolio of projects provides the infrastructure within existing Liquid Waste facilities to support the startup and long term operation of the Salt Waste Processing Facility (SWPF). Within SDI, the Blend and Feed Project will equip existing waste tanks in the Tank Farms to serve as Blend Tanks where 300,000-800,000 gallons of salt solution will be blended in 1.3 million gallon tanks and qualified for use as feedstock for SWPF. Blending requires the miscible salt solutions from potentially multiple source tanks per batch to be well mixed without disturbing settled sludge solids that may be present in a Blend Tank. Disturbing solids may be problematic both from a feed quality perspective as well as from a process safety perspective where hydrogen release from the sludge is a potential flammability concern. To develop the necessary technical basis for the design and operation of blending equipment, Savannah River National Laboratory (SRNL) completed scaled blending and transfer pump tests and computational fluid dynamics (CFD) modeling. A 94 inch diameter pilot-scale blending tank, including tank internals such as the blending pump, transfer pump, removable cooling coils, and center column, were used in this research. The test tank represents a 1/10.85 scaled version of an 85 foot diameter, Type IIIA, nuclear waste tank that may be typical of Blend Tanks used in SDI. Specifically, Tank 50 was selected as the tank to be modeled per the SRR, Project Engineering Manager. SRNL blending tests investigated various fixed position, non-rotating, dual nozzle pump designs, including a blending pump model provided by the blend pump vendor, Curtiss Wright (CW). Primary research goals were to assess blending times and to evaluate incipient sludge disturbance for waste tanks. Incipient sludge disturbance was defined by SRR and SRNL as minor blending of settled sludge from the tank bottom into suspension due to blending pump operation, where the sludge level was shown to remain constant. To experimentally model the sludge layer, a very thin, pourable, sludge simulant was conservatively used for all testing. To experimentally model the liquid, supernate layer above the sludge in waste tanks, two salt solution simulants were used, which provided a bounding range of supernate properties. One solution was water (H{sub 2}O + NaOH), and the other was an inhibited, more viscous salt solution. The research performed and data obtained significantly advances the understanding of fluid mechanics, mixing theory and CFD modeling for nuclear waste tanks by benchmarking CFD results to actual experimental data. This research significantly bridges the gap between previous CFD models and actual field experiences in real waste tanks. A finding of the 2009, DOE, Slurry Retrieval, Pipeline Transport and Plugging, and Mixing Workshop was that CFD models were inadequate to assess blending processes in nuclear waste tanks. One recommendation from that Workshop was that a validation, or bench marking program be performed for CFD modeling versus experiment. This research provided experimental data to validate and correct CFD models as they apply to mixing and blending in nuclear waste tanks. Extensive SDI research was a significant step toward bench marking and applying CFD modeling. This research showed that CFD models not only agreed with experiment, but demonstrated that the large variance in actual experimental data accounts for misunderstood discrepancies between CFD models and experiments. Having documented this finding, SRNL was able to provide correction factors to be used with CFD models to statistically bound full scale CFD results. Through the use of pilot scale tests performed for both types of pumps and available engineering literature, SRNL demonstrated how to effectively apply CFD results to salt batch mixing in full scale waste tanks. In other words, CFD models were in error prior to development of experimental correction factors determined during this research, which provided a technique to use CFD models fo

Leishear, R.; Poirier, M.; Fowley, M.

2011-05-26T23:59:59.000Z

317

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

SciTech Connect

A major function of the Tank Waste Remediation System (TWRS) is to characterize waste in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis and other available information about a tank are compiled and maintained in a tank characterization report (TCR). This report and its appendices serve as the TCR for single-shell tank 241-BX-110. The objectives of this report are (1) to use characterization data in response to technical issues associated with tank 241-BX-110 waste, and (2) to provide a standard characterization of the waste in terms of a best-basis inventory estimate. Section 2.0 summarizes the response to technical issues, Section 3.0 shows the best-basis inventory estimate, and Section 4.0 makes recommendations about the tank's safety status and additional sampling needs. The appendices contain supporting data and information. This report supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1997), Milestone M-44-15b, change request M-44-97-03 to ''issue characterization deliverables consistent with the Waste Information Requirements Document developed for 1998.''

RASMUSSEN, J.H.

1999-02-23T23:59:59.000Z

318

AUTOMATED LEAK DETECTION OF BURIED TANKS USING GEOPHYSICAL METHODS AT THE HANFORD NUCLEAR SITE  

SciTech Connect

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

CALENDINE S; SCHOFIELD JS; LEVITT MT; FINK JB; RUCKER DF

2011-03-30T23:59:59.000Z

319

WRPS MEETING THE CHALLENGE OF TANK WASTE  

SciTech Connect

Washington River Protection Solutions (WRPS) is the Hanford tank operations contractor, charged with managing one of the most challenging environmental cleanup projects in the nation. The U.S. Department of Energy hired WRPS to manage 56 million gallons of high-level radioactive waste stored in 177 underground tanks. The waste is the legacy of 45 years of plutonium production for the U. S. nuclear arsenal. WRPS mission is three-fold: safely manage the waste until it can be processed and immobilized; develop the tools and techniques to retrieve the waste from the tanks, and build the infrastructure needed to deliver the waste to the Waste Treatment Plant (WTP) when it begins operating. WTP will 'vitrify' the waste by mixing it with silica and other materials and heating it in an electric melter. Vitrification turns the waste into a sturdy glass that will isolate the radioactivity from the environment. It will take more than 20 years to process all the tank waste. The tank waste is a complex highly radioactive mixture of liquid, sludge and solids. The radioactivity, chemical composition of the waste and the limited access to the underground storage tanks makes retrieval a challenge. Waste is being retrieved from aging single-shell tanks and transferred to newer, safer double-shell tanks. WRPS is using a new technology known as enhanced-reach sluicing to remove waste. A high-pressure stream of liquid is sprayed at 100 gallons per minute through a telescoping arm onto a hard waste layer several inches thick covering the waste. The waste is broken up, moved to a central pump suction and removed from the tank. The innovative Mobile Arm Retrieval System (MARS) is also being used to retrieve waste. MARS is a remotely operated, telescoping arm installed on a mast in the center of the tank. It uses multiple technologies to scrape, scour and rake the waste toward a pump for removal. The American Reinvestment and Recovery Act (ARRA) provided nearly $326 million over two-and-a-half years to modernize the infrastructure in Hanford's tank farms. WRPS issued 850 subcontracts totaling more than $152 million with nearly 76 percent of that total awarded to small businesses. WRPS used the funding to upgrade tank farm infrastructure, develop technologies to retrieve and consolidate tank waste and extend the life of two critical operating facilities needed to feed waste to the WTP. The 222-S Laboratory analyzes waste to support waste retrievals and transfers. The laboratory was upgraded to support future WTP operations with a new computer system, new analytical equipment, a new office building and a new climate-controlled warehouse. The 242-A Evaporator was upgraded with a control-room simulator for operator training and several upgrades to aging equipment. The facility is used to remove liquid from the tank waste, creating additional storage space, necessary for continued waste retrievals and WTP operation. The One System Integrated Project Team is ajoint effort ofWRPS and Bechtel National to identify and resolve common issues associated with commissioning, feeding and operating the Waste Treatment Plant. Two new facilities are being designed to support WTP hot commlsslomng. The Interim Hanford Storage project is planned to store canisters of immobilized high-level radioactive waste glass produced by the vitrification plant. The facility will use open racks to store the 15-foot long, two-foot diameter canisters of waste, which require remote handling. The Secondary Liquid Waste Treatment Project is a major upgrade to the existing Effluent Treatment Facility at Hanford so it can treat about 10 million gallons of liquid radioactive and hazardous effluent a year from the vitrification plant. The One System approach brings the staff of both companies together to identify and resolve WTP safety issues. A questioning attitude is encouraged and an open forum is maintained for employees to raise issues. WRPS is completing its mission safely with record-setting safety performance. Since WRPS took over the Hanford Tank Operations Contract in October 2

BRITTON JC

2012-02-21T23:59:59.000Z

320

Criticality Safety Evaluation of Hanford Tank Farms Facility  

SciTech Connect

Data and calculations from previous criticality safety evaluations and analyses were used to evaluate criticality safety for the entire Tank Farms facility to support the continued waste storage mission. This criticality safety evaluation concludes that a criticality accident at the Tank Farms facility is an incredible event due to the existing form (chemistry) and distribution (neutron absorbers) of tank waste. Limits and controls for receipt of waste from other facilities and maintenance of tank waste condition are set forth to maintain the margin subcriticality in tank waste.

WEISS, E.V.

