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1

EA-1044: Melton Valley Storage Tanks Capacity Increase Project- Oak Ridge  

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

44: Melton Valley Storage Tanks Capacity Increase Project- Oak 44: Melton Valley Storage Tanks Capacity Increase Project- Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1044: Melton Valley Storage Tanks Capacity Increase Project- Oak Ridge National Laboratory, Oak Ridge, Tennessee SUMMARY This EA evaluates the environmental impacts of the proposal to construct and maintain additional storage capacity at the U.S. Department of Energy's Oak Ridge National Laboratory, Oak Ridge, Tennessee, for liquid low-level radioactive waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD May 25, 1995 EA-1044: Finding of No Significant Impact Melton Valley Storage Tanks Capacity Increase Project- Oak Ridge National Laboratory, Oak Ridge, Tennessee May 25, 1995 EA-1044: Final Environmental Assessment

2

Increasing State Capacity Through Clans  

E-Print Network (OSTI)

their role in increasing state capacity With the decline ofhere focus on state capacity and the associated discussionselements of state capacity during the transition from one

Doyle, Jr, Thomas Martin

2009-01-01T23:59:59.000Z

3

Increasing water holding capacity for irrigation  

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

Increasing water holding capacity for irrigation Reseachers recommend solutions for sediment trapping in irrigation system LANL and SNL leveraged technical expertise to determine...

4

EPRI Increased Transmission Capacity Workshop Proceedings  

Science Conference Proceedings (OSTI)

This report documents the proceedings of EPRI's Increased Overhead Transmission Capacity Workshop. The workshop was held on September 20, 2011 at the offices of the American Transmission Company in Waukesha, Wisconsin. Participants included members of the EPRI Increased Overhead Transmission Capacity Task Force. The workshop was a joint effort of two EPRI research projects: (1) Increased Power Flow Guidebook and Ratings for Overhead Lines, and (2) Impact of High Temperature Operation on Conductor Systems...

2011-11-30T23:59:59.000Z

5

Changing World Product Markets and Potential Refining Capacity Increases  

Reports and Publications (EIA)

The presentation explores potential refinery capacity increases over the next 5 years in various world regions, based on changing demand patterns, changing price incentives, and capacity expansion announcements.

Information Center

2006-03-20T23:59:59.000Z

6

When does noise increase the quantum capacity?  

E-Print Network (OSTI)

Superactivation is the property that two channels with zero quantum capacity can be used together to yield positive capacity. Here we demonstrate that this effect exists for a wide class of inequivalent channels, none of which can simulate each other. We also consider the case where one of two zero capacity channels are applied, but the sender is ignorant of which one is applied. We find examples where the greater the entropy of mixing of the channels, the greater the lower bound for the capacity. Finally, we show that the effect of superactivation is rather generic by providing example of superactivation using the depolarizing channel.

Fernando G. S. L. Brando; Jonathan Oppenheim; Sergii Strelchuk

2011-07-21T23:59:59.000Z

7

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

8

Cesium uptake capacity of simulated ferrocyanide tank waste. Interim report FY 1994, Ferrocyanide Safety Project  

Science Conference Proceedings (OSTI)

The objective of this project is to determine the capacity for {sup 137}CS uptake by mixed metal ferrocyanides present in Hanford waste tanks, and to assess the potential for aggregation of these {sup 137}CS exchanged materials to form tank ``hot-spots.`` This research, performed at the Pacific Northwest Laboratory (PNL) for the Westinghouse Hanford Company (WHC), stems from concerns of possible localized radiolytic heating within the tanks. If radioactive cesium is exchanged and concentrated by the remaining nickel ferrocyanide present in the tanks, this heating could cause temperatures to rise above the safety limits specified for the ferrocyanide tanks. For the purposes of this study, two simulants, In-Farm-2 and U-Plant-2, were chosen to represent the wastes generated by the scavenging processes. These simulants were formulated using protocols from the original cesium scavenging campaign. Later additions of cesium-rich wastes from various processes also were considered. The simulants were prepared and centrifuged to obtain a moist ferrocyanide sludge. The centrifuged sludges were treated with the original supernate spiked with a known amount of cesium nitrate. After analysis by flame atomic absorption spectrometry, distribution coefficients (K{sub d}) were calculated. The capacity of solid waste simulants to exchange radioactive cesium from solution was examined. Initial results showed that the greater the molar ratio of cesium to cesium nickel ferrocyanide, the less effective the exchange of cesium from solution. The theoretical capacity of 2 mol cesium per mol of nickel ferrocyanide was not observed. The maximum capacity under experimental conditions was 0.35 mol cesium per mol nickel ferrocyanide. Future work on this project will examine the layering tendency of the cesium nickel ferrocyanide species.

Burgeson, I.E.; Bryan, S.A.; Burger, L.E.

1994-09-01T23:59:59.000Z

9

Increasing Capacity of an Isolated Merge by Metering its On-Ramp  

E-Print Network (OSTI)

Increasing Capacity of an Isolated Merge by Metering its On-and thereby increase merge capacity. Detailed observationscan favorably affect the capacity of an isolated merge. The

Cassidy, Michael J.; Rudjanakanoknad, Jittichai

2004-01-01T23:59:59.000Z

10

Guide for Increasing the Capacity of Induction Motors  

Science Conference Proceedings (OSTI)

In 2002, as a result of re-licensing, nearly 700 MW of U.S. nuclear power capacity was added in 13 uprate programs. Over the past two years, similar re-licensing efforts have resulted in 33 uprates, which have increased nuclear capacity by over 1,700 MW. With this re-licensing and uprating of nuclear power plants, there is seen an accompanying need to increase the output of some of the major auxiliary motors. With the special motors used in nuclear power plants, some of which have flywheels and some of w...

2004-12-20T23:59:59.000Z

11

Method of increasing the sulfation capacity of alkaline earth sorbents  

DOE Patents (OSTI)

A system and method for increasing the sulfation capacity of alkaline earth carbonates to scrub sulfur dioxide produced during the fluidized bed combustion of coal in which partially sulfated alkaline earth carbonates are hydrated in a fluidized bed to crack the sulfate coating and convert the alkaline earth oxide to the hydroxide. Subsequent dehydration of the sulfate-hydroxide to a sulfate-oxide particle produces particles having larger pore size, increased porosity, decreased grain size and additional sulfation capacity. A continuous process is disclosed.

Shearer, J.A.; Turner, C.B.; Johnson, I.

1980-03-13T23:59:59.000Z

12

Method of increasing the sulfation capacity of alkaline earth sorbents  

DOE Patents (OSTI)

A system and method for increasing the sulfation capacity of alkaline earth carbonates to scrub sulfur dioxide produced during the fluidized bed combustion of coal in which partially sulfated alkaline earth carbonates are hydrated in a fluidized bed to crack the sulfate coating and convert the alkaline earth oxide to the hydroxide. Subsequent dehydration of the sulfate-hydroxide to a sulfate-oxide particle produces particles having larger pore size, increased porosity, decreased grain size and additional sulfation capacity. A continuous process is disclosed.

Shearer, John A. (Chicago, IL); Turner, Clarence B. (Shorewood, IL); Johnson, Irving (Clarendon Hills, IL)

1982-01-01T23:59:59.000Z

13

Increasing NOAA's computational capacity to improve global forecast modeling  

E-Print Network (OSTI)

1 Increasing NOAA's computational capacity to improve global forecast modeling A NOAA of the NWS's forecast products, even its regional forecast products, are constrained by the limitations of NOAA's global forecast model. Unfortunately, our global forecasts are less accurate than those from

Hamill, Tom

14

Multimodal Traffic at Isolated Signalized Intersections: New Management Strategies to Increase Capacity  

E-Print Network (OSTI)

Effect of bicycles on capacity of signalized intersections.can produce significant capacity gains in complicated, real-Strategies to Increase Capacity Yiguang Xuan, Vikash Gayah,

Xuan, Yiguang; Gayah, Vikash; Daganzo, Carlos; Cassidy, Michael

2009-01-01T23:59:59.000Z

15

The use of filtered bags to increase waste payload capacity  

DOE Green Energy (OSTI)

For the past few years, the Department of Energy has favored the direct disposal of low plutonium content residue materials from Rocky Flats rather than engage in expensive and time consuming plutonium recovery operations. One impediment to direct disposal has been the wattage limit imposed by the Waste Isolation Pilot Plant on hydrogenous materials such as combustibles and sludges. The issue of concern is the radiolytic generation and accumulation of hydrogen and other explosive gases in waste containers. The wattage limits that existed through 1996 restricted the amount of plutonium bearing hydrogenous materials that could be packaged in a WIPP bound waste drum to only a fraction of the capacity of a drum. Typically, only about one kilogram of combustible residue could be packaged in a waste drum before the wattage limit was exceeded resulting in an excessively large number of drums to be procured, stored, shipped, and interred. The Rocky Flats Environmental Technology Site has initiated the use of filtered plastic bags (called bag-out bags) used to remove transuranic waste materials from glove box lines. The bags contain small, disk like HEPA filters which are effective in containing radioactively contaminated particulate material but allow for the diffusion of hydrogen gas. Used in conjunction with filtered 55 gallon drums, filtered bag-out bags were pursued as a means to increase the allowable wattage limits for selected residue materials. In February 1997, the Nuclear Regulatory Commission approved the use of filtered bag-out bags for transuranic waste materials destined for WIPP. The concomitant increase in wattage limits now allows for approximately four times the payload per waste drum for wattage limited materials.

Dustin, D.F.; Thorp, D.T. [Safe Sites of Colorado, Golden, CO (United States); Rivera, M.A. [Los Alamos Technical Associates, Albuquerque, NM (United States)

1998-03-03T23:59:59.000Z

16

Evaluating capacity and expansion opportunities at tank farm: a decision support system using discrete event simulation  

Science Conference Proceedings (OSTI)

This paper presents a discrete event simulation based Decision Support System to evaluate tank farm operations. The Decision Support System was developed in order to reduce capital expenditures and assist in decision making for assessing the impact of ...

Bikram Sharda; Adriana Vazquez

2009-12-01T23:59:59.000Z

17

Does More international transmission capacity increase competition in the Belgian electricity market?  

SciTech Connect

From a national market perspective, taking transmission capacity into account reduces current concentration measures, although they remain fairly high even after substantial capacity increases. From an international perspective, a more efficient use of current transmission capacity by coupling regional markets can increase competition. That suggests it may not be appropriate to assess market concentration using national market shares. (author)

Kuepper, Gerd; Delarue, Erik; Delvaux, Bram; Meeus, Leonardo; Bekaert, David; Willems, Bert; Proost, Stef; D'haeseleer, William; Deketelaere, Kurt; Belmans, Ronnie

2009-01-15T23:59:59.000Z

18

Increasing wind capacity requires new approaches to electricity ...  

U.S. Energy Information Administration (EIA)

Electric power generation from wind is increasing rapidly in the United States. Wind power is attractive for its lack of emissions and low operating costs, but its ...

19

Uprates can increase U.S. nuclear capacity substantially without ...  

U.S. Energy Information Administration (EIA)

The electrical output of the nuclear power plant fleet can be increased either by constructing new plants or by 'uprating' operating plants.

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 "tanks capacity increase" 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

FAQs about Storage Capacity  

Gasoline and Diesel Fuel Update (EIA)

about Storage Capacity about Storage Capacity How do I determine if my tanks are in operation or idle or non-reportable? Refer to the following flowchart. Should idle capacity be included with working capacity? No, only report working capacity of tanks and caverns in operation, but not for idle tanks and caverns. Should working capacity match net available shell in operation/total net available shell capacity? Working capacity should be less than net available shell capacity because working capacity excludes contingency space and tank bottoms. What is the difference between net available shell capacity in operation and total net available shell capacity? Net available shell capacity in operation excludes capacity of idle tanks and caverns. What do you mean by transshipment tanks?

22

AvAilAble for licensing Increased battery capacity, safety, stability and reliability at lower cost.  

E-Print Network (OSTI)

cost. The Invention A composite material suitable for use in an anode for a lithium-ion battery and reliability; Lowers battery cost; and Could exceed the technical specifications for electrified vehicles AvAilAble for licensing Increased battery capacity, safety, stability and reliability at lower

Kemner, Ken

23

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

Science Conference Proceedings (OSTI)

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

TC MACKEY; FG ABATT; MW RINKER

2009-01-14T23:59:59.000Z

24

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

DOE Green Energy (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

25

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

Science Conference Proceedings (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

26

Increasing the capacity of the Tory II-C Side Support System  

SciTech Connect

The Tory II-C lateral suspension has been designed for 4 g`s of lateral acceleration of the duct. Calculations and model tests indicate that this requirement has been met or exceeded. In order to have a more realistic model to test, Tory II-C springs are going to be fitted around the full scale core slice which was previously built up. Instrumented accelerations of this assembly should give the most direct demonstration that is possible of the response of the system to flight. This memorandum discusses, knowing the capabilities of the present system, the design changes necessary to suit different maximum accelerations by increasing the capacity of the Tory II-C side support system.

Platt, E. A.; Smiley, P.

1963-07-17T23:59:59.000Z

27

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

Science Conference Proceedings (OSTI)

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

MACKEY TC; ABBOTT FG; CARPENTER BG; RINKER MW

2007-02-16T23:59:59.000Z

28

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

29

Today in Energy - Uprates can increase U.S. nuclear capacity ...  

U.S. Energy Information Administration (EIA)

Energy Information Administration ... Financial market analysis and financial data for major energy companies ... Stretch uprates increase electrical output by 3% to ...

30

A simulation study to increase the capacity of a rusk production line  

Science Conference Proceedings (OSTI)

This study was conducted in a food processing company on its Rusk production line. The goal of the study was to increase the production rate of the line to meet the continuously increasing demand on its product within the existing limited space in the ... Keywords: business process reengineering, food processing, production planning, productivity, simulation models

Seraj Yousef Abed

2008-09-01T23:59:59.000Z

31

Working and Net Available Shell Storage Capacity  

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

and tank farms. Excludes storage capacity of refineries, fuel ethanol plants, and pipelines. 2 Percent exclusive use is that portion of capacity in operation that is for the...

32

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...

33

Precoding by Pairing Subchannels to Increase MIMO Capacity With Discrete Input Alphabets  

E-Print Network (OSTI)

AbstractWe consider Gaussian multiple-input multiple-output (MIMO) channels with discrete input alphabets. We propose a nondiagonal precoder based on the X-Codes in [1] to increase the mutual information. The MIMO channel is transformed into a set of parallel subchannels using singular value decomposition (SVD) and X-Codes are then used to pair the subchannels. X-Codes are fully characterized by the pairings and a 2 2 2 real rotation matrix for each pair (parameterized with a single angle). This precoding structure enables us to express the total mutual information as a sum of the mutual information of all the pairs. The problem of finding the optimal precoder with the above structure, which maximizes the total mutual information, is solved by: i) optimizing the rotation angle and the power allocation within each pair and ii) finding the optimal pairing and power allocation among the pairs. It is shown that the mutual information achieved with the proposed pairing scheme is very close to that achieved with the optimal precoder by Cruz et al., and is significantly better than Mercury/waterfilling strategy by Lozano et al. Our approach greatly simplifies both the precoder optimization and the detection complexity, making it suitable for practical applications. Index TermsCondition number, multiple-input multiple-output (MIMO), mutual information, orthogonal frequency division multiplexing (OFDM), precoding, singular value decomposition (SVD). I.

Saif Khan Mohammed; Emanuele Viterbo; Yi Hong; Senior Member; Ananthanarayanan Chockalingam; Senior Member

2010-01-01T23:59:59.000Z

34

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

35

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

36

Gulf Coast (PADD 3) Shell Storage Capacity at Operable Refineries  

U.S. Energy Information Administration (EIA)

Propane/Propylene: 4,376: 3,520: 3,565-----1982-2013: ... Notes: Shell storage capacity is the design capacity of the tank. See Definitions, Sources, ...

37

Working and Net Available Shell Storage Capacity as of ...  

U.S. Energy Information Administration (EIA)

Revision to Working and Net Available Shell Storage Capacity as of September 30, 2010 . Crude oil storage capacity data at tank farms reported for PAD District 2 and ...

38

RELATIONSHIP BETWEEN FLOWABILITY AND TANK CLOSURE GROUT QUALITY  

Science Conference Proceedings (OSTI)

After completion of waste removal and chemical cleaning operations, Tanks 5-F and 6-F await final closure. The project will proceed with completing operational closure by stabilizing the tanks with grout. Savannah River Remediations (SRR) experience with grouting Tanks 18-F and 19-F showed that slump-flow values were correlated with flow/spread inside these tanks. Less mounding was observed when using grouts with higher slump-flow. Therefore, SRNL was requested to evaluate the relationship between flowability and cured properties to determine whether the slump-flow maximum spread of Mix LP#8-16 could be increased from 28 inches to 30 inches without impacting the grout quality. A request was also made to evaluate increasing the drop height from 5 feet to 10 feet with the objective of enhancing the flow inside the tank by imparting more kinetic energy to the placement. Based on a review of the grout property data for Mix LP#8-16 collected from Tank 18-F and 19-F quality control samples, the upper limit for slump-flow measured per ASTM C 1611 can be increased from 28 to 30 inches without affecting grout quality. However, testing should be performed prior to increasing the drop height from 5 to 10 feet or observations should be made during initial filling operations to determine whether segregation occurs as a function of drop heights between 5 and 10 feet. Segregation will negatively impact grout quality. Additionally, increasing the delivery rate of grout into Tanks 5-F and 6-F by using a higher capacity concrete/grout pump will result in better grout spread/flow inside the tanks.

Langton, C.; Stefanko, D.; Hay, M.

