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Note: This page contains sample records for the topic "liquid wastes natural" 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.


1

Process for preparing liquid wastes  

DOE Patents (OSTI)

A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

Oden, Laurance L. (Albany, OR); Turner, Paul C. (Albany, OR); O'Connor, William K. (Lebanon, OR); Hansen, Jeffrey S. (Corvallis, OR)

1997-01-01T23:59:59.000Z

2

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

waste (i.e, mixture of biohazardous and chemical or radioactive waste), call Environment, Health2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619

Tsien, Roger Y.

3

Liquid Natural Gas  

Science Journals Connector (OSTI)

Liquid Natural Gas ... IN A new technique for storing natural gas at the East Ohio Gas Co. plant, Cleveland, Ohio, the gas is liquefied before passing to the gas holders. ... Natural gas contains moisture and carbon dioxide, both of which liquefy before the natural gas and are somewhat of a nuisance because upon solidification they clog the pipes. ...

W. F. SCHAPHORST

1941-04-25T23:59:59.000Z

4

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

5

DOE Selects Savannah River Remediation, LLC for Liquid Waste...  

Energy Savers (EERE)

objective of the Liquid Waste contract is to achieve closure of the SRS liquid waste tanks in compliance with the Federal Facilities Agreement, utilizing the Defense Waste...

6

Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

far will integrate SWPF with current liquid waste facilities, such as the DWPF and the tanks farms." EM is pleased with the spirit of integration. "A key objective for us over the...

7

SRS Liquid Waste Program Partnering Agreement  

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

We the members of the  SRS Liquid Waste Partnering Team do hereby mutually agree to work in a collaborative and cooperative manner through open communication and coordination with team members, and...

8

Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume...  

Office of Environmental Management (EM)

1: Availability of Feedstock and Technology Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 1: Availability of Feedstock and Technology Municipal solid waste (MSW) is...

9

Savannah River Site's Liquid Waste Operations Adds Multi-Functional...  

Office of Environmental Management (EM)

now been filled. The SDUs play an essential role in the closure of the 45 liquid waste tanks on the site. About 90 percent of the waste in these tanks is salt waste that must be...

10

Ventilation System to Improve Savannah River Site's Liquid Waste Operations  

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

AIKEN, S.C. – The EM program and its liquid waste contractor at the Savannah River Site are improving salt waste disposition work and preparing for eventual operations of the Salt Waste Processing Facility (SWPF) currently being constructed.

11

,"Natural Gas Plant Liquids Proved Reserves"  

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

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Liquids Proved Reserves",49,"Annual",2012,"6301979" ,"Release...

12

,"Natural Gas Plant Liquids Proved Reserves"  

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

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Liquids Proved Reserves",49,"Annual",2013,"6301979" ,"Release...

13

Definition: Liquid natural gas | Open Energy Information  

Open Energy Info (EERE)

Liquid natural gas Liquid natural gas Jump to: navigation, search Dictionary.png Liquid natural gas Natural gas (primarily methane) that has been liquefied by reducing its temperature to -260 degrees Fahrenheit at atmospheric pressure.[1] View on Wikipedia Wikipedia Definition Liquefied natural gas or LNG is natural gas that has been converted to liquid form for ease of storage or transport. Liquefied natural gas takes up about 1/600th the volume of natural gas in the gaseous state. It is odorless, colorless, non-toxic and non-corrosive. Hazards include flammability after vaporization into a gaseous state, freezing and asphyxia. The liquefaction process involves removal of certain components, such as dust, acid gases, helium, water, and heavy hydrocarbons, which could cause difficulty downstream. The natural gas is then condensed into a

14

Natural Gas Total Liquids Extracted  

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

Thousand Barrels) Thousand Barrels) Data Series: Natural Gas Processed Total Liquids Extracted NGPL Production, Gaseous Equivalent Period: Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Data Series Area 2007 2008 2009 2010 2011 2012 View History U.S. 658,291 673,677 720,612 749,095 792,481 873,563 1983-2012 Alabama 13,381 11,753 11,667 13,065 1983-2010 Alaska 22,419 20,779 19,542 17,798 18,314 18,339 1983-2012 Arkansas 126 103 125 160 212 336 1983-2012 California 11,388 11,179 11,042 10,400 9,831 9,923 1983-2012 Colorado 27,447 37,804 47,705 57,924 1983-2010 Florida 103 16 1983-2008 Illinois 38 33 24 231 705 0 1983-2012

15

Natural analogues of nuclear waste glass corrosion.  

SciTech Connect

This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses.

Abrajano, T.A. Jr.; Ebert, W.L.; Luo, J.S.

1999-01-06T23:59:59.000Z

16

SEAPORT LIQUID NATURAL GAS STUDY  

SciTech Connect

The Seaport Liquid Natural Gas Study has attempted to evaluate the potential for using LNG in a variety of heavy-duty vehicle and equipment applications at the Ports of Los Angeles and Oakland. Specifically, this analysis has focused on the handling and transport of containerized cargo to, from and within these two facilities. In terms of containerized cargo throughput, Los Angeles and Oakland are the second and sixth busiest ports in the US, respectively, and together handle nearly 4.5 million TEUs per year. At present, the landside handling and transportation of containerized cargo is heavily dependent on diesel-powered, heavy-duty vehicles and equipment, the utilization of which contributes significantly to the overall emissions impact of port-related activities. Emissions from diesel units have been the subject of increasing scrutiny and regulatory action, particularly in California. In the past two years alone, particulate matter from diesel exhaust has been listed as a toxic air contaminant by CAM, and major lawsuits have been filed against several of California's largest supermarket chains, alleging violation of Proposition 65 statutes in connection with diesel emissions from their distribution facilities. CARE3 has also indicated that it may take further regulatory action relating to the TAC listing. In spite of these developments and the very large diesel emissions associated with port operations, there has been little AFV penetration in these applications. Nearly all port operators interviewed by CALSTART expressed an awareness of the issues surrounding diesel use; however, none appeared to be taking proactive steps to address them. Furthermore, while a less controversial issue than emissions, the dominance of diesel fuel use in heavy-duty vehicles contributes to a continued reliance on imported fuels. The increasing concern regarding diesel use, and the concurrent lack of alternative fuel use and vigorous emissions reduction activity at the Ports provide both the backdrop and the impetus for this study.

COOK,Z.

1999-02-01T23:59:59.000Z

17

Louisiana Offshore Natural Gas Plant Liquids Production Extracted...  

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

Offshore Natural Gas Plant Liquids Production Extracted in Louisiana (Million Cubic Feet) Louisiana Offshore Natural Gas Plant Liquids Production Extracted in Louisiana (Million...

18

Existing data on the 216-Z liquid waste sites  

SciTech Connect

During 36 years of operation at the Hanford Site, the ground has been used for disposal of liquid and solid transuranic and/or low-level wastes. Liquid waste was disposed in surface and subsurface cribs, trenches, French drains, reverse wells, ditches and ponds. Disposal structures associated with Z Plant received liquid waste from plutonium finishing and reclamation, waste treatment and laboratory operations. The nineteen 216-Z sites have received 83% of the plutonium discharged to 325 liquid waste facilities at the Hanford Site. The purpose of this document is to support the Hanford Defense Waste Environmental Impact Statement by drawing the existing data together for the 216-Z liquid waste disposal sites. This document provides an interim reference while a sitewide Waste Information Data System (WIDS) is developed and put on line. Eventually these and additional site data for all Hanford waste disposal sites will be available on WIDS. Compilation of existing data is the first step in evaluating the need and developing the technology for long-term management of these waste sites. The scope of this document is confined to data describing the status of the 216-Z waste sites as of December 31, 1979. Information and sketches are taken from existing documents and drawings.

Owens, K.W.

1981-05-01T23:59:59.000Z

19

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

20

Detection of free liquid in containers of solidified radioactive waste  

DOE Patents (OSTI)

A method of nondestructively detecting the presence of free liquid within a sealed enclosure containing solidified waste by measuring the levels of waste at two diametrically opposite locations while slowly tilting the enclosure toward one of said locations. When the measured level remains constant at the other location, the measured level at said one location is noted and any measured difference of levels indicates the presence of liquid on the surface of the solidified waste. The absence of liquid in the enclosure is verified when the measured levels at both locations are equal.

Greenhalgh, Wilbur O. (Richland, WA)

1985-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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

Oklahoma Natural Gas Plant Liquids, Expected Future Production...  

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

Plant Liquids, Expected Future Production (Million Barrels) Oklahoma Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

22

California Federal Offshore Natural Gas Plant Liquids, Proved...  

Gasoline and Diesel Fuel Update (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) California Federal Offshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

23

California--State Offshore Natural Gas Plant Liquids, Expected...  

Annual Energy Outlook 2012 (EIA)

Plant Liquids, Expected Future Production (Million Barrels) California--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1...

24

Federal Offshore--California Natural Gas Liquids Lease Condensate...  

Annual Energy Outlook 2012 (EIA)

Liquids Lease Condensate, Proved Reserves (Million Barrels) Federal Offshore--California Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0...

25

Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate...  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1...

26

Federal Offshore--Louisiana and Alabama Natural Gas Liquids Lease...  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) Federal Offshore--Louisiana and Alabama Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade...

27

California State Offshore Natural Gas Plant Liquids, Proved Reserves...  

Annual Energy Outlook 2012 (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) California State Offshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

28

California--State Offshore Natural Gas Liquids Lease Condensate...  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) California--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1...

29

Alabama Offshore Natural Gas Plant Liquids Production Extracted...  

Gasoline and Diesel Fuel Update (EIA)

Plant Liquids Production Extracted in Alabama (Million Cubic Feet) Alabama Offshore Natural Gas Plant Liquids Production Extracted in Alabama (Million Cubic Feet) Decade Year-0...

30

California Onshore Natural Gas Plant Liquids Production Extracted...  

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

Plant Liquids Production Extracted in California (Million Cubic Feet) California Onshore Natural Gas Plant Liquids Production Extracted in California (Million Cubic Feet) Decade...

31

California Onshore Natural Gas Total Liquids Extracted in California...  

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

Total Liquids Extracted in California (Thousand Barrels) California Onshore Natural Gas Total Liquids Extracted in California (Thousand Barrels) Decade Year-0 Year-1 Year-2 Year-3...

32

Lower 48 Federal Offshore Natural Gas Plant Liquids, Expected...  

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

Plant Liquids, Expected Future Production (Million Barrels) Lower 48 Federal Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1...

33

Alabama (with State Offshore) Natural Gas Plant Liquids, Expected...  

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

Plant Liquids, Expected Future Production (Million Barrels) Alabama (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0...

34

California (with State Offshore) Natural Gas Plant Liquids, Expected...  

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

Plant Liquids, Expected Future Production (Million Barrels) California (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0...

35

Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility  

SciTech Connect

Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

1998-06-01T23:59:59.000Z

36

Catalyst-Assisted Production of Olefins from Natural Gas Liquids...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Catalyst-Assisted Production of Olefins from Natural Gas Liquids: Prototype Development and Full-Scale Testing, April 2013 Catalyst-Assisted Production of Olefins from Natural Gas...

37

Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility  

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

AIKEN, S.C. – Officials with the EM program at Savannah River Site (SRS) recently announced a key milestone in preparation for the startup of the Salt Waste Processing Facility (SWPF): workers installed more than 1,200 feet of new transfer lines that will eventually connect existing liquid waste facilities to SWPF.

38

China's Scientific Investigation for Liquid Waste Treatment Solutions  

SciTech Connect

Post World War II created the nuclear age with several countries developing nuclear technology for power, defense, space and medical applications. China began its nuclear research and development programs in 1950 with the establishment of the China Institute of Atomic Energy (CIAE) located near Beijing. CIAE has been China's leader in nuclear science and technical development with its efforts to create advanced reactor technology and upgrade reprocessing technology. In addition, with China's new emphasis on environmental safety, CIAE is focusing on waste treatment options and new technologies that may provide solutions to legacy waste and newly generated waste from the full nuclear cycle. Radioactive liquid waste can pose significant challenges for clean up with various treatment options including encapsulation (cement), vitrification, solidification and incineration. Most, if not all, nuclear nations have found the treatment of liquids to be difficult, due in large part to the high economic costs associated with treatment and disposal and the failure of some methods to safely contain or eliminate the liquid. With new environmental regulations in place, Chinese nuclear institutes and waste generators are beginning to seek new technologies that can be used to treat the more complex liquid waste streams in a form that is safe for transport and for long-term storage or final disposal. [1] In 2004, CIAE and Pacific Nuclear Solutions, a division of Pacific World Trade, USA, began discussions about absorbent technology and applications for its use. Preliminary tests were conducted at CIAE's Department of Radiochemistry using generic solutions, such as lubricating oil, with absorbent polymers for solidification. Based on further discussions between both parties, it was decided to proceed with a more formal test program in April, 2005, and additional tests in October, 2005. The overall objective of the test program was to apply absorbent polymers to various waste streams to determine leach rates, stability (immobilization), effective bonding ratios, compression capability, waste minimization and effects of irradiation on the solidified samples. (authors)

Liangjin, B.; Meiqiong, L. [China Institute of Atomic Energy, P.O. Box 275(87), Beijing, 102413 (China); Kelley, D. [Pacific Nuclear Solutions, 450 East 96th Street, Suite 335, Indianapolis, Indiana 46240 (United States)

2006-07-01T23:59:59.000Z

39

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

40

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

Note: This page contains sample records for the topic "liquid wastes natural" 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

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

42

Process for immobilizing radioactive boric acid liquid wastes  

DOE Patents (OSTI)

A method of immobilizing boric acid liquid wastes containing radionuclides by neutralizing the solution and evaporating the resulting precipitate to near dryness. The dry residue is then fused into a reduced volume, insoluble, inert, solid form containing substantially all the radionuclides.

Greenhalgh, Wilbur O. (Richland, WA)

1986-01-01T23:59:59.000Z

43

Natural Gas Plant Field Production: Natural Gas Liquids  

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

Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period-Unit: Monthly-Thousand Barrels Monthly-Thousand Barrels per Day Annual-Thousand Barrels Annual-Thousand Barrels per Day Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period-Unit: Monthly-Thousand Barrels Monthly-Thousand Barrels per Day Annual-Thousand Barrels Annual-Thousand Barrels per Day Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Product Area Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History U.S. 74,056 76,732 74,938 79,040 82,376 81,196 1981-2013 PADD 1 1,525 1,439 2,394 2,918 2,821 2,687 1981-2013 East Coast 1993-2008 Appalachian No. 1 1,525 1,439 2,394 2,918 2,821 2,687 1993-2013 PADD 2 12,892 13,208 13,331 13,524 15,204 15,230 1981-2013 Ind., Ill. and Ky. 1,975 1,690 2,171 1,877 2,630 2,746 1993-2013

44

Natural Gas Plant Stocks of Natural Gas Liquids  

Gasoline and Diesel Fuel Update (EIA)

Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period: Monthly Annual Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period: Monthly Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Product Area Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History U.S. 5,419 6,722 6,801 5,826 6,210 6,249 1993-2013 PADD 1 122 121 115 189 246 248 1993-2013 East Coast 1993-2010 Appalachian No. 1 122 121 115 189 246 248 1993-2013 PADD 2 959 891 880 1,129 1,104 1,041 1993-2013 Ind., Ill. and Ky. 311 300 298 308 262 260 1993-2013 Minn., Wis., N. Dak., S. Dak. 56 64 58 60 51 64 1993-2013 Okla., Kans., Mo. 592 527 524 761 791 717 1993-2013 PADD 3 3,810 5,007 5,032 3,817 4,246 4,272 1993-2013

45

Gulf Of Mexico Natural Gas Plant Liquids Production (Million...  

Gasoline and Diesel Fuel Update (EIA)

Plant Liquids Production (Million Cubic Feet) Gulf Of Mexico Natural Gas Plant Liquids Production (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6...

46

Louisiana State Offshore Natural Gas Plant Liquids, Proved Reserves...  

Annual Energy Outlook 2012 (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) Louisiana State Offshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

47

Texas State Offshore Natural Gas Plant Liquids, Proved Reserves...  

Annual Energy Outlook 2012 (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) Texas State Offshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

48

California Natural Gas Total Liquids Extracted (Thousand Barrels...  

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

Liquids Extracted (Thousand Barrels) California Natural Gas Total Liquids Extracted (Thousand Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

49

Louisiana Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

Liquids, Proved Reserves (Million Barrels) Louisiana Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

50

Alaska Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Annual Energy Outlook 2012 (EIA)

Liquids, Proved Reserves (Million Barrels) Alaska Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8...

51

Alabama Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Annual Energy Outlook 2012 (EIA)

Liquids, Proved Reserves (Million Barrels) Alabama Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

52

California Natural Gas Plant Liquids, Proved Reserves (Million...  

Annual Energy Outlook 2012 (EIA)

Liquids, Proved Reserves (Million Barrels) California Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

53

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

54

Colorado Natural Gas Plant Liquids, Expected Future Production...  

Annual Energy Outlook 2012 (EIA)

Expected Future Production (Million Barrels) Colorado Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5...

55

,"Colorado Natural Gas Liquids Lease Condensate, Proved Reserves...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Colorado Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",2...

56

Colorado Natural Gas Liquids Lease Condensate, Reserves Based...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Colorado Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

57

Catalyst-Assisted Production of Olefins from Natural Gas Liquids...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Catalyst-Assisted Production of Olefins from Natural Gas Liquids: Prototype Development and Full-Scale Testing New Process Produces Ethylene More Efficiently and Reduces Coke...

58

New Mexico Natural Gas Liquids Lease Condensate, Reserves in...  

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

in Nonproducing Reservoirs (Million Barrels) New Mexico Natural Gas Liquids Lease Condensate, Reserves in Nonproducing Reservoirs (Million Barrels) Decade Year-0 Year-1 Year-2...