2000-12-15T23:59:59.000Z

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


321

Underground Storage Tank Regulations for the Certification of Persons Who  

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

Underground Storage Tank Regulations for the Certification of Underground Storage Tank Regulations for the Certification of Persons Who Install, Alter, and Remove Underground Storage Tanks (Mississippi) Underground Storage Tank Regulations for the Certification of Persons Who Install, Alter, and Remove Underground Storage Tanks (Mississippi) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells

322

Status of tank 241-SY-101 data analyses  

DOE Green Energy (OSTI)

The Waste Tank Flammable Gas Stabilization Program was established in 1990 to provide for resolution of a major safety issue identified for 23 of the high-level waste tanks at the Hanford Site. The safety issue involves the production, accumulation, and periodic release from these tanks of flammable gases in concentrations exceeding the lower flammability limits. This document deals primarily with tank 241-SY-101 from the SY Tank Farm. The flammable gas condition has existed for this tank since the tank was first filled in the time period from 1977 to 1980. During a general review of waste tank chemical stability in 1988--1989, this situation was re-examined and, in March 1990, the condition was declared to be an unreviewed safety question. Tank 241-SY-101 was placed under special operating restrictions, and a program of investigation was begun to evaluate the condition and determine appropriate courses of action. This report summarizes the data that have become available on tank 241-SY-101 since it was declared as an unreviewed safety question and updates the information reported in an earlier document (WHC-EP-0517). The report provides a technical basis for use in the evaluation of safety risks of the tank and subsequent resolution of the unreviewed safety question.

Anantatmula, R.P.

1992-09-01T23:59:59.000Z

323

Remedial Alternative Selection for the F Area Tank Farm,  

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

Notice of Availability: Notice of Availability: Explanation of Significant Difference for Incorporating Tanks 18 and 19 into Revision 1 Interim Record Of Decision Remedial Alternative Selection for the F Area Tank Farm, Waste Tanks 17 and 20 at the Savannah River Site The Explanation of Significant Difference for Incorporating Tanks 18 and 19 into Revision 1 Interim Record of Decision Remedial Alternative Selection for the F Area Tank Farm, (hereafter referred to as the Tank 18 and 19 ESD) is being issued by the U.S. Department of Energy (DOE), the lead agency for the Savannah River Site (SRS), with concurrence by the U.S. Environmental Protection Agency - Region 4 (EPA), and South Carolina Department of Health and Environmental Control (SCDHEC). The Tank 18 and 19 ESD modifies

324

Iraq liquid radioactive waste tanks maintenance and monitoring program plan.  

SciTech Connect

The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tank inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.

Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad (Iraq Ministry of Science and Technology)

2011-10-01T23:59:59.000Z

325

Summary - Tank 48 at the Savannah River Site  

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

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

326

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

327

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

328

Mitigation of the most hazardous tank at the Hanford Site  

DOE Green Energy (OSTI)

Various tanks at the Hanford Site have been declared to be unresolved safety problems. This means that the tank has the potential to be beyond the limits covered by the current safety documentation. Tank 241-SY-101 poses the greatest hazard. The waste stored in this tank has periodically released hydrogen gas which exceeds the lower flammable limits. A mixer pump was installed in this tank to stir the waste. Stirring the waste would allow the hydrogen to be released slowly in a controlled manner and mitigate the hazard associated with this tank. The testing of this mixer pump is reported in this document. The mixer pump has been successful in controlling the hydrogen concentration in the tank dome to below the flammable limit which has mitigated the hazardous gas releases.

Reynolds, D.A.

1994-09-01T23:59:59.000Z

329

Tank waste consolidation analysis for transfer of ORNL RH-TRU tank sludges to the Melton Valley Storage Tanks  

SciTech Connect

The objective of this work is to evaluate the schedule and technical issues associated with consolidation of Remote Handled Transuranic (RH-TRU) sludges in the Melton Valley Storage Tanks (MVSTs). This work supports the DOE Transuranic Waste (TRU) Program plans for private sector treatment of all ORNL TRU sludges for disposal at the Waste Isolation Pilot Plant (WIPP). Transfer of these sludges must be completed in FY 2000 to meet the required schedule for beginning shipment of treated sludges to the WIPP by 2002. This study was performed to (1) evaluate the sludge transfer schedule, (2) evaluate the ability of existing tank systems to contain and manage the sludges and liquids generated during the transfers, and (3) evaluate the costs and schedules of different solid/liquid separation and solids-monitoring methods used during sludge transfer for management of sluice waters.

Kent, T.E.; DePaoli, S.M.

1997-01-01T23:59:59.000Z

330

U. S. Department of Energy Savannah River Operations Office - F and H Tank  

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

F and H Tank Farm Closure Documents F and H Tank Farm Closure Documents F and H Tank Farm Closure Documents F Tank Farm Closure Documents F Tank Farm Performance Assessment F Tank Farm Performance Assessment -- Revision 1 Tank 18/Tank 19 Special Analysis Industrial Wastewater General Closure Plan for F-Area Waste Tank System -- Final Industrial Wastewater Closure Module for the Liquid Waste Tanks 18 and 19 DOE agreement to cease waste removal SC approval to Closure Module and agreement to cease waste removal EPA agreement to cease waste removal Tanks 17 and 20 Closure Errata Industrial Wastewater Closure Module for the High-Level Waste Tank 17 System Industrial Wastewater Closure Module for the High-Level Waste Tank 20 System Draft Basis for Section 3116 Determination for Closure of F Tank Farm at SRS

331

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

SciTech Connect

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 authority 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.

N /A

1996-07-31T23:59:59.000Z

332

Three-dimensional fluid-structure interaction dynamics of a pool-reactor in-tank component. [LMFBR  

SciTech Connect

The safety evaluation of reactor-components often involves the analysis of various types of fluid/structural components interacting in three-dimensional space. For example, in the design of a pool-type reactor several vital in-tank components such as the primary pumps and the intermediate heat exchangers are contained within the primary tank. Typically, these components are suspended from the deck structure and largely submersed in the sodium pool. Because of this positioning these components are vulnerable to structural damage due to pressure wave propagation in the tank during a CDA. In order to assess the structural integrity of these components it is necessary to perform a dynamic analysis in three-dimensional space which accounts for the fluid-structure coupling. A model is developed which has many of the salient features of this fluid-structural component system.

Kulak, R.F.

1979-01-01T23:59:59.000Z

333

TANK DEIS SUMMARY TITLE PG.psd  

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

Summary Summary S-iii COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Savannah River Site High-Level Waste Tank Closure Environmental Impact Statement (DOE/EIS-0303), Aiken, South Carolina. CONTACT: For additional information on this environmental impact statement (EIS), write or call: Andrew R. Grainger, NEPA Compliance Officer U.S. Department of Energy, Savannah River Operations Office Building 730B, Room 2418 Aiken, South Carolina 29802 Attention: Tank Closure EIS Local and Nationwide Telephone: (800) 881-7292 Email: nepa@srs.gov For general information on DOE's National Environmental Policy Act (NEPA) process, write or call: Ms. Carol M. Borgstrom, Director Office of NEPA Policy and Compliance, EH-42 U.S. Department of Energy 1000 Independence Avenue, S.W.

334

Hanford Site C Tank Farm Meeting Summary  

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

1878, Rev. 0 1878, Rev. 0 Summary Notes from 5 - 7 May 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV14800 EDT/EON: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 15 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or

335

TANK DEIS TITLE PG.psd  

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

Cover Sheet Cover Sheet iii COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Savannah River Site High-Level Waste Tank Closure Environmental Impact Statement (DOE/EIS-0303), Aiken, South Carolina CONTACT: For additional information on this environmental impact statement (EIS), write or call: Andrew R. Grainger, NEPA Compliance Officer U.S. Department of Energy, Savannah River Operations Office Building 730B, Room 2418 Aiken, South Carolina 29802 Attention: Tank Closure EIS Local and Nationwide Telephone: (800) 881-7292 Email: nepa@srs.gov For general information on DOE's National Environmental Policy Act (NEPA), write or call: Ms. Carol M. Borgstrom, Director Office of NEPA Policy and Compliance, EH-42 U.S. Department of Energy 1000 Independence Avenue, S.W.

336

Hanford Site C Tank Farm Meeting Summary  

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

Summary Notes from 24- 25 February 2009 Office of River Protection Waste Management Area C Performance Assessment Input Meeting Attendees: Representatives from Department of Energy-Office of River Protection (DOE-ORP), DOE Richland Operations Office (DOE-RL), DOE-Headquarters (DOE-HQ), the Washington State Department of Ecology (Ecology), and the U.S. Nuclear Regulatory Commission (NRC), met at the Ecology offices in Richland, Washington on 24 & 25 February 2009. EPA Region X staff participated on 25 February 2009 via teleconference. Discussion: DOE is pursuing closure of Waste Management Area C (WMA-C) located at the Hanford Site. At some point in the future, DOE and NRC will consult on waste determinations for these tank closures; additionally these tanks will be closed in coordination with EPA and

337

Hanford Site C Tank Farm Meeting Summary  

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

3622, Rev. 0 3622, Rev. 0 Summary Notes from 1 - 3 September 2009 Office of River Protection Waste Management Area C Tank Farm Performance Assessment Input Meeting MP Connelly Washington River Protection Solutions LLC Richland, WA 99352 U.S. Department of Energy Contract DE-AC27-08RV1 4800 EDT/ECN: DRF UC: Cost Center: Charge Code: B&R Code: Total Pages: 13 Key Words: Waste Management Area C, Performance Assessment, tank closure, waste inventory Abstract: Summary of meeting between DOE-ORP and Hanford Site regulators/stakeholders regarding Waste Management Area C performance assessment TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or

338

Annual report of tank waste treatability  

SciTech Connect

This report has been prepared as part of the Hanford Federal Facility Agreement and Consent Order* (Tri-Party Agreement) and constitutes completion of Tri-Party Agreement milestone M-04-00D for fiscal year 1993. This report provides a summary of treatment activities for newly generated waste, existing double-shell tank waste, and existing single-shell tank waste, as well as a summary of grout disposal feasibility, glass disposal feasibility, alternate methods for disposal, and safety issues which may impact the treatment and disposal of existing defense nuclear wastes. This report is an update of the 1992 report and is intended to provide traceability for the documentation by statusing the studies, activities, and issues which occurred in these areas listed above over the period of March 1, 1992, through February 28, 1993. Therefore, ongoing studies, activities, and issues which were documented in the previous (1992) report are addressed in this (1993) report.