2012-10-08T23:59:59.000Z

39

Relationship Between Flowability And Tank Closure Grout Quality  

SciTech Connect

After completion of waste removal and chemical cleaning operations, Tanks 5-F and 6-F await final closure. The project will proceed with completing operational closure by stabilizing the tanks with grout. Savannah River Remediation's (SRR) experience with grouting Tanks 18-F and 19-F showed that slump-flow values were correlated with flow/spread inside these tanks. Less mounding was observed when using grouts with higher slump-flow. Therefore, SRNL was requested to evaluate the relationship between flowability and cured properties to determine whether the slump-flow maximum spread of Mix LP#8-16 could be increased from 28 inches to 30 inches without impacting the grout quality. A request was also made to evaluate increasing the drop height from 5 feet to 10 feet with the objective of enhancing the flow inside the tank by imparting more kinetic energy to the placement. Based on a review of the grout property data for Mix LP#8-16 collected from Tank 18-F and 19-F quality control samples, the upper limit for slump-flow measured per ASTM C 1611 can be increased from 28 to 30 inches without affecting grout quality. However, testing should be performed prior to increasing the drop height from 5 to 10 feet or observations should be made during initial filling operations to determine whether segregation occurs as a function of drop heights between 5 and 10 feet. Segregation will negatively impact grout quality. Additionally, increasing the delivery rate of grout into Tanks 5-F and 6-F by using a higher capacity concrete/grout pump will result in better grout spread/flow inside the tanks.

Langton, C. A.; Stefanko, D. B.; Hay, M. S.

2012-10-08T23:59:59.000Z

40

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

Note: This page contains sample records for the topic "tanks capacity increase" 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

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

42

Modeling and analysis of ORNL horizontal storage tank mobilization and mixing  

SciTech Connect

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

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

1994-06-01T23:59:59.000Z

43

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...

44

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

45

Working and Net Available Shell Storage Capacity as of September ...  

U.S. Energy Information Administration (EIA)

Unfortunately, meaningful storage capacity utilization rates for operators of crude oil tank farms and pipelines, or for operators of products pipelines, ...

46

Increasing State Capacity Through Clans  

E-Print Network (OSTI)

Political Institutions of Azerbaijan: A Dichotomy BetweenAffairs. Vol. 2. No. 4. Shaffer, Brenda. 2004. Azerbaijan.in Central Asia and Azerbaijan. Babak, Vladimir, Demian

Doyle, Jr, Thomas Martin

2009-01-01T23:59:59.000Z

47

Increasing State Capacity Through Clans  

E-Print Network (OSTI)

can serve to buttress weak links by becoming part of thehave direct links to the state but these links may be weak.links to the national government. The bridges may be quite strong, very weak,

Doyle, Jr, Thomas Martin

2009-01-01T23:59:59.000Z

48

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

49

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

SciTech Connect

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

Groth, B.D.

1995-01-11T23:59:59.000Z

50

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

51

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

52

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

53

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

54

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

55

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

56

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

57

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

SciTech Connect

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

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

2009-01-15T23:59:59.000Z

58

Correlation models for waste tank sludges and slurries  

SciTech Connect

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

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

1995-07-01T23:59:59.000Z

59

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

60

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

Note: This page contains sample records for the topic "tanks capacity increase" 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

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...

62

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

63

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

64

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

65

Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste  

Science Conference Proceedings (OSTI)

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of "tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization." The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would "...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028." In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP.

Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

2004-07-15T23:59:59.000Z

66

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

67

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

68

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

69

DOE, City of Richland and Benton PUD Increase Fiber Optic Telecommunication Capacity in Benton County- Upgrade improves communications at Hanford Site, schools and libraries  

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

RICHLAND, Wash. ? The Department of Energy (DOE), city of Richland, and Benton Countys Public Utility District (Benton PUD) jointly implemented a high-capacity fiber optic cable in Richland and at the Hanford Site. The project will improve communications throughout the area.

70

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

DOE Green Energy (OSTI)

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

Shadday, M.A. Jr.

1996-04-01T23:59:59.000Z

71

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

72

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

73

Thermal and Radiolytic Gas Generation Tests on Material from Tanks 241-U-103, 241-AW-101, 241-S-106, and 241-S-102: Status Report  

DOE Green Energy (OSTI)

This report summarizes progress in evaluating thermal and radiolytic flammable gas generation in actual Hanford single-shell tank wastes. The work described was conducted at Pacific Northwest National Laboratory (PNNL) for the Flammable Gas Safety Project, whose purpose is to develop information to support DE&S Hanford (DESH) and Project Management Hanford Contract (PHMC) subcontractors in their efforts to ensure the safe interim storage of wastes at the Hanford Site. This work is related to gas generation studies performed by Numatec Hanford Corporation (formerly Westinghouse Hanford Company). This report describes the results of laboratory tests of gas generation from actual convective layer wastes from Tank 241-U-103 under thermal and radiolytic conditions. Accurate measurements of gas generation rates from highly radioactive tank wastes are needed to assess the potential for producing and storing flammable gases within the tanks. The gas generation capacity of the waste in Tank 241-U-103 is a high priority for the Flammable Gas Safety Program due to its potential for accumulating gases above the flammability limit (Johnson et al, 1997). The objective of this work was to establish the composition of gaseous degradation products formed in actual tank wastes by thermal and radiolytic processes as a function of temperature. The gas generation tests on Tank 241-U-103 samples focused first on the effect of temperature on the composition and rate of gas generation Generation rates of nitrogen, nitrous oxide, methane, and hydrogen increased with temperature, and the composition of the product gas mixture varied with temperature.

King, C.M.; Bryan, S.A.

1999-06-17T23:59:59.000Z

74

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

75

Upgrade of 400,000 gallon water storage tank at Argonne National Laboratory-West to UCRL-15910 high hazard seismic requirements  

SciTech Connect

As part of the Integral Fast Reactor (IFR) Project at Argonne National Laboratory West (ANL-W), it was necessary to strengthen an existing 400,000 gallon flat-bottom water storage tank to meet UCRL-15910 (currently formulated as DOE Standard DOE-STD-1020-92, Draft) high hazard natural phenomena requirements. The tank was constructed in 1988 and preliminary calculations indicated that the existing base anchorage was insufficient to prevent buckling and potential failure during a high hazard seismic event. General design criteria, including ground motion input, load combinations, etc., were based upon the requirements of UCRL-15910 for high hazard facilities. The analysis and capacity assessment criteria were based on the Generic Implementation Procedure developed by the Seismic Qualification Utilities Group (SQUG). Upgrade modifications, consisting of increasing the size of the Generic Implementation Procedure developed by the Seismic Qualification Utilities Group (SQUG). Upgrade modifications, consisting of increasing the size of the foundation and installing additional anchor bolts and chairs, were necessary to increase the capacity of the tank anchorage/support system. The construction of the upgrades took place in 1992 while the tank remained in service to allow continued operation of the EBR-II reactor. The major phases of construction included the installation and testing of 144 1/14in. {times} 15in., and 366 1in. {times} 16in. epoxied concrete anchors, placement of 220 cubic yards of concrete heavily reinforced, and installation of 24 1-1/2in. {times} 60in. tank anchor bolts and chairs. A follow-up inspection of the tank interior by a diver was conducted to determine if the interior tank coating had been damaged by the chair welding. The project was completed on schedule and within budget.

Griffin, M.J. [EQE International, Inc., Irvine, CA (United States); Harris, B.G. [Argonne National Lab., Idaho Falls, ID (United States)

1993-10-01T23:59:59.000Z

76

Tank 48 Treatment Process  

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

77

Estimating retained gas volumes in the Hanford tanks using waste level measurements  

SciTech Connect

The Hanford site is home to 177 large, underground nuclear waste storage tanks. Safety and environmental concerns surround these tanks and their contents. One such concern is the propensity for the waste in these tanks to generate and trap flammable gases. This report focuses on understanding and improving the quality of retained gas volume estimates derived from tank waste level measurements. While direct measurements of gas volume are available for a small number of the Hanford tanks, the increasingly wide availability of tank waste level measurements provides an opportunity for less expensive (than direct gas volume measurement) assessment of gas hazard for the Hanford tanks. Retained gas in the tank waste is inferred from level measurements -- either long-term increase in the tank waste level, or fluctuations in tank waste level with atmospheric pressure changes. This report concentrates on the latter phenomena. As atmospheric pressure increases, the pressure on the gas in the tank waste increases, resulting in a level decrease (as long as the tank waste is {open_quotes}soft{close_quotes} enough). Tanks with waste levels exhibiting fluctuations inversely correlated with atmospheric pressure fluctuations were catalogued in an earlier study. Additionally, models incorporating ideal-gas law behavior and waste material properties have been proposed. These models explicitly relate the retained gas volume in the tank with the magnitude of the waste level fluctuations, dL/dP. This report describes how these models compare with the tank waste level measurements.

Whitney, P.D.; Chen, G.; Gauglitz, P.A.; Meyer, P.A.; Miller, N.E.

1997-09-01T23:59:59.000Z

78

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

79

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

80

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 ...

Note: This page contains sample records for the topic "tanks capacity increase" 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

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

Science Conference Proceedings (OSTI)

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

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

1997-09-15T23:59:59.000Z

82

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

83

GENERATING CAPACITY  

E-Print Network (OSTI)

Evidence from the U.S. and some other countries indicates that organized wholesale markets for electrical energy and operating reserves do not provide adequate incentives to stimulate the proper quantity or mix of generating capacity consistent with mandatory reliability criteria. A large part of the problem can be associated with the failure of wholesale spot market prices for energy and operating reserves to rise to high enough levels during periods when generating capacity is fully utilized. Reforms to wholesale energy markets, the introduction of well-design forward capacity markets, and symmetrical treatment of demand response and generating capacity resources to respond to market and institutional imperfections are discussed. This policy reform program is compatible with improving the efficiency of spot wholesale electricity markets, the continued evolution of competitive retail markets, and restores incentives for efficient investment in generating capacity consistent with operating reliability criteria applied by system operators. It also responds to investment disincentives that have been associated with volatility in wholesale energy prices, limited hedging opportunities and to concerns about regulatory opportunism. 1

Paul L. Joskow; Paul L. Joskow; Paul L. Joskow

2006-01-01T23:59:59.000Z

84

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

85

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

86

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

87

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

88

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

SciTech Connect

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

WASHENFELDER DJ

2008-01-22T23:59:59.000Z

89

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

90

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

91

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

SciTech Connect

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

Piepho, M.G.

1994-12-01T23:59:59.000Z

92

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

93

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

94

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

95

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

96

Retrieval of Ninth Single-Shell Tank Complete | Department of Energy  

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

Retrieval of Ninth Single-Shell Tank Complete Retrieval of Ninth Single-Shell Tank Complete Retrieval of Ninth Single-Shell Tank Complete September 6, 2012 - 12:00pm Addthis Media Contacts Lori Gamache, ORP 509-372-9130 Rob Roxburgh, WRPS 509-376-5188 Richland - Washington River Protection Solutions (WRPS) has completed the retrieval of radioactive and chemical waste from single-shell tank (SST) C-104, an underground storage tank that once held 259,000 gallons of waste left over from nuclear weapons production at Hanford. WRPS is the tank operations contractor for the U.S. Department of Energy (DOE) Office of River Protection (ORP). Tank C-104 is a 530,000-gallon-capacity SST that once contained the second-highest waste volume of the 16 SSTs in Hanford's C Farm, including a significant amount of plutonium and uranium.

97

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

98

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

99

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

100

In-Tank Precipitation (ITP) Structures Summary Report  

Science Conference Proceedings (OSTI)

This report summarized the results of structural evaluations conducted for the three high-level waste storage tanks, filtration building, and four above ground transfer lines associated with the ITP facility. The evaluations are performed to assure that demands resulting from normal operating and natural phenomena hazard loads do not exceed the structural capacities when evaluated to current criteria and the revised usage classifications.

Houston, T. [Westinghouse Savannah River Company, Aiken, SC (United States); Mertz, G.E.; Flanders, H.E.; Estochen, E.G.; Baldwin, G.R.; Rieck, P.J.; Amin, J.A.

1994-09-20T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

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

102

Capacity Markets for Electricity  

E-Print Network (OSTI)

ternative Approaches for Power Capacity Markets, Papers andand Steven Stoft, Installed Capacity and Price Caps: Oil onElectricity Markets Have a Capacity requirement? If So, How

Creti, Anna; Fabra, Natalia

2004-01-01T23:59:59.000Z

103

2. Gas Productive Capacity  

U.S. Energy Information Administration (EIA)

2. Gas Productive Capacity Gas Capacity to Meet Lower 48 States Requirements The United States has sufficient dry gas productive capacity at the wellhead to meet ...

104

Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River  

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

Retrieval of Tenth Single-shell Tank Complete at Hanford's Office Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River Protection Retrieval of Tenth Single-shell Tank Complete at Hanford's Office of River Protection December 27, 2012 - 12:00pm Addthis EM’s Office of River Protection has successfully removed waste from a tenth storage tank at the Hanford site. Located in C Farm, C-109 is one of 16 underground tanks ranging in capacity from 55,000 to 530,000 gallons. EM's Office of River Protection has successfully removed waste from a tenth storage tank at the Hanford site. Located in C Farm, C-109 is one of 16 underground tanks ranging in capacity from 55,000 to 530,000 gallons. Standing near a pipe providing access to the tank below, workers initiate a water soak aimed at loosening hard-to-remove-waste from the bottom of the underground tank known as C-109.

105

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

106

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

107

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

108

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

109

INITIAL SELECTION OF SUPPLEMENTAL TREATMENT TECHNOLOGIES FOR HANFORDS LOW ACTIVITY TANK WASTE  

SciTech Connect

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology proposed to accelerate--from 2014 to 2006--the Hanford Federal Facility Agreement and Consent Order milestone (M-62-11) associated with a final decision on the balance of tank waste that is beyond the capacity of the WTP. The DOE Office of River Protection tank farm contractor, CH2M HILL Hanford Group, Inc. (CH2M HILL), was tasked with testing and evaluating selected supplemental technologies to support final decisions on tank waste treatment. Three technologies and corresponding vendors were selected to support an initial technology selection in 2003. The three technologies were containerized grout called cast stone (Fluor Federal Services); bulk vitrification (AMEC Earth and Environmental, Inc.); and steam reforming (THOR Treatment Technologies, LLC.). The cast stone process applies an effective grout waste formulation to the LAW and places the cement-based product in a large container for solidification and disposal. Unlike the WTP LAW treatment, which applies vitrification within continuous-fed joule-heated ceramic melters, bulk vitrification produces a glass waste form using batch melting within the disposal container. Steam reforming produces a granular denitrified mineral waste form using a high-temperature fluidized bed process. An initial supplemental technology selection was completed in December 2003, enabling DOE and CH2M HILL to focus investments in 2004 on the testing and production-scale demonstrations needed to support the 2006 milestone.

RAYMOND, R.E.

2004-02-20T23:59:59.000Z

110

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

111

Gunite and Associated Tanks Waste Conditioning System: Description and Operational Summary  

SciTech Connect

The purpose of this report is to describe and document the function, operational performance, problems encountered, lessons-learned, and overall assessment of the performance of the waste conditioning system (WCS) in the Gunite{trademark} and Associated Tanks (GAAT) remediation project at the Oak Ridge National Laboratory (ORNL). The GAAT are located in the main plant area of ORNL in the North and South Tank Farms. These tanks were constructed in 1943 as part of the Manhattan Project during World War II. Each tank in the South Tank Farm (STF) has a 50-ft inside diameter and a capacity of {approx}170,000 gal. Each Gunite tank in the North Tank Farm (NTF) has a 25-ft inside diameter with a capacity of {approx}44,000 gal. The GAAT were designed to receive radioactive and chemical wastes from ORNL processes. The tanks were constructed of Gunite, which is created by pneumatically spraying concrete over a wire mesh. Following construction, the site was backfilled so the domes of the tanks were covered with {approx}6 ft of earth. The STF tanks (W-5, -6, -7, -8, -9, and -10) are set in a 2 x 3 array with an east-west axis. The two GAAT in the NTF are on the north side of Central Avenue, and the STF is across the street. One additional Gunite tank, TH-4, is located {approx}300 ft east of the STF. TH-4 is a smaller, 20-ft inside diameter tank with a capacity of {approx}14,000 gal. Approximately 90% of the sludge inventory was removed from the STF tanks during a sluicing campaign in 1982-84 (Autry et al., 1990). Over 95% of the residual from the original sluicing was removed during the GAAT Remediation Project of 1997-2000. The NTF and STF tanks, as well as tank TH-4 were remediated under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) with regulatory oversight by the U.S. Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC).

Emison, JA

2002-03-14T23:59:59.000Z

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

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

114

Changing World Product Markets and Potential Refining Capacity ...  

U.S. Energy Information Administration (EIA)

Changing World Product Markets and Potential Refining Capacity Increases. NPRA Annual Meeting March 2006

115

Structural analysis of Hanford`s single-shell 241-C-106 tank: A first step toward waste-tank remediation  

SciTech Connect

The buried single-shell waste tank 241-C-106, located at the US Department of Energy`s Hanford Site, has been a repository for various liquid radioactive waste materials since its construction in 1943. A first step toward waste tank remediation is demonstrating that remediation activities can be performed safely. Determination of the current structural capacity of this high-heat tank is an important element in this assessment. A structural finite-element model of tank 241-C-106 has been developed to assess the tank`s structural integrity with respect to in situ conditions and additional remediation surface loads. To predict structural integrity realistically, the model appropriately addresses two complex issues: (1) surrounding soil-tank interaction associated with thermal expansion cycling and surcharge load distribution and (2) concrete-property degradation and creep resulting from exposure to high temperatures generated by the waste. This paper describes the development of the 241-C-106 structural model, analysis methodology, and tank-specific structural acceptance criteria.