59

,"New York Natural Gas Liquids Lease Condensate, Proved Reserves...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New York Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",198...

60

Biomass and Natural Gas to Liquid Transportation Fuels  

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

Breakout Session 1: New Developments and Hot Topics Session 1-D: Natural Gas & Biomass to Liquids Josephine Elia, Graduate Student, Princeton University

Note: This page contains sample records for the topic "liquid wastes natural" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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to obtain the most current and comprehensive results.


61

Federal Offshore--Texas Natural Gas Liquids Lease Condensate...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Federal Offshore--Texas Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

62

Federal Offshore--California Natural Gas Plant Liquids, Reserves...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Federal Offshore--California Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

63

Louisiana--State Offshore Natural Gas Plant Liquids, Expected...  

Annual Energy Outlook 2012 (EIA)

Expected Future Production (Million Barrels) Louisiana--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

64

,"Federal Offshore--California Natural Gas Liquids Lease Condensate...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--California Natural Gas Liquids Lease Condensate, Proved Reserves (Million...

65

Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1...

66

,"Lower 48 Federal Offshore Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Lower 48 Federal Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",2...

67

Federal Offshore--Texas Natural Gas Plant Liquids, Expected Future...  

Gasoline and Diesel Fuel Update (EIA)

Expected Future Production (Million Barrels) Federal Offshore--Texas Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

68

Louisiana--State Offshore Natural Gas Plant Liquids, Reserves...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Louisiana--State Offshore Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

69

,"Texas--State Offshore Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Texas--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",2...

70

,"Louisiana (with State Offshore) Natural Gas Plant Liquids,...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Louisiana (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

71

,"Louisiana--State Offshore Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Louisiana--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",2...

72

Louisiana--State Offshore Natural Gas Liquids Lease Condensate...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Louisiana--State Offshore Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

73

,"Texas--State Offshore Natural Gas Plant Liquids, Expected Future...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Texas--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",2...

74

,"Federal Offshore--Louisiana and Alabama Natural Gas Liquids...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--Louisiana and Alabama Natural Gas Liquids Lease Condensate, Proved Reserves (Million...

75

Federal Offshore--California Natural Gas Plant Liquids, Expected...  

Annual Energy Outlook 2012 (EIA)

Expected Future Production (Million Barrels) Federal Offshore--California Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

76

,"Mississippi (with State Offshore) Natural Gas Liquids Lease...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Mississippi (with State Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

77

,"Mississippi (with State Offshore) Natural Gas Plant Liquids...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Mississippi (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

78

,"Alaska (with Total Offshore) Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Alaska (with Total Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

79

,"Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",2...

80

,"Federal Offshore--California Natural Gas Plant Liquids, Expected...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--California Natural Gas Plant Liquids, Expected Future Production (Million...

Note: This page contains sample records for the topic "liquid wastes natural" 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

,"California--State Offshore Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","California--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",2...

82

Texas--State Offshore Natural Gas Liquids Lease Condensate, Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Texas--State Offshore Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

83

,"Texas (with State Offshore) Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Texas (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

84

,"Alaska (with Total Offshore) Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Alaska (with Total Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

85

,"Texas (with State Offshore) Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Texas (with State Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

86

,"Louisiana (with State Offshore) Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Louisiana (with State Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

87

,"Louisiana--State Offshore Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Louisiana--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",2...

88

,"Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids, Expected Future Production (Million...

89

,"California (with State Offshore) Natural Gas Plant Liquids...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","California (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

90

,"Federal Offshore--Texas Natural Gas Liquids Lease Condensate...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--Texas Natural Gas Liquids Lease Condensate, Proved Reserves (Million...

91

Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Lower 48 Federal Offshore Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

92

,"Alabama (with State Offshore) Natural Gas Plant Liquids, Expected...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Alabama (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels)",1,"Annual",...

93

,"Federal Offshore--Texas Natural Gas Plant Liquids, Expected...  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Federal Offshore--Texas Natural Gas Plant Liquids, Expected Future Production (Million...

94

,"California--State Offshore Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","California--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",2...

95

,"California (with State Offshore) Natural Gas Liquids Lease...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","California (with State Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

96

,"Alabama (with State Offshore) Natural Gas Liquids Lease Condensate...  

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

Of Series","Frequency","Latest Data for" ,"Data 1","Alabama (with State Offshore) Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels)",1,"Annual",...

97

Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids...  

Gasoline and Diesel Fuel Update (EIA)

Expected Future Production (Million Barrels) Federal Offshore--Louisiana and Alabama Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1...

98

California (with State Offshore) Natural Gas Liquids Lease Condensate...  

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

in Nonproducing Reservoirs (Million Barrels) California (with State Offshore) Natural Gas Liquids Lease Condensate, Reserves in Nonproducing Reservoirs (Million Barrels) Decade...

99

California--State Offshore Natural Gas Liquids Lease Condensate...  

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

Reserves in Nonproducing Reservoirs (Million Barrels) California--State Offshore Natural Gas Liquids Lease Condensate, Reserves in Nonproducing Reservoirs (Million Barrels) Decade...

100

California--State Offshore Natural Gas Plant Liquids, Reserves...  

Annual Energy Outlook 2012 (EIA)

Available; W Withheld to avoid disclosure of individual company data. Release Date: 1242014 Next Release Date: 12312015 Referring Pages: Natural Gas Plant Liquids Production...

Note: This page contains sample records for the topic "liquid wastes natural" 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

Texas (with State Offshore) Natural Gas Plant Liquids, Expected...  

Gasoline and Diesel Fuel Update (EIA)

Expected Future Production (Million Barrels) Texas (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

102

Louisiana (with State Offshore) Natural Gas Plant Liquids, Reserves...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Louisiana (with State Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

103

Alaska (with Total Offshore) Natural Gas Plant Liquids, Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Alaska (with Total Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

104

California (with State Offshore) Natural Gas Plant Liquids, Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) California (with State Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

105

Louisiana (with State Offshore) Natural Gas Plant Liquids, Expected...  

Gasoline and Diesel Fuel Update (EIA)

Expected Future Production (Million Barrels) Louisiana (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2...

106

Mississippi (with State Offshore) Natural Gas Plant Liquids,...  

Gasoline and Diesel Fuel Update (EIA)

Expected Future Production (Million Barrels) Mississippi (with State Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2...

107

Alaska (with Total Offshore) Natural Gas Plant Liquids, Expected...  

Annual Energy Outlook 2012 (EIA)

Expected Future Production (Million Barrels) Alaska (with Total Offshore) Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

108

Mississippi (with State Offshore) Natural Gas Plant Liquids,...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Mississippi (with State Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2...

109

Alabama (with State Offshore) Natural Gas Plant Liquids, Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Alabama (with State Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

110

Texas (with State Offshore) Natural Gas Plant Liquids, Reserves...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Texas (with State Offshore) Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

111

Lower 48 Federal Offshore Natural Gas Plant Liquids, Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Lower 48 Federal Offshore Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3...

112

Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 1: Availability of Feedstock and Technology  

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

Municipal solid waste (MSW) is a domestic energy resource with the potential to provide a significant amount of energy to meet US liquid fuel requirements. MSW is defined as household waste, commercial solid waste, nonhazardous sludge, conditionally exempt, small quantity hazardous waste, and industrial solid waste. It includes food waste, residential rubbish, commercial and industrial wastes, and construction and demolition debris. It has an average higher heating value (HHV) of approximately 5100 btu/lb (as arrived basis).

113

California - San Joaquin Basin Onshore Natural Gas Plant Liquids, Proved  

Gasoline and Diesel Fuel Update (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) Gas Plant Liquids, Proved Reserves (Million Barrels) California - San Joaquin Basin Onshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 77 1980's 81 57 124 117 105 120 109 107 101 95 1990's 86 75 83 85 75 80 80 82 58 60 2000's 64 52 68 78 95 112 100 103 97 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Natural Gas Liquids Proved Reserves as of Dec. 31 CA, San Joaquin Basin Onshore Natural Gas Liquids Proved Reserves Natural Gas Liquids Proved Reserves as of Dec.

114

EIAs Proposed Definitions for Natural Gas Liquids  

Gasoline and Diesel Fuel Update (EIA)

Definitions for Natural Gas Liquids 1 Definitions for Natural Gas Liquids 1 June 14, 2013 EIA's Proposed Definitions for Natural Gas Liquids Term Current Definition Proposed Definition Note Lease condensate Condensate (lease condensate): A natural gas liquid recovered from associated and non associated gas wells from lease separators or field facilities, reported in barrels of 42 U.S. gallons at atmospheric pressure and 60 degrees Fahrenheit. Lease condensate: Light liquid hydrocarbons recovered from lease separators or field facilities at associated and non-associated natural gas wells. Mostly pentanes and heavier hydrocarbons. Normally enters the crude oil stream after production. Includes lease condensate as part of the crude oil stream, not an NGL. Plant condensate Plant condensate: One of the

115

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect

This report addresses an alternative concept for potentially managing the sodium-bearing liquid waste generated at the Idaho Chemical Processing Plant from the current method of calcining a blend of sodium waste and high-level liquid waste. The concept is based on removing the radioactive components from sodium-bearing waste by neutralization and grouting the resulting low-level waste for on-site near-surface disposal. Solidifying the sodium waste as a remote-handled transuranic waste is not considered to be practical because of excessive costs and inability to dispose of the waste in a timely fashion. Although neutralization can remove most radioactive components to provide feed for a solidified low-level waste, and can reduce liquid inventories four to nine years more rapidly than the current practice of blending sodium-bearing liquid waste with first-cycle raffinite, the alternative will require major new facilities and will generate large volumes of low-level waste. Additional facility and operating costs are estimated to be at least $500 million above the current practice of blending and calcining. On-site, low-level waste disposal may be technically difficult and conflict which national and state policies. Therefore, it is recommended that the current practice of calcining a blend of sodium-bearing liquid waste and high-level liquid waste be continued to minimize overall cost and process complexities. 17 refs., 4 figs., 16 tabs.

Chipman, N.A.; Engelgau, G.O.; Berreth, J.R.

1989-01-01T23:59:59.000Z

116

Underground storage of natural gas, liquid hydrocarbons, and carbon dioxide  

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

storage of natural gas, liquid hydrocarbons, and carbon storage of natural gas, liquid hydrocarbons, and carbon dioxide (Louisiana) Underground storage of natural gas, liquid hydrocarbons, and carbon dioxide (Louisiana) < Back Eligibility Commercial Construction Industrial Investor-Owned Utility Municipal/Public Utility Utility Program Info State Louisiana Program Type Environmental Regulations Siting and Permitting The Louisiana Department of Environmental Quality regulates the underground storage of natural gas or liquid hydrocarbons and carbon dioxide. Prior to the use of any underground reservoir for the storage of natural gas and prior to the exercise of eminent domain by any person, firm, or corporation having such right under laws of the state of Louisiana, the commissioner, shall have found all of the following:

117

Enclosure 3 DOE Response to EPA Question Regarding "High-Level Liquid Radioactive Waste"  

E-Print Network (OSTI)

to date, which is from the definitions in the Nuclear Waste Policy Act: The term "high-level radioactive of waste streams as from the applicable definition of HLW in the Nuclear Waste Policy Act. 5/11/20051 #12 defining High Level Waste: For the purpose of this statement of policy, "high-level liquid radioactive

118

Importation into Britain of Liquid Natural Gas  

Science Journals Connector (OSTI)

... of singular interest has recently been reported, namely, the importation into Britain of liquefied natural ...naturalgas ...

1958-03-08T23:59:59.000Z

119

The Savannah River Site's liquid radioactive waste operations involves the man  

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

Site's liquid radioactive waste operations involves the management of space in the Site's Site's liquid radioactive waste operations involves the management of space in the Site's 49 underground waste tanks, including the removal of waste materials. Once water is removed from the waste tanks, two materials remain: salt and sludge waste. Removing salt waste, which fills approximately 90 percent of the tank space in the SRS tank farms, is a major step toward closing the Site's waste tanks that currently contain approximately 38 million gallons of waste. Due to the limited amount of tank space available in new-style tanks, some salt waste must be dispositioned in the interim to ensure sufficient tank space for continued sludge washing and to support the initial start-up and salt processing operations at the Salt Waste Processing Facility (SWPF).

120

Voluntary Protection Program Onsite, Liquid Waste Contract Savannah River Site- February 2011  

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

Evaluation to determine whether the Liquid Waste Contract Savannah River Site is continuing to perform at a level deserving DOE-VPP Star recognition.

Note: This page contains sample records for the topic "liquid wastes natural" 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

Liquid and gaseous waste operations section. Annual operating report CY 1997  

SciTech Connect

This document presents information on the liquid and gaseous wastes operations section for calendar year 1997. Operating activities, upgrade activities, and maintenance activities are described.

Maddox, J.J.; Scott, C.B.

1998-03-01T23:59:59.000Z

122

Colorado Natural Gas Plant Liquids, Proved Reserves (Million...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Colorado Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

123

Colorado Natural Gas Plant Liquids, Reserves Based Production...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Colorado Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6...

124

Colorado Natural Gas Liquids Lease Condensate, Proved Reserves...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Colorado Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7...

125

Federal Offshore--Texas Natural Gas Liquids Lease Condensate...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Federal Offshore--Texas Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5...

126

Gulf of Mexico Federal Offshore Natural Gas Liquids Proved Reserves...  

Gasoline and Diesel Fuel Update (EIA)

(Million Barrels) Gulf of Mexico Federal Offshore Natural Gas Liquids Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

127

Texas--State Offshore Natural Gas Plant Liquids, Reserves Based...  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Texas--State Offshore Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

128

Federal Offshore--Texas Natural Gas Plant Liquids, Reserves Based...  

Annual Energy Outlook 2012 (EIA)

Reserves Based Production (Million Barrels) Federal Offshore--Texas Natural Gas Plant Liquids, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

129

Texas--State Offshore Natural Gas Liquids Lease Condensate, Proved...  

Gasoline and Diesel Fuel Update (EIA)

Proved Reserves (Million Barrels) Texas--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5...

130

Texas--State Offshore Natural Gas Plant Liquids, Expected Future...  

Annual Energy Outlook 2012 (EIA)

Expected Future Production (Million Barrels) Texas--State Offshore Natural Gas Plant Liquids, Expected Future Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

131

Alaska--State Offshore Natural Gas Plant Liquids Production,...  

Gasoline and Diesel Fuel Update (EIA)

Alaska--State Offshore Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

132

Louisiana--State Offshore Natural Gas Liquids Lease Condensate...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Louisiana--State Offshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5...

133

California Offshore Natural Gas Plant Liquids Production Extracted...  

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

Offshore Natural Gas Plant Liquids Production Extracted in California (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 2010's NA -...

134

Florida Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Florida Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

135

Michigan Natural Gas Plant Liquids, Proved Reserves (Million...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Michigan Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

136

Arkansas Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

Proved Reserves (Million Barrels) Arkansas Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

137

Kansas Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Gasoline and Diesel Fuel Update (EIA)

Proved Reserves (Million Barrels) Kansas Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

138

Wyoming Natural Gas Liquids Proved Reserves (Million Barrels...  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Wyoming Natural Gas Liquids Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's...

139

Pennsylvania Natural Gas Liquids Proved Reserves (Million Barrels...  

Gasoline and Diesel Fuel Update (EIA)

Proved Reserves (Million Barrels) Pennsylvania Natural Gas Liquids Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9...

140

Utah Natural Gas Liquids Proved Reserves (Million Barrels)  

Annual Energy Outlook 2012 (EIA)

Proved Reserves (Million Barrels) Utah Natural Gas Liquids Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 59...

Note: This page contains sample records for the topic "liquid wastes natural" 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

Ohio Natural Gas Liquids Proved Reserves (Million Barrels)  

Annual Energy Outlook 2012 (EIA)

Natural Gas Liquids Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 0 1980's 0 0 - No Data Reported; -- ...

142

Texas--State Offshore Natural Gas Plant Liquids Production, Gaseous...  

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

Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 2010's NA - No Data...

143

U.S. crude oil, natural gas, and natural gas liquids reserves 1997 annual report  

SciTech Connect

This report presents estimates of proved reserves of crude oil, natural gas, and natural gas liquids as of December 31, 1997, as well as production volumes for the US and selected States and State subdivisions for the year 1997. Estimates are presented for the following four categories of natural gas: total gas (wet after lease separation), nonassociated gas and associated-dissolved gas (which are the two major types of wet natural gas), and total dry gas (wet gas adjusted for the removal of liquids at natural gas processing plants). In addition, reserve estimates for two types of natural gas liquids, lease condensate and natural gas plant liquids, are presented. Also included is information on indicated additional crude oil reserves and crude oil, natural gas, and lease condensate reserves in nonproducing reservoirs. A discussion of notable oil and gas exploration and development activities during 1997 is provided. 21 figs., 16 tabs.

NONE

1998-12-01T23:59:59.000Z

144

Summary: U.S. Crude Oil, Natural Gas, and Natural Gas Liquids...  

Annual Energy Outlook 2012 (EIA)

Summary: U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Proved Reserves 2009 November 2010 U.S. Energy Information Administration Office of Oil, Gas, and Coal Supply...

145

"U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Reserves...  

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

Crude Oil, Natural Gas, and Natural Gas Liquids Reserves Summary Data Tables, 2013" "Contents" "Table 1: U.S. proved reserves, and reserves changes, 2012-2013" "Table 2: Principal...

146

Effect of Natural Gas Composition on the Design of Natural Gas Liquid Demethanizers  

Science Journals Connector (OSTI)

Effect of Natural Gas Composition on the Design of Natural Gas Liquid Demethanizers ... The hydrocarbon composition of natural gas varies fairly significantly from location to location. ... The relative amounts of methane (C1) and ethane (C2) have a profound effect on the cryogenic high-pressure distillation column used to recover the C2 and heavier components as a bottoms product called “natural gas liquid” (NGL). ...