Lane, A.G. [Los Alamos Technical Associates, Inc., NM (United States); Kirkbride, R.A. [Westinghouse Hanford Co., Richland, WA (United States)

1993-09-01T23:59:59.000Z

339

Organic liner for thermoset composite tank  

DOE Patents (OSTI)

Previously, scientists have followed two approaches in the development of cryotanks that were impervious to deterioration caused by the contained material and environmental factors. One is a metal lined tank with the metal usually in the form of a foil. The other is an organically coated tank where the coating is a film. Both the foil and the film are theoretically impermeable; however, the bond to the substrate and the integrity of the final surface have proven to be unsatisfactory in both applications. This invention relates to a coating for sealing surfaces having complex geometry, particularly to a coating of epoxy layers that forms a surface impermeable in harsh cryogenic and chemically corrosive environments. 8 tabs.

Garvey, R.E.

1989-12-13T23:59:59.000Z

340

Think Tank: Delaware Department of Natural Resources  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

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

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


341

Storage tanks, particularly for liquefied gases  

SciTech Connect

Marine and Industrial Developments, Ltd., Greece, has developed a new, low-cost LNG-tank lining which is highly resistant to impairment by tensile stresses encountered during cooldown to cryogenic temperatures. The thermal insulation is incorporated in the unitary cellular matrix lining composed of layers of plastics (polyurethane rubbers) including the primary barrier and at least one other fluid-impervious layer between the primary barrier and the tank wall. The plastic layers are thin, less than 0.24 in. (6 mm) in thickness. The layers of plastic for forming the cellular matrix can be formed in situ as the lining is built by applying a polymerizable or curable polymeric composition under, between, and over blocks of the selected thermally insulating material as they are laid. The polymerizable composition thus constitutes a kind of mortar which is then polymerized and/or cured in situ.

Papanicolaou, J.P.; Galatis, T.N.

1976-04-06T23:59:59.000Z

342

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT SEISMIC ANALYSIS OF HANFORD DOUBLE SHELL TANKS  

Science Conference Proceedings (OSTI)

M&D Professional Services, Inc. (M&D) is under subcontract to Pacific Northwest National Laboratory (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). The work statement provided to M&D (PNNL 2003) required that the seismic analysis of the DSTs assess the impacts of potentially non-conservative assumptions in previous analyses and account for the additional soil mass due to the as-found soil density increase, the effects of material degradation, additional thermal profiles applied to the full structure including the soil-structure response with the footings, the non-rigid (low frequency) response of the tank roof, the asymmetric seismic-induced soil loading, the structural discontinuity between the concrete tank wall and the support footing and the sloshing of the tank waste. The seismic analysis considers the interaction of the tank with the surrounding soil and the effects of the primary tank contents. The DSTs and the surrounding soil are modeled as a system of finite elements. The depth and width of the soil incorporated into the analysis model are sufficient to obtain appropriately accurate analytical results. The analyses required to support the work statement differ from previous analysis of the DSTs in that the soil-structure interaction (SSI) model includes several (nonlinear) contact surfaces in the tank structure, and the contained waste must be modeled explicitly in order to capture the fluid-structure interaction behavior between the primary tank and contained waste.

MACKEY, T.C.

2006-03-17T23:59:59.000Z

343

Tank waste remediation system mission analysis report  

SciTech Connect

This document describes and analyzes the technical requirements that the Tank Waste Remediation System (TWRS) must satisfy for the mission. This document further defines the technical requirements that TWRS must satisfy to supply feed to the private contractors` facilities and to store or dispose the immobilized waste following processing in these facilities. This document uses a two phased approach to the analysis to reflect the two-phased nature of the mission.

Acree, C.D.

1998-01-09T23:59:59.000Z

344

Tank Farm Operations Surveillance Automation Analysis  

Science Conference Proceedings (OSTI)

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

MARQUEZ, D.L.

2000-12-21T23:59:59.000Z

345

Organic Tanks Safety Program: Waste aging studies  

Science Conference Proceedings (OSTI)

The underground storage tanks at the Hanford Complex contain wastes generated from many years of plutonium production and recovery processes, and mixed wastes from radiological degradation processes. The chemical changes of the organic materials used in the extraction processes have a direct on several specific safety issues, including potential energy releases from these tanks. This report details the first year`s findings of a study charged with determining how thermal and radiological processes may change the composition of organic compounds disposed to the tank. Their approach relies on literature precedent, experiments with simulated waste, and studies of model reactions. During the past year, efforts have focused on the global reaction kinetics of a simulated waste exposed to {gamma} radiation, the reactions of organic radicals with nitrite ion, and the decomposition reactions of nitro compounds. In experiments with an organic tank non-radioactive simulant, the authors found that gas production is predominantly radiolytically induced. Concurrent with gas generation they observe the disappearance of EDTA, TBP, DBP and hexone. In the absence of radiolysis, the TBP readily saponifies in the basic medium, but decomposition of the other compounds required radiolysis. Key organic intermediates in the model are C-N bonded compounds such as oximes. As discussed in the report, oximes and nitro compounds decompose in strong base to yield aldehydes, ketones and carboxylic acids (from nitriles). Certain aldehydes can react in the absence of radiolysis to form H{sub 2}. Thus, if the pathways are correct, then organic compounds reacting via these pathways are oxidizing to lower energy content. 75 refs.

Camaioni, D.M.; Samuels, W.D.; Lenihan, B.D.; Clauss, S.A.; Wahl, K.L.; Campbell, J.A.

1994-11-01T23:59:59.000Z

346

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

Science Conference Proceedings (OSTI)

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

Conner, J.M.

1997-04-28T23:59:59.000Z

347

Tank characterization report for double-shell tank 241-AN-105  

Science Conference Proceedings (OSTI)

A major function of the Tank Waste Remediation System (TWRS) is to characterize wastes in support of waste management and disposal activities at the Hanford Site. Analytical data from sampling and analysis, along with other available information about a tank, are compiled and maintained in a tank characterization report (TCR). This report and its appendixes serve as the TCR for double-shell tank 241-AN-105. The objectives of this report are: (1) to use characterization data in response to technical issues associated with tank 241-AN-105 waste; and (2) to provide a standard characterization of this waste in terms of a best-basis inventory estimate. The response to technical issues is summarized in Section 2.0, and the best-basis inventory estimate is presented in Section 3.0. Recommendations regarding safety status and additional sampling needs are provided in Section 4.0. Supporting data and information are contained in the appendices. This report also supports the requirements of the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1996) milestone M-44-10.

Jo, J.

1997-05-02T23:59:59.000Z

348

Tanks focus area multiyear program plan FY97-FY99  

Science Conference Proceedings (OSTI)

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. The 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.

NONE

1996-08-01T23:59:59.000Z

349

Tank waste remediation system configuration management plan  

SciTech Connect

The configuration management program for the Tank Waste Remediation System (TWRS) Project Mission supports management of the project baseline by providing the mechanisms to identify, document, and control the functional and physical characteristics of the products. This document is one of the tools used to develop and control the mission and work. It is an integrated approach for control of technical, cost, schedule, and administrative information necessary to manage the configurations for the TWRS Project Mission. Configuration management focuses on five principal activities: configuration management system management, configuration identification, configuration status accounting, change control, and configuration management assessments. TWRS Project personnel must execute work in a controlled fashion. Work must be performed by verbatim use of authorized and released technical information and documentation. Application of configuration management will be consistently applied across all TWRS Project activities and assessed accordingly. The Project Hanford Management Contract (PHMC) configuration management requirements are prescribed in HNF-MP-013, Configuration Management Plan (FDH 1997a). This TWRS Configuration Management Plan (CMP) implements those requirements and supersedes the Tank Waste Remediation System Configuration Management Program Plan described in Vann, 1996. HNF-SD-WM-CM-014, Tank Waste Remediation System Configuration Management Implementation Plan (Vann, 1997) will be revised to implement the requirements of this plan. This plan provides the responsibilities, actions and tools necessary to implement the requirements as defined in the above referenced documents.

Vann, J.M.

1998-01-08T23:59:59.000Z

350

Evaluation of TANK Water Heater Simulation Model as Embedded in HWSim  

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

TANK Water Heater Simulation Model as Embedded in HWSim TANK Water Heater Simulation Model as Embedded in HWSim Title Evaluation of TANK Water Heater Simulation Model as Embedded in HWSim Publication Type Report LBNL Report Number LBNL-5092E Year of Publication 2010 Authors Lutz, James D. Document Number LBNL-5092E Pagination 11 Date Published December 22 Publisher Lawrence Berkeley National Laboratory City Berkeley ISBN Number LBNL-5092E Abstract This report evaluates the hot water temperatures and flow rates as calculated by the combined HWSim and TANK simulation models. Notes This work was sponsored by the Gas Technology Institute (GTI) which is funded by the California Energy Commission, Public Interest Energy Research (PIER) Program, under Residential Water Heating Program Contract No. 500-08-060. This work was supported by the Assistant Secretary for Energy Efficiency and Renewable Energy, Office of Building Technology, State, and Community Programs, of the U.S. Department of Energy under Contract No. DE-AC02-05CH11231.