Harris, J.P.; Julyk, L.J.; Marlow, R.S.; Moore, C.J. [Westinghouse Hanford Co., Richland, WA (United States); Day, J.P.; Dyrness, A.D.; Jagadish, P.; Shulman, J.S. [Advent Engineering Services, Inc., San Ramon, CA (United States)

1993-10-01T23:59:59.000Z

116

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

117

Tank Waste and Waste Processing | Department of Energy  

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

Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

118

Heat pipe cooling system for underground, radioactive waste storage tanks  

SciTech Connect

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

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

1980-02-01T23:59:59.000Z

119

Comparison of Productive Capacity  

U.S. Energy Information Administration (EIA)

Appendix B Comparison of Productive Capacity Comparisons of base case productive capacities for this and all previous studies were made (Figure B1).

120

Tables - Refinery Capacity Report  

U.S. Energy Information Administration (EIA)

Tables: 1: Number and Capacity of Operable Petroleum Refineries by PAD District and State as of January 1, 2009: PDF: 2: Production Capacity of Operable ...

Note: This page contains sample records for the topic "tanks capacity increase" 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

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...

122

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

123

Y-12 builds capacity to meet nuclear testing schedule - Or: ...  

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

builds capacity to meet nuclear testing schedule - Or: Increasing capacity to meet nuclear testing schedule (title as it appeared in The Oak Ridger) The continuing high volume...

124

High Capacity Immobilized Amine Sorbents  

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

Capacity Immobilized Amine Sorbents Capacity Immobilized Amine Sorbents Opportunity The Department of Energy's National Energy Technology Laboratory is seeking licensing partners interested in implementing United States Patent Number 7,288,136 entitled "High Capacity Immobilized Amine Sorbents." Disclosed in this patent is the invention of a method that facilitates the production of low-cost carbon dioxide (CO 2 ) sorbents for use in large-scale gas-solid processes. This method treats an amine to increase the number of secondary amine groups and impregnates the amine in a porous solid support. As a result of this improvement, the method increases CO 2 capture capacity and decreases the cost of using an amine-enriched solid sorbent in CO 2 capture systems. Overview The U.S. Department of Energy has placed a high priority on the separation

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

Investment Timing and Capacity Choice for Small-Scale Wind Power Under Uncertainty  

E-Print Network (OSTI)

INVESTMENT TIMING AND CAPACITY CHOICE FOR SMALL-SCALE WINDvalue as a func- tion of capacity is declining because ais reduced with increased capacity. A possible approach for

Fleten, Stein-Erik; Maribu, Karl Magnus

2004-01-01T23:59:59.000Z

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

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

132

Network Routing Capacity  

E-Print Network (OSTI)

We define the routing capacity of a network to be the supremum of all possible fractional message throughputs achievable by routing. We prove that the routing capacity of every network is achievable and rational, we present an algorithm for its computation, and we prove that every non-negative rational number is the routing capacity of some network. We also determine the routing capacity for various example networks. Finally, we discuss the extension of routing capacity to fractional coding solutions and show that the coding capacity of a network is independent of the alphabet used.

Jillian Cannons; Randall Dougherty; Christopher Freiling; Kenneth Zeger

2005-01-01T23:59:59.000Z

133

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)

134

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...

135

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

136

Evaluating Feed Delivery Performance in Scaled Double-Shell Tanks - 14070  

Science Conference Proceedings (OSTI)

The Hanford Tank Operations Contractor (TOC) and the Hanford Waste Treatment and Immobilization Plant (WTP) contractor are both engaged in demonstrating mixing, sampling, and transfer system capability using simulated Hanford High-Level Waste (HLW) formulations. This work represents one of the remaining technical issues with the high-level waste treatment mission at Hanford. The TOCs? ability to adequately mix and sample high-level waste feed to meet the WTP WAC Data Quality Objectives must be demonstrated. The tank mixing and feed delivery must support both TOC and WTP operations. The tank mixing method must be able to remove settled solids from the tank and provide consistent feed to the WTP to facilitate waste treatment operations. Two geometrically scaled tanks were used with a broad spectrum of tank waste simulants to demonstrate that mixing using two rotating mixer jet pumps yields consistent slurry compositions as the tank is emptied in a series of sequential batch transfers. Testing showed that the concentration of slow settling solids in each transfer batch was consistent over a wide range of tank operating conditions. Although testing demonstrated that the concentration of fast settling solids decreased by up to 25% as the tank was emptied, batch-to-batch consistency improved as mixer jet nozzle velocity in the scaled tanks increased.

Lee, Kearn P.; Thien, Michael G.

2013-11-07T23:59:59.000Z

137

Tank Waste Retrieval Lessons Learned at the Hanford Site  

SciTech Connect

One of the environmental remediation challenges facing the nation is the retrieval and permanent disposal of approximately 90 million gallons of radioactive waste stored in underground tanks at the U. S. Department of Energy (DOE) facilities. The Hanford Site is located in southeastern Washington State and stores roughly 60 percent of this waste. An estimated 53 million gallons of high-level, transuranic, and low-level radioactive waste is stored underground in 149 single-shell tanks (SSTs) and 28 newer double-shell tanks (DSTs) at the Hanford Site. These SSTs range in size from 55,000 gallons to 1,000,000 gallon capacity. Approximately 30 million gallons of this waste is stored in SSTs. The SSTs were constructed between 1943 and 1964 and all have exceeded the nominal 20-year design life. Sixty-seven SSTs are known or suspected to have leaked an estimated 1,000,000 gallons of waste to the surrounding soil. The risk of additional SST leakage has been greatly reduced by removing more than 3 million gallons of interstitial liquids and supernatant and transferring this waste to the DST system. Retrieval of SST salt-cake and sludge waste is underway to further reduce risks and stage feed materials for the Hanford Site Waste Treatment Plant. Regulatory requirements for SST waste retrieval and tank farm closure are established in the Hanford Federal Facility Agreement and Consent Order (HFFACO), better known as the Tri- Party Agreement, or TPA. The HFFACO was signed by the DOE, the State of Washington Department of Ecology (Ecology), and U.S. Environmental Protection Agency (EPA) and requires retrieval of as much waste as technically possible, with waste residues not to exceed 360 ft{sup 3} in 530,000 gallon or larger tanks; 30 ft{sup 3} in 55,000 gallon or smaller tanks; or the limit of waste retrieval technology, whichever is less. If residual waste volume requirements cannot be achieved, then HFFACO Appendix H provisions can be invoked to request Ecology and EPA approval of an exception to the waste retrieval criteria for a specific tank. Tank waste retrieval has been conducted at the Hanford Site over the last few decades using a method referred to as Past Practice Hydraulic Sluicing. Past Practice Hydraulic Sluicing employs large volumes of DST supernatant and water to dislodge, dissolve, mobilize, and retrieve tank waste. Concern over the leak integrity of SSTs resulted in the need for tank waste retrieval methods capable of using smaller volumes of liquid in a more controlled manner. Retrieval of SST waste in accordance with HFFACO requirements was initiated at the Hanford Site in April 2003. New and innovative tank waste retrieval methods that minimize and control the use of liquids are being implemented for the first time. These tank waste retrieval methods replace Past Practice Hydraulic Sluicing and employ modified sluicing, vacuum retrieval, and in-tank vehicle techniques. Waste retrieval has been completed in seven Hanford Site SSTs (C-106, C-103, C-201, C-202, C-203, C-204, and S-112) in accordance with HFFACO requirements. Three additional tanks are currently in the process of being retrieved (C-108, C-109 and S-102) Preparation for retrieval of two additional SSTs (C-104 and C-110) is ongoing with retrieval operations forecasted to start in calendar year 2008. Tank C-106 was retrieved to a residual waste volume of 470 ft{sup 3} using oxalic acid dissolution and modified sluicing. An Appendix H exception request for Tank C-106 is undergoing review. Tank C-103 was retrieved to a residual volume of 351 ft{sup 3} using a modified sluicing technology. This approach was successful at reaching the TPA limits for this tank of less than 360 ft{sup 3}and the limits of the technology. Tanks C-201, C-202, C-203, and C-204 are smaller (55,000 gallon) tanks and waste removal was completed in accordance with HFFACO requirements using a vacuum retrieval system. Residual waste volumes in each of these four tanks were less than 25 ft{sup 3}. Tank S-112 retrieval was completed February 28, 2007, meeting the TPA Limits of less than

Dodd, R.A. [CH2M HILL Hanford Group, Inc., Richland, Washington (United States)

2008-07-01T23:59:59.000Z

138

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

DOE Green Energy (OSTI)

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

Sherwood, D.J.

1994-03-01T23:59:59.000Z

139

TFA Tank Focus Area - multiyear program plan FY98-FY00  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation problem with hundreds of waste tanks containing hundreds of thousands of cubic meters of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Approximately 80 tanks are known or assumed to have leaked. Some of the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in a safe condition and eventually remediated to minimize the risk of waste migration and/or exposure to workers, the public, and the environment. However, programmatic drivers are more ambitious than baseline technologies and budgets will support. Science and technology development investments are required to reduce the technical and programmatic risks associated with the tank remediation baselines. The Tanks Focus Area (TFA) was initiated in 1994 to serve as the DOE`s Office of Environmental Management`s (EM`s) national technology development program for radioactive waste tank remediation. The national program was formed to increase integration and realize greater benefits from DOE`s technology development budget. The TFA is responsible for managing, coordinating, and leveraging technology development to support DOE`s four major tank sites: Hanford Site (Washington), Idaho National Engineering and Environmental Laboratory (INEEL) (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: waste retrieval, waste pretreatment, waste immobilization, tank closure, and characterization of both the waste and tank with safety integrated into all the functions. The TFA integrates program activities across organizations that fund tank technology development EM, including the Offices of Waste Management (EM-30), Environmental Restoration (EM-40), and Science and Technology (EM-50).

NONE

1997-09-01T23:59:59.000Z

140

TFA Tanks Focus Area Multiyear Program Plan FY00-FY04  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation problem with hundreds of waste tanks containing hundreds of thousands of cubic meters of high-level waste (HLW) and transuranic (TRU) waste across the DOE complex. Approximately 68 tanks are known or assumed to have leaked contamination to the soil. Some of the tank contents have reacted to form flammable gases, introducing additional safety risks. These tanks must be maintained in a safe condition and eventually remediated to minimize the risk of waste migration and/or exposure to workers, the public, and the environment. However, programmatic drivers are more ambitious than baseline technologies and budgets will support. Science and technology development investments are required to reduce the technical and programmatic risks associated with the tank remediation baselines. The Tanks Focus Area (TFA) was initiated in 1994 to serve as the DOE Office of Environmental Management's (EM's) national technology development program. for radioactive waste tank remediation. The national program was formed to increase integration and realize greater benefits from DOE's technology development budget. The TFA is responsible for managing, coordinating, and leveraging technology development to support DOE's five major tank sites: Hanford Site (Washington), Idaho National Engineering and Environmental Laboratory (INEEL) (Idaho), Oak Ridge Reservation (ORR) (Tennessee), Savannah River Site (SRS) (South Carolina), and West Valley Demonstration Project (WVDP) (New York). Its 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 with safety integrated into all the functions. The TFA integrates program activities across EM organizations that fund tank technology development, including the Offices of Waste Management (EM-30), Environmental Restoration (EM-40), and Science and Technology (EM-50 or OST).

BA Carteret; JH Westsik; LR Roeder-Smith; RL Gilchrist; RW Allen; SN Schlahta; TM Brouns

1999-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Capacity Value of Wind Power  

Science Conference Proceedings (OSTI)

Power systems are planned such that they have adequate generation capacity to meet the load, according to a defined reliability target. The increase in the penetration of wind generation in recent years has led to a number of challenges for the planning and operation of power systems. A key metric for system adequacy is the capacity value of generation. The capacity value of a generator is the contribution that a given generator makes to overall system adequacy. The variable and stochastic nature of wind sets it apart from conventional energy sources. As a result, the modeling of wind generation in the same manner as conventional generation for capacity value calculations is inappropriate. In this paper a preferred method for calculation of the capacity value of wind is described and a discussion of the pertinent issues surrounding it is given. Approximate methods for the calculation are also described with their limitations highlighted. The outcome of recent wind capacity value analyses in Europe and North America are highlighted with a description of open research questions also given.

Keane, Andrew; Milligan, Michael; Dent, Chris; Hasche, Bernhard; DAnnunzio, Claudine; Dragoon, Ken; Holttinen, Hannele; Samaan, Nader A.; Soder, Lennart; O'Malley, Mark J.

2011-05-04T23:59:59.000Z

142

URANIUM AND PLUTONIUM LOADING ONTO MONOSODIUM TITANATE MST IN TANK 50H  

SciTech Connect

A possible disposition pathway for the residue from the abandoned In-Tank Precipitation (ITP) sends the material from Tank 48H in increments to Saltstone via aggregation in Tank 50H. After entering Tank 50H, the amount of fissile material sorbed on MST may increase as a result of contacting waste solutions with dissolved uranium and plutonium. SRNL recommends that nuclear criticality safety evaluations use uranium and plutonium loadings onto MST of 14.0 {+-} 1.04 weight percent (wt %) for uranium and 2.79 {+-} 0.197 wt % for plutonium given the assumed streams defined in this report. These values derive from recently measured for conditions relevant to the Actinide Removal Process (ARP) and serve as conservative upper bounds for uranium and plutonium loadings during the proposed transfers of MST from Tank 48H into Tank 50H.

Hobbs, D

2006-08-31T23:59:59.000Z

143

Criteria for temperature monitoring in ferrocyanide waste tanks at the Hanford Site  

Science Conference Proceedings (OSTI)

This report is relevant to the twenty underground waste storage tanks at the Hanford Site that have been identified as potentially containing a significant amount of ferrocyanide compounds. Tanks believed to contain > 1,000 gram moles of ferrocyanide have been classified as Watch List tanks. This report addresses temperature monitoring criteria for the Ferrocyanide Watch List tanks. These criteria must comply with governing regulations to ensure that safe continued storage of the tank wastes is not jeopardized. Temperature monitoring is defined in this report as the routine as the routine continuous measurement of a waste tank temperature with an output that is tied to an actively interrogated information collection system that includes an automated warning of temperature increases beyond the established limits.

Fowler, K.D.; Dukelow, G.T.

1994-09-01T23:59:59.000Z

144

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

145

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

146

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

147

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 -...

148

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...

149

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...

150

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...

151

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...

152

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

153

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

154

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

155

Installed Geothermal Capacity | Open Energy Information  

Open Energy Info (EERE)

Geothermal Capacity Geothermal Capacity Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Print PDF Installed Geothermal Capacity International Market Map of U.S. Geothermal Power Plants List of U.S. Geothermal Power Plants Throughout the world geothermal energy is looked at as a potential source of renewable base-load power. As of 2005 there was 8,933 MW of installed power capacity within 24 countries. The International Geothermal Association (IGA) reported 55,709 GWh per year of geothermal electricity. The generation from 2005 to 2010 increased to 67,246 GWh, representing a 20% increase in the 5 year period. The IGA has projected that by 2015 the new installed capacity will reach 18,500 MW, nearly 10,000 MW greater than 2005. [1] Countries with the greatest increase in installed capacity (MW) between

156

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

157

ORISE: Capacity Building  

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

Capacity Building Capacity Building Because public health agencies must maintain the resources to respond to public health challenges, critical situations and emergencies, the Oak Ridge Institute for Science and Education (ORISE) helps government agencies and organizations develop a solid infrastructure through capacity building. Capacity building refers to activities that improve an organization's ability to achieve its mission or a person's ability do his or her job more effectively. For organizations, capacity building may relate to almost any aspect of its work-from leadership and administration to program development and implementation. Strengthening an organizational infrastructure can help agencies and community-based organizations more quickly identify targeted audiences for

158

Capacity Value of Concentrating Solar Power Plants  

DOE Green Energy (OSTI)

This study estimates the capacity value of a concentrating solar power (CSP) plant at a variety of locations within the western United States. This is done by optimizing the operation of the CSP plant and by using the effective load carrying capability (ELCC) metric, which is a standard reliability-based capacity value estimation technique. Although the ELCC metric is the most accurate estimation technique, we show that a simpler capacity-factor-based approximation method can closely estimate the ELCC value. Without storage, the capacity value of CSP plants varies widely depending on the year and solar multiple. The average capacity value of plants evaluated ranged from 45%?90% with a solar multiple range of 1.0-1.5. When introducing thermal energy storage (TES), the capacity value of the CSP plant is more difficult to estimate since one must account for energy in storage. We apply a capacity-factor-based technique under two different market settings: an energy-only market and an energy and capacity market. Our results show that adding TES to a CSP plant can increase its capacity value significantly at all of the locations. Adding a single hour of TES significantly increases the capacity value above the no-TES case, and with four hours of storage or more, the average capacity value at all locations exceeds 90%.

Madaeni, S. H.; Sioshansi, R.; Denholm, P.

2011-06-01T23:59:59.000Z

159

Project Execution Plan for Project W-211 Initial Tank Retrieval Systems (ITRS)  

Science Conference Proceedings (OSTI)

Project W-211, Initial Tank Retrieval Systems (ITRS), is a fiscal year 1994 Major Systems Acquisition that will provide systems for retrieval of radioactive wastes from selected double-shell tanks (DST). The contents of these tanks are a combination of supernatant liquids and settled solids. To retrieve waste from the tanks, it is first necessary to mix the liquid and solids prior to transferring the slurry to alternative storage or treatment facilities. The ITRS will provide systems to mobilize the settled solids and transfer the wastes out of the tanks. In so doing, ITRS provides feed for future processing plants, allows for consolidation of tank solids to manage space within existing DST storage capacity, and supports continued safe storage of tank waste. The ITRS scope has been revised to include waste retrieval systems for tanks AP-102, AP-104, AP-108, AN-103, AN-104, AN-105, AY-102, AZ-102, and SY-102. This current tank selection and sequence provides retrieval systems supporting the Privatized waste processing plant and sustains the ability to provide final remediation of several watch list DSTs via treatment. The ITRS is configured to support changing program needs, as constrained by available budget, by maintaining the flexibility for exchanging tanks requiring mixer pump-based retrieval systems and shifting the retrieval sequence. Preliminary design was configured such that an adequate basis exists for initiating Title II design of a mixer pump based retrieval system for any DST. This Project Management Plan (PMP) documents the methodology for managing the ITRS, formalizes organizational responsibilities and interfaces, and identifies project requirements such as change control, design verification, systems engineering, and human factors engineering.