William L. Luyben

2013-04-17T23:59:59.000Z

147

,"Natural Gas Plant Field Production: Natural Gas Liquids "  

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

Field Production: Natural Gas Liquids " Field Production: Natural Gas Liquids " ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Field Production: Natural Gas Liquids ",16,"Monthly","9/2013","1/15/1981" ,"Release Date:","11/27/2013" ,"Next Release Date:","Last Week of December 2013" ,"Excel File Name:","pet_pnp_gp_a_epl0_fpf_mbbl_m.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pnp_gp_a_epl0_fpf_mbbl_m.htm" ,"Source:","Energy Information Administration"

148

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

SciTech Connect

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

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)] [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

149

Natural Gas Plant Liquids Proved Reserves  

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

Liquids Proved Reserves Liquids Proved Reserves (Million Barrels) Period: Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes 2006 2007 2008 2009 2010 2011 View History U.S. 7,133 7,648 7,842 8,557 9,809 10,825 1979-2011 Alabama 41 32 92 55 68 68 1979-2011 Alaska 338 325 312 299 288 288 1979-2011 Arkansas 2 2 1 2 2 3 1979-2011 California 130 126 113 129 114 94 1979-2011 Coastal Region Onshore 22 14 10 10 11 12 1979-2011 Los Angeles Basin Onshore 8 9 6 6 5 4 1979-2011 San Joaquin Basin Onshore 100 103 97 113 98 78 1979-2011 State Offshore 0 0 0 0 0 0 1979-2011 Colorado 382 452 612 722 879 925 1979-2011 Florida 3 2 0 0 0 0 1979-2011 Kansas 204 194 175 162 195 192 1979-2011

150

U.S. crude oil, natural gas, and natural gas liquids reserves 1995 annual report  

SciTech Connect

The EIA annual reserves report series is the only source of comprehensive domestic proved reserves estimates. This publication is used by the Congress, Federal and State agencies, industry, and other interested parties to obtain accurate estimates of the Nation`s proved reserves of crude oil, natural gas, and natural gas liquids. These data are essential to the development, implementation, and evaluation of energy policy and legislation. This report presents estimates of proved reserves of crude oil, natural gas, and natural gas liquids as of December 31, 1995, as well as production volumes for the US and selected States and State subdivisions for the year 1995. Estimates are presented for the following four categories of natural gas: total gas (wet after lease separation), nonassociated gas and associated-dissolved gas (which are the two major types of wet natural gas), and total dry gas (wet gas adjusted for the removal of liquids at natural gas processing plants). In addition, reserve estimates for two types of natural gas liquids, lease condensate and natural gas plant liquids, are presented. Also included is information on indicated additional crude oil reserves and crude oil, natural gas, and lease condensate reserves in nonproducing reservoirs. A discussion of notable oil and gas exploration and development activities during 1995 is provided. 21 figs., 16 tabs.

NONE

1996-11-01T23:59:59.000Z

151

US crude oil, natural gas, and natural gas liquids reserves 1996 annual report  

SciTech Connect

The EIA annual reserves report series is the only source of comprehensive domestic proved reserves estimates. This publication is used by the Congress, Federal and State agencies, industry, and other interested parties to obtain accurate estimates of the Nation`s proved reserves of crude oil, natural gas, and natural gas liquids. These data are essential to the development, implementation, and evaluation of energy policy and legislation. This report presents estimates of proved reserves of crude oil, natural gas, and natural gas liquids as of December 31, 1996, as well as production volumes for the US and selected States and State subdivisions for the year 1996. Estimates are presented for the following four categories of natural gas: total gas (wet after lease separation), nonassociated gas and associated-dissolved gas (which are the two major types of wet natural gas), and total dry gas (wet gas adjusted for the removal of liquids at natural gas processing plants). In addition, reserve estimates for two types of natural gas liquids, lease condensate and natural gas plant liquids, are presented. Also included is information on indicated additional crude oil reserves and crude oil, natural gas, and lease condensate reserves in nonproducing reservoirs. A discussion of notable oil and gas exploration and development activities during 1996 is provided. 21 figs., 16 tabs.

NONE

1997-12-01T23:59:59.000Z

152

The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory  

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

Radioactive Liquid Waste Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory OAS-L-13-15 September 2013 Department of Energy Washington, DC 20585 September 26, 2013 MEMORANDUM FOR THE ASSOCIATE ADMINISTRATOR FOR ACQUISITION AND PROJECT MANAGEMENT MANAGER LOS ALAMOS FIELD OFFICE FROM: David Sedillo Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The Radioactive Liquid Waste Treatment Facility Replacement Project at Los Alamos National Laboratory" BACKGROUND The Department of Energy's Los Alamos National Laboratory (Los Alamos) is a Government- owned, contractor operated Laboratory that is part of the National Nuclear Security Administration's (NNSA) nuclear weapons complex. Los Alamos' primary responsibility is to

153

Pennsylvania Natural Gas Plant Liquids Production, Gaseous Equivalent  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Pennsylvania Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 121 116 93 1970's 79 55 70 71 75 68 61 45 64 49 1980's 41 29 40 55 61 145 234 318 272 254 1990's 300 395 604 513 513 582 603 734 732 879 2000's 586 691 566 647 634 700 794 859 1,008 1,295 2010's 4,578 8,931 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013 Next Release Date: 1/7/2014 Referring Pages: NGPL Production, Gaseous Equivalent Pennsylvania Natural Gas Plant Processing

154

No loss fueling station for liquid natural gas vehicles  

SciTech Connect

A no loss liquid natural gas (LNG) delivery system is described comprising: (a) means for storing LNG and natural gas at low pressure; (b) means for delivering LNG from the means for storing to a use device including means for sub-cooling the LNG; (c) means for pre-cooling the means for sub-cooling before the LNG is delivered to the use device to substantially reduce vaporization of the initial LNG delivered to the use device; and (d) means for delivering a selectable quantity of the natural gas in said storing means to said use device with the LNG.

Gustafson, K.

1993-07-20T23:59:59.000Z

155

DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at  

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

DOE Selects Savannah River Remediation, LLC for Liquid Waste DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site December 8, 2008 - 4:58pm Addthis Washington, D.C. -The U.S. Department of Energy (DOE) today announced the award to Savannah River Remediation, LLC as the liquid waste contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $3.3 billion over the entire contract, consisting of a base period of six years, plus an option to extend for up to two additional years. The base performance period of the contract will be from April 1, 2009 through March 31, 2015. A 90-day transition period will begin January 2, 2009.

156

DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at  

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

DOE Selects Savannah River Remediation, LLC for Liquid Waste DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site DOE Selects Savannah River Remediation, LLC for Liquid Waste Contract at Savannah River Site December 8, 2008 - 4:58pm Addthis Washington, D.C. -The U.S. Department of Energy (DOE) today announced the award to Savannah River Remediation, LLC as the liquid waste contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The contract is a cost-plus award-fee contract valued at approximately $3.3 billion over the entire contract, consisting of a base period of six years, plus an option to extend for up to two additional years. The base performance period of the contract will be from April 1, 2009 through March 31, 2015. A 90-day transition period will begin January 2, 2009.

157

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator  

SciTech Connect

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Deckers, Jan; Mols, Ludo [Belgoprocess NV, Operations Department, Gravenstraat 73, B-2480 Dessel (Belgium)

2007-07-01T23:59:59.000Z

158

Naturally occurring crystalline phases: analogues for radioactive waste forms  

SciTech Connect

Naturally occurring mineral analogues to crystalline phases that are constituents of crystalline radioactive waste forms provide a basis for comparison by which the long-term stability of these phases may be estimated. The crystal structures and the crystal chemistry of the following natural analogues are presented: baddeleyite, hematite, nepheline; pollucite, scheelite;sodalite, spinel, apatite, monazite, uraninite, hollandite-priderite, perovskite, and zirconolite. For each phase in geochemistry, occurrence, alteration and radiation effects are described. A selected bibliography for each phase is included.

Haaker, R.F.; Ewing, R.C.

1981-01-01T23:59:59.000Z

159

Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility  

SciTech Connect

The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating text. 38 39 Information provided in this Liquid Effluent Retention Facility and 40 200 Area Effluent Treatment Facility permit application documentation is 41 current as of June 1, 1997.

Coenenberg, J.G.

1997-08-15T23:59:59.000Z

160

Louisiana--South Onshore Natural Gas Liquids Lease Condensate, Proved  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) Liquids Lease Condensate, Proved Reserves (Million Barrels) Louisiana--South Onshore Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 263 1980's 267 253 243 238 229 220 208 194 193 196 1990's 182 175 151 133 123 136 127 134 138 142 2000's 159 141 107 82 66 65 65 71 64 74 2010's 68 64 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Lease Condensate Proved Reserves as of Dec. 31 LA, South Onshore Lease Condensate Proved Reserves, Reserve Changes, and Production

Note: This page contains sample records for the topic "liquid wastes natural" 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

No loss fueling station for liquid natural gas vehicles  

SciTech Connect

This patent describes a no loss fueling station for delivery of liquid natural gas (LNG) to a use device such as a motor vehicle. It comprises: a pressure building tank holding a quantity of LNG and gas head; means for delivering LNG to the pressure building tank; means for selectively building the pressure in the pressure building tank; means for selectively reducing the pressure in the pressure building tank; means for controlling the pressure building and pressure reducing means to maintain a desired pressure in the pressure building tank without venting natural gas to the atmosphere; and means for delivering the LNG from the pressure building tank to the use device.

Cieslukowski, R.E.

1992-06-16T23:59:59.000Z

162

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

SciTech Connect

This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological studies that have been conducted in the vicinity of new Proposed RLWTF site and an Alternative site. The Proposed site is located on Mesita del Buey, a mess top, and the Alternative site is located in Mortandad Canyon. The Proposed Site is devoid of overstory species due to previous disturbance and is dominated by a mixture of grasses, forbs, and scattered low-growing shrubs. Vegetation immediately adjacent to the site is a pinyon-juniper woodland. The Mortandad canyon bottom overstory is dominated by ponderosa pine, willow, and rush. The south-facing slope was dominated by ponderosa pine, mountain mahogany, oak, and muhly. The north-facing slope is dominated by Douglas fir, ponderosa pine, and oak. Studies on wildlife species are limited in the vicinity of the proposed project and further studies will be necessary to accurately identify wildlife populations and to what extent they utilize the project area. Some information is provided on invertebrates, amphibians and reptiles, and small mammals. Additional species information from other nearby locations is discussed in detail. Habitat requirements exist in the project area for one federally threatened wildlife species, the peregrine falcon, and one federal candidate species, the spotted bat. However, based on surveys outside of the project area but in similar habitats, these species are not expected to occur in either the Proposed or Alternative RLWTF sites. Habitat Evaluation Procedures were used to evaluate ecological functioning in the project area.

Biggs, J.

1995-12-31T23:59:59.000Z

163

Performance of Liquid Metals in Natural Circulation Cooled Nuclear Reactors  

SciTech Connect

The inherent safety capability of natural circulation makes reactor design more reliable. Additionally, the construction and operation of a nuclear power plant with natural circulation in the primary cooling circuit is an interesting alternative for nuclear plant designers, due to their lower operational and investment costs obtained by simplifying systems and controls. This paper deals with the feasibility of application of natural circulation in the primary cooling circuit of a liquid metal fast reactor. The methodology employed is a non-dimensional analysis, which describes the relationship between the physical properties and system variables. The performance criterion is bounded by a safety argument, referring to the maximum cladding temperature allowed during operation. The study considers several coolants, which can play a part in reactor cooling systems, such as lead, lead-bismuth and sodium. Bismuth and gallium are included in this analysis, in order to extend the range of properties for reference purposes. The results present a characterization of natural circulation flow in a reactor and compare the cooling capabilities from different liquid metals coolants. (authors)

Ceballos, Carlos; Lathouwers, Danny; Verkooijen, Adrian [Interfacultair Reactor Instituut, Technische Universiteit Delft, Mekelweg 15, Delft (Netherlands)

2004-07-01T23:59:59.000Z

164

Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process  

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

Savannah River Site Liquid Waste Process Savannah River Site Liquid Waste Process June 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM Sahid C. Smith Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Savannah River Site Liquid Waste Process June 2009 ACKNOWLEDGEMENTS The Review Team thanks Ms. Sonitza Blanco, Team Lead Planning and Coordination Waste Disposition Project U.S. Department of Energy Savannah River Operations Office and Mr. Pete Hill, Liquid Waste Planning Manager for Washington Savannah River Company, for their

165

Contact glow discharge electrolysis for liquid waste processing  

E-Print Network (OSTI)

for an alka- line water electrolysis at a small pin verticaldischarge electrolysis applied to waste water treatment.water treatment induced by plasma with contact glow discharge electrolysis.

Sharma, Neeraj

2014-01-01T23:59:59.000Z

166

PROBABILITY BASED CORROSION CONTROL FOR LIQUID WASTE TANKS - PART III  

SciTech Connect

The liquid waste chemistry control program is designed to reduce the pitting corrosion occurrence on tank walls. The chemistry control program has been implemented, in part, by applying engineering judgment safety factors to experimental data. However, the simple application of a general safety factor can result in use of excessive corrosion inhibiting agents. The required use of excess corrosion inhibitors can be costly for tank maintenance, waste processing, and in future tank closure. It is proposed that a probability-based approach can be used to quantify the risk associated with the chemistry control program. This approach can lead to the application of tank-specific chemistry control programs reducing overall costs associated with overly conservative use of inhibitor. Furthermore, when using nitrite as an inhibitor, the current chemistry control program is based on a linear model of increased aggressive species requiring increased protective species. This linear model was primarily supported by experimental data obtained from dilute solutions with nitrate concentrations less than 0.6 M, but is used to produce the current chemistry control program up to 1.0 M nitrate. Therefore, in the nitrate space between 0.6 and 1.0 M, the current control limit is based on assumptions that the linear model developed from data in the <0.6 M region is applicable in the 0.6-1.0 M region. Due to this assumption, further investigation of the nitrate region of 0.6 M to 1.0 M has potential for significant inhibitor reduction, while maintaining the same level of corrosion risk associated with the current chemistry control program. Ongoing studies have been conducted in FY07, FY08, FY09 and FY10 to evaluate the corrosion controls at the SRS tank farm and to assess the minimum nitrite concentrations to inhibit pitting in ASTM A537 carbon steel below 1.0 molar nitrate. The experimentation from FY08 suggested a non-linear model known as the mixture/amount model could be used to predict the probability of corrosion in ASTM A537 in varying solutions as shown in Figure 1. The mixture/amount model takes into account not only the ratio (or mixture) of inhibitors and aggressive species, but also the total concentration (or amount) of species in a solution. Historically, the ratio was the only factor taken into consideration in the development of the current chemistry control program. During FY09, an experimental program was undertaken to refine the mixture/amount model by further investigating the risk associated with reducing the minimum molar nitrite concentration required to confidently inhibit pitting in dilute solutions. The results of FY09, as shown in Figure 2, quantified the probability for a corrosion free outcome for combinations of nitrate and nitrite. The FY09 data predict probabilities up to 70%. Additional experimental data are needed to increase the probability to an acceptable percentage.

Hoffman, E.; Edwards, T.

2010-12-09T23:59:59.000Z

167

Treatment of Bottled Liquid Waste During Remediation of the Hanford 618-10 Burial Ground - 13001  

SciTech Connect

A problematic waste form encountered during remediation of the Hanford Site 618-10 burial ground consists of bottled aqueous waste potentially contaminated with regulated metals. The liquid waste requires stabilization prior to landfill disposal. Prior remediation activities at other Hanford burial grounds resulted in a standard process for sampling and analyzing liquid waste using manual methods. Due to the highly dispersible characteristics of alpha contamination, and the potential for shock sensitive chemicals, a different method for bottle processing was needed for the 618-10 burial ground. Discussions with the United States Department of Energy (DOE) and United States Environmental Protection Agency (EPA) led to development of a modified approach. The modified approach involves treatment of liquid waste in bottles, up to one gallon per bottle, in a tray or box within the excavation of the remediation site. Bottles are placed in the box, covered with soil and fixative, crushed, and mixed with a Portland cement grout. The potential hazards of the liquid waste preclude sampling prior to treatment. Post treatment verification sampling is performed to demonstrate compliance with land disposal restrictions and disposal facility acceptance criteria. (authors)

Faulk, Darrin E.; Pearson, Chris M.; Vedder, Barry L.; Martin, David W. [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)] [Washington Closure Hanford, LLC, Richland, WA 99354 (United States)

2013-07-01T23:59:59.000Z

168

Liquid and Gaseous Waste Operations Project Annual Operating Report CY 1999  

SciTech Connect

A total of 5.77 x 10 7 gallons (gal) of liquid waste was decontaminated by the Process Waste Treatment Complex (PWTC) - Building 3544 ion exchange system during calendar year (CY) 1999. This averaged to 110 gpm throughout the year. An additional 3.94 x 10 6 gal of liquid waste (average of 8 gpm throughout the year) was decontaminated using the zeolite treatment system due to periods of high Cesium levels in the influent wastewater. A total of 6.17 x 10 7 gal of liquid waste (average of 118 gpm throughout the year) was decontaminated at Building 3544 during the year. During the year, the regeneration of the ion exchange resins resulted in the generation of 8.00 x 10 3 gal of Liquid Low-Level Waste (LLLW) concentrate and 9.00 x 10 2 gal of LLLW supernate. See Table 1 for a monthly summary of activities at Building 3544. Figure 1 shows a diagram of the Process Waste Collection and Transfer System and Figure 2 shows a diagram of the Building 3544 treatment process. Figures 3, 4 5, and 6 s how a comparison of operations at Building 3544 in 1997 with previous years. Figure 7 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1995.