351

Hanford Tank Farms Vadose Zone, Addendum to the TX Tank Farm Report  

Science Conference Proceedings (OSTI)

This addendum to the TX Tank Farm Report (GJO-97-13-TAR, GJO-HAN-11) published in September 1997 incorporates the results of high-rate and repeat logging activities along with shape factor analysis of the logging data. A high-rate logging system was developed and deployed in the TX Tank Farm to measure cesium-137 concentration levels in high gamma flux zones where the spectral gamma logging system was unable to collect usable data because of high dead times and detector saturation. This report presents additional data and revised visualizations of subsurface contaminant distribution in the TX Tank Farm at the DOE Hanford Site in the state of Washington.

Spatz, R.

2000-08-01T23:59:59.000Z

352

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

SciTech Connect

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

Raphael, G.F.

1994-09-01T23:59:59.000Z

353

TANK 7 CHARACTERIZATION AND WASHING STUDIES  

SciTech Connect

A 3-L PUREX sludge sample from Tank 7 was characterized and then processed through a series of inhibited water washes to remove oxalate, sodium, and other soluble ions. Current plans use Tank 7 as one of the feed sources for Sludge Batch 7 (SB7). Tank 7 is high in oxalate due to the oxalic acid cleaning of the sludge heels from Tanks 5 and 6 and subsequent transfer to Tank 7. Ten decant and nine wash cycles were performed over a 47 day period at ambient temperature. Initially, seven decants and seven washes were completed based on preliminary estimates of the number of wash cycles required to remove the oxalate in the sludge. After reviewing the composition data, SRNL recommended the completion of 2 or 3 more decant/wash cycles to ensure all of the sodium oxalate had redissolved. In the first 7 washes, the slurry oxalate concentration was 12,300 mg/kg (69.6% oxalate removal compared to 96.1% removal of the other soluble ions). After all ten decants were complete, the slurry oxalate concentration was 3,080 mg/kg (89.2% oxalate removal compared to 99.0% of the other soluble ions). The rate of dissolution of oxalate increased significantly with subsequent washes until all of the sodium oxalate had been redissolved after seven decant/wash cycles. The measured oxalate concentrations agreed very well with LWO predictions for washing of the Tank 7 sample. Highlights of the analysis and washing of the Tank 7 sample include: (1) Sodium oxalate was detected in the as-received filtered solids. 95% of the oxalate was insoluble (undissolved) in the as-received slurry. (2) No sodium oxalate was detected in the post-wash filtered solids. (3) Sodium oxalate is the last soluble species that redissolves during washing with inhibited water. In order to significantly reduce the sodium oxalate concentration, the sludge must be highly washed, leaving the other soluble anions and cations (including sodium) very low in concentration. (4) The post-wash slurry had 1% of the soluble anions and cations remaining, with the exception of sodium and oxalate, for which the percentages were 2.8% and 10.8% respectively. The post-wash sodium concentration was 9.25 wt% slurry total solids basis and 0.15 M supernate. (5) The settling rate of slurry was very fast allowing the completion of one decant/wash cycle each day. (6) The measured yield stress of as-received (6.42 wt% undissolved solids) and post-wash (7.77 wt% undissolved solids) slurry was <1 Pa. For rapidly settling slurries, it can be hard to measure the yield stress of the slurry so this result may be closer to the supernate result than the slurry. The recommended strategy for developing the oxalate target for sludge preparation for Sludge Batch 7 includes the following steps: (1) CPC simulant testing to determine the percent oxalate destruction and acid mix needed to produce a predicted redox of approximately 0.2 Fe{sup +2}/{Sigma}Fe in a SME product while meeting all DWPF processing constraints. (2) Perform a DWPF melter flammability assessment to ensure that the additional carbon in the oxalate together with other carbon sources will not lead to a flammability issue. (3) Perform a DWPF glass paper assessment to ensure the glass produced will meet all DWPF glass limits due to the sodium concentration in the sludge batch. The testing would need to be repeated if a significant CPC processing change, such as an alternative reductant to formic acid, is implemented.

Lambert, D.; Pareizs, J.; Click, D.

2010-02-04T23:59:59.000Z

354

Tank Farms at the Savannah River Site | Department of Energy  

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

Tank Farms at the Savannah River Site Tank Farms at the Savannah River Site Tank Farms at the Savannah River Site Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. A Waste Determination Basis (WD Basis) provides the analysis to document the Secretary's determination to manage the residuals as low-level radioactive waste. The Savannah River Site has several facilities managed under Section 3116. The F-Area Tank Farm (FTF) WD Basis covers 20 tanks remaining to be closed in the FTF and the H-Area Tank Farm (HTF) WD Basis will cover all 29 HTF

355

EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington |  

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

391: Hanford Tank Closure and Waste Management, Richland, 391: Hanford Tank Closure and Waste Management, Richland, Washington EIS-0391: Hanford Tank Closure and Waste Management, Richland, Washington Summary This EIS evaluates the environmental impacts for the following three key areas: (1) retrieval, treatment, and disposal of waste from 149 single-shell tanks (SSTs) and 28 double-shell tanks and closure of the SST system, (2) decommissioning of the Fast Flux Test Facility, a nuclear test reactor, and (3) disposal of Hanford's waste and other DOE sites' low-level and mixed low-level radioactive waste. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 13, 2013 EIS-0391: Record of Decision Final Tank Closure and Waste Management Environmental Impact Statement for

356

DOE Selects Washington River Protection Solutions, LLC for Tank Operations  

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

DOE Selects Washington River Protection Solutions, LLC for Tank DOE Selects Washington River Protection Solutions, LLC for Tank Operations Contract at Hanford Site DOE Selects Washington River Protection Solutions, LLC for Tank Operations Contract at Hanford Site May 29, 2008 - 12:51pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Washington River Protection Solutions (WRPS), LLC has been selected as the tank operations contractor to store, retrieve and treat Hanford tank waste and close the tank farms at DOE's Hanford Site in southeastern Washington State. The contract is a cost-plus award-fee contract valued at approximately $7.1 billion over ten years (a five-year base period with options to extend it for up to five years). WRPS is a limited liability company comprised of Washington Group

357

Analysis of Enriched Uranyl Nitrate in Nested Annular Tank Array  

SciTech Connect

Two series of experiments were performed at the Rocky Flats Critical Mass Laboratory during the 1980s using highly enriched (93%) uranyl nitrate solution in annular tanks. [1, 2] Tanks were of typical sizes found in nuclear production plants. Experiments looked at tanks of varying radii in a co-located set of nested tanks, a 1 by 2 array, and a 1 by 3 array. The co-located set of tanks had been analyzed previously [3] as a benchmark for inclusion within the International Handbook of Evaluated Criticality Safety Benchmark Experiments. [4] The current study represents the benchmark analysis of the 1 by 3 array of a series of nested annular tanks. Of the seventeen configurations performed in this set of experiments, twelve were evaluated and nine were judged as acceptable benchmarks.

John D. Bess; James D. Cleaver

2009-06-01T23:59:59.000Z

358

Savannah River Site - Tank 48 SRS Review Report  

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

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

359

Flammable gas project: Criteria for flammable gas watch list tanks  

Science Conference Proceedings (OSTI)

The Flammable Gas Watch List is the listing of tanks that are subject to the provisions of Public Law 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation`` (Appendix A). Tanks on the Flammable Gas Watch List are judged to have a serious potential for release of high-level waste due to the ignition of flammable gases released from the waste in the tank. The purpose of this document is to provide criteria for identifying and categorizing the Hanford Site high4evel waste tanks to be included on the Flammable Gas Watch List. This document also provides criteria on which to base a recommendation to remove tanks from the Flammable Gas Watch List.

Cash, R.J.

1997-01-29T23:59:59.000Z

360

DOE Selects Washington River Protection Solutions, LLC for Tank Operations  

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

Selects Washington River Protection Solutions, LLC for Tank Selects Washington River Protection Solutions, LLC for Tank Operations Contract at Hanford Site DOE Selects Washington River Protection Solutions, LLC for Tank Operations Contract at Hanford Site May 29, 2008 - 12:51pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Washington River Protection Solutions (WRPS), LLC has been selected as the tank operations contractor to store, retrieve and treat Hanford tank waste and close the tank farms at DOE's Hanford Site in southeastern Washington State. The contract is a cost-plus award-fee contract valued at approximately $7.1 billion over ten years (a five-year base period with options to extend it for up to five years). WRPS is a limited liability company comprised of Washington Group

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


361

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

Science Conference Proceedings (OSTI)

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

Bhatia, P.K.

1995-01-31T23:59:59.000Z

362

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

SciTech Connect

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 well 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.

KP Recknagle; Y Onishi

1999-05-19T23:59:59.000Z

363

241-AN Double Shell Tanks (DST) Integrity Assessment Report  

Science Conference Proceedings (OSTI)

This report presents the results of the integrity assessment of the 241-AN 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.

JENSEN, C.E.