VAN BEEK, J.E.

1999-09-02T23:59:59.000Z

160

Project Execution Plan for Project W-211 Initial Tank Retrieval Systems (ITRS)  

SciTech Connect

This Project Execution Plan documents the methodology for managing Project W-211. Project W-211, Initial Tank Retrieval Systems (ITRS), is a fiscal year 1994 Major Systems Acquisition that will provide systems for retrieval of radioactive wastes from selected double-shell tanks (DST). The contents of these tanks are a combination of supernatant liquids and settled solids. To retrieve waste from the tanks, it is first necessary to mix the liquid and solids prior to transferring the slurry to alternative storage or treatment facilities. The ITRS will provide systems to mobilize the settled solids and transfer the wastes out of the tanks. In so doing, ITRS provides feed for the future waste treatment plant, allows for consolidation of tank solids to manage space within existing DST storage capacity, and supports continued safe storage of tank waste. The ITRS scope has been revised to include waste retrieval systems for tanks AP-102, AP-104, AN-102, AN-103, AN-104, AN-105, AY-102, AZ-102, and SY-102. This current tank selection and sequence provides retrieval systems supporting the River Protection Project (RF'P) Waste Treatment Facility and sustains the ability to provide final remediation of several watch list DSTs via treatment. The ITRS is configured to support changing program needs, as constrained by available budget, by maintaining the flexibility for exchanging tanks requiring mixer pump-based retrieval systems and shifting the retrieval sequence. Preliminary design was configured such that an adequate basis exists for initiating Title II design of a mixer pump-based retrieval system for any DST. This Project Execution Plan (PEP), derived from the predecessor Project Management Plan, documents the methodology for managing the ITRS, formalizes organizational responsibilities and interfaces, and identifies project requirements such as change control, design verification, systems engineering, and human factors engineering.

VAN BEEK, J.E.

2000-04-19T23:59:59.000Z

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


161

Modeling Capacity Reservation Contract  

E-Print Network (OSTI)

In this paper we model a scenario where a chip designer (buyer) buys capacity from chip manufacturers (suppliers) in the presence of demand uncertainty faced by the buyer. We assume that the buyer knows the probability distribution of his demand. The supplier offers the buyer to reserve capacity in advance at a price that is lower than the historical average of the spot price. The suppliers price (if the buyer reserves capacity in advance) is function of her capacity, demand for her capacity, unit production cost, the average spot market price and the amount of capacity reserved by the buyer. Based on these parameters we derive the price the suppliers will charge. We formulate the problem from the buyers perspective. The buyers decisions are how much capacity to reserve and from how many suppliers. The optimal solution is obtained numerically. Our model addresses the following issues that are not covered in the current literature on capacity reservation models. In the existing literature the suppliers price is an exogenous parameter. We model the suppliers price from relevant parameters mentioned above. This makes our model richer. For example, if the expected capacity utilization for the supplier is likely to be low then the supplier will charge a lower price for capacity reservation. In reality, the buyer sources from multiple suppliers. Most mathematical models on capacity reservation, we are aware of, assumes a single buyer and a single supplier. We generalize this to a single buyer and multiple suppliers.

Jishnu Hazra; B. Mahadevan; Sudhi Seshadri

2002-01-01T23:59:59.000Z

162

Flammable gas tank waste level reconciliation for 241-S-111  

SciTech Connect

Fluor Daniel Northwest (FDNW) was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 241-S-111. The trapped gas evaluation document states that Tank S-111 exceeds the 25% of the lower flammable-limit criterion, based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the Welty Report is the basis for this letter report. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unaccounted for surface level rise. From 1973 through 1980, the Welty Report tracked Tank S-111 transfers. This surface level increase is from an unknown source or is unaccounted for. Duke Engineering and Services Hanford and Lockheed Martin Hanford Corporation are interested in determining the validity of the unexplained surface level changes reported in the Welty Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unaccounted for surface level changes as shown in the Welty Report from 1973 through 1980. Tank S-111 initially received waste from REDOX in 1952, and after April 1974, primarily received processed waste slurry from the 242-S Evaporator/Crystallizer and transferred supernatant waste to Tank S-102. From the FDNW review and comparisons of the Welty Report versus other daily records for Tank S-111, FDNW determined that the majority of the time, the Welty Report is consistent with daily records. Surface level decreases that occurred following saltwell pumping were identified as unaccounted for decreases in the Welty Report, however they were probably a continued settlement caused by saltwell pumping of the interstitial liquids. Because the flammable/trapped gas issue is linked to the unexplained increase in the surface level, FDNW recommends that all occurrence reports, concerning tank waste level increases or decreases from 1970 through 1980, be reevaluated for acceptability of the evaluation as to the root cause of the occurrence.

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

1997-06-23T23:59:59.000Z

163

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

164

Thermal and radiolytic gas generation from Tank 241-S-102 waste  

SciTech Connect

This report summarizes progress in evaluating thermal and radiolytic rate parameters for flammable gas generation in Hanford single-shell tank wastes based on the results of laboratory tests using actual waste from Tank 241-S-102 (S-102). Work described in this report was conducted at Pacific Northwest National Laboratory (PNNL) for the Flammable Gas Safety Project, whose purpose is to develop information to support Fluor Daniel Hanford (FDH) and its Project Management Hanford Contract (PHMC) subcontractors in their efforts to ensure the safe interim storage of wastes at the Hanford Site. This work is related to gas generation studies being performed at Georgia Institute of Technology (GIT) under subcontract to PNNL, using simulated wastes, and to studies being performed at Numatec Hanford Corporation (formerly Westinghouse Hanford Company) using actual wastes. The results of gas generation from Tank S-102 waste under thermal and radiolytic conditions are described in this report. The accurate measurement of gas generation rates in 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 Tank S-102, a waste tank listed as high priority by the Flammable Gas Safety Program due to its potential for flammable gas accumulation above the flammability limit.

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

1997-07-01T23:59:59.000Z

165

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

SciTech Connect

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

Thaxton, D; Timothy Baughman, T

2008-01-16T23:59:59.000Z

166

Increased Power Flow Guidebook  

Science Conference Proceedings (OSTI)

The Increased Power Flow (IPF) Guidebook is a state-of-the-art and best practices guidebook on increasing power flow capacities of existing overhead transmission lines, underground cables, power transformers, and substation equipment without compromising safety and reliability. The Guidebook discusses power system concerns and limiting conditions to increasing capacity, reviews available technology options and methods, illustrates alternatives with case studies, and analyzes costs and benefits of differe...

2005-11-16T23:59:59.000Z

167

High capacity immobilized amine sorbents  

DOE Patents (OSTI)

A method is provided for making low-cost CO.sub.2 sorbents that can be used in large-scale gas-solid processes. The improved method entails treating an amine to increase the number of secondary amine groups and impregnating the amine in a porous solid support. The method increases the CO.sub.2 capture capacity and decreases the cost of utilizing an amine-enriched solid sorbent in CO.sub.2 capture systems.

Gray, McMahan L. (Pittsburgh, PA); Champagne, Kenneth J. (Fredericktown, PA); Soong, Yee (Monroeville, PA); Filburn, Thomas (Granby, CT)

2007-10-30T23:59:59.000Z

168

Approach for tank safety characterization of Hanford site waste  

Science Conference Proceedings (OSTI)

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

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

1995-03-01T23:59:59.000Z

169

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

170

Natural Gas Underground Storage Capacity (Summary)  

Gasoline and Diesel Fuel Update (EIA)

Salt Caverns Storage Capacity Aquifers Storage Capacity Depleted Fields Storage Capacity Total Working Gas Capacity Working Gas Capacity of Salt Caverns Working Gas Capacity of...

171

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...

172

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

173

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

174

Capacity Markets for Electricity  

E-Print Network (OSTI)

Designing Markets for Electricity. Wiley IEEE Press. [25]in the England and Wales Electricity Market, Power WorkingFelder (1996), Should Electricity Markets Have a Capacity

Creti, Anna; Fabra, Natalia

2004-01-01T23:59:59.000Z

175

ORISE: Capacity Building  

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

Capacity Building Because public health agencies must maintain the resources to respond to public health challenges, critical situations and emergencies, the Oak Ridge Institute...

176

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

177

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.

178

MODELING ANALYSIS FOR GROUT HOPPER WASTE TANK  

SciTech Connect

The Saltstone facility at Savannah River Site (SRS) has a grout hopper tank to provide agitator stirring of the Saltstone feed materials. The tank has about 300 gallon capacity to provide a larger working volume for the grout nuclear waste slurry to be held in case of a process upset, and it is equipped with a mechanical agitator, which is intended to keep the grout in motion and agitated so that it won't start to set up. The primary objective of the work was to evaluate the flow performance for mechanical agitators to prevent vortex pull-through for an adequate stirring of the feed materials and to estimate an agitator speed which provides acceptable flow performance with a 45{sup o} pitched four-blade agitator. In addition, the power consumption required for the agitator operation was estimated. The modeling calculations were performed by taking two steps of the Computational Fluid Dynamics (CFD) modeling approach. As a first step, a simple single-stage agitator model with 45{sup o} pitched propeller blades was developed for the initial scoping analysis of the flow pattern behaviors for a range of different operating conditions. Based on the initial phase-1 results, the phase-2 model with a two-stage agitator was developed for the final performance evaluations. A series of sensitivity calculations for different designs of agitators and operating conditions have been performed to investigate the impact of key parameters on the grout hydraulic performance in a 300-gallon hopper tank. For the analysis, viscous shear was modeled by using the Bingham plastic approximation. Steady state analyses with a two-equation turbulence model were performed. All analyses were based on three-dimensional results. Recommended operational guidance was developed by using the basic concept that local shear rate profiles and flow patterns can be used as a measure of hydraulic performance and spatial stirring. Flow patterns were estimated by a Lagrangian integration technique along the flow paths from the material feed inlet.

Lee, S.

2012-01-04T23:59:59.000Z

179

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

180

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

Note: This page contains sample records for the topic "tanks capacity increase" 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

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.)

182

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

183

Capacity on Finsler Spaces  

E-Print Network (OSTI)

Here, the concept of electric capacity on Finsler spaces is introduced and the fundamental conformal invariant property is proved, i.e. the capacity of a compact set on a connected non-compact Finsler manifold is conformal invariant. This work enables mathematicians and theoretical physicists to become more familiar with the global Finsler geometry and one of its new applications.

Bidabad, B

2009-01-01T23:59:59.000Z

184

Liquid heat capacity lasers  

DOE Patents (OSTI)

The heat capacity laser concept is extended to systems in which the heat capacity lasing media is a liquid. The laser active liquid is circulated from a reservoir (where the bulk of the media and hence waste heat resides) through a channel so configured for both optical pumping of the media for gain and for light amplification from the resulting gain.

Comaskey, Brian J. (Walnut Creek, CA); Scheibner, Karl F. (Tracy, CA); Ault, Earl R. (Livermore, CA)

2007-05-01T23:59:59.000Z

185

capacity | OpenEI  

Open Energy Info (EERE)

capacity capacity Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 9, and contains only the reference case. The dataset uses gigawatts. The data is broken down into power only, combined heat and power, cumulative planned additions, cumulative unplanned conditions, and cumulative retirements and total electric power sector capacity . Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO capacity consumption EIA Electricity generating Data application/vnd.ms-excel icon AEO2011: Electricity Generating Capacity- Reference Case (xls, 130.1 KiB) Quality Metrics Level of Review Peer Reviewed Comment

186

Battery capacity indicator  

SciTech Connect

This patent describes a battery capacity indicator for providing a continuous indication of battery capacity for a battery powered device. It comprises means for periodically effecting a first and a second positive discharge rate of the battery; voltage measurement means, for measuring the battery terminal voltage at the first and second positive discharge rates during the operation of the device, and for generating a differential battery voltage value in response thereto; memory means for storing a set of predetermined differential battery voltage values and a set of predetermined battery capacity values, each of the set of predetermined differential battery voltage values defining one of the set of predetermined battery capacity values; comparison means, coupled to the memory means and to the voltage measurement means, for comparing the measured differential battery voltage values with the set of predetermined differential battery voltage values, and for selecting the predetermined battery capacity value corresponding thereto.

Kunznicki, W.J.

1991-07-16T23:59:59.000Z

187

Flammable gas tank waste level reconcilliation for 241-SX-102  

SciTech Connect

Fluoro Dynel Northwest (FDNW) was authorized to address flammable gas issues by reconciling the unexplained surface level increases in Tank 24 1-S-1 1 1 (S-I 1 1, typical). The trapped gas evaluation document (ref 1) states that Tank SX-102 exceeds the 25% of the lower flammable limit (FL) criterion (ref 2), based on a surface level rise evaluation. The Waste Storage Tank Status and Leak Detection Criteria document, commonly referred to as the ``Wallet Report`` is the basis for this letter report (ref 3). The Wallet Report is also a part of the trapped gas evaluation document criteria. The Wallet Report contains various tank information, including: physical information, status, levels, and dry wells, see Appendix A. The unexplained waste level rises were attributed to the production and retention of gas in the column of waste corresponding to the unacquainted for surface level rise. From 1973 through 1980, the Wallet Report tracked Tank S- 102 transfers and reported a net cumulative change of 19.95 in. This surface level increase is from an unknown source or is unacquainted for. Duke Engineering and Services Hanford (DASH) and Leached Martin Hanford Corporation (LMHC) are interested in determining the validity of the unexplained surface level changes reported in the 0611e Wallet Report based upon other corroborative sources of data. The purpose of this letter report is to assemble detailed surface level and waste addition data from daily tank records, logbooks, and other corroborative data that indicate surface levels, and to reconcile the cumulative unacquainted for surface level changes as shown in the Wallet Report from 1973 through 1980.

Brevick, C.H.; Gaddie, L.A.

1997-06-23T23:59:59.000Z

188

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

189

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

190

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

DOE Green Energy (OSTI)

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

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

2011-02-09T23:59:59.000Z

191

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

Science Conference Proceedings (OSTI)

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

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

2011-02-01T23:59:59.000Z

192

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

193

Multi-Function Waste Tank Facility thermal hydraulic analysis for Title II design  

Science Conference Proceedings (OSTI)

The purpose of this work was to provide the thermal hydraulic analysis for the Multi-Function Waste Tank Facility (MWTF) Title II design. Temperature distributions throughout the tank structure were calculated for subsequent use in the structural analysis and in the safety evaluation. Calculated temperatures of critical areas were compared to design allowables. Expected operating parameters were calculated for use in the ventilation system design and in the environmental impact documentation. The design requirements were obtained from the MWTF Functional Design Criteria (FDC). The most restrictive temperature limit given in the FDC is the 200 limit for the haunch and dome steel and concrete. The temperature limit for the rest of the primary and secondary tanks and concrete base mat and supporting pad is 250 F. Also, the waste should not be allowed to boil. The tank geometry was taken from ICF Kaiser Engineers Hanford drawing ES-W236A-Z1, Revision 1, included here in Appendix B. Heat removal rates by evaporation from the waste surface were obtained from experimental data. It is concluded that the MWTF tank cooling system will meet the design temperature limits for the design heat load of 700,000 Btu/h, even if cooling flow is lost to the annulus region, and temperatures change very slowly during transients due to the high heat capacity of the tank structure and the waste. Accordingly, transients will not be a significant operational problem from the viewpoint of meeting the specified temperature limits.

Cramer, E.R.

1994-11-10T23:59:59.000Z

194

Lateral Capacity Exchange and Its Impact on Capacity Investment Decisions  

E-Print Network (OSTI)

We study the problem of capacity exchange between two rms in anticipation of the mismatch between demand and capacity and its impact on rms capacity investment decisions. For given capacity investment levels of the two rms, we demonstrate how capacity price may be determined and how much capacity should be exchanged when either manufacturer acts as a Stackelberg leader in the capacity exchange game. By benchmarking against the centralized system, we show that a side payment may be used to coordinate the capacity exchange decisions. We then study the rmscapacity investment decisions using a biform game framework in which capacity investment decisions are made individually and exchange decisions are made as in a centralized system. We demonstrate the existence and uniqueness of the Nash equilibrium capacity investment levels and study the impact of rmsshare of the capacity exchange surplus on their capacity investment levels.

Amiya K. Chakravartyz; Jun Zhangy

2005-01-01T23:59:59.000Z

195

Capacity Markets for Electricity  

E-Print Network (OSTI)

Global Agenda, August 15. [6] FERC, Docket No. EL01-63-003,at http://www.pjm.com. [7] FERC, Docket No. ER01-1440-capacity of the others (FERC, 2001). Therefore, if an LSE

Creti, Anna; Fabra, Natalia

2004-01-01T23:59:59.000Z

196

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

197

Refinery Capacity Report 2007  

Reports and Publications (EIA)

Data series include fuel, electricity, and steam purchased for consumption at the refinery; refinery receipts of crude oil by method of transportation; current and projected capacities for atmospheric crude oil distillation, downstream charge, production, and storage capacities. Respondents are operators of all operating and idle petroleum refineries (including new refineries under construction) and refineries shut down during the previous year, located in the 50 States, the District of Columbia, Puerto Rico, the Virgin Islands, Guam, and other U.S. possessions.

Information Center

2007-06-29T23:59:59.000Z

198

Refinery Capacity Report 2009  

Reports and Publications (EIA)

Data series include fuel, electricity, and steam purchased for consumption at the refinery; refinery receipts of crude oil by method of transportation; current and projected capacities for atmospheric crude oil distillation, downstream charge, production, and storage capacities. Respondents are operators of all operating and idle petroleum refineries (including new refineries under construction) and refineries shut down during the previous year, located in the 50 States, the District of Columbia, Puerto Rico, the Virgin Islands, Guam, and other U.S. possessions.