Maddox, J.J.; Scott, C.B.

2000-03-01T23:59:59.000Z

169

US and Russian innovative technologies to process low-level liquid radioactive wastes: The Murmansk initiative  

SciTech Connect

This paper documents the status of the technical design for the upgrade and expansion to the existing Low-level Liquid Radioactive Waste (LLLRW) treatment facility in Murmansk, the Russian Federation. This facility, owned by the Ministry of Transportation and operated by the Russian company RTP Atomflot in Murmansk, Russia, has been used by the Murmansk Shipping Company (MSCo) to process low-level liquid radioactive waste generated by the operation of its civilian icebreaker fleet. The purpose of the new design is to enable Russia to permanently cease the disposal at sea of LLLRW in the Arctic, and to treat liquid waste and high saline solutions from both the Civil and North Navy Fleet operations and decommissioning activities. Innovative treatments are to be used in the plant which are discussed in this paper.

Dyer, R.S. [Environmental Protection Agency, Washington, DC (United States); Penzin, R. [Association for Advanced Technologies, Moscow (Russian Federation); Duffey, R.B. [Brookhaven National Lab., Upton, NY (United States); Sorlie, A. [Norwegian Radiation Protection Authority, Osteras (Norway)

1996-12-31T23:59:59.000Z

170

Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission  

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

Role of Liquid Waste Pretreatment Technologies in Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission W. R. Wilmarth March 5 2009 March 5, 2009 HLW Corporate Board Phoenix AZ HLW Corporate Board, Phoenix, AZ Co-authors M. E. Johnson, CH2M Hill Plateau Remediation Company G. Lumetta, Pacific Northwest National Laboratory N Machara DOE Office of Engineering and Technology N. Machara, DOE Office of Engineering and Technology M. R. Poirier, Savannah River National Laboratory P C S DOE S h Ri P. C. Suggs, DOE Savannah River M. C. Thompson, Savannah River National Laboratory, Retired Retired 2 Background Separations is a fundamental business within DOE. The role of separations today is to expedite waste retrieval The role of separations today is to expedite waste retrieval, processing and closure. Recognized as part of E&T Roadmap

171

Louisiana Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Louisiana Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 115,177 140,290 179,117 1970's 193,209 195,072 197,967 206,833 194,329 189,541 172,584 166,392 161,511 165,515 1980's 142,171 142,423 128,858 124,193 132,501 117,736 115,604 124,890 120,092 121,425 1990's 119,405 129,154 132,656 130,336 128,583 146,048 139,841 150,008 144,609 164,794 2000's 164,908 152,862 152,724 124,955 133,434 103,381 105,236 110,745 94,785 95,359 2010's 102,448 95,630 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data.

172

Michigan Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Michigan Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 3,351 3,244 2,705 1970's 2,330 2,013 1,912 1,581 1,921 2,879 6,665 11,494 14,641 15,686 1980's 15,933 14,540 14,182 13,537 12,829 11,129 11,644 10,876 10,483 9,886 1990's 8,317 8,103 8,093 7,012 6,371 6,328 6,399 6,147 5,938 5,945 2000's 5,322 4,502 4,230 3,838 4,199 3,708 3,277 3,094 3,921 2,334 2010's 2,943 2,465 2,480 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013

173

California Natural Gas Plant Liquids Production, Gaseous Equivalent  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) California Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 34,803 32,639 30,334 1970's 29,901 27,585 24,156 17,498 17,201 15,221 14,125 13,567 13,288 10,720 1980's 8,583 7,278 14,113 14,943 15,442 16,973 16,203 15,002 14,892 13,376 1990's 12,424 11,786 12,385 12,053 11,250 11,509 12,169 11,600 10,242 10,762 2000's 11,063 11,060 12,982 13,971 14,061 13,748 14,056 13,521 13,972 13,722 2010's 13,244 12,095 12,755 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data.

174

Kentucky Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Kentucky Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 11,500 8,573 8,579 1970's 6,574 6,133 6,063 5,441 5,557 5,454 5,231 4,764 6,192 3,923 1980's 6,845 5,638 6,854 6,213 6,516 6,334 4,466 2,003 2,142 1,444 1990's 1,899 2,181 2,342 2,252 2,024 2,303 2,385 2,404 2,263 2,287 2000's 1,416 1,558 1,836 1,463 2,413 1,716 2,252 1,957 2,401 3,270 2010's 4,576 4,684 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013 Next Release Date: 1/7/2014

175

New Mexico Natural Gas Plant Liquids Production, Gaseous Equivalent  

Gasoline and Diesel Fuel Update (EIA)

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) New Mexico Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 46,149 48,635 50,484 1970's 52,647 53,810 54,157 55,782 54,986 56,109 61,778 72,484 77,653 62,107 1980's 59,457 60,544 56,857 56,304 58,580 53,953 51,295 65,156 63,355 61,594 1990's 66,626 70,463 75,520 83,193 86,607 85,668 108,341 109,046 106,665 107,850 2000's 110,411 108,958 110,036 111,292 105,412 101,064 99,971 96,250 92,579 94,840 2010's 91,963 90,291 84,562 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data.

176

Colorado Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Colorado Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 4,126 4,546 4,058 1970's 3,405 4,152 4,114 4,674 6,210 9,620 11,944 13,507 13,094 12,606 1980's 12,651 13,427 12,962 11,314 10,771 11,913 10,441 10,195 11,589 13,340 1990's 13,178 15,822 18,149 18,658 19,612 25,225 23,362 28,851 24,365 26,423 2000's 29,105 29,195 31,952 33,650 35,821 34,782 36,317 38,180 53,590 67,607 2010's 82,637 90,801 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data.

177

Alabama Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Alabama Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 236 1970's 225 281 243 199 501 694 661 933 1,967 4,845 1980's 4,371 4,484 4,727 4,709 5,123 5,236 4,836 4,887 4,774 5,022 1990's 4,939 4,997 5,490 5,589 5,647 5,273 5,361 4,637 4,263 18,079 2000's 24,086 13,754 14,826 11,293 15,133 13,759 21,065 19,831 17,222 17,232 2010's 19,059 17,271 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013 Next Release Date: 1/7/2014 Referring Pages:

178

North Dakota Natural Gas Plant Liquids Production, Gaseous Equivalent  

Gasoline and Diesel Fuel Update (EIA)

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) North Dakota Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 5,150 5,428 4,707 1970's 4,490 3,592 3,199 2,969 2,571 2,404 2,421 2,257 2,394 2,986 1980's 3,677 5,008 5,602 7,171 7,860 8,420 6,956 7,859 6,945 6,133 1990's 6,444 6,342 6,055 5,924 5,671 5,327 4,937 5,076 5,481 5,804 2000's 6,021 6,168 5,996 5,818 6,233 6,858 7,254 7,438 7,878 10,140 2010's 11,381 14,182 26,156 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 1/7/2014

179

Lower 48 States Natural Gas Liquids Lease Condensate, Proved Reserves  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) Liquids Lease Condensate, Proved Reserves (Million Barrels) Lower 48 States Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 1,401 1980's 1,530 1,580 1,601 1,613 1,503 1,452 1,436 1,402 1,389 1,389 1990's 1,302 1,244 1,226 1,192 1,147 1,197 1,307 1,341 1,336 1,403 2000's 1,472 1,398 1,346 1,215 1,221 1,262 1,339 1,495 1,433 1,633 2010's 1,914 2,370 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Lease Condensate Proved Reserves as of Dec. 31 Lower 48 States Lease Condensate Proved Reserves, Reserve Changes,

180

Texas Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Texas Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 433,684 457,117 447,325 1970's 466,016 448,288 470,105 466,143 448,993 435,571 428,635 421,110 393,819 352,650 1980's 350,312 345,262 356,406 375,849 393,873 383,719 384,693 364,477 357,756 343,233 1990's 342,186 353,737 374,126 385,063 381,020 381,712 398,442 391,174 388,011 372,566 2000's 380,535 355,860 360,535 332,405 360,110 355,589 373,350 387,349 401,503 424,042 2010's 433,622 481,308 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data.

Note: This page contains sample records for the topic "liquid wastes natural" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Mississippi Natural Gas Plant Liquids Production, Gaseous Equivalent  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Mississippi Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 1,127 971 1,334 1970's 1,270 1,217 1,058 878 679 567 520 367 485 1,146 1980's 553 830 831 633 618 458 463 437 811 380 1990's 445 511 416 395 425 377 340 300 495 5,462 2000's 11,377 15,454 16,477 11,430 13,697 14,308 14,662 13,097 10,846 18,354 2010's 18,405 11,221 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013 Next Release Date: 1/7/2014 Referring Pages: NGPL Production, Gaseous Equivalent

182

Arkansas Natural Gas Plant Liquids Production, Gaseous Equivalent (Million  

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

Liquids Production, Gaseous Equivalent (Million Cubic Feet) Liquids Production, Gaseous Equivalent (Million Cubic Feet) Arkansas Natural Gas Plant Liquids Production, Gaseous Equivalent (Million Cubic Feet) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1960's 3,499 3,667 3,475 1970's 3,235 2,563 1,197 1,118 952 899 823 674 883 1,308 1980's 1,351 1,327 1,287 1,258 1,200 1,141 1,318 1,275 1,061 849 1990's 800 290 413 507 553 488 479 554 451 431 2000's 377 408 395 320 254 231 212 162 139 168 2010's 213 268 424 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 12/12/2013 Next Release Date: 1/7/2014 Referring Pages: NGPL Production, Gaseous Equivalent

183

Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet  

SciTech Connect

The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere.

Abotsi, G.M.K. [Clark Atlanta Univ., GA (United States); Bostick, D.T.; Beck, D.E. [Oak Ridge National Lab., TN (United States)] [and others

1996-05-01T23:59:59.000Z

184

Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume...  

Energy Savers (EERE)

Synthesis, Volume 2: A Techno-economic Evaluation of the Production of Mixed Alcohols Biomass is a renewable energy resource that can be converted into liquid fuel suitable for...

185

Development of Advanced Electrochemical Emission Spectroscopy for Monitoring Corrosion in Simulated DOE Liquid Waste  

SciTech Connect

Various forms of general and localized corrosion represent principal threats to the integrity of DOE liquid waste storage tanks. These tanks, which are of a single wall or double wall design, depending upon their age, are fabricated from welded carbon steel and contain a complex waste-form comprised of NaOH and NaNO3, along with trace amounts of phosphate, sulfate, carbonate, and chloride. Because waste leakage can have a profound environmental impact, considerable interest exists in predicting the accumulation of corrosion damage, so as to more effectively schedule maintenance and repair.

MacDonal, Digby D.; Marx, Brian M.; Ahn, Sejin; Ruiz, Julio de; Soundararajan, Balaji; Smith, Morgan; Coulson, Wendy

2005-06-15T23:59:59.000Z

186

Evaluation of gas-liquid separation performance of natural gas filters  

Science Journals Connector (OSTI)

Fibrous filters are often used to remove contaminants including both dusts and liquid droplets from natural gas. This paper aims to evaluate the gas-liquid separation performance of three types of cartridge filte...

Baisong Li; Zhongli Ji; Xue Yang

2009-12-01T23:59:59.000Z

187

U.S. Federal Offshore Natural Gas Plant Liquids, Proved Reserves...  

Gasoline and Diesel Fuel Update (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) U.S. Federal Offshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4...

188

Removal of Radioactive Nuclides from Mo-99 Acidic Liquid Waste - 13027  

SciTech Connect

About 200 liters highly radioactive acidic liquid waste originating from Mo-99 production was stored at INER (Institute of Nuclear Energy Research). A study regarding the treatment of the radioactive acidic liquid waste was conducted to solve storage-related issues and allow discharge of the waste while avoiding environmental pollution. Before discharging the liquid waste, the acidity, NO{sub 3}{sup -} and Hg ions in high concentrations, and radionuclides must comply with environmental regulations. Therefore, the treatment plan was to neutralize the acidic liquid waste, remove key radionuclides to reduce the dose rate, and then remove the nitrate and mercury ions. Bench tests revealed that NaOH is the preferred solution to neutralize the high acidic waste solution and the pH of solution must be adjusted to 9?11 prior to the removal of nuclides. Significant precipitation was produced when the pH of solution reached 9. NaNO{sub 3} was the major content in the precipitate and part of NaNO{sub 3} was too fine to be completely collected by filter paper with a pore size of approximately 3 ?m. The residual fine particles remaining in solution therefore blocked the adsorption column during operation. Two kinds of adsorbents were employed for Cs-137 and a third for Sr-90 removal to minimize cost. For personnel radiation protection, significant lead shielding was required at a number of points in the process. The final process design and treatment facilities successfully treated the waste solutions and allowed for environmentally compliant discharge. (authors)

Hsiao, Hsien-Ming; Pen, Ben-Li [Chemical Engineering Division, Institute of Nuclear Energy Research, P.O. Box 3-7, Longtan 32546 Taiwan, Republic of China (China)] [Chemical Engineering Division, Institute of Nuclear Energy Research, P.O. Box 3-7, Longtan 32546 Taiwan, Republic of China (China)

2013-07-01T23:59:59.000Z

189

Selection of Controlled Variables for a Natural Gas to Liquids Process Mehdi Panahi and Sigurd Skogestad*  

E-Print Network (OSTI)

Selection of Controlled Variables for a Natural Gas to Liquids Process Mehdi Panahi and Sigurd variables (CVs) for a natural gas to hydrocarbon liquids (GTL) process based on the idea of self of operation are studied. In mode I, where the natural gas flow rate is given, there are three unconstrained

Skogestad, Sigurd

190

ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage and  

E-Print Network (OSTI)

, The Texas A&M University System. #12;Pumping Pumping from the lagoon should be conducted annually, at least the designed life of sludge storage, frequent agitation and pumping may be necessary. In addition, solidsL ivestock and poultry operations frequently use anaerobic lagoons as liquid waste storage

Mukhtar, Saqib

191

Federal Offshore--Louisiana and Alabama Natural Gas Liquids Lease  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Reserves Based Production (Million Barrels) Federal Offshore--Louisiana and Alabama Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1980's 34 28 27 29 32 1990's 33 34 35 35 37 40 49 59 57 61 2000's 76 60 60 53 49 39 37 40 28 28 2010's 28 24 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Lease Condensate Estimated Production Federal Offshore, Gulf of Mexico, Louisiana & Alabama Lease Condensate Proved Reserves, Reserve Changes, and Production Lease Condensate

192

Lower 48 States Natural Gas Liquids Lease Condensate, Reserves Based  

Gasoline and Diesel Fuel Update (EIA)

Reserves Based Production (Million Barrels) Reserves Based Production (Million Barrels) Lower 48 States Natural Gas Liquids Lease Condensate, Reserves Based Production (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 147 1980's 159 161 157 157 179 168 169 162 162 165 1990's 158 153 147 153 157 145 162 174 178 199 2000's 208 215 207 191 182 174 182 181 173 178 2010's 224 211 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Lease Condensate Estimated Production Lower 48 States Lease Condensate Proved Reserves, Reserve Changes, and Production Lease Condensate

193

Natural Gas Liquids Proved Reserves as of Dec. 31  

Gasoline and Diesel Fuel Update (EIA)

Million Barrels) Million Barrels) Data Series: Dry Natural Gas Wet NG Wet Nonassociated NG Wet Associated-Dissolved NG Natural Gas Liquids Period: Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Data Series Area 2003 2004 2005 2006 2007 2008 View History U.S. 7,459 7,928 8,165 8,472 9,143 9,275 1979-2008 Federal Offshore U.S. 725 721 696 653 624 548 1981-2008 Pacific (California) 8 8 8 4 4 1 1979-2008 Gulf of Mexico 717 713 688 649 620 1992-2007 Louisiana & Alabama 598 615 603 575 528 464 1981-2008 Texas 119 98 85 74 92 83 1981-2008 Alaska 387 369 352 338 325 312 1979-2008 Lower 48 States 7,072 7,559 7,813 8,134 8,818 8,963 1979-2008

194

External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process  

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

Hanford Site Liquid Waste Process Hanford Site Liquid Waste Process September 2009 Monica C. Regalbuto Office of Waste Processing DOE/EM Kevin G. Brown Vanderbilt University and CRESP David W. DePaoli Oak Ridge National Laboratory Candido Pereira Argonne National Laboratory John R. Shultz Office of Waste Processing DOE/EM External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process September 2009 Acknowledgements The Review Team thanks Mr. Glyn Trenchard, Team Lead for Planning and Coordination Waste Disposition Project, U.S. Department of Energy--Office of River Protection, Mr. Paul Rutland, RPP System Planning Manager for Washington River Protection Solutions, and Mr. Ernie Lee,

195

Treatment of Liquid Radioactive Waste with High Salt Content by Colloidal Adsorbents - 13274  

SciTech Connect

Treatment processes have been fully developed for most of the liquid radioactive wastes generated during the operation of nuclear power plants. However, a process for radioactive liquid waste with high salt content, such as waste seawater generated from the unexpected accident at nuclear power station, has not been studied extensively. In this study, the adsorption efficiencies of cesium (Cs) and strontium (Sr) in radioactive liquid waste with high salt content were investigated using several types of zeolite with different particle sizes. Synthesized and commercial zeolites were used for the treatment of simulated seawater containing Cs and Sr, and the reaction kinetics and adsorption capacities of colloidal zeolites were compared with those of bulk zeolites. The experimental results demonstrated that the colloidal adsorbents showed fast adsorption kinetic and high binding capacity for Cs and Sr. Also, the colloidal zeolites could be successfully applied to the static adsorption condition, therefore, an economical benefit might be expected in an actual processes where stirring is not achievable. (authors)

Lee, Keun-Young; Chung, Dong-Yong; Kim, Kwang-Wook; Lee, Eil-Hee; Moon, Jei-Kwon [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)] [Korea Atomic Energy Research Institute - KAERI, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