1999-09-21T23:59:59.000Z

364

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

Science Conference Proceedings (OSTI)

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.

JENSEN, C.E.

1999-09-21T23:59:59.000Z

365

Seismically-induced sloshing phenomena in LMFBR reactor tanks  

Science Conference Proceedings (OSTI)

A coupled fluid-structure interaction solution procedure for analyzing seismically-induced sloshing phenomena in fluid-tank systems is presented. Both rigid and flexible tanks are considered. Surface-wave effects are also included. Results demonstrate that tank flexibility could affect the free surface-wave amplitude and the sloshing pressuare if the natural frequency of the fluid-structure system is below 5 Hz. Furthermore, the presence of higher sloshing modes do enhance the post-earthquake sloshing response.

Ma, D.C.; Liu, W.K.; Gvildys, J.; Chang, Y.W.

1982-01-01T23:59:59.000Z

366

Heat exchanger and water tank arrangement for passive cooling system  

DOE Patents (OSTI)

A water storage tank in the coolant water loop of a nuclear reactor contains a tubular heat exchanger. The heat exchanger has tubesheets mounted to the tank connections so that the tubesheets and tubes may be readily inspected and repaired. Preferably, the tubes extend from the tubesheets on a square pitch and then on a rectangular pitch therebetween. Also, the heat exchanger is supported by a frame so that the tank wall is not required to support all of its weight.

Gillett, James E. (Greensburg, PA); Johnson, F. Thomas (Baldwin Boro, PA); Orr, Richard S. (Pittsburgh, PA); Schulz, Terry L. (Murrysville Boro, PA)

1993-01-01T23:59:59.000Z

367

Formulation Development for Processing Tank 48H in Saltstone  

Science Conference Proceedings (OSTI)

Salt Program Engineering (SPE) requested research to help evaluate the Saltstone process as a disposition path for the contents of Tank 48H. The main objective of the task was to evaluate the processing and cured properties of Saltstone prepared with Tank 48H material aggregated with other Tank 50H inflows to determine the suitability of Saltstone as a disposition path for the contents of Tank 48H. The Tank 48H waste was aggregated with inhibited water (IW) and a simulant of the recycle stream from the Defense Waste Processing Facility (DWPF). The aggregates targeted three tetraphenyl borate (TPB) concentrations: (1) 5500 mg/L, the aggregate determined from assumptions at the maximum reasonable limits, (2) 1500 mg/L, the aggregate containing the minimum proportion of Tank 48H material that is programmatically acceptable, and (3) 3500 mg/L, the average of the two endpoints. Saltstone prepared with Tank 48H waste aggregated with IW and a simulant of the recycle stream from the DWPF was produced in the Savannah River National Laboratory (SRNL) shielded cells. Processable Saltstone slurry formulations can be prepared with Tank 48H material and both DWPF recycle simulant and inhibited water with concentrations of 1500, 3500, and 5500 mg/L TPB. Toxic Characterization Leaching Procedure (TCLP) extractions were performed on the six aggregates. The extracts were analyzed for benzene, nitrobenzene and mercury. All of the samples passed TCLP. Saltstone was also prepared with a Tank 48H simulant and DWPF recycle simulant. Testing of the fresh Saltstone slurry and cured Saltstone prepared with simulants indicate that neither the fresh nor cured Saltstone is hazardous for ignitability. After transferring Tank 48H material to Tank 50H and prior to processing through the Saltstone Production Facility (SPF), Tank 50H should be sampled to verify processability.

COZZI, ALEX

2004-10-01T23:59:59.000Z

368

Tank Monitoring and Control System (TMACS) Version Description Document (VDD)  

SciTech Connect

This document updates the Version Description Document with the changes incorporated in the Revision 11.2 software installation on the Tank Monitor and Control System (TMACS).

BARNES, D.A.

2000-03-02T23:59:59.000Z

369

ORP Tank Farms Unreviewed Safety Question Process Implementation...  

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

Activity Report for the Selected Aspects of Tank Farms Unreviewed Safety Question Process Implementation Dates of Activity 02212011 - 04182011 Report Preparer Shivaji S....

370

ELECTROCHEMICAL CORROSION STUDY FOR TANK 241-AY-102 SLUDGE  

SciTech Connect

The report describes the analyses performed on core samples from the sludge region of the waste in Tank 241-AY-102 to determine the electrochemical corrosion potential.

DUNCAN JB

2002-09-24T23:59:59.000Z

371

Resolution of Hanford tanks organic complexant safety issue  

SciTech Connect

The Hanford Site tanks have been assessed for organic complexant reaction hazards. The results have shown that most tanks contain insufficient concentrations of TOC to support a propagating reaction. It has also been shown that those tanks where the TOC concentration approaches levels of concern, degradation of the organic complexants to less energetic compounds has occurred. The results of the investigations have been documented. The residual organic complexants in the Hanford Site waste tanks do not present a safety concern for long-term storage.

Kirch, N.W.

1998-05-14T23:59:59.000Z

372

Forklift Storage Tank R&D: Timely, Critical, Exemplary  

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

Forklift Storage Tank R&D: Timely, Critical, Exemplary August 14, 2012 DOE EERE Fuel Cell Technologies Program Webinar Daniel E. Dedrick and Chris San Marchi Sandia National...

373

Hanford tanks initiative (HTI) work breakdown structure (WBS)dictionary  

Science Conference Proceedings (OSTI)

This dictionary lists the scope, deliverables, and interfaces for the various work elements of the Hanford Tanks Initiative. Cost detail is included for information only.

Mckinney, K.E.

1997-03-31T23:59:59.000Z

374

PERFORMANCE OBJECTIVES FOR TANK FARM CLOSURE PERFORMANCE ASSESSMENTS  

Science Conference Proceedings (OSTI)

This report documents the performance objectives (metrics, times of analyses, and times of compliance) to be used in performance assessments of Hanford Site tank farm closure.

MANN, F.M.; CRUMPLER, J.D.

2005-09-30T23:59:59.000Z

375

PSA results for Hanford high level waste Tank 101-SY  

DOE Green Energy (OSTI)

Los Alamos National Laboratory has performed a comprehensive probabilistic safety assessment (PSA) that includes consideration of external events for the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (``burps``) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is underway in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. This PSA for Tank 101-SY, which did not consider the pump experiment or future tank-remediation activities, involved three distinct tasks. First, the accident sequence analysis identified and quantified those potential accidents whose consequences result in tank material release. Second, characteristics and release paths for the airborne and liquid radioactive source terms were determined. Finally, the consequences, primarily onsite and offsite potential health effects resulting from radionuclide release, were estimated, and overall risk curves were constructed. An overview of each of these tasks and a summary of the overall results of the analysis are presented in the following sections.

MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W. [Los Alamos National Lab., NM (United States); Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J. [PLG, Inc., Newport Beach, CA (United States)

1993-10-01T23:59:59.000Z

376

Review of the Hanford Tank Farms Radiological Controls Activity...  

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

tank pump and slurry distributer, as well as excavation and installation of associated instrumentation. Independent Oversight also interviewed a selection of key personnel...

377

Parameters Impacting Crossflow Filter Performance of Hanford Tank ...  

Parameters Impacting Crossflow Filter Performance of Hanford Tank Waste Simulants Reid Peterson Justin Billings, Carolyn Burns, Richard Daniel, Phil Schonewill, Rick ...

378

Deflagration studies on waste Tank 101-SY: Test plan  

DOE Green Energy (OSTI)

This report discusses test procedures and calibration of equipment to study the flammability and deflagration of hydrogen, nitrous oxide, and air in waste tanks. (JL)

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

1991-06-01T23:59:59.000Z

379

INVESTIGATION OF THE POTENTIAL FOR CAUSTIC STRESS CORROSION CRACKING OF A537 CARBON STEEL NUCLEAR WASTE TANKS  

SciTech Connect

The evaporator recycle streams contain waste in a chemistry and temperature regime that may be outside of the current waste tank corrosion control program, which imposes temperature limits to mitigate caustic stress corrosion cracking (CSCC). A review of the recent service history (1998-2008) of Tanks 30 and 32 showed that these tanks were operated in highly concentrated hydroxide solution at high temperature. Visual inspections, experimental testing, and a review of the tank service history have shown that CSCC has occurred in uncooled/un-stress relieved F-Area tanks. Therefore, for the Type III/IIIA waste tanks the efficacy of the stress relief of welding residual stress is the only corrosion-limiting mechanism. The objective of this experimental program is to test carbon steel small scale welded U-bend specimens and large welded plates (12 x 12 x 1 in.) in a caustic solution with upper bound chemistry (12 M hydroxide and 1 M each of nitrate, nitrite, and aluminate) and temperature (125 C). These conditions simulate worst-case situations in Tanks 30 and 32. Both as-welded and stress-relieved specimens have been tested. No evidence of stress corrosion cracking was found in the U-bend specimens after 21 days of testing. The large plate test is currently in progress, but no cracking has been observed after 9 weeks of immersion. Based on the preliminary results, it appears that the environmental conditions of the tests are unable to develop stress corrosion cracking within the duration of these tests.

Lam, P.