Information Center

2009-06-25T23:59:59.000Z

199

Refinery Capacity Report 2008  

Reports and Publications (EIA)

Data series include fuel, electricity, and steam purchased for consumption at the refinery; refinery receipts of crude oil by method of transportation; current and projected capacities for atmospheric crude oil distillation, downstream charge, production, and storage capacities. Respondents are operators of all operating and idle petroleum refineries (including new refineries under construction) and refineries shut down during the previous year, located in the 50 States, the District of Columbia, Puerto Rico, the Virgin Islands, Guam, and other U.S. possessions.

Information Center

2008-06-20T23:59:59.000Z

200

Forward capacity market CONEfusion  

Science Conference Proceedings (OSTI)

In ISO New England and PJM it was assumed that sponsors of new capacity projects would offer them into the newly established forward centralized capacity markets at prices based on their levelized net cost of new entry, or ''Net CONE.'' But the FCCMs have not operated in the way their proponents had expected. To clear up the CONEfusion, FCCM designs should be reconsidered to adapt them to the changing circumstances and to be grounded in realistic expectations of market conduct. (author)

Wilson, James F.

2010-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Use belowground storage tanks to manage stormwater  

Science Conference Proceedings (OSTI)

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

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

1996-01-01T23:59:59.000Z

202

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

203

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

204

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

205

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

206

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

207

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

208

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

209

TANK WASTE RETRIEVAL LESSONS LEARNED AT THE HANFORD SITE  

SciTech Connect

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

DODD, R.A.

2006-01-17T23:59:59.000Z

210

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT BUCKLING EVALUATION METHODS AND 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 (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 anchor 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 concrete anchor 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 anchor bolt failure leading to global buckling of the tank under increased vacuum) could occur. After releasing Revision 0 of this report, an independent review of the Double Shell Tanks (DST) Thermal and Operating Loads Analysis (TaLA) combined with the Seismic Analysis was conducted by Dr. Robert P. Kennedy of RPK Structural Mechanics Consulting and Dr. Anestis S. Veletsos of Rice University. Revision I was then issued to address their review comments (included in Appendix D). Additional concerns involving the evaluation of concrete anchor loads and allowables were found during a second review by Drs. Kennedy and Veletsos (see Appendix G). Extensive additional analysis was performed on the anchors, which is detailed by Deibler et al. (2008a, 2008b). The current report (Revision 2) references this recent work, and additional analysis is presented to show that anchor loads do not concentrate significantly in the presence of a local buckle.

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

2009-01-14T23:59:59.000Z

211

Review of Waste Retrieval Sluicing System Operations and Data for Tanks 241-C-106 and 241-AY-102  

Science Conference Proceedings (OSTI)

Sluicing operations were performed to retrieve high-heat sludge from single-shell tank 241-C-106 and transfer it to double-shell tank 241-AY-102 using the Waste Retrieval Sluicing System. This eliminated the high-heat safety issue for C-106 and demonstrated a technology for retrieval of single-shell tank waste. Both AY-102 and C-106 were monitored during the waste transfer operations, providing a clear picture of general trends in each tank. Specific issues addressed were evaluation of the data for evidence of flammable gas accumulation in AY-102 and thermal performance of AY-102 under the increasing heat load.

Cuta, Judith M.; Carothers, Kelly G.; Damschen, Dennis W.; Kuhn, William L.; Lechelt, Jeanne A.; Sathyanarayana, Kurabalakota; Stauffer, Leslie A.

2000-09-26T23:59:59.000Z

212

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

Science Conference Proceedings (OSTI)

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

LEHMAN LL

2008-01-23T23:59:59.000Z

213

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

214

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

215

Definition: Deferred Distribution Capacity Investments | Open Energy  

Open Energy Info (EERE)

Deferred Distribution Capacity Investments Deferred Distribution Capacity Investments Jump to: navigation, search Dictionary.png Deferred Distribution Capacity Investments As with the transmission system, reducing the load and stress on distribution elements increases asset utilization and reduces the potential need for upgrades. Closer monitoring and load management on distribution feeders could potentially extend the time before upgrades or capacity additions are required.[1] Related Terms load, transmission lines, transmission line, sustainability References ↑ SmartGrid.gov 'Description of Benefits' An inl LikeLike UnlikeLike You like this.Sign Up to see what your friends like. ine Glossary Definition Retrieved from "http://en.openei.org/w/index.php?title=Definition:Deferred_Distribution_Capacity_Investments&oldid=502613

216

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

217

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

218

Hydrogen Peroxide Storage in Small Sealed Tanks  

DOE Green Energy (OSTI)

Unstabilized hydrogen peroxide of 85% concentration has been prepared in laboratory quantities for testing material compatibility and long term storage on a small scale. Vessels made of candidate tank and liner materials ranged in volume from 1 cc to 2540 cc. Numerous metals and plastics were tried at the smallest scales, while promising ones were used to fabricate larger vessels and liners. An aluminum alloy (6061-T6) performed poorly, including increasing homogeneous decay due to alloying elements entering solution. The decay rate in this high strength aluminum was greatly reduced by anodizing. Better results were obtained with polymers, particularly polyvinylidene fluoride. Data reported herein include ullage pressures as a function of time with changing decay rates, and contamination analysis results.

Whitehead, J.

1999-10-20T23:59:59.000Z

219

Refinery Capacity Report  

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

Refinery Capacity Report Refinery Capacity Report June 2013 With Data as of January 1, 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies. Table 1. Number and Capacity of Operable Petroleum Refineries by PAD District and State as of January 1, 2013

220

Dual capacity reciprocating compressor  

DOE Patents (OSTI)

A multi-cylinder compressor particularly useful in connection with northern climate heat pumps and in which different capacities are available in accordance with reversing motor rotation is provided with an eccentric cam on a crank pin under a fraction of the connecting rods, and arranged for rotation upon the crank pin between opposite positions 180[degree] apart so that with cam rotation on the crank pin such that the crank throw is at its normal maximum value all pistons pump at full capacity, and with rotation of the crank shaft in the opposite direction the cam moves to a circumferential position on the crank pin such that the overall crank throw is zero. Pistons whose connecting rods ride on a crank pin without a cam pump their normal rate with either crank rotational direction. Thus a small clearance volume is provided for any piston that moves when in either capacity mode of operation. 6 figs.

Wolfe, R.W.

1984-10-30T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Dual capacity reciprocating compressor  

DOE Patents (OSTI)

A multi-cylinder compressor 10 particularly useful in connection with northern climate heat pumps and in which different capacities are available in accordance with reversing motor 16 rotation is provided with an eccentric cam 38 on a crank pin 34 under a fraction of the connecting rods, and arranged for rotation upon the crank pin between opposite positions 180.degree. apart so that with cam rotation on the crank pin such that the crank throw is at its normal maximum value all pistons pump at full capacity, and with rotation of the crank shaft in the opposite direction the cam moves to a circumferential position on the crank pin such that the overall crank throw is zero. Pistons 24 whose connecting rods 30 ride on a crank pin 36 without a cam pump their normal rate with either crank rotational direction. Thus a small clearance volume is provided for any piston that moves when in either capacity mode of operation.

Wolfe, Robert W. (Wilkinsburg, PA)

1984-01-01T23:59:59.000Z

222

Refinery Capacity Report  

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

Refinery Capacity Report Refinery Capacity Report With Data as of January 1, 2013 | Release Date: June 21, 2013 | Next Release Date: June 20, 2014 Previous Issues Year: 2013 2012 2011 2010 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1997 1995 1994 Go Data series include fuel, electricity, and steam purchased for consumption at the refinery; refinery receipts of crude oil by method of transportation; and current and projected atmospheric crude oil distillation, downstream charge, and production capacities. Respondents are operators of all operating and idle petroleum refineries (including new refineries under construction) and refineries shut down during the previous year, located in the 50 States, the District of Columbia, Puerto Rico, the Virgin Islands, Guam, and other U.S. possessions.

223

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

224

Using heat demand prediction to optimise Virtual Power Plant production capacity  

E-Print Network (OSTI)

CHP appliances on the grid in the near future. In case of a microCHP, adding a heat buffer (hot water tank1 Using heat demand prediction to optimise Virtual Power Plant production capacity Vincent Bakker that generate electricity (and heat) at the kilowatt level, which allows them to be installed in households

Al Hanbali, Ahmad

225

Tank vessels transferring Outer Continental Shelf (OCS) oil proposed design and equipment standards  

SciTech Connect

The US Coast Guard proposes to require US and foreign flag tank vessels engaged in the transfer of OCS oil in bulk as cargo from an offshore oil exploitation or production facility to shore to have segregated ballast tanks, dedicated clean ballast tanks, or special ballast arrangements by 6/1/80. This proposal would implement the Port and Tanker Safety Act of 1978 and would eliminate the mixing of ballast water and oil, thus reducing operational pollution that could occur if there was a substantial increase in vessel traffic. Comments must be received by 6/16/80.

1980-05-01T23:59:59.000Z

226

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

227

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

228

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

229

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

230

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

231

Gas generation and retention in Tank 101-SY: A summary of laboratory studies, tank data, and information needs  

DOE Green Energy (OSTI)

Chemical and radioactive wastes from processes used to separate plutonium from uranium are stored in underground tanks at the Hanford Site in Washington state. In March 1981, it was observed that the volume of wastes in Tank 101-SY slowly increased, followed by a rapid decrease and the venting of large quantities of gases. These cycles occurred every 8 to 15 weeks and continue to the present time. Subsequent analyses showed that these gases were composed primarily of hydrogen and nitrous oxide (N{sub 2}O). In response to the potential for explosion and release of hazardous materials to the environment, laboratory programs were initiated at Argonne National Laboratory (ANL), Georgia Institute of Technology (GIT), Pacific Northwest Laboratory (PNL), and Westinghouse Hanford Company (WHC), to develop a better understanding of the physical and chemical processes occurring in this waste tank. An aggressive sampling and analysis effort is also under way to characterize the wastes as fully as possible. These efforts will provide a technically defensible basis for safety analyses and future mitigation/remediation of the tank and its contents.

Pederson, L.R. (comp.) (Pacific Northwest Lab., Richland, WA (United States)); Ashby, E.C. (Georgia Inst. of Tech., Atlanta, GA (United States)); Jonah, C.; Meisel, D. (Argonne National Lab., IL (United States)); Strachan, D.M. (Pacific Northwest Lab., Richland, WA (United States))

1992-06-01T23:59:59.000Z

232

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

233

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...

234

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...

235

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...

236

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...

237

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...

238

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...

239

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...

240

Measuring the capacity impacts of demand response  

Science Conference Proceedings (OSTI)

Critical peak pricing and peak time rebate programs offer benefits by increasing system reliability, and therefore, reducing capacity needs of the electric power system. These benefits, however, decrease substantially as the size of the programs grows relative to the system size. More flexible schemes for deployment of demand response can help address the decreasing returns to scale in capacity value, but more flexible demand response has decreasing returns to scale as well. (author)

Earle, Robert; Kahn, Edward P.; Macan, Edo

2009-07-15T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Neutron and Gamma Probe Application to Hanford Tank 241-SY-101  

SciTech Connect

A neutron (moisture-sensitive) and gamma (in-situ radiation) probe technique has been utilized at a number of Hanford radioactive waste tanks for many years. This technology has been adapted for use in tank 241-SY-101's two Multifunction Instrument Trees (MITs) which have a hollow dry-well center opening two inches (51 cm) in diameter. These probes provide scans starting within a few inches of the tank bottom and traversing up through the top of the tank revealing a variety of waste features as a function of tank elevation. These features have been correlated with void fraction data obtained independently from two other devices, the Retained Gas Sampler (RGS) and the Void Fraction Instrument (VFI). The MIT probes offer the advantage of nearly continuous count-rate versus elevation scans and they can be operated significantly more often and at lower cost than temperature probes or the RGS or VFI devices while providing better depth resolution. The waste level in tank 241-SY-101 had been rising at higher rates than expected during 1998 and early 1999 indicating an increasing amount of trapped gas in the waste. The use of the MIT probes has assisted in evaluating changes in crust thickness and level and also in estimating relative changes in gas stored in the crust. This information is important in assuring that the tank remains in a safe configuration and will support safe waste transfer when those operations take place.

CANNON, N.S.

2000-02-01T23:59:59.000Z

242

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

243

Quantum Zero-error Capacity  

E-Print Network (OSTI)

We define here a new kind of quantum channel capacity by extending the concept of zero-error capacity for a noisy quantum channel. The necessary requirement for which a quantum channel has zero-error capacity greater than zero is given. Finally, we point out some directions on how to calculate the zero-error capacity of such channels.

Rex A. C. Medeiros; Francisco M. De Assis

2006-11-08T23:59:59.000Z

244

Energy Storage in a Restructured Electric Utility Industry: Report on EPRI Think Tanks I and II  

Science Conference Proceedings (OSTI)

Energy storage will play an increasingly crucial role in the deregulated electric power industry, with future generation probably decreasing in size and becoming more distributed. EPRI sponsored two think tanks to explore the need for energy storage in a deregulated environment and to assess the state of development of energy storage technologies. The think tanks described the U.S. Federal Energy Regulatory Commission (FERC) view of deregulation and how electric utility deregulation compares to the dereg...

1997-09-30T23:59:59.000Z

245

Capacity of ultra-wideband power-constrained ad hoc networks  

E-Print Network (OSTI)

increases ad hoc wireless capacity, in Proc. IEEE Int.Negi and A. Rajeswaran, Capacity of power constrained ad-Gupta and P. R. Kumar, The capacity of wireless networks,

Tang, Xiaojun; Hua, Yingbo

2008-01-01T23:59:59.000Z

246

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

247

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

248

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

249

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

250

Increasing capacity of baseband digital data communication networks  

DOE Patents (OSTI)

This invention provides broadband network capabilities for baseband digital collision detection transceiver equipment for communication between a plurality of data stations by affording simultaneous transmission of multiple channels over a broadband pass transmission link such as a coaxial cable. Thus, a fundamental carrier wave is transmitted on said link, received at local data stations and used to detect signals on different baseband channels for reception. For transmission the carrier wave typically is used for segregating a plurality of at least two transmission channels into typically single sideband upper and lower pass bands of baseband bandwidth capability adequately separated with guard bands to permit simple separation for receiving by means of pass band filters, etc.

Frankel, Robert S. (Centereach, NY); Herman, Alexander (Hertzelia, IL)

1985-01-01T23:59:59.000Z

251

Increasing Freeway Merge Capacity Through On-Ramp Metering  

E-Print Network (OSTI)

1998), ALINEA local ramp metering-summary of field results,adaptive local ramp metering strategy, In Transportation2002), Freeway ramp metering: an overview, IEEE Transactions

Rudjanakanoknad, Jittichai

2005-01-01T23:59:59.000Z

252

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

253

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

254

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...

255

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...

256

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...

257

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...

258

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...

259

Analysis of vehicle fuel release resulting in waste tank fire  

SciTech Connect

The purpose of the calculation documented here is to support in-tank vehicle fuel fire accident frequencies in the Documented Safety Analysis. This analysis demonstrates that the frequency of the pool fire and deflagration scenarios of the in-tank vehicle fuel fire/deflagration accident are ''extremely unlikely'' to ''unlikely.'' The chains of events that result in each scenario are presented in this document and are the same as used in previous analyses of this accident. Probabilities and frequencies are developed for each event, using wherever possible, information from RPP-13121, Tables B-1 and B-2, and from the River Protection Project ORPS. The estimated probabilities are considered reasonably conservative, but do not necessarily assume the worst possible outcomes or the most conservative possible cases. A sensitivity analysis performed in Section 4.2 shows that if the probability of either the ignition of fuel event or the fuel flows into riser event were underestimated by an order of magnitude, the accident frequency for a pool fire could increase and shift into the ''unlikely'' category. If the probability of an increase in riser strikes, or an increase in broken risers, unignited fuel entering a riser, or a fuel ignition source being present in a tank were underestimated by an order of magnitude, the accident frequency for a deflagration would remain in the ''unlikely'' category. When the likelihood of a broken riser is increased by an order of magnitude, a pool fire remains in the ''extremely unlikely'' category. The DSA accident analysis indicates that an unmitigated flammable gas deflagration resulting from an induced gas release event or an organic solvent fire occurring in either an SST or a DST is an anticipated event (> 10{sup -2}). Deflagration in a DST annulus is considered unlikely (> 10{sup -4} to {le}10{sup -2}). These frequencies clearly bound those of the in-tank vehicle fuel fire family of accidents.

HARRIS, J.P.

2003-10-14T23:59:59.000Z

260

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

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261

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

262

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

263

Capacity Value of Solar Power  

Science Conference Proceedings (OSTI)

Evaluating the capacity value of renewable energy sources can pose significant challenges due to their variable and uncertain nature. In this paper the capacity value of solar power is investigated. Solar capacity value metrics and their associated calculation methodologies are reviewed and several solar capacity studies are summarized. The differences between wind and solar power are examined, the economic importance of solar capacity value is discussed and other assessments and recommendations are presented.

Duignan, Roisin; Dent, Chris; Mills, Andrew; Samaan, Nader A.; Milligan, Michael; Keane, Andrew; O'Malley, Mark

2012-11-10T23:59:59.000Z

264

Load Capacity of Bodies  

E-Print Network (OSTI)

For the stress analysis in a plastic body $\\Omega$, we prove that there exists a maximal positive number $C$, the \\emph{load capacity ratio,} such that the body will not collapse under any external traction field $t$ bounded by $Y_{0}C$, where $Y_0$ is the elastic limit. The load capacity ratio depends only on the geometry of the body and is given by $$ \\frac{1}{C}=\\sup_{w\\in LD(\\Omega)_D} \\frac{\\int_{\\partial\\Omega}|w|dA} {\\int_{\\Omega}|\\epsilon(w)|dV}=\\left\\|\\gamma_D\\right\\|. $$ Here, $LD(\\Omega)_D$ is the space of isochoric vector fields $w$ for which the corresponding stretchings $\\epsilon(w)$ are assumed to be integrable and $\\gamma_D$ is the trace mapping assigning the boundary value $\\gamma_D(w)$ to any $w\\in LD(\\Omega)_D$.