196

Savannah River Site, Liquid Waste Program, Savannah River Remediation American Recovery and Reinvestment Act Benefits and Lessons Learned - 12559  

SciTech Connect

Utilizing funding provided by the American Recovery and Reinvestment Act (ARRA), the Liquid Waste Program at Savannah River site successfully executed forty-one design, procurement, construction, and operating activities in the period from September 2009 through December 2011. Project Management of the program included noteworthy practices involving safety, integrated project teams, communication, and cost, schedule and risk management. Significant upgrades to plant capacity, progress toward waste tank closure and procurement of needed infrastructure were accomplished. Over 1.5 million hours were worked without a single lost work day case. Lessons Learned were continually identified and applied to enhance the program. Investment of Recovery Act monies into the Liquid Waste Program has ensured continued success in the disposition of radioactive wastes and the closure of high level waste tanks at SRS. The funding of a portion of the Liquid Waste Program at SRS by ARRA was a major success. Significant upgrades to plant capacity, progress toward waste tank closure and procurement of needed infrastructure was accomplished. Integrated Project Teams ensured quality products and services were provided to the Operations customers. Over 1.5 million hours were worked without a single lost work day case. Lessons Learned were continually reviewed and reapplied to enhance the program. Investment of Recovery Act monies into the Liquid Waste Program has ensured continued success in the disposition of radioactive wastes and the closure of high level waste tanks at SRS. (authors)

Schmitz, Mark A.; Crouse, Thomas N. [Savannah River Remediation, Aiken, South Carolina 29808 (United States)

2012-07-01T23:59:59.000Z

197

Recovery and utilization of waste liquids in ultra-clean coal preparation by chemical leaching  

SciTech Connect

Coal with ash lower than 1%, being called an ultra-clean coal, has many potential applications, such as a substitute for diesel fuel, production of carbon electrodes, superior activated carbon and other chemical materials. It is difficult to reduce coal ash to such a level by conventional coal preparation technology. By means of chemical leaching with the proper concentration of alkali and acid solutions, any coal can be deeply deashed to 1% ash level. However, the cost of chemical methods is higher than that of physical ones, additionally, the waste liquids would give rise to environmental pollution if used on a large scale. If the waste liquids from chemical preparation of ultra-clean coal can be recovered and utilized, so as to produce salable by-products, the cost of chemical leaching will be reduced. This processing will also solve the pollution problem of these waste liquids. This paper describes recovery and utilization methods for these liquids used in chemical leaching, including the recoveries of alkali, silica, sodium-salt and aluminium-salt. A preliminary estimate was made regarding its economic benefits. It shows that this research solves the two problems in the chemical preparation of ultra-clean coal. One is the high-cost and the other is environmental pollution. This research demonstrates good potential for the production of ultra-clean coal on an industrial scale.

Xu Zesheng; Shi Zhimin; Yang Qiaowen; Wang Xinguo [China Univ. of Mining and Technology, Beijing (China). Beijing Graduate School

1997-12-31T23:59:59.000Z

198

Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312  

SciTech Connect

Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

Fournel, B.; Barre, Y.; Lepeytre, C.; Peycelon, H. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Grandjean, A. [Institut de Chimie Separative de Marcoule, UMR5257 CEA-CNRS-UM2-ENSCM, BP17171, 30207 Bagnols sur Ceze (France); Prevost, T.; Valery, J.F. [AREVA NC, Paris La Defense (France); Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191 Gif sur Yvette (France)

2012-07-01T23:59:59.000Z

199

Texas - RRC District 3 Onshore Natural Gas Plant Liquids, Proved Reserves  

Gasoline and Diesel Fuel Update (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) Gas Plant Liquids, Proved Reserves (Million Barrels) Texas - RRC District 3 Onshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 231 1980's 216 230 265 285 270 260 237 241 208 213 1990's 181 208 211 253 254 272 289 286 246 226 2000's 209 226 241 207 221 226 234 271 196 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Natural Gas Liquids Proved Reserves as of Dec. 31 TX, RRC District 3 Onshore Natural Gas Liquids Proved Reserves Natural Gas Liquids Proved Reserves as of Dec.

200

Texas - RRC District 4 Onshore Natural Gas Plant Liquids, Proved Reserves  

Gasoline and Diesel Fuel Update (EIA)

Gas Plant Liquids, Proved Reserves (Million Barrels) Gas Plant Liquids, Proved Reserves (Million Barrels) Texas - RRC District 4 Onshore Natural Gas Plant Liquids, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 248 1980's 252 260 289 292 295 269 281 277 260 260 1990's 279 273 272 278 290 287 323 347 363 422 2000's 406 378 370 287 326 309 333 327 310 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Natural Gas Liquids Proved Reserves as of Dec. 31 TX, RRC District 4 Onshore Natural Gas Liquids Proved Reserves Natural Gas Liquids Proved Reserves as of Dec.

Note: This page contains sample records for the topic "liquid wastes natural" 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

Microsoft PowerPoint - S05-07_Varona_Solid-Liquid Waste Interface.pptx  

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

Liquid Interface Monitor Liquid Interface Monitor (SLIM) Jose Varona D. Roelant, A. Awwad, D. McDaniel Florida International University's Applied Research Center EM Waste Processing Technical Exchange November 17, 2010 Print Close Disclaimer This presentation was prepared as an account of work sponsored by an agency of the United States government (Department of Energy, Office of Environmental Management, under Grant No. DE-FG01-05EW07033). Neither the United States government nor any agency thereof, nor any of their employees, nor any of its contractors, subcontractors, nor their employees makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness,

202

SOLIEX: A Novel Solid-Liquid Method of Radionuclides Extraction from Radioactive Waste Solutions - 13486  

SciTech Connect

This paper describes recent developments in new solid-liquid extraction method, called SOLIEX, to remove cesium from alkaline solutions. SOLIEX relies on the use of a reversible complexing system comprising a carbon felt bearing molecular traps (calixarenes). This complexing system exhibits a high selectivity for Cs, and is thus expected to be helpful for the treatment of highly diluted cesium wastes even with a high concentration of competing alkali metal cations. As additional advantage, this complexing system can be adapted by molecular engineering to capture other radionuclides, such as Sr, Eu, Am. Finally, this complexing system can be easily and efficiently regenerated by using a cost effective stripping procedure, which limits further generation of waste to meet 'zero liquid' discharge requirements for nuclear facilities. (authors)

Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191Gif sur Yvette (France)] [CEA Saclay, DSM/IRAMIS/SPCSI, 91191Gif sur Yvette (France); Fournel, B.; Barre, Y. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France)] [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Huc, V. [ICMMO - UMR CNRS 8182 - Bat. 420 Universite Paris-Sud (France)] [ICMMO - UMR CNRS 8182 - Bat. 420 Universite Paris-Sud (France)

2013-07-01T23:59:59.000Z

203

Physicochemical Processes Occurring in Long-Term Storage of Liquid Radioactive Waste in Deep Underground Collector Beds  

Science Journals Connector (OSTI)

Interaction under hydrothermal conditions (pressure 3 MPa; temperature 80-170°C; contact time up to 2500 h) of intermediate-level acidic waste with bed rock of the underground repository for liquid radioactive...

E. V. Zakharova; E. P. Kaimin; E. N. Darskaya; K. A. Menyailo…

2001-07-01T23:59:59.000Z

204

Identification and differentiation of individual beta emitters in waste mixtures by liquid scintillation spectrometry  

E-Print Network (OSTI)

carbon-14, tritium, and iodine-125 liquid scintillation wastes, provided that the activity and isotopes present can be documented. This legislation has generated a significant interest in developing a quick, cost efficient method of identificatior.... Differentiation of various components within a two isotope mixture, and the detection level of a small activity of one nuclide in a large activity of a second radioisotope was examined. A catalogue of spectra, including the isotopic ratio of each component...

Siskel, Robin Lynn

1988-01-01T23:59:59.000Z

205

EA-437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory  

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

437; Environmental Assessment Process Equipment Waste and 437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory TABLE OF CONTENTS Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory 1. INTRODUCTION 2. DESCRIPTION OF THE PROPOSED ACTION AND ALTERNATIVES 2.1 Purpose and Need of the Proposed Action 2.2 Description of the Affected Facilities 2.3 Description of Proposed Action 2.4 Alternatives to the Proposed Action 2.5 Separate But Related Actions 3. AFFECTED ENVIRONMENT 3.1 Introduction 3.2 Physical Environment 3.3 Biological Resources 3.4 Cultural Resources 3.5 Environmental Quality and Monitoring Programs

206

Deployment of Performance Management Methodology as part of Liquid Waste Program at Savannah River Site - 12178  

SciTech Connect

In 2009, Savannah River Remediation LLC (SRR) assumed the management lead of the Liquid Waste (LW) Program at the Savannah River Site (SRS). The four SRR partners and AREVA, as an integrated subcontractor are performing the ongoing effort to safely and reliably: - Close High Level Waste (HLW) storage tanks; - Maximize waste throughput at the Defense Waste Processing Facility (DWPF); - Process salt waste into stable final waste form; - Manage the HLW liquid waste material stored at SRS. As part of these initiatives, SRR and AREVA deployed a performance management methodology based on Overall Equipment Effectiveness (OEE) at the DWPF in order to support the required production increase. This project took advantage of lessons learned by AREVA through the deployment of Total Productive Maintenance and Visual Management methodologies at the La Hague reprocessing facility in France. The project also took advantage of measurement data collected from different steps of the DWPF process by the SRR team (Melter Engineering, Chemical Process Engineering, Laboratory Operations, Plant Operations). Today the SRR team has a standard method for measuring processing time throughout the facility, a reliable source of objective data for use in decision-making at all levels, and a better balance between engineering department goals and operational goals. Preliminary results show that the deployment of this performance management methodology to the LW program at SRS has already significantly contributed to the DWPF throughput increases and is being deployed in the Saltstone facility. As part of the liquid waste program on Savannah River Site, SRR committed to enhance production throughput of DWPF. Beyond technical modifications implemented at different location of the facility, SRR deployed performance management methodology based on OEE metrics. The implementation benefited from the experience gained by AREVA in its own facilities in France. OEE proved to be a valuable tool in order to support the enhancement program in DWPF by providing unified metrics to measure plant performances, identify bottleneck location, and rank the most time consuming causes from objective data shared between the different groups belonging to the organization. Beyond OEE, the Visual Management tool adapted from the one used at La Hague were also provided in order to further enhance communication within the operating teams. As a result of all the initiatives implemented on DWPF, achieved production has been increased to record rates from FY10 to FY11. It is expected that thanks to the performance management tools now available within DWPF, these results will be sustained and even improved in the future to meet system plan targets. (authors)

Prod'homme, A.; Drouvot, O.; Gregory, J. [AREVA, Paris (France); Barnes, B.; Hodges, B.; Hart, M. [SRR, Aiken, SC (United States)

2012-07-01T23:59:59.000Z

207

U.S. Natural Gas Liquids Proved Reserves  

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

Liquids Proved Reserves (Million Barrels) Area: U.S. Federal Offshore U.S. Federal Offshore, Pacific (California) Federal Offshore, Gulf of Mexico, LA & AL Federal Offshore, Gulf...

208

Catalyst-Assisted Production of Olefins from Natural Gas Liquids: Prototype Development and Full-Scale Testing, April 2013  

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

Catalyst-Assisted Production of Olefins from Natural Gas Liquids: Prototype Development and Full-Scale Testing

209

Third-order gas-liquid phase transition and the nature of Andrews critical Tian Ma and Shouhong Wang  

E-Print Network (OSTI)

Third-order gas-liquid phase transition and the nature of Andrews critical point Tian Ma-order gas-liquid phase transition and the nature of Andrews critical point Tian Ma1 and Shouhong Wang2 1 is to study the nature of the Andrews critical point in the gas-liquid transition in a physical

Wang, Shouhong

210

Natural glass analogues to alteration of nuclear waste glass: A review and recommendations for further study  

SciTech Connect

The purpose of this report is to review previous work on the weathering of natural glasses; and to make recommendations for further work with respect to studying the alteration of natural glasses as it relates quantifying rates of dissolution. the first task was greatly simplified by the published papers of Jercinovic and Ewing (1987) and Byers, Jercinovic, and Ewing (1987). The second task is obviously the more difficult of the two and the author makes no claim of completeness in this regard. Glasses weather in the natural environment by reacting with aqueous solutions producing a rind of secondary solid phases. It had been proposed by some workers that the thickness of this rind is a function of the age of the glass and thus could be used to estimate glass dissolution rates. However, Jercinovic and Ewing (1987) point out that in general the rind thickness does not correlate with the age of the glass owing to the differences in time of contact with the solution compared to the actual age of the sample. It should be noted that the rate of glass dissolution is also a function of the composition of both the glass and the solution, and the temperature. Quantification of the effects of these parameters (as well as time of contact with the aqueous phase and flow rates) would thus permit a prediction of the consequences of glass-fluid interactions under varying environmental conditions. Defense high- level nuclear waste (DHLW), consisting primarily of liquid and sludge, will be encapsulated by and dispersed in a borosilicate glass before permanent storage in a HLW repository. This glass containing the DHLW serves to dilute the radionuclides and to retard their dispersion into the environment. 318 refs.

McKenzie, W.F.

1990-01-01T23:59:59.000Z

211

LOW LEVEL LIQUID RADIOACTIVE WASTE TREATMENT AT MURMANSK, RUSSIA: FACILITY UPGRADE AND EXPANSION  

SciTech Connect

Today there exist many almost overfilled storage tanks with liquid radioactive waste in the Russian Federation. This waste was generated over several years by the civil and military utilization of nuclear power. The current waste treatment capacity is either not available or inadequate. Following the London Convention, dumping of the waste in the Arctic seas is no longer an alternative. Waste is being generated from today's operations, and large volumes are expected to be generated from the dismantling of decommissioned nuclear submarines. The US and Norway have an ongoing co-operation project with the Russian Federation to upgrade and expand the capacity of a treatment facility for low level liquid waste at the RTP Atomflot site in Murmansk. The capacity will be increased from 1,200 m{sup 3}/year to 5,000 m{sup 3} /year. The facility will also be able to treat high saline waste. The construction phase will be completed the first half of 1998. This will be followed by a start-up and a one year post-construction phase, with US and Norwegian involvement for the entire project. The new facility will consist of 9 units containing various electrochemical, filtration, and sorbent-based treatment systems. The units will be housed in two existing buildings, and must meet more stringent radiation protection requirements that were not enacted when the facility was originally designed. The US and Norwegian technical teams have evaluated the Russian design and associated documentation. The Russian partners send monthly progress reports to US and Norway. Not only technical issues must be overcome but also cultural differences resulting from different methods of management techniques. Six to eight hour time differentials between the partners make real time decisions difficult and relying on electronic age tools becomes extremely important. Language difficulties is another challenge that must be solved. Finding a common vocabulary, and working through interpreters make the process very vulnerable. Each of these obstacles can be overcome when there is a common goal and vision shared by all parties and adequate funds are provided to accomplish the task. The upgrading and expansion of this facility and the construction of a similar facility on the Far East coast of Russia will enable the Russians to sign the London Convention dumping prohibition. This project is one of the first waste management construction projects in the north-west of Russia with foreign contribution. Its success may open for additional co-operative projects with Russia in the future.

BOWERMAN,B.; CZAJKOWSKI,C.; DYER,R.S.; SORLIE,A.

2000-03-01T23:59:59.000Z

212

Treatment requirements for decontamination of ORNL low-level liquid waste  

SciTech Connect

Experimental studies have been made to provide data for the development of improved processes for decontaminating low-level liquid wastes (LLLWs) that exist and continue to be generated at Oak Ridge National Laboratory. The concept underlying this work is that there is a net benefit if the major radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 90}Sr, and actinides) can be separated into small volumes, thereby reducing the activity of the bulk of the waste so that it can be disposed of or managed at a lower total cost. Data-base calculations on the LLLW supernate and sludges contained in the active Melton Valley Storage Tanks and evaporator storage and service tanks are essential in order to define and determine the extent of the problem. These calculations indicate to what extent alpha- and beta-gamma-emitting radionuclides must be removed and/or treated before final disposition of the waste can be made. They also show that many of the inorganic constitutents (e.g., regulated metals and nitrate) and minor radionuclides such as {sup 14}C and actinides (in terms of quantity present) must be removed before the LLLW can be disposed of as either liquid to the environment or solidified and disposed of as solid NUS Class L-1 or L-2 LLW. 25 refs., 31 tabs.

Lee, D.D.; Campbell, D.O.

1991-10-01T23:59:59.000Z

213

A Management Tool for Analyzing CHP Natural Gas Liquids Recovery System  

E-Print Network (OSTI)

The objective of this research is to develop a management tool for analyzing combined heat and power (CHP) natural gas liquids (NGL) recovery systems. The methodology is developed around the central ideas of product recovery, possible recovery...

Olsen, C.; Kozman, T. A.; Lee, J.

2008-01-01T23:59:59.000Z

214

Selection of Controlled Variables for a Natural Gas to Liquids Process  

Science Journals Connector (OSTI)

Selection of Controlled Variables for a Natural Gas to Liquids Process ... Also, dynamic issues, such as inverse response, may cause problems for control, and it may be necessary to use cascade control. ...