2009-10-15T23:59:59.000Z

380

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT INCREASED LIQUID LEVEL ANALYSIS FOR 241-AP TANK FARMS  

SciTech Connect

The essential difference between Revision 1 and the original issue of this report is the analysis of the anchor bolts that tie the steel dome of the primary tank to the concrete tank dome. The reevaluation of the AP anchor bolts showed that (for a given temperature increase) the anchor shear load distribution did not change significantly from the initially higher stiffness to the new secant shear stiffness. Therefore, the forces and displacements of the other tank components such as the primary tanks stresses, secondary liner strains, and concrete tank forces and moments also did not change significantly. Consequently, the revised work in Revision 1 focused on the changes in the anchor bolt responses and a full reevaluation of all tank components was judged to be unnecessary.

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

2009-01-14T23:59:59.000Z

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


381

Selection of AT-Tank Analysis Equipment for Determining Completion of Mixing and Particle Concentration in Hanford Waste Tanks  

SciTech Connect

This document will describe the functions and requirements of the at-tank analysis system concept developed by the Robotics Technology Development Program (RTDP) and Berkeley Instruments. It will discuss commercially available at-tank analysis equipment, and compare those that meet the stated functions and requirements. This is followed by a discussion of the considerations used in the selection of instrumentation for the concept design, and an overall description of the proposed at-tank analysis system.

Dodson, M.G.; Ozanich, R.M.; Bailey, S.A.

1999-06-10T23:59:59.000Z

382

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

Science Conference Proceedings (OSTI)

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

Jo, J.

1997-04-15T23:59:59.000Z

383

Preliminary tank characterization report for single-shell tank 241-BY-109: best-basis inventory  

Science Conference Proceedings (OSTI)

An effort is underway to provide waste inventory estimates that will serve as standard characterization source terms for the various waste management activities. As part of this effort, an evaluation of available information for single-shell tank 241-BY-109 was performed, and a best-basis inventory was established. This work follows the methodology that was established by the standard inventory task.

Kupfer, M.J.

1997-09-02T23:59:59.000Z

384

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

Science Conference Proceedings (OSTI)

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

DEFIGH PRICE, C.

2000-09-20T23:59:59.000Z

385

CHARACTERIZATION OF TANK 16H ANNULUS SAMPLES  

Science Conference Proceedings (OSTI)

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

Hay, M.; Reboul, S.

2012-04-16T23:59:59.000Z

386

Property:Programmable Wavemaking | Open Energy Information  

Open Energy Info (EERE)

Programmable Wavemaking Programmable Wavemaking Jump to: navigation, search Property Name Programmable Wavemaking Property Type String Pages using the property "Programmable Wavemaking" Showing 25 pages using this property. (previous 25) (next 25) 1 1.5-ft Wave Flume Facility + Yes + 10-ft Wave Flume Facility + Yes + 11-ft Wave Flume Facility + Yes + 2 2-ft Flume Facility + Yes + 3 3-ft Wave Flume Facility + Yes + 5 5-ft Wave Flume Facility + Yes + 6 6-ft Wave Flume Facility + Yes + A Alden Large Flume + Yes + Alden Small Flume + Yes + Alden Wave Basin + Yes + B Breakwater Research Facility + No + C Carderock Maneuvering & Seakeeping Basin + Yes + Carderock Tow Tank 2 + Yes + Carderock Tow Tank 3 + Yes + Chase Tow Tank + Yes + Coastal Harbors Modeling Facility + Yes +

387

Property:Data Comparison to Computational Models | Open Energy Information  

Open Energy Info (EERE)

Comparison to Computational Models Comparison to Computational Models Jump to: navigation, search Property Name Data Comparison to Computational Models Property Type Text Pages using the property "Data Comparison to Computational Models" Showing 14 pages using this property. A Alden Large Flume + Designed as needed Alden Small Flume + Designed as needed Alden Tow Tank + Velocity, flow characteristics Alden Wave Basin + Wave height, period, length, velocity D Davidson Laboratory Tow Tank + Comparisons to validate and improve CFD models are made periodically. M MHL Free Surface Channel + Custom MHL Data Acquisition System includes graphical displays for the results of each sampling channel. MHL Tow Tank + Custom MHL Data Acquisition System includes graphical displays for the results of each sampling channel.

388

Property:Integrated Display/Graphics | Open Energy Information  

Open Energy Info (EERE)

Display/Graphics Display/Graphics Jump to: navigation, search Property Name Integrated Display/Graphics Property Type Text Pages using the property "Integrated Display/Graphics" Showing 22 pages using this property. A Alden Large Flume + Lab View, Test Point Alden Small Flume + Lab View, Test Point Alden Tow Tank + Lab View, Test Point Alden Wave Basin + Lab View, Test Point B Bucknell Hydraulic Flume + Microsoft Windows based systems C Conte Large Flume + Conventional PC and video displays; TecPlot Conte Small Flume + Conventional PC and video displays; TecPlot D Davidson Laboratory Tow Tank + Standard PC-based tools H Haynes Tow Tank + National Instruments LabView Haynes Wave Basin + National Instruments LabView Hinsdale Wave Basin 1 + Remote telepresence and experiment participation as part of George E. Brown Jr. Network for Earthquake Engineering Simulation (NEES)

389

Property:Simulated Beach | Open Energy Information  

Open Energy Info (EERE)

Simulated Beach Simulated Beach Jump to: navigation, search Property Name Simulated Beach Property Type String Pages using the property "Simulated Beach" Showing 25 pages using this property. (previous 25) (next 25) 1 1.5-ft Wave Flume Facility + No + 10-ft Wave Flume Facility + No + 11-ft Wave Flume Facility + No + 2 2-ft Flume Facility + No + 3 3-ft Wave Flume Facility + No + 5 5-ft Wave Flume Facility + No + 6 6-ft Wave Flume Facility + No + A Alden Large Flume + No + Alden Small Flume + No + Alden Wave Basin + Yes + B Breakwater Research Facility + No + C Carderock Maneuvering & Seakeeping Basin + Yes + Carderock Tow Tank 2 + Yes + Carderock Tow Tank 3 + Yes + Chase Tow Tank + No + Coastal Harbors Modeling Facility + No + Coastal Inlet Model Facility + No +

390

Investigation of methods to transfer heat from solar liquid-heating collectors to heat storage tanks. Final report  

DOE Green Energy (OSTI)

A study was made of the methods available to transfer heat from the collector to the water storage tank in water heating systems. In counterflow heat exchangers used in double loop water heating systems, it was found to be more important to use a high water flowrate than a high heat transfer fluid flowrate. It was earlier thought to be best to have matched WC/sub p/ (mass flowrate-specific heat) products in the loops. It was shown in this study that the water WC/sub p/ product should be about twice as large as that of the heat transfer fluid. It was found that neither the heat exchanger type nor the size was very critical, so that very simple criteria were adequate in determining optimum heat exchanger size. It was found that there is a definite system size below which one should use a traced tank or a coil in a tank. Equations and optimization criteria were developed for traced tanks or tanks with coils. At present, there is no quantitative understanding of liquid to liquid (direct contact) heat exchangers, though they are clearly quite effective. Draindown systems are discussed, and several appendices are included on heat transfer and other characteristics of fluid and of equipment.

Horel, J. D.; de Winter, F.

1978-04-20T23:59:59.000Z

391

A Value of Information approach to data quality objectives for the Hanford high-level waste tanks  

SciTech Connect

This report summarizes a Pacific Northwest Laboratory review of the organic-nitrate reaction safety issue in the Hanford single-shell tanks. This study employed a decision analytic method known as Value of Information (VOI). VOI analysis is a special form of decision analysis that has an information collection alternative as one of the initial decision choices. This type of decision analysis, therefore results in the ability to specify the preferred information collection alternative, taking into account all information gathering and other relevant alternatives. For example, the risk reduction benefit associated with further sampling to quantify total organic carbon inventory or to improve information on energetics can be compared to the risk reduction benefit of better temperature monitoring, operational restrictions, or mitigation by moisture control. This approach allows freedom from built-in assumptions, e.g., that all tanks must be sampled to some degree or that all tanks must be deemed intrinsically safe by some means or another. It allows for each tank management decision to be judged in terms of risk reduction from the current state of affairs, and for that state of affairs to be continuously updated to incorporate new information on tank contents, the phenomenology of safety issues, or the effectiveness of mitigation schemes.

Wood, T.W.; Hunter, V.L. [Pacific Northwest Lab., Richland, WA (United States); Ulvila, J.W. [Decision Science Associates (United States)

1995-02-01T23:59:59.000Z

392

Overview of Hanford Single Shell Tank (SST) Structural Integrity - 14023  

Science Conference Proceedings (OSTI)

To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford Single-Shell Tanks. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS. The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford Single-Shell Tanks has concluded that the tanks are structurally sound and meet current industry standards. Analysis of the remaining Hanford Single-Shell Tanks is scheduled for FY2014. Hanford Single-Shell Tanks are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than ? 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.

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

2013-11-14T23:59:59.000Z

393

Flame Arrester Evaluation for E-Diesel Fuel Tanks: September 3, 2002 - May 28, 2003  

DOE Green Energy (OSTI)

An evaluation of various flame arresters for use with E-Diesel fuel was conducted on four diesel fuel tanks selected to represent typical fuel tank and fill neck designs. Multiple flame arresters were tested on each fuel tank.

Weyandt, N.; Janssens, M. L.