Reuven Segev

2005-11-01T23:59:59.000Z

265

Refinery Capacity Report  

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

1 1 Idle Operating Total Stream Day Barrels per Idle Operating Total Calendar Day Barrels per Atmospheric Crude Oil Distillation Capacity Idle Operating Total Operable Refineries Number of State and PAD District a b b 14 10 4 1,617,500 1,205,000 412,500 1,708,500 1,273,500 435,000 ............................................................................................................................................... PAD District I 1 0 1 182,200 0 182,200 190,200 0 190,200 ................................................................................................................................................................................................................................................................................................ Delaware......................................

266

Total Natural Gas Underground Storage Capacity  

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

Capacity Working Gas Capacity of Salt Caverns Working Gas Capacity of Aquifers Working Gas Capacity of Depleted Fields Total Number of Existing Fields Number of Existing Salt...

267

Changing World Product Markets and Potential Refining Capacity ...  

U.S. Energy Information Administration (EIA)

The presentation explores potential refinery capacity increases over the next 5 years in various world regions, based on changing demand patterns, changing price ...

268

Global nuclear generation capacity totaled more than 370 gigawatts ...  

U.S. Energy Information Administration (EIA)

Chinawhere plans for large increases in nuclear capacity had been announcedinstituted a temporary moratorium on new approvals for nuclear power ...

269

Natural Gas Productive Capacity for the Lower-48 States  

U.S. Energy Information Administration (EIA)

An analysis report from the Energy Information Administration which estimates the increases in natural gas productive capacity which should be expected in 2001, given ...

270

EVALUATION OF LOW TEMPERATURE ALUMINUM DISSOLUTION IN TANK 51  

Science Conference Proceedings (OSTI)

Liquid Waste Organization (LWO) identified aluminum dissolution as a method to mitigate the effect of having about 50% more solids in High Level Waste (HLW) sludge than previously planned. Previous aluminum dissolution performed in a HLW tank in 1982 was performed at approximately 85 C for 5 days, which became the baseline aluminum dissolution process. LWO initiated a project to modify a waste tank to meet these requirements. Subsequent to an alternative evaluation, LWO management identified an opportunity to perform aluminum dissolution on sludge destined for Sludge Batch 5, but within a limited window that would not allow time for any modifications for tank heating. A variation of the baseline process, dubbed Low Temperature Aluminum Dissolution (LTAD), was developed based on the constraint of available energy input in Tank 51 and the window of opportunity, but was not constrained to a minimum extent of dissolution, i.e. dissolve as much aluminum as possible within the time available. This process was intended to operate between 55 and 70 C, but for a significantly longer time than the baseline process. LTAD proceeded in parallel with the baseline project. The preliminary evaluation at the completion of LTAD focused on the material balance and extent of the aluminum dissolved. The range of values of extent of dissolution, 56% to 64%, resulted from the variation in liquid phase sample data available at the time. Additional solid phase data is available from a sample taken after LTAD to refine this range. This report provides additional detailed evaluation of the LTAD process based on analytical and field data and includes: a summary of the process chronology; a determination of an acceptable blending strategy for the aluminum-laden supernate stored in Tank 11; an update to the determination of aluminum dissolved using more complete sample results; a determination of the effect of LTAD on uranium, plutonium, and other metals; a determination of the rate of heat loss from a quiescent tank; and an evaluation of the aluminum dissolution rate model and actual dissolution rate. LTAD was successfully completed in Tank 51 with minimal waste tank changes. The following general conclusions may be drawn about the LTAD process: (1) Dissolution at about 60 C for 46 days dissolved 64% of the aluminum from the sludge slurry. (2) The aluminum-laden leach solution decanted to Tank 11 can be blended with a wide variety of supernates without risk of precipitating the dissolved aluminum based on thermodynamic chemical equilibrium models. (3) Uranium and plutonium leached into solution without corresponding leaching of iron or metal other than aluminum, but the total mass leached was a small fraction of the total uranium and plutonium in the sludge. (4) The concentration of uranium and plutonium in the leach solution was indistinguishable from other tank farm supernates, thus, the leach solutions can be managed relative to the risk of criticality like any other supernate. (5) A small amount of mercury leached into solution from the sludge causing the liquid phase concentration to increase 6 to 10 fold, which is consistent with the 4 to 14 fold increase observed during the 1982 aluminum dissolution demonstration. (6) Chromium did not dissolve during LTAD. (7) Chloride concentration increased in the liquid phase during LTAD due to chloride contamination in the 50% sodium hydroxide solution. (8) The rate of heat loss from Tank 51 at temperatures above 45 C appeared linear and predictable at 8E+7 cal/hr. (9) The rate of heat transfer from Tank 51 did not follow a simplified bulk heat transfer model. (10) Prediction of the aluminum dissolution rate was prone to error due to a lack of active specific surface area data of sludge particles. (11) The higher than expected dissolution rate during LTAD was likely due to smaller than expected particle sizes of most of the sludge particles. While evaluating the LTAD process, the dissolved salt solution from Tank 41 that was stored and sampled in Tank 49 was determined to be supersaturated relative to alu

Pike, J

2008-09-04T23:59:59.000Z

271

CSER 94-09: Implications of the heat anomaly in Tank 106-C to criticality safety  

Science Conference Proceedings (OSTI)

Water is periodically added to Tank C-106 to cool its waste. In March 1994 addition of water was temporarily discontinued to determine if the tank could be adequately cooled at a lower water level. Following an addition of water, a temperature fluctuation was observed on one of the thermocouple trees. This Criticality Safety Evaluation Report (CSER) explains why the anomalous temperature measurements could not have been caused by nuclear criticality. Waste in Tank C-106 was discharged from processing facilities under controls designed to ensure that the contents of the tank would remain well subcritical under all credible conditions. The observed temperature profile does not fit the profile expected from a criticality event. In addition, there has been no indication of any significant increase in the rate of water evaporation.

Rogers, C.A.

1994-10-01T23:59:59.000Z

272

Experimental evaluation of a simulation model for wrap-around heat exchanger, solar storage tanks  

DOE Green Energy (OSTI)

The thermal performance of a commercially available 80 gallon, solar storage tank with an integral wrap-around heat exchanger is characterized experimentally an indoor test stand. The experimental results are used to evaluated the accuracy of a previously developed simulation model. Heat input on the collector side of the heat exchanger is held constant causing the heat transfer to reach a quasi-steady state. Temperatures in the heat exchanger and tank increase with time, however, the temperature differences across the heat exchanger remain nearly constant. Several combinations of heat input and collector loop flow are investigated. The development of the tank temperature profiles over time and the overall heat transfer performance predicted by the model are compared with experimental results. The influence of an electric auxiliary heater located in the top of the solar storage tank on the heat exchanger performance is investigated. Experimental normalization of the model is considered and modifications to the model and experiments are recommended.

Miller, J.A.; Hittle, D.C.

1995-05-01T23:59:59.000Z

273

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

274

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

275

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

276

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

277

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

278

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

279

DEMONSTRATION OF MIXING AND TRANSFERRING SETTLING COHESIVE SLURRY SIMULANTS IN THE AY-102 TANK  

SciTech Connect

In support of Hanford's feed delivery of high level waste (HLW) to the Waste Treatment and Immobilization Plant (WTP), pilot-scale testing and demonstrations with simulants containing cohesive particles were performed as a joint collaboration between Savannah River National Laboratory (SRNL) and the Pacific Northwest National Laboratory (PNNL) staff. The objective of the demonstrations was to determine the impact that cohesive particle interactions in the simulants, and the resulting non-Newtonian rheology, have on tank mixing and batch transfer of large and dense seed particles. The work addressed the impacts cohesive simulants have on mixing and batch transfer performance in a pilot-scale system. Kaolin slurries with a range of wt% concentrations to vary the Bingham yield stress were used in all the non-Newtonian simulants. To study the effects of just increasing the liquid viscosity (no yield stress) on mixing and batch transfers, a glycerol/water mixture was used. Stainless steel 100 micron particles were used as seed particles due to their density and their contrasting color to the kaolin and glycerol. In support of Hanford's waste certification and delivery of tank waste to the Waste Treatment and Immobilization Plant (WTP), Savannah River National Laboratory (SRNL) was tasked by Washington River Protection Solutions (WRPS) to evaluate the effectiveness of mixing and transferring tank waste in a Double Shell Tank (DST) to the WTP Receipt Tank. The work addresses the impacts cohesive simulants have on mixing and batch transfer performance. This work is follow-on to the previous tasks 'Demonstration of Mixer Jet Pump Rotational Sensitivity on Mixing and Transfers of the AY-102 Tank' and 'Demonstration of Simulated Waste Transfers from Tank AY-102 to the Hanford Waste Treatment Facility'. The cohesive simulants were investigated and selected jointly by SRNL and PNNL and a white paper was written on this evaluation. The testing and demonstrations of cohesive simulants was a joint effort performed as collaboration between SRNL and PNNL staff. The objective of the demonstrations was to determine the impact that cohesive particle interactions in the simulants have on tank mixing using the 1/22nd scale mixing system and batch transfer of seed particles. Seed particles are particles of contracting color added to mixing tank for visual inspection and an indicator of how well the contents of the tank are mixing. Also the seed particles serve as a measuring stick for how well the contents of the tank are transferred from the mixing tank during batch transfers. This testing is intended to provide supporting evidence to the assumption that Hanford Small Scale Mixing Demonstration (SSMD) testing in water is conservative.

Adamson, D.; Gauglitz, P.

2012-01-03T23:59:59.000Z

280

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 "tanks capacity increase" 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

Increased Power Flow Guidebook - 2012  

Science Conference Proceedings (OSTI)

The EPRI Increased Power Flow (IPF) Guidebook is a state-of-the-art and best- practices reference and guidebook on increasing the power flow capacities of existing overhead transmission lines, underground cables, power transformers, and substation equipment, without compromising safety and reliability. The Guidebook discusses power system concerns and limiting conditions to increasing capacity, reviews available technology options and methods, illustrates the alternatives with case ...

2012-12-31T23:59:59.000Z

282

Increased Power Flow Guidebook - 2013  

Science Conference Proceedings (OSTI)

The EPRI Increased Power Flow (IPF) Guidebook is a state-of-the-art and best- practices reference and guidebook on increasing the power flow capacities of existing overhead transmission lines, underground cables, power transformers, and substation equipment, without compromising safety and reliability. The Guidebook discusses power system concerns and limiting conditions to increasing capacity, reviews available technology options and methods, illustrates the alternatives with case ...

2013-11-18T23:59:59.000Z

283

Capacities associated with scalar signed Riesz kernels, and analytic capacity  

E-Print Network (OSTI)

The real and imaginari parts of the Cauchy kernel in the plane are scalar Riesz kernels of homogeneity -1. One can associate with each of them a natural notion of capacity related to bounded potentials. The main result of the paper asserts that these capacities are comparable to classical analytic capacity, thus stressing the real variables nature of analytic capacity. Higher dimensional versions of this result are also considered.

Mateu, Joan; Verdera, Joan

2010-01-01T23:59:59.000Z

284

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

285

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

286

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

287

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

288

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

289

PROBABILITY BASED CORROSION CONTROL FOR WASTE TANKS - PART II  

SciTech Connect

As part of an ongoing study to evaluate the discontinuity in the corrosion controls at the SRS tank farm, a study was conducted this year to assess the minimum concentrations below 1 molar nitrate, see Figure 1. Current controls on the tank farm solution chemistry are in place to prevent the initiation and propagation of pitting and stress corrosion cracking in the primary steel waste tanks. The controls are based upon a series of experiments performed with simulated solutions on materials used for construction of the tanks, namely ASTM A537 carbon steel (A537). During FY09, an experimental program was undertaken to investigate the risk associated with reducing the minimum molar nitrite concentration required to confidently inhibit pitting in dilute solutions (i.e., less than 1 molar nitrate). The experimental results and conclusions herein provide a statistical basis to quantify the probability of pitting for the tank wall exposed to various solutions with dilute concentrations of nitrate and nitrite. Understanding the probability for pitting will allow the facility to make tank-specific risk-based decisions for chemistry control. Based on previous electrochemical testing, a statistical test matrix was developed to refine and solidify the application of the statistical mixture/amount model to corrosion of A537 steel. A mixture/amount model was identified based on statistical analysis of recent and historically collected electrochemical data. This model provides a more complex relationship between the nitrate and nitrite concentrations and the probability of pitting than is represented by the model underlying the current chemistry control program, and its use may provide a technical basis for the utilization of less nitrite to inhibit pitting at concentrations below 1 molar nitrate. FY09 results fit within the mixture/amount model, and further refine the nitrate regime in which the model is applicable. The combination of visual observations and cyclic potentiodynamic polarization scans indicates a potential for significant inhibitor reductions at nitrate concentrations near 1.0 M without a significant increase in corrosion risk. The complete data sets from FY08 and FY09 testing have determined the statistical basis to confidently inhibit against pitting using nitrite inhibition with the current pH controls. Future testing will complete the spectrum of nitrate concentrations around 1 molar. These results will be combined to provide a complete spectrum for corrosion controls with a risk based component.

Hoffman, E.; Edwards, T.

2010-12-09T23:59:59.000Z

290

Multipath Channels of Unbounded Capacity  

E-Print Network (OSTI)

The capacity of discrete-time, noncoherent, multipath fading channels is considered. It is shown that if the variances of the path gains decay faster than exponentially, then capacity is unbounded in the transmit power.

Koch, Tobias

2008-01-01T23:59:59.000Z

291

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

DOE Green Energy (OSTI)

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

Bryan, S.A.; Pederson, L.R.; Ryan, J.L.; Scheele, R.D.; Tingey, J.M.

1992-08-01T23:59:59.000Z

292

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

293

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

294

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

295

Heat capacities of elastic solids  

E-Print Network (OSTI)

The work function is embedded in the equation describing the relationship between the constant volume and constant pressure heat capacities. The modification of the work function results that the relationship between these quantities must be changed accordingly. Using the newly derived work functions of elastic solids the description of the heat capacities and the relationship between the heat capacities are given for solid phase.

Garai, J

2005-01-01T23:59:59.000Z

296

Symmetrical Symplectic Capacity with Applications  

E-Print Network (OSTI)

In this paper, we first introduce the concept of symmetrical symplectic capacity for symmetrical symplectic manifolds, and by using this symmetrical symplectic capacity theory we prove that there exists at least one symmetric closed characteristic (brake orbit and $S$-invariant brake orbit are two examples) on prescribed symmetric energy surface which has a compact neighborhood with finite symmetrical symplectic capacity.

Liu, Chungen

2010-01-01T23:59:59.000Z

297

Capacity Value of Wind Power - Summary  

Science Conference Proceedings (OSTI)

Power systems are planned such that they have adequate generation capacity to meet the load, according to a defined reliability target. The increase in the penetration of wind generation in recent years has led to a number of challenges for the planning and operation of power systems. A key metric for generation system adequacy is the capacity value of generation. The capacity value of a generator is the contribution that a given generator makes to generation system aequacy. The variable and stochastic nature of wind sets it apart from conventional energy sources. As a result, the modeling of wind generation in the same manner as conventional generation for capacity value calculations is inappropriate. In this paper a preferred method for calculation of the capacity value of wind is described and a discussion of the pertinent issues surrounding it is given. Approximate methods for the calculation are also described with their limitations highlighted. The outcome of recent wind capacity value analyses in Europe and North America, along with some new analysis, are highlighted with a discussion of relevant issues also given.

O'Malley, M.; Milligan, M.; Holttinen, H.; Dent, C.; Keane, A.

2010-01-01T23:59:59.000Z

298

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...

299

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

300

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

Note: This page contains sample records for the topic "tanks capacity increase" 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

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

302

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

303

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

304

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

305

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

306

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

307

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

308

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

309

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

310

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

311

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

312

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

313

Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank  

DOE Patents (OSTI)

The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.

Corletti, Michael M. (New Kensington, PA); Lau, Louis K. (Monroeville, PA); Schulz, Terry L. (Murrysville Boro, PA)

1993-01-01T23:59:59.000Z

314

Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank  

DOE Patents (OSTI)

The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps. 1 figures.

Corletti, M.M.; Lau, L.K.; Schulz, T.L.

1993-12-14T23:59:59.000Z

315

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

SciTech Connect

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

Rogers, C.A.

1994-09-22T23:59:59.000Z

316

Environmental Program Description for the Tank Farm Contractor  

SciTech Connect

This Environmental Program Description has been developed in support of the Integrated Environmental, Safety, and Health Management System and consistent with the goals of DOE/RL-96-50, Hanford Strategic Plan. This Environmental Program Plan was developed in support of the Integrated Environment, Safety, and Health Management System Description for the Tank Farm Contractor (ISMS) (RPP-MP-003), which establishes a single, defined environmental, safety, and health management system that integrates requirements into the work planning and execution processes to protect workers, the public, and the environment. The ISMS also provides mechanisms for increasing worker involvement in work planning, including hazard and environmental impact identification, analysis, and control; work execution; and feedback/improvement processes. The ISMS plan consists of five core functions. Each section of this plan describes the activities (formerly known as the Tank Waste Remediation System) of the Tank Farm Contractor (TFC) environmental organization according to the following core functions: Establish Environmental Policy and Define Work Scope; Identify Hazards, Environmental Impacts, and Requirements; Analyze Hazards and Environmental Impacts and Implement Controls; Provide Feedback and Continuous Improvement; and Perform Work within Controls.