Mehdi Panahi; Sigurd Skogestad

2012-06-20T23:59:59.000Z

215

Treatment of low-level radioactive waste liquid by reverse osmosis  

SciTech Connect

The processing of low-level radioactive waste (LLRW) liquids that result from operation of nuclear power plants with reverse osmosis systems is not common practice. A demonstration facility is operating at Chalk River Laboratories (of Atomic Energy of Canada Limited), processing much of the LLRW liquids generated at the site from a multitude of radioactive facilities, ranging from isotope production through decontamination operations and including chemical laboratory drains. The reverse osmosis system comprises two treatment steps--spiral wound reverse osmosis followed by tubular reverse osmosis--to achieve an average volume reduction factor of 30:1 and a removal efficiency in excess of 99% for most radioactive and chemical species. The separation allows the clean effluent to be discharged without further treatment. The concentrated waste stream of 3 wt% total solids is further processed to generate a solid product. The typical lifetimes of the membranes have been nearly 4000 hours, and replacement was required based on increased pressure drops and irreversible loss of permeate flux. Four years of operating experience with the reverse osmosis system, to demonstrate its practicality and to observe and record its efficiency, maintenance requirements and effectiveness, have proven it to be viable for volume reduction and concentration of LLRW liquids generated from nuclear-power-plant operations.

Buckley, L.P.; Sen Gupta, S.K.; Slade, J.A. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada). Chalk River Labs.

1995-12-31T23:59:59.000Z

216

Waste Tank Organic Safety Project: Analysis of liquid samples from Hanford waste tank 241-C-103  

SciTech Connect

A suite of physical and chemical analyses has been performed in support of activities directed toward the resolution of an Unreviewed Safety Question concerning the potential for a floating organic layer in Hanford waste tank 241-C-103 to sustain a pool fire. The analysis program was the result of a Data Quality Objectives exercise conducted jointly with staff from Westinghouse Hanford Company and Pacific Northwest Laboratory (PNL). The organic layer has been analyzed for flash point, organic composition including volatile organics, inorganic anions and cations, radionuclides, and other physical and chemical parameters needed for a safety assessment leading to the resolution of the Unreviewed Safety Question. The aqueous layer underlying the floating organic material was also analyzed for inorganic, organic, and radionuclide composition, as well as other physical and chemical properties. This work was conducted to PNL Quality Assurance impact level III standards (Good Laboratory Practices).

Pool, K.H.; Bean, R.M.

1994-03-01T23:59:59.000Z

217

Relative contributions of natural and waste-derived organics to the subsurface transport of radionuclides  

SciTech Connect

Our laboratory is studying the role of organic compounds in the subsurface transport of radionuclides at shallow-land burial sites of low-level nuclear waste, including a commercial site at Maxey Flats, Kentucky, and an aqueous waste disposal site. At the Maxey Flats site, several radionuclides, notably Pu and /sup 60/Co, appear to exist as anionic, organic complexes. Waste-derived organics, particularly chelating agents such as EDTA, HEDTA and associated degradation products (e.g., ED3A), are abundant in aqueous waste leachates and appear to account for the complexation. EDTA, and probably other waste-derived chelating agents as well, are chelated to the Pu and /sup 60/Co in the leachates, potentially mobilizing these radionuclides. In contrast, at the low-level aqueous waste disposal site, naturally-occurring organics, ranging from low molecular weight (MW) acids to high MW humic acids, account for the bulk of the groundwater's organic content. Certain radionuclides, notably /sup 60/Co, /sup 103/Ru and /sup 125/Sb, are mobile as anionic complexes. These radionuclides are clearly associated with higher MW organics, presumably humic and fulvic acids with nominal MW's > 1000. It is clear, therefore, that naturally-occurring organics may play an important role in radionuclide transport, particularly at nuclear waste burial sites containing little in the way of waste-derived organics.

Toste, A.P.; Myers, R.B.

1985-06-01T23:59:59.000Z

218

Alternatives for the disposal of NORM (naturally occurring radioactive materials) wastes in Texas  

SciTech Connect

Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios.

Nielson, K.K.; Rogers, V.C. (Rogers Associates Engineering Corporation, Salt Lake City, UT (USA)); Pollard, C.G. (Texas Low-Level Radioactive Waste Disposal Authority, Austin (USA))

1989-11-01T23:59:59.000Z

219

Waste Characterization Data Manual for the inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect

This Waste Characterization Data Manual contains the results of an analysis of the contents of liquid low-level waste (LLLW) tanks that have been removed from service in accordance with the requirements of the Oak Ridge National Laboratory (ORNL) Federal Facility Agreement (FFA), Section IX.G.1. Section IX.G.1 of the FFA requires waste characterizations be conducted and provided to EPA and TDEC for all LLLW tanks that are removed from service. These waste characterizations shall include the results of sampling and analysis of the tank contents, including wastes, liquids, and sludges. This manual was first issued as ORNL/ER-80 in June 1992. The waste characterization data were extracted from ORNL reports that described tank sampling and analysis conducted in 1988 for 32 out-of-service tanks. This revision of the manual contains waste characterization data for 54 tanks, including the 32 tanks from the 1988 sampling campaign (Sects. 2.1 through 2.32) and the 22 additional tanks from a subsequent sampling campaign in 1992 and 1993 (Sects. 2.33 through 2.54). Data are presented from analyses of volatile organic compounds, semivolatile organic compounds, polychlorinated biphenyls (PCBs), pesticides, radiochemical compounds, and inorganic compounds. As additional data resulting from analyses of out-of-service tank samples become available, they will be added to this manual.

Not Available

1993-06-01T23:59:59.000Z

220

Federal Offshore California Natural Gas Plant Liquids Production...  

Gasoline and Diesel Fuel Update (EIA)

Next Release Date: 10312014 Referring Pages: NGPL Production, Gaseous Equivalent at Processing Plants Federal Offshore California Natural Gas Gross Withdrawals and Production...

Note: This page contains sample records for the topic "liquid wastes natural" 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

California--State Offshore Natural Gas Plant Liquids Production...  

Gasoline and Diesel Fuel Update (EIA)

2014 Next Release Date: 10312014 Referring Pages: NGPL Production, Gaseous Equivalent at Processing Plants California State Offshore Natural Gas Gross Withdrawals and Production...

222

EMSL - liquids  

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

liquids en Iodine Solubility in Low-Activity Waste Borosilicate Glass at 1000 °C. http:www.emsl.pnl.govemslwebpublicationsiodine-solubility-low-activity-waste-borosilicate...

223

Liquid absorbent solutions for separating nitrogen from natural gas  

DOE Patents (OSTI)

Nitrogen-absorbing and -desorbing compositions, novel ligands and transition metal complexes, and methods of using the same, which are useful for the selective separation of nitrogen from other gases, especially natural gas.

Friesen, Dwayne T. (Bend, OR); Babcock, Walter C. (Bend, OR); Edlund, David J. (Redmond, OR); Lyon, David K. (Bend, OR); Miller, Warren K. (Bend, OR)

2000-01-01T23:59:59.000Z

224

EXPLORING ENGINEERING CONTROL THROUGH PROCESS MANIPULATION OF RADIOACTIVE LIQUID WASTE TANK CHEMICAL CLEANING  

SciTech Connect

One method of remediating legacy liquid radioactive waste produced during the cold war, is aggressive in-tank chemical cleaning. Chemical cleaning has successfully reduced the curie content of residual waste heels in large underground storage tanks; however this process generates significant chemical hazards. Mercury is often the bounding hazard due to its extensive use in the separations process that produced the waste. This paper explores how variations in controllable process factors, tank level and temperature, may be manipulated to reduce the hazard potential related to mercury vapor generation. When compared using a multivariate regression analysis, findings indicated that there was a significant relationship between both tank level (p value of 1.65x10{sup -23}) and temperature (p value of 6.39x10{sup -6}) to the mercury vapor concentration in the tank ventilation system. Tank temperature showed the most promise as a controllable parameter for future tank cleaning endeavors. Despite statistically significant relationships, there may not be confidence in the ability to control accident scenarios to below mercury’s IDLH or PAC-III levels for future cleaning initiatives.

Brown, A.

2014-04-27T23:59:59.000Z

225

Sampling and analysis of radioactive liquid wastes and sludges in the Melton Valley and evaporator facility storage tanks at ORNL  

SciTech Connect

The sampling and analysis of the radioactive liquid wastes and sludges in the Melton Valley Storage Tanks (MVSTs), as well as two of the evaporator service facility storage tanks at ORNL, are described. Aqueous samples of the supernatant liquid and composite samples of the sludges were analyzed for major constituents, radionuclides, total organic carbon, and metals listed as hazardous under the Resource Conservation and Recovery Act (RCRA). Liquid samples from five tanks and sludge samples from three tanks were analyzed for organic compounds on the Environmental Protection Agency (EPA) Target Compound List. Estimates were made of the inventory of liquid and sludge phases in the tanks. Descriptions of the sampling and analytical activities and tabulations of the results are included. The report provides data in support of the design of the proposed Waste Handling and Packaging Plant, the Liquid Low-Level Waste Solidification Project, and research and development activities (R D) activities in developing waste management alternatives. 7 refs., 8 figs., 16 tabs.

Sears, M.B.; Botts, J.L.; Ceo, R.N.; Ferrada, J.J.; Griest, W.H.; Keller, J.M.; Schenley, R.L.

1990-09-01T23:59:59.000Z

226

,"Montana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Montana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_smt_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_smt_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

227

,"Kansas Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Kansas Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sks_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sks_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

228

,"Alabama Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Alabama Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sal_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sal_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

229

,"California Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","California Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sca_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sca_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

230

,"Oklahoma Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Oklahoma Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sok_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sok_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

231

,"Ohio Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Ohio Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_soh_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_soh_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

232

,"Utah Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Utah Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sut_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sut_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

233

,"Alaska Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Alaska Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sak_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sak_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

234

,"Indiana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Plant Liquids Production, Gaseous Equivalent (MMcf)" Plant Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Indiana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sin_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sin_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

235

,"Louisiana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Louisiana Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sla_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sla_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

236

,"Nebraska Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Nebraska Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sne_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sne_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

237

,"Pennsylvania Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Pennsylvania Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_spa_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_spa_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

238

,"South Dakota Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Plant Liquids Production, Gaseous Equivalent (MMcf)" Plant Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","South Dakota Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_ssd_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_ssd_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

239

,"Wyoming Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Wyoming Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_swy_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_swy_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

240

,"Michigan Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Michigan Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_smi_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_smi_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

Note: This page contains sample records for the topic "liquid wastes natural" 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

,"Florida Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Florida Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2012 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sfl_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sfl_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

242

,"Mississippi Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Mississippi Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_sms_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_sms_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

243

,"Texas Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)"  

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

Liquids Production, Gaseous Equivalent (MMcf)" Liquids Production, Gaseous Equivalent (MMcf)" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Texas Natural Gas Plant Liquids Production, Gaseous Equivalent (MMcf)",1,"Annual",2011 ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","na1150_stx_2a.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/na1150_stx_2a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov"

244

Annual report of the origin of natural gas liquids production form EIA-64A  

SciTech Connect

The collection of basic, verifiable information on the Nation`s reserves and production of natural gas liquids (NGL) is mandated by the Federal Energy Administration Act of 1974 (FEAA) (Public Law 93-275) and the Department of Energy Organization Act of 1977 (Public Law 95-91). Gas shrinkage volumes reported on Form EIA-64A by natural gas processing plant operators are used with natural gas data collected on a {open_quotes}wet after lease separation{close_quotes} basis on Form EIA-23, Annual Survey of Domestic Oil and Gas Reserves, to estimate {open_quotes}dry{close_quotes} natural gas reserves and production volumes regionally and nationally. The shrinkage data are also used, along with the plant liquids production data reported on Form EIA-64A, and lease condensate data reported on Form EIA-23, to estimate regional and national gas liquids reserves and production volumes. This information is the only comprehensive source of credible natural gas liquids data, and is required by DOE to assist in the formulation of national energy policies.

NONE

1995-12-31T23:59:59.000Z

245

DOE/BNL Liquid Natural Gas Heavy Vehicle Program  

SciTech Connect

As a means of lowering greenhouse gas emissions, increasing economic growth, and reducing the dependency on imported oil, the Department of Energy and Brookhaven National Laboratory (DOE/ BNL) is promoting the substitution of liquefied natural gas (LNG) in heavy-vehicles that are currently being fueled by diesel. Heavy vehicles are defined as Class 7 and 8 trucks (> 118,000 pounds GVVV), and transit buses that have a fuel usage greater than 10,000 gallons per year and driving range of more than 300 miles. The key in making LNG market-competitive with all types of diesel fuels is in improving energy efficiency and reducing costs of LNG technologies through systems integration. This paper integrates together the three LNG technologies of: (1) production from landfills and remote well sites; (2) cryogenic fuel delivery systems; and (3) state-of-the-art storage tank and refueling facilities, with market end-use strategies. The program's goal is to develop these technologies and strategies under a ''green'' and ''clean'' strategy. This ''green'' approach reduces the net contribution of global warming gases by reducing levels of methane and carbon dioxide released by heavy vehicles usage to below recoverable amounts of natural gas from landfills and other natural resources. Clean technology refers to efficient use of energy with low environmental emissions. The objective of the program is to promote fuel competition by having LNG priced between $0.40 - $0.50 per gallon with a combined production, fuel delivery and engine systems efficiency approaching 45%. This can make LNG a viable alternative to diesel.

James E. Wegrzyn; Wai-Lin Litzke; Michael Gurevich

1998-08-11T23:59:59.000Z

246

Investigation of the organic matter in inactive nuclear tank liquids  

SciTech Connect

Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

Schenley, R.L.; Griest, W.H.

1990-08-01T23:59:59.000Z

247

Isolation of metals from liquid wastes: Reactive scavenging in turbulent thermal reactors. 1998 annual progress report  

SciTech Connect

'The objective of this project is to develop the fundamental science base necessary to assess the utility of high-temperature processes to volatilize metals in DOE metal-bearing liquid wastes, so that they can be reactively scavenged by sorbents. The problem is addressed through a collaborative research program involving a team of five senior scientists and their respective laboratories, at four institutions. Specific goals are to: (1) Understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals in the DOE liquid waste inventory (e.g., Cs and Sr), using a laminar-flow reactor for which extraction of kinetic data is not complicated by turbulence; (2) Develop models to predict both trajectories of individual droplets in turbulent high-temperature reactors, and rates of metal evolution from droplets, and compare model predictions with experimental data from a pilot-scale turbulent thermal reactor; (3) Connect the reaction kinetic models with the droplet trajectory/mass evolution models, in order to predict and optimize metal scavenging processes in turbulent-flow reactors, and to test these combined models against data taken from a turbulent high temperature reactor. This report summarizes work at a point midway through the first year of a 3-year project. At the University of Arizona (UA), two tasks are underway. The first task is concerned with attempting to understand high-temperature reaction kinetics between sorbent substrates and certain volatile and semi-volatile metals. The second task is concerned with applying Kerstein''s One Dimensional Turbulence model to prediction of droplet trajectories in turbulent flow.'

Wendt, J.O.L. [Univ. of Arizona, Tucson, AZ (US); Linak, W.P. [Environmental Protection Agency, Research Triangle Park, NC (US); Kerstein, A.R. [Sandia National Labs., Livermore, CA (US); Pearlstein, A.J.; Scheeline, A. [Univ. of Illinois, Urbana, IL (US)

1998-06-01T23:59:59.000Z

248

CERTIFICATION DOCKET FOR THE F0RhqE.R SITE OF THE RADIOACTIVE LIQUID WASTE TREATMENT PLANT (TA-45)  

Office of Legacy Management (LM)

CERTIFICATION DOCKET CERTIFICATION DOCKET FOR THE F0RhqE.R SITE OF THE RADIOACTIVE LIQUID WASTE TREATMENT PLANT (TA-45) AND THE EFFLUENT RECEIVING AREAS OF ACID, PUEBLO, AND LOS ALAMOS CANYOM, LOS ALAMOS, NEW MEXICO DEPARTMENT OF ENERGY Office of Nuclear Energy Office of Terminal Waste Disposal and Remedial Action Division of Remedial Action Projects -. CONTENTS A Page - Introduction to the Certification Docket for the Former Site of the Radioactive Liquid Waste Treatment Plant (TA-45) and the Effluent Receiving Areas of Acid, Pueblo, and Los Alamos Canyons, Los Alamos, New Mexico Description of the Formeriy Utilized Sites Program at the Former Site of the T.4-45 Treatment Plant and Acid, Pueblo, and Los Alamos Canyons Purpose Property Identification Docket Contents

249

222-S radioactive liquid waste line replacement and 219-S secondary containment upgrade, Hanford Site, Richland, Washington  

SciTech Connect

The U.S. Department of Energy (DOE) is proposing to: (1) replace the 222-S Laboratory (222-S) radioactive liquid waste drain lines to the 219-S Waste Handling Facility (219-S); (2) upgrade 219-S by replacing or upgrading the waste storage tanks and providing secondary containment and seismic restraints to the concrete cells which house the tanks; and (3) replace the transfer lines from 219-S to the 241-SY Tank Farm. This environmental assessment (EA) has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, the Council on Environmental Quality Regulations for Implementing the Procedural Provisions of NEPA (40 Code of Federal Regulations [CFR] 1500-1508), and the DOE Implementing Procedures for NEPA (10 CFR 1021). 222-S is used to perform analytical services on radioactive samples in support of the Tank Waste Remediation System and Hanford Site environmental restoration programs. Activities conducted at 222-S include decontamination of analytical processing and support equipment and disposal of nonarchived radioactive samples. These activities generate low-level liquid mixed waste. The liquid mixed waste is drained through pipelines in the 222-S service tunnels and underground concrete encasements, to two of three tanks in 219-S, where it is accumulated. 219-S is a treatment, storage, and/or disposal (TSD) unit, and is therefore required to meet Washington Administrative Code (WAC) 173-303, Dangerous Waste Regulations, and the associated requirements for secondary containment and leak detection. The service tunnels are periodically inspected by workers and decontaminated as necessary to maintain as low as reasonably achievable (ALARA) radiation levels. Although no contamination is reaching the environment from the service tunnels, the risk of worker exposure is present and could increase. 222-S is expected to remain in use for at least the next 30 years to serve the Hanford Site environmental cleanup mission.