2003-06-01T23:59:59.000Z

394

Gas generation from Tank 241-SY-103 waste  

DOE Green Energy (OSTI)

This report summarizes progress made in evaluating mechanisms by which flammable gases are generated in Hanford double-shell tank wastes, based on the results of laboratory tests using actual waste from Tank 241-SY-103. The objective of this work is to establish the identity and stoichiometry of degradation products formed in actual tank wastes by thermal and radiolytic processes as a function of temperature. The focus of the gas generation tests on Tank 241-SY-103 samples is first the effect of temperature on gas generation (volume and composition). Secondly, gas generation from irradiation of Tank 241-SY-103 samples at the corresponding temperatures as the thermal-only treatments will be measured in the presence of an external radiation source (using a {sup 137}Cs capsule). The organic content will be measured on a representative sample prior to gas generation experiments and again at the termination of heating and irradiation. The gas generation will be related to the extent of organic species consumption during heating. Described in this report are experimental methods used for producing and measuring gases generated at various temperatures from highly radioactive actual tank waste, and results of gas generation from Tank 241-SY-103 waste taken from its convective layer. The accurate measurement of gas generation rates from actual waste from highly radioactive waste tanks is needed to assess the potential for producing and storing flammable gases within the waste tanks. This report addresses the gas generation capacity of the waste from the convective layer of Tank 241-SY-103, a waste tank listed on the Flammable Gas Watch List due to its potential for flammable gas accumulation above the flammability limit.

Bryan, S.A.; King, C.M.; Pederson, L.R.; Forbes, S.V.; Sell, R.L.

1996-04-01T23:59:59.000Z

395

Hanford waste tanks - light at the end of the tunnel  

DOE Green Energy (OSTI)

The U.S. Department of Energy (DOE) faced several problems in its Hanford Site tank farms in the early nineties. It had 177 waste tanks, ranging in size from 55,000 to 1,100,000 gallons, which contained more than 55 million gallons of liquid and solid high-level radioactive waste (HLW) from a variety of processes. Unfortunately, waste transfer records were incomplete. Chemical reactions going on in the tanks were not totally understood. Every tank had high concentrations of powerful oxidizers in the form of nitrates and nitrites, and some tanks had relatively high concentrations of potential fuels that could react explosively with oxidizers. A few of these tanks periodically released large quantities of hydrogen and nitrous oxide, a mixture that was potentially more explosive than hydrogen and air. Both the nitrate/fuel and hydrogen/nitrous oxide reactions had the potential to rupture a tank exposing workers and the general public to unacceptably large quantities of radioactive material. One tank (241-C-106) was generating so much heat that water had to be added regularly to avoid thermal damage to the tank's concrete exterior shell. The tanks contained more than 250 million Curies of radioactivity. Some of that radioactivity was in the form of fissile plutonium, which represented a potential criticality problem. As awareness of the potential hazards grew, the public and various regulatory agencies brought increasing pressure on DOE to quantify the hazards and mitigate any that were found to be outside accepted risk guidelines. In 1990, then Representative, now Senator Ron Wyden (D-Oregon), introduced an amendment to Public Law 101-510, Section 3137, that required DOE to identify Hanford tanks that might have a serious potential for release of high-level waste.

POPPITI, J.A.

1999-09-29T23:59:59.000Z

396

A summary description of the flammable gas tank safety program  

DOE Green Energy (OSTI)

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

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

1994-10-01T23:59:59.000Z

397

Modifications to, and Vibration Analysis of Tank 7 Slurry Pumps, F Tank Farm  

SciTech Connect

Slurry pumps have demonstrated short life spans when operated in nuclear waste tanks. Their life approximates one thousand hours or approximately 42 days of continuous operation, evidenced by past performance in H-Area and F-Area at the Savannah River Site (SRS). Several investigations over the past six years have isolated the most significant reliability problems. These problems are seal and bearing failures caused by the vibrations of the long drive shafts in the pump, manufacturing tolerance accumulations, failures caused by material incompatibility between the waste and the lowest process bearing that is exposed to the waste, and vibrations which occur when the pump operates at critical speeds. Only vibration and material problems were corrected. Potential bearing and seal degradation still exists for those pumps with a critical speed near the operating speed. Bearing damage can be expected below 700 rpm. The pumps are used to mix or slurry nuclear waste products contained in waste storage tanks prior to transferring the tank contents for further processing. In particular, Lawrence Pumps, Inc. slurry pumps are installed on Tank 7 in F Tank Farm. Appendix A provides the initial recommendations, and further states that this follow up report would provide detailed descriptions of the pump components, failure mechanisms, and corrective actions which include tilt pad bearings, a Stellite process bearing, and modified split shaft retainers. By testing the pumps in a non-radioactive test facility, these corrections have been shown to significantly decrease the vibrations associated with bearing and seal failures, and consequently are expected to improve reliability.

Lieshear, R.A.

2002-05-10T23:59:59.000Z

398

Initial parametric study of the flammability of plume releases in Hanford waste tanks  

SciTech Connect

This study comprised systematic analyses of waste tank headspace flammability following a plume-type of gas release from the waste. First, critical parameters affecting plume flammability were selected, evaluated, and refined. As part of the evaluation the effect of ventilation (breathing) air inflow on the convective flow field inside the tank headspace was assessed, and the magnitude of the so-called {open_quotes}numerical diffusion{close_quotes} on numerical simulation accuracy was investigated. Both issues were concluded to be negligible influences on predicted flammable gas concentrations in the tank headspace. Previous validation of the TEMPEST code against experimental data is also discussed, with calculated results in good agreements with experimental data. Twelve plume release simulations were then run, using release volumes and flow rates that were thought to cover the range of actual release volumes and rates. The results indicate that most plume-type releases remain flammable only during the actual release ends. Only for very large releases representing a significant fraction of the volume necessary to make the entire mixed headspace flammable (many thousands of cubic feet) can flammable concentrations persist for several hours after the release ends. However, as in the smaller plumes, only a fraction of the total release volume is flammable at any one time. The transient evolution of several plume sizes is illustrated in a number of color contour plots that provide insight into plume mixing behavior.

Antoniak, Z.I.; Recknagle, K.P.

1997-08-01T23:59:59.000Z

399

Property:Wavemaking Description | Open Energy Information  

Open Energy Info (EERE)

Description Description Jump to: navigation, search Property Name Wavemaking Description Property Type Text Pages using the property "Wavemaking Description" Showing 25 pages using this property. (previous 25) (next 25) A Alden Large Flume + Wave generators not yet designed Alden Small Flume + Period adjustable electronically, height adjustable mechanically Alden Wave Basin + Period adjustable electronically, height adjustable mechanically C Carderock Maneuvering & Seakeeping Basin + Irregular waves with a spectrum resembling typical ocean wave patterns with appropriate scale reductions. Carderock Tow Tank 2 + Irregular waves with a spectrum resembling typical ocean wave patterns with appropriate scale reductions Carderock Tow Tank 3 + Irregular waves with a spectrum resembling typical ocean wave patterns with appropriate scale reductions.

400

Numerical simulation of cloud droplet formation in a tank  

Science Conference Proceedings (OSTI)

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

Matthias Schtze; Frank Stratmann

2008-09-01T23:59:59.000Z

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


401

ECOSYSTEM COMPONENT CHARACTERIZATION 461 Failing or nearby septic tank systems  

E-Print Network (OSTI)

or natural environment Leaks from underground storage tanks and pipes are a common source of soil.g., petroleum refineries. Pipes that are plugged or collapsed, as well as leaking storage tanks, may cause: · Sanitary wastewater sources: ­ Raw sanitary wastewater from improper sewerage connections, exfiltration

Pitt, Robert E.

402

Bulk heating cleans paraffinic bottoms from crude tanks  

SciTech Connect

It is often challenging to remove from service crude oil tanks that have been in use for many years. Bulk heating, as opposed to localized heating, has been used to successfully liquefy heavy paraffinic or asphaltic bases in crude oil tanks. The process provides economical product recovery, while minimizing waste production and reducing human exposure to hazardous working conditions. Statia Terminals Point Tupper Inc., Point Tupper, N.S., used bulk heating to remove 2 ft of weathered, paraffinic tank bottoms from six 450,000 bbl tanks that held Cabinda crude from West Africa. Immersion tube heaters were installed through the tank manholes and a diluent was added. Two 10-million BTU/hr propane burners supplied heat, and tank mixers operated continuously to aid in heat transfer. The tank contents were heated to 135 F and the temperature was held constant for 3 days. The resulting hot liquid was a pumpable and recoverable product. About 10 days were required to clean each tank. The paper describes the heating and cleaning operation as well as the economics of the Statia project.

Badrock, J. (Cooperheat Inc., Houston, TX (United States)); Coutu, R. (Cooperheat Inc., Mississauga, Ontario (Canada)); Johnson, N. (Statia Terminals N.V. St. Eustatius (Netherlands)); Martin, A. (Chicago Bridge and Iron Co., Oak Brook, IL (United States))

1995-02-20T23:59:59.000Z

403

ANFIS based sensor fault detection for continuous stirred tank reactor  

Science Conference Proceedings (OSTI)

In this paper, an Adaptive Neuro-Fuzzy Inference System (ANFIS) based Sensor fault detection and isolation for Continuous Stirred Tank Reactor (CSTR) is proposed. CSTR is a highly nonlinear process exhibiting stable and unstable steady state at different ... Keywords: ANFIS observer, Continuous stirred tank reactor, Dedicated observer, Fault detection

U. Sabura Banu; G. Uma

2011-03-01T23:59:59.000Z

404

Hanford Waste Tank Bump Accident and Consequence Analysis  

Science Conference Proceedings (OSTI)

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

BRATZEL, D.R.