POWELL, P.A.

2000-04-20T23:59:59.000Z

317

An Assessment of Railway Capacity  

E-Print Network (OSTI)

In this paper, we review the main concepts and methods to perform capacity analyses, and we present an automated tool that is able to perform several capacity analyses. Capacity is extremely dependent on infrastructure, traffic, and operating parameters. Therefore, an in-depth study of the main factors that influence railway capacity is performed on several Spanish railway infrastructures. The results show how the capacity varies according to factors such as train speed, commercial stops, train heterogeneity, distance between railway signals, and timetable robustness.

M. Abril; F. Barber; A L. Ingolotti; A M. A. Salido; P. Tormos; B A. Lova

2007-01-01T23:59:59.000Z

318

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

319

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

320

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

Note: This page contains sample records for the topic "tanks capacity increase" 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

Entangling capacity with local ancilla  

E-Print Network (OSTI)

We investigate the entangling capacity of a dynamical operation with access to local ancilla. A comparison is made between the entangling capacity with and without the assistance of prior entanglement. An analytic solution is found for the log-negativity entangling capacity of two-qubit gates, which equals the entanglement of the Choi matrix isomorphic to the unitary operator. Surprisingly, the availability of prior entanglement does not affect this result; a property we call resource independence of the entangling capacity. We prove several useful upper-bounds on the entangling capacity that hold for general qudit dynamical operations, and for a whole family of entanglement measures including log-negativity and log-robustness. The log-robustness entangling capacity is shown to be resource independent for general dynamics. We provide numerical results supporting a conjecture that the log-negativity entangling capacity is resource independence for all two-qudit unitaries.

Campbell, Earl T

2010-01-01T23:59:59.000Z

322

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

323

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

324

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

325

Classical capacity of a qubit depolarizing channel with memory  

E-Print Network (OSTI)

The classical product state capacity of a noisy quantum channel with memory is investigated. A forgetful noise-memory channel is constructed by Markov switching between two depolarizing channels which introduces non-Markovian noise correlations between successive channel uses. The computation of the capacity is reduced to an entropy computation for a function of a Markov process. A reformulation in terms of algebraic measures then enables its calculation. The effects of the hidden-Markovian memory on the capacity are explored. An increase in noise-correlations is found to increase the capacity.

Jeroen Wouters; Ismail Akhalwaya; Mark Fannes; Francesco Petruccione

2009-01-16T23:59:59.000Z

326

STATUS OF THE DEVELOPMENT OF IN-TANK/AT-TANK SEPARATIONS TECHNOLOGIES FOR FOR HIGH-LEVEL WASTE PROCESSING FOR THE U.S. DEPARTMENT OF ENERGY  

SciTech Connect

Within the U.S. Department of Energy's (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in 'tank farms'). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are 'first-of-a-kind' and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant re-engineering to adapt to DOE's specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanford's Waste Treatment and Immobilization Plant (WTP) or Savannah River's Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration. This paper will review the status of several of the R&D projects being developed by the U.S. DOE including insertion of the ion exchange (IX) technologies, such as Small Column Ion Exchange (SCIX) at Savannah River. This has the potential to align the salt and sludge processing life cycle, thereby reducing the Defense Waste Processing Facility (DWPF) mission by 7 years. Additionally at the Hanford site, problematic waste streams, such as high boehmite and phosphate wastes, could be treated prior to receipt by WTP and thus dramatically improve the capacity of the facility to process HLW. Treatment of boehmite by continuous sludge leaching (CSL) before receipt by WTP will dramatically reduce the process cycle time for the WTP pretreatment facility, while treatment of phosphate will significantly reduce the number of HLW borosilicate glass canisters produced at the WTP. These and other promising technologies will be discussed.

Aaron, G.; Wilmarth, B.

2011-09-19T23:59:59.000Z

327

Data reconcilation study of Tank 241-AN-105 at the Hanford Site  

Science Conference Proceedings (OSTI)

The Project Hanford Management Contractor gave the Los Alamos National Laboratory Nuclear Systems Design and Analysis Group (TSA-10) the task of performing data reconciliation studies on flammable-gas watchlist tanks at the Hanford Site. This task is being performed in support of the flammable-gas programs at the Hanford Site and for closure of the flammable-gas unreviewed safety question. In our data reconciliation studies, we examine all available data from a global point of view. Our goal is to find an explanation, or conceptual model, of the tank behavior that is consistent with all available data. Our primary tool in this study of Tank 241-AN-105 is the maximum likelihood method of data reconciliation, which we have applied successfully to other tanks in the past. This method helps us (1) determine whether a model is consistent with the data, and (2) obtain quantitative estimates that are consistent with the data. A release of a flammable quantity of hydrogen in Tank 241-AN-105 is possible but unlikely at the current time. Any changes to the waste that could cause large releases would be accompanied by a measurable increase in the surface level of the waste. We also theorize that a significant increase in the waste temperature may signal a qualitative change in the behavior of the waste and an increase in the flammability hazard.

Kubic, W.L. Jr.; Pillay, G.

1998-12-31T23:59:59.000Z

328

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

Nuclear power provides about 20 % of the total electricity generated in the United States. In 2005, this was about 782 Billion kWh of the total electricity generation (EIA 2006). 2 As with fossil-fueled electricity generating plants, electricity in a nuclear power plant is produced by heated steam that drives a turbine generator. In a nuclear power plant, however, nuclear fission reactions in the core produce heat that is absorbed by a liquid that flows through the system and is converted to steam. Nuclear power plants are highly efficient and have become more so over the last 25 years. Operational efficiency (also referred to as plant performance or electricity production) can be measured by the capacity factor. The capacity factor is the ratio of the actual amount of electricity generated to the maximum possible amount that could be generated in a given period of time usually a year. Today, nuclear power plants operate at an average 90 % capacity factor (compared to 56 % in 1980) (EIA 2006a). Thus, although nuclear generating capacity has remained roughly constant since 1990, at about 99 gigawatts (or about 10 % of the total U.S. electric generating capacity), the amount of electricity produced has increased 33 % since that time because of increased capacity utilization. Nuclear plants have the highest capacity factors of

unknown authors

2006-01-01T23:59:59.000Z

329

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

330

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

331

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

332

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

333

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

334

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

335

Oak Ridge National Laboratory Gunite and Associated Tanks Stabilization Project-Low-Tech Approach with High-Tech Results  

SciTech Connect

Environmental restoration of the Gunite and Associated Tanks (GAAT) at the Oak Ridge National Laboratory (ORNL) was a priority to the U. S. Department of Energy (DOE) because of their age and deteriorating structure. These eight tanks ranging up to 170,000 gallons in capacity were constructed in 1943 of a Gunite or ''sprayed concrete material'' as part of the Manhattan Project. The tanks initially received highly radioactive waste from the Graphite Reactor and associated chemical processing facilities. The waste was temporarily stored in these tanks to allow for radioactive decay prior to dilution and release into surface waters. Over time, additional wastes from ongoing ORNL operations (e.g., isotope separation and materials research) were discharged to the tanks for storage and treatment. These tanks were taken out of service in the 1970s. Based on the structure integrity of GAAT evaluated in 1995, the worst-case scenario for the tanks, even assuming they are in good condition, is to remain empty. A recently completed interim action conducted from April 1997 through September 2000 removed the tank liquids and residual solids to the extent practical. Interior video surveys of the tanks indicated signs of degradation of the Gunite material. The tanks continued to receive inleakage, which generated a relatively high volume waste stream that required periodic removal, treatment, and disposal. For these reasons, DOE chose in-place stabilization of Tanks W-3 through W-10 as a non-timecritical removal action under Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Tank stabilization activities involved removal of liquid from inleakage and placement of a grout mixture or ''flowable fill'' into the tanks to within 3-ft of the ground surface. Bechtel Jacobs Company, LLC (BJC) awarded Safety and Ecology Corporation (SEC) a subcontract in March 2001 to complete the documentation and fieldwork necessary to achieve tank stabilization in accordance with the Action Memorandum. Tank stabilization activities began on April 23, 2001, and were completed one month ahead of schedule on August 31, 2001. Over 7400 cubic yards of grout were placed in these tanks stabilizing over 4,000 Ci of radioactive material in place. This schedule acceleration was the result of good pre-planning during pre-mobilization by working with BJC, grout vendor, and pumping company, and other subcontractors. This planning allowed refinement of the pump and hose system used to convey the grout and the formulation of the grout mixture. Because of expediting the work, additional activities could be accomplished at the GAAT site that resulted in complete site restoration to a paved area for future parking, which was completed by September 30, 2001. This paper will focus on the following items associated with this successful environmental restoration project: regulatory process; integrated safety management systems used to achieve zero accident performance while expediting the schedule; tank stabilization design and implementation; and implementation strategies involving partnering of multiple subcontractors, DOE, and regulators.

Brill, A.; Alsup, T.; Bolling, D.

2002-02-26T23:59:59.000Z

336

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

337

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

338

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

339

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

340

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

Note: This page contains sample records for the topic "tanks capacity increase" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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341

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

342

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

343

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

344

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

345

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

346

Heat capacity at the glass transition  

E-Print Network (OSTI)

A fundamental problem of glass transition is to explain the jump of heat capacity at the glass transition temperature $T_g$ without asserting the existence of a distinct solid glass phase. This problem is also common to other disordered systems, including spin glasses. We propose that if $T_g$ is defined as the temperature at which the liquid stops relaxing at the experimental time scale, the jump of heat capacity at $T_g$ follows as a necessary consequence due to the change of system's elastic, vibrational and thermal properties. In this picture, we discuss time-dependent effects of glass transition, and identify three distinct regimes of relaxation. Our approach explains widely observed logarithmic increase of $T_g$ with the quench rate and the correlation of heat capacity jump with liquid fragility.

Kostya Trachenko; Vadim Brazhkin

2010-02-10T23:59:59.000Z

347

Underground Natural Gas Working Storage Capacity - Energy Information  

Gasoline and Diesel Fuel Update (EIA)

Underground Natural Gas Working Storage Capacity Underground Natural Gas Working Storage Capacity With Data for November 2012 | Release Date: July 24, 2013 | Next Release Date: Spring 2014 Previous Issues Year: 2013 2012 2011 2010 2009 2008 2007 2006 Go Overview Natural gas working storage capacity increased by about 2 percent in the Lower 48 states between November 2011 and November 2012. The U.S. Energy Information Administration (EIA) has two measures of working gas storage capacity, and both increased by similar amounts: Demonstrated maximum volume increased 1.8 percent to 4,265 billion cubic feet (Bcf) Design capacity increased 2.0 percent to 4,575 Bcf Maximum demonstrated working gas volume is an operational measure of the highest level of working gas reported at each storage facility at any time

348

Decentralized capacity management and internal pricing  

E-Print Network (OSTI)

Press. Goex, R. (2002). Capacity planning and pricing undermanufacturing on innovation, capacity and pro?tability.Mieghem, V. J. (2003). Capacity management, investment and

Dutta, Sunil; Reichelstein, Stefan

2010-01-01T23:59:59.000Z

349

Capacity consideration of wireless ad hoc networks  

E-Print Network (OSTI)

Capacity ProblemCurrent Research on Capacity of Wireless Ad HocChapter 3 Upper Bound on the Capacity of Wireless Ad Hoc

Tan, Yusong

2008-01-01T23:59:59.000Z

350

Are there capacity limitations in symmetry perception?  

E-Print Network (OSTI)

1980). The demonstration of capacity limitation. Cognitive1972). Visual processing capacity and attentional control.J. (1996). Goodness of CAPACITY LIMIT OF SYMMETRY PERCEPTION

Huang, L Q; Pashler, Harold; Junge, J A

2004-01-01T23:59:59.000Z

351

The Ergodic Capacity of Interference Networks  

E-Print Network (OSTI)

A. Jafar, The ergodic capacity of interference networks,Gupta and P. R. Kumar, The capacity of wireless networks,cooperation achieves optimal capacity scaling in ad hoc

Jafar, Syed A

2010-01-01T23:59:59.000Z

352

Mapping Individual Variations in Learning Capacity  

E-Print Network (OSTI)

in working memory capacity. Integrative Physiological andVariations in Learning Capacity Eduardo Mercado IIIdifferences in learning capacity are evident in humans and

Mercado III, Eduardo

2011-01-01T23:59:59.000Z

353

Definition: Capacity Emergency | Open Energy Information  

Open Energy Info (EERE)

Emergency Jump to: navigation, search Dictionary.png Capacity Emergency A capacity emergency exists when a Balancing Authority Area's operating capacity, plus firm purchases from...

354

Two-stage approach for the assessment of distributed generation capacity mixture in active distribution networks  

Science Conference Proceedings (OSTI)

Distribution networks are limited with spare capacities to integrate increased volumes of distributed generation (DG). Network constraints and congestion

D. Jayaweera; S. Islam; S. Neduvelil

2013-01-01T23:59:59.000Z

355

Capacity Markets for Electricity  

E-Print Network (OSTI)

or to increase the energy price-cap in order to avoid thei.e. K + ? ? 1. A3 : The foreign energy price is higherthan the national energy price-cap, i.e. f > P. If recalled,

Creti, Anna; Fabra, Natalia

2004-01-01T23:59:59.000Z

356

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

SciTech Connect

To improve the understanding of the single-shell tanks integrity, Washington River Protection Solutions, LLC, the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank (SST) Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The change package identified two phases of work for SST integrity. The initial phase has been focused on efforts to envelope the integrity of the tanks. The initial phase was divided into two primary areas of investigation: structural integrity and leak integrity. If necessary based on the outcome from the initial work, a second phase would be focused on further definition of the integrity of the concrete and liners. Combined these two phases are designed to support the formal integrity assessment of the Hanford SSTs in 2018 by Independent Qualified Registered Engineer. The work to further define the DOE's understanding of the structural integrity SSTs involves preparing a modern Analysis of Record using a finite element analysis program. Structural analyses of the SSTs have been conducted since 1957, but these analyses used analog calculation, less rigorous models, or focused on individual structures. As such, an integrated understanding of all of the SSTs has not been developed to modern expectations. In support of this effort, other milestones will address the visual inspection of the tank concrete and the collection of concrete core samples from the tanks for analysis of current mechanics properties. The work on the liner leak integrity has examined the leaks from 23 tanks with liner failures. Individual leak assessments are being developed for each tank to identify the leak cause and location. Also a common cause study is being performed to take the data from individual tanks to look for trends in the failure. Supporting this work is an assessment of the leak rate from tanks at both Hanford and the Savannah River Site and a new method to locate leak sites in tank liner using ionic conductivity. A separate activity is being conducted to examine the propensity for corrosion in select single shell tanks with aggressive waste layers. The work for these two main efforts will provide the basis for the phase two planning. If the margins identified aren't sufficient to ensure the integrity through the life of the mission, phase two would focus on activities to further enhance the understanding of tank integrity. Also coincident with any phase-two work would be the integrity analysis for the tanks, which would be complete in 2018. With delays in the completion of waste treatment facilities at Hanford, greater reliance on safe, continued storage of waste in the single shell tanks is increased in importance. The goal of integrity assessment would provide basis to continue SST activities till the end of the treatment mission.

VENETZ TJ; BOOMER KD; WASHENFELDER DJ; JOHNSON JB

2012-01-25T23:59:59.000Z

357

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

358

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

359

Electric Capacity | OpenEI  

Open Energy Info (EERE)

Capacity Capacity Dataset Summary Description The New Zealand Ministry of Economic Development publishes an annual Energy Outlook, which presents projections of New Zealand's future energy supply, demand, prices and greenhouse gas emissions. The principle aim of these projections is to inform the national energy debate. Included here are the model results for electricity and generation capacity. The spreadsheet provides an interactive tool for selecting which model results to view, and which scenarios to evaluate; full model results for each scenario are also included. Source New Zealand Ministry of Economic Development Date Released Unknown Date Updated December 15th, 2010 (3 years ago) Keywords Electric Capacity Electricity Generation New Zealand projections

360

Adaptive capacity and its assessment  

SciTech Connect

This paper reviews the concept of adaptive capacity and various approaches to assessing it, particularly with respect to climate variability and change. I find that adaptive capacity is a relatively under-researched topic within the sustainability science and global change communities, particularly since it is uniquely positioned to improve linkages between vulnerability and resilience research. I identify opportunities for advancing the measurement and characterization of adaptive capacity by combining insights from both vulnerability and resilience frameworks, and I suggest several assessment approaches for possible future development that draw from both frameworks and focus on analyzing the governance, institutions, and management that have helped foster adaptive capacity in light of recent climatic events.

Engle, Nathan L.

2011-04-20T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Pemex increasing offshore activity  

SciTech Connect

Although austere by boom-year standards, Mexico's National Energy Program for 1984-1988 calls for forty wildcats and 90 to 144 development wells off the coast, primarily in the prolific Campeche Bay area. Platform additions will include nine drilling platforms, each for twelve wells, and eight eight platforms to drill injection wells. Additionally, 7 production, 6 accomodation, 6 linkage and 8 compression platforms and 13 tetrapods will be installed. The main objectives of the plan are energy self-sufficiency through the turn of the century, and energy diversification, savings and productivity. The most controversial portion of Mexico's energy program is that calling for nuclear energy development. The energy program lists three basic goals in hydrocarbon production: continuing research on better techniques of secondary recovery; increasing capacity for refining primary and secondary crude products and improving production of heavy crudes; and increasing storage capacity and installing pipelines capable of carrying a greater volume of crude.

Beachy, D.