NONE

1995-01-01T23:59:59.000Z

250

Cryogenic cooling system of HTS transformers by natural convection of subcooled liquid nitrogen  

E-Print Network (OSTI)

Cryogenic cooling system of HTS transformers by natural convection of subcooled liquid nitrogen Ho-793, South Korea Abstract Heat transfer analysis on a newly proposed cryogenic cooling system is performed, and over-load operation. One of the key techniques to realize these advantages in practice is the cryogenic

Chang, Ho-Myung

251

NATURAL RADIONUCLIDES MEASUREMENTS IN DRINKING WATER BY LIQUID SCINTILLATION COUNTING. METHODS AND RESULTS  

E-Print Network (OSTI)

to dose evaluation, namely gross alpha and beta activity, uranium and radium isotopes content. For tritium activity and uranium isotope concentration have been measured. A Quantulus-Wallac scintillation counter hasNATURAL RADIONUCLIDES MEASUREMENTS IN DRINKING WATER BY LIQUID SCINTILLATION COUNTING. METHODS

252

U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Proved Reserves  

Annual Energy Outlook 2012 (EIA)

Crude Oil and Natural Gas Proved Reserves With Data for 2013 | Release Date: December 4, 2014 | Revision: December 19, 2014 Next Release Date: December 2015 | full report Previous...

253

U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Proved Reserves, 2011  

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

Crude Oil and Natural Gas Crude Oil and Natural Gas Proved Reserves, 2011 August 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | U.S. Crude Oil and Natural Gas Proved Reserves, 2011 i 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. August 2013 U.S. Energy Information Administration | U.S. Crude Oil and Natural Gas Proved Reserves, 2011 ii

254

SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING  

SciTech Connect

This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

2011-01-12T23:59:59.000Z

255

New Standards in Liquid Waste Treatment at Fukushima Dai-ichi - 13134  

SciTech Connect

The earthquake and tsunami on March 11, 2011 severely damaged the Fukushima Dai-ichi nuclear plant leading to the most severe nuclear incident since Chernobyl. Ongoing operations to cool the damaged reactors at the site have led to the generation of highly radioactive coolant water. This is currently mainly treated to remove Cs-137 and Cs-134 and passed through a reverse osmosis (RO) unit to reduce the salinity before being cycled back to the reactors. Because only the Cs isotopes are removed, the RO reject water still contains many radioactive isotopes and this has led to the accumulation of over 200,000 cubic meters (52 million gallons) of extremely contaminated water which is currently stored on site in tanks. EnergySolutions, in partnership with Toshiba, were contracted to develop a system to reduce 62 isotopes in this waste down to allowable levels. This was a significant technical challenge given the high background salt content of the wastewater, the variation in aqueous chemistry of the radioactive isotopes and the presence of non-active competing ions (e.g. Ca and Mg) which inhibit the removal of isotopes such as Sr-89 and Sr-90. Extensive testing was performed to design a suitable system that could meet the required decontamination goals. These tests were performed over a 6 month period at facilities available in the nearby Fukushima Dai-ni laboratory using actual waste samples. This data was then utilized to design a Multi Radioactive Nuclides Removal System (MRRS) for Fukushima which is a modified version of EnergySolutions' proprietary Advanced Liquid Processing System (ALPS)'. The stored tank waste is fed into a preliminary precipitation system where iron flocculation is performed to remove a number of isotopes, including Sb-125, Ru-106, Mn-54 and Co-60. The supernatant is then fed into a second precipitation tank where the pH is adjusted and the bulk of the Mg, Ca and Sr precipitated out as carbonates and hydroxides. After passing through a cross-flow ultrafiltration membrane, the permeate then goes through a total of 14 fixed ion exchange and adsorbent columns followed by a disposable polishing column to polish the residual isotopes down to allowable levels. At the end of the system, the effluent is filtered for a final time to removal any particulates that may have been picked up from the media columns and then stored prior to analysis. (authors)

Sylvester, Paul; Milner, Tim; Ruffing, Jennifer; Poole, Scott [EnergySolutions, 100 Center Point Circle, Suite 100, Center Point II, Columbia, SC 29210 (United States)] [EnergySolutions, 100 Center Point Circle, Suite 100, Center Point II, Columbia, SC 29210 (United States); Townson, Paul; Jensen, Jesse [EnergySolutions, 2345 Stevens Drive, Suite 240, Richland, WA 99354 (United States)] [EnergySolutions, 2345 Stevens Drive, Suite 240, Richland, WA 99354 (United States)

2013-07-01T23:59:59.000Z

256

U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Proved Reserves  

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

U.S. Crude Oil and Natural Gas Proved Reserves U.S. Crude Oil and Natural Gas Proved Reserves With Data for 2011 | Release Date: August 1, 2013 | Next Release Date: Early 2014 | full report Previous Issues: Year: 2010 2009 2008 2007 2006 2005 2004 2003 2002 2001 2000 1999 1998 1997 1996 Go Summary In 2011, oil and gas exploration and production companies operating in the United States added almost 3.8 billion barrels of crude oil and lease condensate proved reserves, an increase of 15 percent, and the greatest volume increase since the U.S. Energy Information Administration (EIA) began publishing proved reserves estimates in 1977 (Table 1). Proved reserves of crude oil and lease condensate increased by 2.9 billion barrels in 2010, the previous record. Proved reserves of U.S. wet natural gas1 rose

257

Microsoft Word - FINAL 7-12-10 Site Visit Report - LANL Radioactive Liquid Waste Facility FCA.docx  

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

Site Visit Report Facility Centered Assessment of the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility - June 2010 This site visit report documents the results of the Office of Health, Safety and Security's (HSS) review of the Facility Centered Assessment (FCA) of the Los Alamos National Laboratory (LANL) Radioactive Liquid Waste Treatment Facility (RLW). This review, conducted June 9-25, 2010, was sponsored by the U.S. Department of Energy (DOE) Los Alamos Site Office (LASO) and LANL, and conducted jointly by HSS, LASO, and LANL staff. The Office of Environment, Safety and Health Evaluations was the overall lead organization for evaluation of the FCA process with the participation of the LASO Facility Representative assigned to RLW.

258

Precipitation of cesium jointly with uranium from nitric acid liquid radioactive wastes to obtain solid matrices for long-term storage  

Science Journals Connector (OSTI)

The possibility of converting liquid radioactive wastes containing Cs into chemically and thermodynamically stable...4U5O17...can be prepared by different procedures. The resulting compounds are characterized by ...

Yu. I. Korneiko; A. A. Murzin; O. V. Shmidt

2009-08-01T23:59:59.000Z

259

Third-Order Gas-Liquid Phase Transition and the Nature of Andrews Critical Point  

E-Print Network (OSTI)

The main objective of this article is to study the nature of the Andrews critical point in the gas-liquid transition in a physical-vapor transport (PVT) system. A dynamical model, consistent with the van der Waals equation near the Andrews critical point, is derived. With this model, we deduce two physical parameters, which interact exactly at the Andrews critical point, and which dictate the dynamic transition behavior near the Andrews critical point. In particular, it is shown that 1) the Andrews critical point is a switching point where the phase transition changes from the first order to the third order, 2) the gas-liquid co-existence curve can be extended beyond the Andrews critical point, and 3) the liquid-gas phase transition going beyond Andrews point is of the third order. This clearly explains why it is hard to observe the gas-liquid phase transition beyond the Andrews critical point. Furthermore, the analysis leads naturally the introduction of a general asymmetry principle of fluctuations and the preferred transition mechanism for a thermodynamic system.

Tian Ma; Shouhong Wang

2010-07-13T23:59:59.000Z

260

,"U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)"  

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

Monthly","8/2013" Monthly","8/2013" ,"Release Date:","10/31/2013" ,"Next Release Date:","11/29/2013" ,"Excel File Name:","ngm_epg0_plc_nus_dmmbtum.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/ngm_epg0_plc_nus_dmmbtum.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov" ,,"(202) 586-8800",,,"12/18/2013 12:22:47 PM" "Back to Contents","Data 1: U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)" "Sourcekey","NGM_EPG0_PLC_NUS_DMMBTU" "Date","U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)"

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


261

,"U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)"  

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

Annual",2012 Annual",2012 ,"Release Date:","10/31/2013" ,"Next Release Date:","11/29/2013" ,"Excel File Name:","ngm_epg0_plc_nus_dmmbtua.xls" ,"Available from Web Page:","http://tonto.eia.gov/dnav/ng/hist/ngm_epg0_plc_nus_dmmbtua.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.doe.gov" ,,"(202) 586-8800",,,"12/18/2013 12:22:46 PM" "Back to Contents","Data 1: U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)" "Sourcekey","NGM_EPG0_PLC_NUS_DMMBTU" "Date","U.S. Natural Gas Liquid Composite Price (Dollars per Million Btu)"

262

Rhizopus oligosporus grown on natural rubber waste serum for production of single cell protein: a preliminary study  

Science Journals Connector (OSTI)

Maximum production of mycelium and utilization of total organic...R. oligosporus grown on natural rubber waste serum was achieved at 28°C ... initial pH of 4.0. The maximum production of total crude protein, howe...

M. S. Mahat; I. C. MacRae

1992-01-01T23:59:59.000Z

263

Evaluation of DMDOHEMA based supported liquid membrane system for high level waste remediation under simulated conditions  

Science Journals Connector (OSTI)

Abstract N,N?-dimethyl-N,N?-dioctyl-2,(2?-hexyloxyethyl) malonamide (DMDOHEMA) has been proposed as solvent for the partitioning of radiotoxic minor actinides from high-level waste (HLW) solutions. The facilitated transport of 241Am(III), 239Pu(IV), 233U(VI), 237Np(V) across supported liquid membrane (SLM) impregnated with DMDOHEMA solution in n-dodecane was investigated under varying conditions of feed acidity, receiver phase composition, carrier concentration, and membrane thickness. Micro porous PTFE membrane was used as the polymeric support. There was a decrease in the transport of metal ions under the pressurized heavy water reactor simulated HLW (PHWR-SHLW) conditions. The physical stability of the SLM impregnated with the carrier was investigated for ~60 days by performing Am(III) permeation studies. Marginal variation in the transport behavior suggested reasonably good stability of the impregnated carrier in the membrane pores. A simple mathematical model has been developed to simulate experimental data and to explain quantitatively the role of different parameters.

Ajay B. Patil; Pankaj Kandwal; V.S. Shinde; P.N. Pathak; P.K. Mohapatra

2013-01-01T23:59:59.000Z

264

EIS-0081: Long-Term Management of Liquid High-Level Radioactive Waste Stored at Western New York Nuclear Service Center, West Valley, New York  

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

The U.S. Department of Energy Office of Terminal Waste Disposal and Remedial Action prepared this statement to analyze the environmental and socioeconomic impacts resulting from the Department’s proposed action to construct and operate facilities necessary to solidify the liquid high level wastes currently stored in underground tanks at Wes t Valley, New York.

265

1M. Panahi, S. Skogestad ' Controlled Variables Selection for a Natural Gas to Liquids (GTL) process' Controlled Variables Selection for a  

E-Print Network (OSTI)

1M. Panahi, S. Skogestad ' Controlled Variables Selection for a Natural Gas to Liquids (GTL) process' Controlled Variables Selection for a Natural Gas to Liquids (GTL) process Mehdi Panahi Sigurd for a Natural Gas to Liquids (GTL) process' Skogestad plantwide control procedure* I Top Down · Step 1: Identify

Skogestad, Sigurd

266

Unloading using auger tool and foam and experimental identification of liquid loading of low rate natural gas wells  

E-Print Network (OSTI)

Low-pressure, low-producing natural gas wells commonly encounter liquid loading during production. Because of the decline in the reservoir pressure and the flow capacity, wells can fall below terminal velocity. Identifying and predicting the onset...

Bose, Rana

2007-09-17T23:59:59.000Z

267

Investigation of the organic matter in inactive nuclear tank liquids. Environmental Restoration Program  

SciTech Connect

Environmental Protection Agency (EPA) methodology for regulatory organics fails to account for the organic matter that is suggested by total organic carbon (TOC) analysis in the Oak Ridge National Laboratory (ORNL) inactive nuclear waste-tank liquids and sludges. Identification and measurement of the total organics are needed to select appropriate waste treatment technologies. An initial investigation was made of the nature of the organics in several waste-tank liquids. This report details the analysis of ORNL wastes.

Schenley, R.L.; Griest, W.H.

1990-08-01T23:59:59.000Z

268

Mixed refrigerants proven efficient in natural-gas-liquids recovery process  

SciTech Connect

Lower processing temperatures for higher recoveries of natural gas liquids (NGL) leads to increasingly complex and expensive refrigeration techniques. This paper describes the mixed component refrigeration technique and that it has been proven as a viable alternative to the turboexpander plant. Mixed component refrigeration systems have been primarily used in applications such as LNG terminals and peak-shaving plants, where overall compression horse-power requirements are of primary concern due to operating cost. Recently, development of high pressure, brazed aluminum plate/fin exchangers and increasing compression costs have made economic potential of the mixed refrigerant alternative apparent. If the residue gas must be compressed to the same pressure as the plant inlet using the turbo-expander design, the mixed refrigerant system will require approximately 15% less horsepower for the same liquids production.

Mac Kenzie, D.H.

1985-03-04T23:59:59.000Z

269

Distinguishing Between Site Waste, Natural, and Other Sources of Contamination at Uranium and Thorium Contaminated Sites - 12274  

SciTech Connect

Uranium and thorium processing and milling sites generate wastes (source, byproduct, or technically enhanced naturally occurring material), that contain contaminants that are similar to naturally occurring radioactive material deposits and other industry wastes. This can lead to mis-identification of other materials as Site wastes. A review of methods used by the US Army Corps of Engineers and the Environmental Protection Agency to distinguish Site wastes from potential other sources, enhanced materials, and natural deposits, at three different thorium mills was conducted. Real case examples demonstrate the importance of understanding the methods of distinguishing wastes. Distinguishing between Site wastes and enhanced Background material can be facilitated by establishing and applying a formal process. Significant project cost avoidance may be realized by distinguishing Site wastes from enhanced NORM. Collection of information on other potential sources of radioactive material and physical information related to the potential for other radioactive material sources should be gathered and reported in the Historical Site Assessment. At a minimum, locations of other such information should be recorded. Site decision makers should approach each Site area with the expectation that non site related radioactive material may be present and have a process in place to distinguish from Site and non Site related materials. (authors)

Hays, David C. [United States Army Corps of Engineers, Kansas City, Missouri, 64106 (United States)

2012-07-01T23:59:59.000Z

270

THE ROLE OF LIQUID WASTE PRETREATMENT TECHNOLOGIES IN SOLVING THE DOE CLEAN-UP MISSION  

SciTech Connect

The objective of this report is to describe the pretreatment solutions that allow treatment to be tailored to specific wastes, processing ahead of the completion schedules for the main treatment facilities, and reduction of technical risks associated with future processing schedules. Wastes stored at Hanford and Savannah River offer challenging scientific and engineering tasks. At both sites, space limitations confound the ability to effectively retrieve and treat the wastes. Additionally, the radiation dose to the worker operating and maintaining the radiochemical plants has a large role in establishing the desired radioactivity removal. However, the regulatory requirements to treat supernatant and saltcake tank wastes differ at the two sites. Hanford must treat and remove radioactivity from the tanks based on the TriParty Agreement and Waste Incidental to Reprocessing (WIR) documentation. These authorizing documents do not specify treatment technologies; rather, they specify endstate conditions. Dissimilarly, Waste Determinations prepared at SRS in accordance with Section 3116 of the 2005 National Defense Authorization Act along with state operating permits establish the methodology and amounts of radioactivity that must be removed and may be disposed of in South Carolina. After removal of entrained solids and site-specific radionuclides, supernatant and saltcake wastes are considered to be low activity waste (LAW) and are immobilized in glass and disposed of at the Hanford Site Integrated Disposal Facility (IDF) or formulated into a grout for disposal at the Savannah River Site Saltstone Disposal Facility. Wastes stored at the Hanford Site or SRS comprise saltcake, supernate, and sludges. The supernatant and saltcake waste fractions contain primarily sodium salts, metals (e.g., Al, Cr), cesium-137 (Cs-137), technetium-99 (Tc-99) and entrained solids containing radionuclides such as strontium-90 (Sr-90) and transuranic elements. The sludges contain many of the transition metal hydroxides that precipitate when the spent acidic process solutions are rendered alkaline with sodium hydroxide. The sludges contain Sr-90 and transuranic elements. The wastes stored at each site have been generated and stored for over fifty years. Although the majority of the wastes were generated to support nuclear weapons production and reprocessing, the wastes differ substantially between the sites. Table 5 shows the volumes and total radioactivity (including decay daughters) of the waste phases stored in tanks at each site. At Hanford, there are 177 tanks that contain 56.5 Mgal of waste. SRS has 51 larger tanks, of which 2 are closed, that contain 36.5 Mgal. Mainly due to recovery operations, the waste stored at Hanford has less total curies than that stored at Savannah River. The total radioactivity of the Hanford wastes contains approximately 190 MCi, and the total radioactivity of the Savannah River wastes contains 400 MCi.