2000-06-20T23:59:59.000Z

405

Tanks Focus Area Site Needs Assessment FY 2000  

SciTech Connect

This document summarizes the Tanks Focus Area (TFA's) process of collecting, analyzing, and responding to high-level radioactive tank waste science and technology needs developed from across the DOE complex in FY 2000. The document also summarizes each science and technology need, and provides an initial prioritization of TFA's projected work scope for FY 2001 and FY 2002.

Allen, Robert W.

2000-03-10T23:59:59.000Z

406

Effect of water storage tanks design in solar combisystems efficiency  

Science Conference Proceedings (OSTI)

One of the key components of a solar combisystem is the heat store. In the international literature the matter of storage necessity for solar systems is well justified. We build an experimental system assisted by a stratified storage tank and we estimate ... Keywords: fractional savings, storage tank, stratification

Nikolaos Taoussanidis

2007-05-01T23:59:59.000Z

407

Permanent Closure of the TAN-664 Underground Storage Tank  

SciTech Connect

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

Bradley K. Griffith

2011-12-01T23:59:59.000Z

408

Caustic Leaching of Hanford Tank S-110 Sludge  

SciTech Connect

This report describes the Hanford Tank S-110 sludge caustic leaching test conducted in FY 2001 at the Pacific Northwest National Laboratory. The data presented here can be used to develop the baseline and alternative flowsheets for pretreating Hanford tank sludge. The U.S. Department of Energy funded the work through the Efficient Separations and Processing Crosscutting Program (ESP; EM?50).

Lumetta, Gregg J.; Carson, Katharine J.; Darnell, Lori P.; Greenwood, Lawrence R.; Hoopes, Francis V.; Sell, Richard L.; Sinkov, Sergey I.; Soderquist, Chuck Z.; Urie, Michael W.; Wagner, John J.

2001-10-31T23:59:59.000Z

409

Mineral formation during simulated leaks of Hanford waste tanks  

E-Print Network (OSTI)

Mineral formation during simulated leaks of Hanford waste tanks Youjun Deng a , James B. Harsh a at the US DOE Hanford Site, Washington, caus- ing mineral dissolution and re-precipitation upon contact mimicking tank leak conditions at the US DOE Hanford Site. In batch experiments, Si-rich solutions

Flury, Markus

410

General requirements for RCRA regulated hazardous waste tanks  

Science Conference Proceedings (OSTI)

The Resource Conservation and Recovery Act (RCRA), as amended, requires that tanks used for the storage or treatment of hazardous waste (HazW) be permitted, and comply with the requirements contained within the Code of Federal Regulations (CFR) TItle 40 in Subpart J of Part 264/265, unless those tanks have been exempted. Subpart J specifies requirements for the design, construction, installation, operation, inspection, maintenance, repair, release, response, and closure of HazW tanks. Also, the regulations make a distinction between new and existing tanks. Effective December 6, 1995, standards for controlling volatile organic air emissions will apply to non-exempt HazW tanks. HazW tanks will have to be equipped with a cover or floating roof, or be designed to operate as a closed system, to be in compliance with the air emission control requirements. This information brief describes those tanks that are subject to the Subpart J requirements, and will also discuss secondary containment, inspection, restrictions on waste storage, release response, and closure requirements associated with regulated HazW tanks.

NONE

1995-11-01T23:59:59.000Z

411

Technical Baseline Summary Description for the Tank Farm Contractor  

Science Conference Proceedings (OSTI)

This document is a revision of the document titled above, summarizing the technical baseline of the Tank Farm Contractor. It is one of several documents prepared by CH2M HILL Hanford Group, Inc. to support the U.S. Department of Energy Office of River Protection Tank Waste Retrieval and Disposal Mission at Hanford.

TEDESCHI, A.R.

2000-04-21T23:59:59.000Z

412

Sludge mobilization with submerged nozzles in horizontal cylindrical tanks  

SciTech Connect

The Melton Valley Storage Tanks (MVSTs) and the evaporator service tanks at the Oak Ridge National Laboratory (ORNL) are used for the collection and storage of liquid low-level waste (LLLW). Wastes collected in these tanks are typically acidic when generated and are neutralized with sodium hydroxide to protect the tanks from corrosion; however, the high pH of the solution causes the formation of insoluble compounds that precipitate. These precipitates formed a sludge layer approximately 0.6 to 1.2 m (2 to 4 ft) deep in the bottom of the tanks. The sludge in the MVSTs and the evaporator service tanks will eventually need to be removed from the tanks and treated for final disposal or transferred to another storage facility. The primary options for removing the sludge include single-point sluicing, use of a floating pump, robotic sluicing, and submerged-nozzle sluicing. The objectives of this study were to (1) evaluate the feasibility of submerged-nozzle sluicing in horizontal cylindrical tanks and (2) obtain experimental data to validate the TEMPEST (time-dependent, energy, momentun, pressure, equation solution in three dimensions) computer code.

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

1995-10-01T23:59:59.000Z

413

Study of large tank barges and solicitation of information  

SciTech Connect

The US Coast Guard (USCG) solicits information on the operation of tank barges of 20,000 dwt or more which carry crude oil and of 30,000 dwt or more which carry oil products; and on certain operations at terminals serving large tank barges, to determine the causes of air pollution from these barges. Also of particular interest are data on the number and size of tank barges of over 20,000 and over 30,000 dwt now on order or planned for construction for the carriage of crude oil and products; the impact of crude oil washing (COW) on the terminal facilities used by large tank barges; the feasibility of COW or inert gas system on these barges; the amount of ballast required for sea-keeping on tank barges of 20,000 dwt and over; the probable effect that a standard requiring all oily ballast, tank washings, or cargo residues to be retained on board for discharge to reception/treatment facilities would have on the operation of those barges which ballast cargo tanks or conduct tank washing at sea; and other related information. USCG must be provided with notice of forthcoming information by 10/1/80.

1980-08-07T23:59:59.000Z

414

Safety criteria for organic watch list tanks at the Hanford Site  

SciTech Connect

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.

Meacham, J.E., Westinghouse Hanford

1996-08-01T23:59:59.000Z

415

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

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

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

416

Microsoft PowerPoint - S05-02_Rinker_Single Shell Tank Structural...  

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

on Hanford Single Shell Waste Tanks EM Waste Processing Technical Exchange Waste Storage and Tank Inspection Mike Rinker Pacific Northwest National Laboratory November 17, 2010 1...

417

SRS Tank 48H Waste Treatment Project Technology Readiness Assessment  

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

Savannah River Site Tank 48H Savannah River Site Tank 48H Waste Treatment Project Technology Readiness Assessment Harry D. Harmon Joan B. Berkowitz John C. DeVine, Jr. Herbert G. Sutter Joan K. Young SPD-07-195 July 31, 2007 Prepared by the U.S. Department of Energy Aiken, South Carolina SRS Tank 48H Waste Treatment Project SPD-07-195 Technology Readiness Assessment July 31, 2007 Signature Page 7/31/07 ___________________________ _________________________ John C. DeVine, Jr., Team Member Date SRS Tank 48H Waste Treatment Project SPD-07-195 Technology Readiness Assessment July 31, 2007 Executive Summary The purpose of this assessment was to determine the technology maturity level of the candidate Tank 48H treatment technologies that are being considered for implementation at DOE's

418

Idaho Nuclear Technology and Engineering Center Tank Farm Facility |  

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

Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility Idaho Nuclear Technology and Engineering Center Tank Farm Facility The Secretary of Energy signed Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 basis of determination for the disposal of grouted residual waste in the tank systems at the Idaho Nuclear Technology and Engineering Center (INTEC) Tank Farm Facility (TFF) on November 19, 2006. Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set

419

Retooling Michigan: Tanks to Turbines | Department of Energy  

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

Tanks to Turbines Tanks to Turbines Retooling Michigan: Tanks to Turbines June 8, 2010 - 6:13pm Addthis Joshua DeLung Editor's Note: This story was updated Oct. 13, 2010, to reflect the additional equipment purchases, manufacturing goals and customer additions for Loc Performance Products. Tanks strike fear in enemies during battle, and for good reason - the 120-mm main gun of an M1 Abrams tank is both deafening and destructive. Now a company that has manufactured geared systems for those mobile weapons for more than 20 years is part of the forces working toward energy security and independence. Weapons of mass production In southern Michigan, Loc Performance Products is retooling space in its existing factory in Plymouth, where it builds gears and gearboxes -which provide rotating force from gears to move vehicles - for the U.S.

420

Fuel Cell Technologies Office: Onboard Storage Tank Workshop  

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

Onboard Storage Tank Workshop Onboard Storage Tank Workshop The U.S. Department of Energy (DOE) and Sandia National Laboratories co-hosted the Onboard Storage Tank Workshop on April 29th, 2010. Onboard storage tank experts gathered to share lessons learned about research and development (R&D) needs; regulations, codes and standards (RCS); and a path forward to enable the successful deployment of hydrogen storage tanks in early market