1985-05-01T23:59:59.000Z

362

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

363

HANFORD DOUBLE SHELL TANK (DST) THERMAL & SEISMIC PROJECT DYTRAN BENCHMARK ANALYSIS OF SEISMICALLY INDUCED FLUID STRUCTURE INTERACTION IN FLAT TOP TANKS  

SciTech Connect

The work reported in this document was performed in support of a project entitled ''Double-Shell Tank (DST) 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. 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 herein was motivated by review comments from a Project Review Meeting held on March 20-21, 2006. One of the recommendations from that meeting was that the effects of the interaction between the tank liquid and the roof be further studied (Rinker, Deibler, Johnson, Karri, Pilli, Abatt, Carpenter, and Hendrix - Appendix E of RPP-RPT-28968, Rev. 1). The reviewers recommended that solutions be obtained for seismic excitation of flat roof tanks containing liquid with varying headspace between the top of the liquid and the tank roof. It was recommended that the solutions be compared with simple, approximate procedures described in BNL (1995) and Malhotra (2005). This report documents the results of the requested studies and compares the predictions of Dytran simulations to the approximate procedures in BNL (1995) and Malhotra (2005) for flat roof tanks. The four cases analyzed all employed a rigid circular cylindrical flat top tank with a radius of 450 in. and a height of 500 in. The initial liquid levels in the tank were 460,480,490, and 500 in. For the given tank geometry and the selected seismic input, the maximum unconstrained slosh height of the liquid is slightly greater than 25 in. Thus, the initial liquid level of 460 in. represents an effectively roofless tank, the two intermediate liquid levels lead to intermittent interaction between the liquid and tank roof, and the 500 in. liquid level represents a completely full tank with no sloshing. Although this work was performed in support of the seismic analysis of the Hanford DSTs, the tank models in this study are for an idealized flat top configuration. Moreover, the liquid levels used in the present models are for study purposes only and are independent of the actual operating levels of the DSTs. The response parameters that are evaluated in this study are the total hydrodynamic reaction forces, the peak convective hydrodynamic forces, the fundamental convective frequencies, the liquid pressures, and peak slosh heights. The results show that the Dytran solutions agree well with the known solutions for the roofless tank and completely full tank. At the two intermediate liquid levels, there are some significant differences between the Dytran results and the approximate estimates. The results show that the estimates of peak hydrodynamic reaction forces appearing in BNL (1995) and Malhotra (2005) are reasonable and generally conservative relative to the Dytran solutions. At the 460 and 480 in. liquid levels, Dytran underestimates the convective component of the reaction force compared to the estimated in BNL (1995) and Malhotra (2005), but the convective component of the reaction force is small relative to the total reaction force. At the 490 in. liquid levels, the peak convective reaction force is more than twice as large as predicted by the approximate methods in BNL (1995) and Malhotra (2005). All three methods give similar answers for the fundamental convective frequency at the 460 and 480 in. liquid levels, but the Dytran solution indicates a significant increase in the apparent convective frequency at the 490 in. liquid level that is caused by the interaction with the roof. The peak wall pressures in the tank at the two intermediate liquid levels are essentially the same as for a roofless tank in the lower two-thirds of the tank wall, but diverge from that solution in the upper third of the tank wall. The estimates of peak wall pressures appearing in BNL (1995) are quite conservative lower in the tank, but may underestimate the peak wall pressures closer to the tank roof. Finally, the peak roof pre

MACKEY, T.C.

2007-02-16T23:59:59.000Z

364

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

365

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

366

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

367

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

368

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

369

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

370

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

371

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

372

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

373

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

374

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

375

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

376

Realistic Probability Estimates For Destructive Overpressure Events In Heated Center Wing Tanks Of Commercial Jet Aircraft  

SciTech Connect

The Federal Aviation Administration (FAA) identified 17 accidents that may have resulted from fuel tank explosions on commercial aircraft from 1959 to 2001. Seven events involved JP 4 or JP 4/Jet A mixtures that are no longer used for commercial aircraft fuel. The remaining 10 events involved Jet A or Jet A1 fuels that are in current use by the commercial aircraft industry. Four fuel tank explosions occurred in center wing tanks (CWTs) where on-board appliances can potentially transfer heat to the tank. These tanks are designated as ''Heated Center Wing Tanks'' (HCWT). Since 1996, the FAA has significantly increased the rate at which it has mandated airworthiness directives (ADs) directed at elimination of ignition sources. This effort includes the adoption, in 2001, of Special Federal Aviation Regulation 88 of 14 CFR part 21 (SFAR 88 ''Fuel Tank System Fault Tolerance Evaluation Requirements''). This paper addresses SFAR 88 effectiveness in reducing HCWT ignition source probability. Our statistical analysis, relating the occurrence of both on-ground and in-flight HCWT explosions to the cumulative flight hours of commercial passenger aircraft containing HCWT's reveals that the best estimate of HCWT explosion rate is 1 explosion in 1.4 x 10{sup 8} flight hours. Based on an analysis of SFAR 88 by Sandia National Laboratories and our independent analysis, SFAR 88 reduces current risk of historical HCWT explosion by at least a factor of 10, thus meeting an FAA risk criteria of 1 accident in billion flight hours. This paper also surveys and analyzes parameters for Jet A fuel ignition in HCWT's. Because of the paucity of in-flight HCWT explosions, we conclude that the intersection of the parameters necessary and sufficient to result in an HCWT explosion with sufficient overpressure to rupture the HCWT is extremely rare.

Alvares, N; Lambert, H

2007-02-07T23:59:59.000Z

377

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

378

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

379

HANFORD DOUBLE SHELL TANK THERMAL AND SEISMIC PROJECT SENSITIVITY OF DOUBLE SHELL DYNAMIC RESPONSE TO THE WASTE ELASTIC PROPERTIES  

SciTech Connect

The purpose of this study was to determine the sensitivity of the dynamic response of the Hanford double-shell tanks (DSTs) to the assumptions regarding the constitutive properties of the contained waste. In all cases, the waste was modeled as a uniform linearly elastic material. The focus of the study was on the changes in the modal response of the tank and waste system as the extensional modulus (elastic modulus in tension and compression) and shear modulus of the waste were varied through six orders of magnitude. Time-history analyses were also performed for selected cases and peak horizontal reaction forces and axial stresses at the bottom of the primary tank were evaluated. Because the analysis focused on the differences in the responses between solid-filled and liquid-filled tanks, it is a comparative analysis rather than an analysis of record for a specific tank or set of tanks. The shear modulus was varied between 4 x 10{sup 3} Pa and 4.135 x 10{sup 9} Pa. The lowest value of shear modulus was sufficient to simulate the modal response of a liquid-containing tank, while the higher values are several orders of magnitude greater than the upper limit of expected properties for tank contents. The range of elastic properties used was sufficient to show liquid-like response at the lower values, followed by a transition range of semi-solid-like response to a clearly identifiable solid-like response. It was assumed that the mechanical properties of the tank contents were spatially uniform. Because sludge-like materials are expected only to exist in the lower part of the tanks, this assumption leads to an exaggeration of the effects of sludge-like materials in the tanks. The results of the study show that up to a waste shear modulus of at least 40,000 Pa, the modal properties of the tank and waste system are very nearly the same as for the equivalent liquid-containing tank. This suggests that the differences in critical tank responses between liquid-containing tanks and tanks containing sludge-like materials having a shear modulus not exceeding 40,000 Pa are unlikely to be greater than those due to the uncertainties involved in the definition of the design ground motion or in the properties of the tank-waste system. This is the fundamental conclusion of the study. The study also shows that increasing the waste extensional modulus and shear modulus does not lead to increased mass participation at the impulsive frequency of the liquid-containing system. Instead, increasing the waste stiffness eventually leads to fundamental changes in the modal properties including an increase in the fundamental system frequency.

MACKEY TC; ABATT FG; JOHNSON KI

2009-01-16T23:59:59.000Z

380

Battery Capacity Measurement And Analysis  

E-Print Network (OSTI)

In this paper, we look at different battery capacity models that have been introduced in the literatures. These models describe the battery capacity utilization based on how the battery is discharged by the circuits that consume power. In an attempt to validate these models, we characterize a commercially available lithium coin cell battery through careful measurements of the current and the voltage output of the battery under different load profile applied by a micro sensor node. In the result, we show how the capacity of the battery is affected by the different load profile and provide analysis on whether the conventional battery models are applicable in the real world. One of the most significant finding of our work will show that DC/DC converter plays a significant role in determining the battery capacity, and that the true capacity of the battery may only be found by careful measurements.

Using Lithium Coin; Sung Park; Andreas Savvides; Mani B. Srivastava

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Capacity of a UMTS system for aeronautical communications  

Science Conference Proceedings (OSTI)

Current Air Traffic Management and Air Traffic Control systems will experience a demand increase in the following years due to the large number of operating aircrafts. As a consequence, new solution must be studied to overcome this capacity limitation ... Keywords: ATC, ATM, ENR, SDR, TMA, UMTS, W-CDMA, air traffic, capacity

Miguel Calvo Ramn; Ramn Martnez Rodrguez-Osorio; Bazil Taha Ahmed; Juan Jos Iglesias Jimnez

2007-07-01T23:59:59.000Z

382

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

383

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

384

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

385

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...

386

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...

387

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

388

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

389

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

390

Measuring wind plant capacity value  

DOE Green Energy (OSTI)

Electric utility planners and wind energy researchers pose a common question: What is the capacity value of a wind plant? Tentative answers, which can be phrased in a variety of ways, are based on widely varying definitions and methods of calculation. From the utility`s point of view, a resource that has no capacity value also has a reduced economic value. Utility planners must be able to quantify the capacity value of a wind plant so that investment in conventional generating capacity can be potentially offset by the capacity value of the wind plant. Utility operations personnel must schedule its conventional resources to ensure adequate generation to meet load. Given a choice between two resources, one that can be counted on and the other that can`t, the utility will avoid the risky resource. This choice will be reflected in the price that the utility will pay for the capacity: higher capacity credits result in higher payments. This issue is therefore also important to the other side of the power purchase transaction -- the wind plant developer. Both the utility and the developer must accurately assess the capacity value of wind. This article summarizes and evaluates some common methods of evaluating capacity credit. During the new era of utility deregulation in the United States, it is clear that many changes will occur in both utility planning and operations. However, it is my judgement that the evaluation of capacity credit for wind plants will continue to play an important part in renewable energy development in the future.

Milligan, M.R.

1996-01-01T23:59:59.000Z

391

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

392

12/2000 Low-Level Waste Disposal Capacity Report Version 2 | Department of  

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

Services » Waste Management » Waste Disposition » 12/2000 Services » Waste Management » Waste Disposition » 12/2000 Low-Level Waste Disposal Capacity Report Version 2 12/2000 Low-Level Waste Disposal Capacity Report Version 2 The purpose of this Report is to assess whether U.S. Department of Energy (DOE or the Department) disposal facilities have sufficient volumetric and radiological capacity to accommodate the low-level waste (LLW) and mixed low-level waste (MLLW) that the Department expects to dispose at these facilities. 12/2000 Low-Level Waste Disposal Capacity Report Version 2 More Documents & Publications EIS-0243: Record of Decision EIS-0200: Record of Decision EIS-0286: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation

393

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

394

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

395

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

396

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.

397

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

398

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...

399

RESULTS FOR THE FIRST QUARTER 2012 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS  

Science Conference Proceedings (OSTI)

This report details the chemical and radionuclide contaminant results for the characterization of the 2012 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this memorandum: The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted; The reported detection limit for {sup 94}Nb is above the requested limit but below the estimated limit; {sup 247}Cm and {sup 249}Cf are above the requested limits. However, they are below the limits established; The reported detection limit for Norpar 13 is greater than the limit from the WAC; The reported detection limit for Isopar L is greater than the limit from WAC; Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples; The values reported in this report are the concentrations in the sub-sample as detected by the instrument, however, the results may not accurately represent the concentrations of the analytes in Tank 50; The low insoluble solids content increases the measurement uncertainty for insoluble species.

Bannochie, C.

2012-07-16T23:59:59.000Z

400

Results For The First Quarter 2012 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminant Results  

SciTech Connect

This report details the chemical and radionuclide contaminant results for the characterization of the 2012 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this memorandum: The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted; The reported detection limit for {sup 94}Nb is above the requested limit but below the estimated limit; {sup 247}Cm and {sup 249}Cf are above the requested limits. However, they are below the limits established; The reported detection limit for Norpar 13 is greater than the limit from the WAC; The reported detection limit for Isopar L is greater than the limit from WAC; Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples; The values reported in this report are the concentrations in the sub-sample as detected by the instrument, however, the results may not accurately represent the concentrations of the analytes in Tank 50; The low insoluble solids content increases the measurement uncertainty for insoluble species.

Bannochie, C. J.

2012-07-16T23:59:59.000Z

Note: This page contains sample records for the topic "tanks capacity increase" 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

Results For The First Quarter 2013 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminants  

SciTech Connect

This report details the chemical and radionuclide contaminant results for the characterization of the 2013 First Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Waste Solidification Engineering (WSE) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: SRR WAC targets or limits were met for all analyzed chemical and radioactive contaminates unless noted in this section; {sup 59}Ni, {sup 94}Nb, {sup 247}Cm, {sup 249}Cf, and {sup 251}Cf are above the requested SRR target concentrations. However, they are below the detection limits established by SRNL; Norpar 13 and Isopar L have higher detection limits compared with the Saltstone WAC. The data provided in this report is based upon the concentrations in the sub-sample, and due to the limited solubility in aqueous solution, may not represent the concentrations of the analytes in Tank 50; and, The low insoluble solids content increases the measurement uncertainty for insoluble species.

Bannochie, C. J.

2013-05-14T23:59:59.000Z

402

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

403

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

404

Underground Natural Gas Storage Capacity  

Gasoline and Diesel Fuel Update (EIA)

. . Underground Natural Gas Storage Capacity by State, December 31, 1996 (Capacity in Billion Cubic Feet) Table State Interstate Companies Intrastate Companies Independent Companies Total Number of Active Fields Capacity Number of Active Fields Capacity Number of Active Fields Capacity Number of Active Fields Capacity Percent of U.S. Capacity Alabama................. 0 0 1 3 0 0 1 3 0.04 Arkansas ................ 0 0 3 32 0 0 3 32 0.40 California................ 0 0 10 470 0 0 10 470 5.89 Colorado ................ 4 66 5 34 0 0 9 100 1.25 Illinois ..................... 6 259 24 639 0 0 30 898 11.26 Indiana ................... 6 16 22 97 0 0 28 113 1.42 Iowa ....................... 4 270 0 0 0 0 4 270 3.39 Kansas ................... 16 279 2 6 0 0 18 285 3.57 Kentucky ................ 6 167 18 49 0 0 24 216 2.71 Louisiana................ 8 530 4 25 0 0 12 555 6.95 Maryland ................ 1 62

405

North Dakota Refining Capacity Study  

Science Conference Proceedings (OSTI)

According to a 2008 report issued by the United States Geological Survey, North Dakota and Montana have an estimated 3.0 to 4.3 billion barrels of undiscovered, technically recoverable oil in an area known as the Bakken Formation. With the size and remoteness of the discovery, the question became 'can a business case be made for increasing refining capacity in North Dakota?' And, if so what is the impact to existing players in the region. To answer the question, a study committee comprised of leaders in the region's petroleum industry were brought together to define the scope of the study, hire a consulting firm and oversee the study. The study committee met frequently to provide input on the findings and modify the course of the study, as needed. The study concluded that the Petroleum Area Defense District II (PADD II) has an oversupply of gasoline. With that in mind, a niche market, naphtha, was identified. Naphtha is used as a diluent used for pipelining the bitumen (heavy crude) from Canada to crude markets. The study predicted there will continue to be an increase in the demand for naphtha through 2030. The study estimated the optimal configuration for the refinery at 34,000 barrels per day (BPD) producing 15,000 BPD of naphtha and a 52 percent refinery charge for jet and diesel yield. The financial modeling assumed the sponsor of a refinery would invest its own capital to pay for construction costs. With this assumption, the internal rate of return is 9.2 percent which is not sufficient to attract traditional investment given the risk factor of the project. With that in mind, those interested in pursuing this niche market will need to identify incentives to improve the rate of return.

Dennis Hill; Kurt Swenson; Carl Tuura; Jim Simon; Robert Vermette; Gilberto Marcha; Steve Kelly; David Wells; Ed Palmer; Kuo Yu; Tram Nguyen; Juliam Migliavacca

2011-01-05T23:59:59.000Z

406

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

407

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

408

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

409

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

410

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

411

Historical trends in tank 241-SY-101 waste temperatures and levels  

Science Conference Proceedings (OSTI)

The gas release and fluctuating level of the waste in tank 241-SY-101 have prompted more detailed interest in its historical behavior, in hopes of achieving a better understanding of its current status. To examine the historical behavior, essentially all of the tank waste temperature and level data record has been retrieved, examined, and plotted in various ways. To aid in interpreting the data, the depth of the non-convective waste layer was estimated by using a least-squares Chebyshev approximation to the temperatures. This report documents the retrieval critical examination, and graphic presentation of 241-SY-101 temperature and waste level histories. The graphic presentations clearly indicate a tank cooling trend that has become precipitous since late 1991. The plots also clearly show the decreasing frequency of waste gas release events, increasing height of the non-convective layer, and larger level drops per event.

Antoniak, Z.I.

1993-09-01T23:59:59.000Z

412

COMMUNITY CAPACITY BUILDING THROUGH TECHNOLOGY  

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

COMMUNITY CAPACITY BUILDING THROUGH TECHNOLOGY COMMUNITY CAPACITY BUILDING THROUGH TECHNOLOGY Empowering Communities in the Age of E-Government Prepared by Melinda Downing, Environmental Justice Program Manager, U.S. Department of Energy MAR 06 MARCH 2006 Since 1999, the Department of Energy has worked with the National Urban Internet and others to create community capacity through technology.  Empowering Communities in the Age of E-Government Table of Contents Message from the Environmental Justice Program Manager . . . . . . . . 3 Introduction. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Partnerships. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Process Chart: From Agency to Community. . . . . . . . . . . . . . . . . . . 7 Case Studies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8

413

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.

414

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

415

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

416

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