Wilmarth, B; Sheryl Bush, S

2008-10-31T23:59:59.000Z

271

Natural Convection Heat Transfer in a Rectangular Liquid Metal Pool With Bottom Heating and Top Cooling  

SciTech Connect

An experimental study is performed to investigate the natural convection heat transfer characteristics with subcooled coolant to create engineering database for basic applications in a lead alloy cooled reactor. Tests are performed in the ALTOS (Applied Liquid-metal Thermal Operation Study) apparatus as part of MITHOS (Metal Integrated Thermo Hydrodynamic Operation System). A relationship is determined between the Nusselt number Nu and the Rayleigh number Ra in the liquid metal rectangular pool. Results are compared with correlations and experimental data in the literature. Given the similar Ra condition, the present test results for Nu of the liquid metal pool with top subcooling are found to be similar to those predicted by the existing correlations or experiments. The current test results are utilized to develop natural convection heat transfer correlations applicable to low Prandtl number Pr fluids that are heated from below and cooled by the external coolant above. Results from this study are slated to be used in designing BORIS (Battery Optimized Reactor Integral System), a small lead cooled modular fast reactor for deployment at remote sites cycled with MOBIS (Modular Optimized Brayton Integral System) for electricity generation, tied with NAVIS (Naval Application Vessel Integral System) for ship propulsion, joined with THAIS (Thermochemical Hydrogen Acquisition Integral System) for hydrogen production, and coupled with DORIS (Desalination Optimized Reactor Integral System) for seawater desalination. Tests are performed with Wood's metal (Pb-Bi-Sn-Cd) filling a rectangular pool whose lower surface is heated and upper surface cooled by forced convection of water. The test section is 20 cm long, 11.3 cm high and 15 cm wide. The simulant has a melting temperature of 78 deg. C. The constant temperature and heat flux condition was realized for the bottom heating once the steady state had been met. The test parameters include the heated bottom surface temperature of the liquid metal pool, the input power to the bottom surface of the section, and the coolant temperature. (authors)

Lee, Il S.; Yu, Yong H.; Son, Hyoung M.; Hwang, Jin S.; Suh, Kune Y. [Seoul National University, 599 Gwanangno, Gwanak-gu, Seoul, 151-742 (Korea, Republic of)

2006-07-01T23:59:59.000Z

272

Use of waste gypsum to replace natural gypsum as set retarders in portland cement  

SciTech Connect

The present study is focused on clarifying the influence of waste gypsum (WG) in replacing natural gypsum (NG) in the production of ordinary Portland cement (OPC). WG taken from slip casting moulds in a ceramic factory was formed from the hydration of plaster of paris. Clinker and 3-5 wt% of WG was ground in a laboratory ball mill to produce cement waste gypsum (CMWG). The same procedure was repeated with NG to substitute WG to prepare cement natural gypsum (CMNG). The properties of NG and WG were investigated via X-ray Diffraction (XRD), X-ray fluorescence (XRF) and differential scanning calorimetry (DSC)/thermogravimetric (TG) to evaluate the properties of CMNG and CMWG. The mechanical properties of cement were tested in terms of setting time, flexural and compressive strength. The XRD result of NG revealed the presence of dihydrate while WG contained dihydrate and hemihydrate. The content of dihydrate and hemihydrates were obtained via DSC/TG, and the results showed that WG and NG contained 12.45% and 1.61% of hemihydrate, respectively. Furthermore, CMWG was found to set faster than CMNG, an average of 15.29% and 13.67% faster for the initial and final setting times, respectively. This was due to the presence of hemihydrate in WG. However, the values obtained for flexural and compressive strength were relatively the same for CMNG and CMWG. Therefore, this result provides evidence that WG can be used as an alternative material to NG in the production of OPC.

Chandara, Chea; Azizli, Khairun Azizi Mohd [School of Materials and Mineral Resources Engineering, Universiti Sains Malaysia, 14300 Nibong Tebal, Penang (Malaysia); Ahmad, Zainal Arifin [School of Materials and Mineral Resources Engineering, Universiti Sains Malaysia, 14300 Nibong Tebal, Penang (Malaysia)], E-mail: zainal@eng.usm.my; Sakai, Etsuo [Tokyo Institute of Technology, Graduate School of Science and Engineering, Department of Metallurgy and Ceramic Science, 2-12-1 Meguro-ku, Ookayama, Meguro-ku, Tokyo 152-8552 (Japan)

2009-05-15T23:59:59.000Z

273

Cylinder wall waste heat recovery from liquid-cooled internal combustion engines utilizing thermoelectric generators.  

E-Print Network (OSTI)

?? This report is a dissertation proposal that focuses on the energy balance within an internal combustion engine with a unique coolant-based waste heat recovery… (more)

Armstead, John Randall

2012-01-01T23:59:59.000Z

274

U.S. Natural Gas Liquids Lease Condensate, Proved Reserves (Million  

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

Liquids Lease Condensate, Proved Reserves (Million Barrels) Liquids Lease Condensate, Proved Reserves (Million Barrels) U.S. Natural Gas Liquids Lease Condensate, Proved Reserves (Million Barrels) Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6 Year-7 Year-8 Year-9 1970's 1,411 1980's 1,530 1,580 1,601 1,613 1,522 1,453 1,436 1,402 1,389 1,389 1990's 1,302 1,244 1,226 1,192 1,147 1,197 1,307 1,341 1,336 1,403 2000's 1,472 1,398 1,346 1,215 1,221 1,262 1,339 1,495 1,433 1,633 2010's 1,914 2,406 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 8/1/2013 Next Release Date: 8/1/2014 Referring Pages: Lease Condensate Proved Reserves as of Dec. 31 U.S. Lease Condensate Proved Reserves, Reserve Changes, and

275

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. (Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering); Spence, R.D. (Oak Ridge National Lab., TN (United States))

1993-01-01T23:59:59.000Z

276

Engineering assessment of low-level liquid waste disposal caisson locations at the 618-11 Burial Grounds  

SciTech Connect

Rockwell Hanford Operations is currently involved in an extensive effort to perform interim ground surface stabilization activities at retired low-level waste burial grounds located at the Hanford Site, Richland, Washington. The principal objective of these activities is to promote increased occupational and radiological safety at burial grounds. Interim stabilization activities include: (1) load testing (traversing burial ground surfaces with heavy equipment to promote incipient collapse of void spaces within the disposal structure and overburden), (2) barrier placement (placement of a {ge} 0.6 m soil barrier over existing overburden), and (3) revegetation (establishment of shallow rooted vegetation on the barrier to mitigate deep rooted plant growth and to reduce erosion). Low-level waste disposal caissons were used in 300 Area Burial Grounds as internment structures for containerized liquid wastes. These caissons, by virtue of their contents, design and methods of closure, require long-term performance evaluation. As an initial activity to evaluate long-term performance, the accurate location of these structures is required. This topical report summarizes engineering activities used to locate caissons in the subsurface environment at the Burial Ground. Activities were conducted to locate caissons during surface stabilization activities. The surface locations were marked, photographed, and recorded on an as built engineering drawing. The recorded location of these caissons will augment long-term observations of confinement structure and engineered surface barrier performance. In addition, accurate caisson location will minimize occupational risk during monitoring and observation activities periodically conducted at the burial ground.

Phillips, S.J.; Fischer, D.D.; Crawford, R.C. [Westinghouse Hanford Co., Richland, WA (United States); Rising, J.L. [Pacific Northwest Lab., Richland, WA (United States)

1982-06-01T23:59:59.000Z

277

Experimental data and analysis to support the design of an ion-exchange process for the treatment of Hanford tank waste supernatant liquids  

SciTech Connect

Hanford`s 177 underground storage tanks contain a mixture of sludge, salt cake, and alkaline supernatant liquids. Disposal options for these wastes are high-level waste (HLW) glass for disposal in a repository or low-level waste (LLW) glass for onsite disposal. Systems-engineering studies show that economic and environmental considerations preclude disposal of these wastes without further treatment. Difficulties inherent in transportation and disposal of relatively large volumes of HLW make it impossible to vitrify all of the tank waste as HLW. Potential environmental impacts make direct disposal of all of the tank waste as LLW glass unacceptable. Although the pretreatment and disposal requirements are still being defined, most pretreatment scenarios include retrieval of the aqueous liquids, dissolution of the salt cakes, and washing of the sludges to remove soluble components. Most of the cesium is expected to be in the aqueous liquids, which are the focus of this report on cesium removal by ion exchange. The main objectives of the ion-exchange process are removing cesium from the bulk of the tank waste (i.e., decontamination) and concentrating the separated cesium for vitrification. Because exact requirements for removal of {sup 137}Cs have not yet been defined, a range of removal requirements will be considered. This study addresses requirements to achieve {sup 137}Cs levels in LLW glass between (1) the Nuclear Regulatory Commission (NRC) Class C (10 CFR 61) limit of 4600 Ci/m{sup 3} and (2) 1/10th of the NRC Class A limit of 1 Ci/m{sup 3} i.e., 0.1/m{sup 3}. The required degrees of separation of cesium from other waste components is a complex function involving interactions between the design of the vitrification process, waste form considerations, and other HLW stream components that are to be vitrified.

Kurath, D.E.; Bray, L.A.; Brooks, K.P.; Brown, G.N.; Bryan, S.A.; Carlson, C.D.; Carson, K.J.; DesChane, J.R.; Elovich, R.J.; Kim, A.Y.

1994-12-01T23:59:59.000Z

278

State-of-the-art of liquid waste disposal for geothermal energy systems: 1979. Report PNL-2404  

SciTech Connect

The state-of-the-art of geothermal liquid waste disposal is reviewed and surface and subsurface disposal methods are evaluated with respect to technical, economic, legal, and environmental factors. Three disposal techniques are currently in use at numerous geothermal sites around the world: direct discharge into surface waters; deep-well injection; and ponding for evaporation. The review shows that effluents are directly discharged into surface waters at Wairakei, New Zealand; Larderello, Italy; and Ahuachapan, El Salvador. Ponding for evaporation is employed at Cerro Prieto, Mexico. Deep-well injection is being practiced at Larderello; Ahuachapan; Otake and Hatchobaru, Japan; and at The Geysers in California. All sites except Ahuachapan (which is injecting only 30% of total plant flow) have reported difficulties with their systems. Disposal techniques used in related industries are also reviewed. The oil industry's efforts at disposal of large quantities of liquid effluents have been quite successful as long as the effluents have been treated prior to injection. This study has determined that seven liquid disposal methods - four surface and three subsurface - are viable options for use in the geothermal energy industry. However, additional research and development is needed to reduce the uncertainties and to minimize the adverse environmental impacts of disposal. (MHR)

Defferding, L.J.

1980-06-01T23:59:59.000Z

279

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network (OSTI)

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

280

Low-level liquid radioactive waste treatment at Murmansk, Russia: Technical design and review of facility upgrade and expansion  

SciTech Connect

The governments of Norway and the US have committed their mutual cooperation and support the Murmansk Shipping Company (MSCo) to expand and upgrade the Low-Level Liquid Radioactive Waste (LLRW) treatment system located at the facilities of the Russian company RTP Atomflot, in Murmansk, Russia. RTP Atomflot provides support services to the Russian icebreaker fleet operated by the MSCo. The objective is to enable Russia to permanently cease disposing of this waste in Arctic waters. The proposed modifications will increase the facility`s capacity from 1,200 m{sup 3} per year to 5,000 m{sup 3} per year, will permit the facility to process high-salt wastes from the Russian Navy`s Northern fleet, and will improve the stabilization and interim storage of the processed wastes. The three countries set up a cooperative review of the evolving design information, conducted by a joint US and Norwegian technical team from April through December, 1995. To ensure that US and Norwegian funds produce a final facility which will meet the objectives, this report documents the design as described by Atomflot and the Russian business organization, ASPECT, both in design documents and orally. During the detailed review process, many questions were generated, and many design details developed which are outlined here. The design is based on the adsorption of radionuclides on selected inorganic resins, and desalination and concentration using electromembranes. The US/Norwegian technical team reviewed the available information and recommended that the construction commence; they also recommended that a monitoring program for facility performance be instituted.

Dyer, R.S.; Diamante, J.M. [Environmental Protection Agency, Washington, DC (United States). Office of International Activities; Duffey, R.B. [Brookhaven National Lab., Upton, NY (United States)] [and others

1996-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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

Forecast of U. S. Refinery Demand for NGL's (natural gas liquids) in 1978-1985  

SciTech Connect

A forecast of U.S. Refinery Demand for NGL's (Natural Gas Liquids) in 1978-1985 is based on a predicted 1.4%/yr decline in motor gasoline consumption from 7.4 to 6.7 million bbl/day (Mbd), including a 2.6%/yr reduction from 5.3 to 4.4 Mbd for automobiles and a 1.3%/yr growth from 2.1 to 2.3 Mbd for trucks, because of slow growth rates in the U.S. automobile fleet (1.1%/yr) and average annual miles driven (0.9%/yr), a 3.9%/yr growth in average mileage from 14.2 to 18.6 mpg, and diesel penetration to the automobile market which should increase from 0.3 to 3.3%. Leaded gasoline's share is expected to decline from 68% of the market (5.1 Mbd, including 0.8 Mbd leaded premium) to 24% (1.7 Mbd, leaded regular only), including a drop from 56 to 6% for automobiles and from approx. 100 to 60% for trucks. This will require increased production of clean-octane reformates and alkylates and reduce the need for straight-run gasolines, but because of the decline in the total gasoline demand, these changes should be minimal. Butane demand from outside-refinery production should decrease by 5-6%/yr, and natural gasoline will be consumed according to available production as an isopentane source.

Laskosky, J.

1980-01-01T23:59:59.000Z

282

Savannah River Site’s Liquid Waste Operations Adds Multi-Functional Laboratory  

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

AIKEN, S.C. – A new multi-functional laboratory supporting high-level waste processing at the Savannah River Site (SRS) gives workers a new and improved place to provide back-up laboratory support and more space for chemical storage.

283

A Comparative Review of Hydrologic Issues Involved in Geologic Storage of CO2 and Injection Disposal of Liquid Waste  

SciTech Connect

The paper presents a comparison of hydrologic issues and technical approaches used in deep-well injection and disposal of liquid wastes, and those issues and approaches associated with injection and storage of CO{sub 2} in deep brine formations. These comparisons have been discussed in nine areas: (1) Injection well integrity; (2) Abandoned well problems; (3) Buoyancy effects; (4) Multiphase flow effects; (5) Heterogeneity and flow channeling; (6) Multilayer isolation effects; (7) Caprock effectiveness and hydrogeomechanics; (8) Site characterization and monitoring; and (9) Effects of CO{sub 2} storage on groundwater resources There are considerable similarities, as well as significant differences. Scientifically and technically, these two fields can learn much from each other. The discussions presented in this paper should help to focus on the key scientific issues facing deep injection of fluids. A substantial but by no means exhaustive reference list has been provided for further studies into the subject.

Tsang, C.-F.; Birkholzer, J.; Rutqvist, J.

2008-04-15T23:59:59.000Z

284

Application of curium measurements for safeguarding at reprocessing plants. Study 1: High-level liquid waste and Study 2: Spent fuel assemblies and leached hulls  

SciTech Connect

In large-scale reprocessing plants for spent fuel assemblies, the quantity of plutonium in the waste streams each year is large enough to be important for nuclear safeguards. The wastes are drums of leached hulls and cylinders of vitrified high-level liquid waste. The plutonium amounts in these wastes cannot be measured directly by a nondestructive assay (NDA) technique because the gamma rays emitted by plutonium are obscured by gamma rays from fission products, and the neutrons from spontaneous fissions are obscured by those from curium. The most practical NDA signal from the waste is the neutron emission from curium. A diversion of waste for its plutonium would also take a detectable amount of curium, so if the amount of curium in a waste stream is reduced, it can be inferred that there is also a reduced amount of plutonium. This report studies the feasibility of tracking the curium through a reprocessing plant with neutron measurements at key locations: spent fuel assemblies prior to shearing, the accountability tank after dissolution, drums of leached hulls after dissolution, and canisters of vitrified high-level waste after separation. Existing pertinent measurement techniques are reviewed, improvements are suggested, and new measurements are proposed. The authors integrate these curium measurements into a safeguards system.

Rinard, P.M.; Menlove, H.O.

1996-03-01T23:59:59.000Z

285

Treatment Options for Liquid Radioactive Waste. Factors Important for Selecting of Treatment Methods  

SciTech Connect

The cleanup of liquid streams contaminated with radionuclides is obtained by the selection or a combination of a number of physical and chemical separations, processes or unit operations. Among those are: Chemical treatment; Evaporation; Ion exchange and sorption; Physical separation; Electrodialysis; Osmosis; Electrocoagulation/electroflotation; Biotechnological processes; and Solvent extraction.

Dziewinski, J.J.

1998-09-28T23:59:59.000Z

286

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))...

287

Natural Circulation and Linear Stability Analysis for Liquid-Metal Reactors with the Effect of Fluid Axial Conduction  

SciTech Connect

The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through nondimensional analysis, steady-state assessment, and linear perturbation evaluation. The Nyquist criterion and a root-search method were employed to find the linear stability boundary of both forward and backward circulations. The study provided a relatively complete analysis method for one-dimensional natural circulation problems with the consideration of fluid axial heat conduction. The results suggest that fluid axial heat conduction in a natural circulation loop should be considered only when the modified Peclet number is {approx}1 or less, which is significantly smaller than the practical value of a lead liquid metal-cooled reactor.

Piyush Sabharwall; Qiao Wu; James J. Sienicki

2012-06-01T23:59:59.000Z

288

Development And Initial Testing Of Off-Gas Recycle Liquid From The WTP Low Activity Waste Vitrification Process - 14333  

SciTech Connect

The Waste Treatment and Immobilization Plant (WTP) process flow was designed to pre-treat feed from the Hanford tank farms, separate it into a High Level Waste (HLW) and Low Activity Waste (LAW) fraction and vitrify each fraction in separate facilities. Vitrification of the waste generates an aqueous condensate stream from the off-gas processes. This stream originates from two off-gas treatment unit operations, the Submerged Bed Scrubber (SBS) and the Wet Electrospray Precipitator (WESP). Currently, the baseline plan for disposition of the stream from the LAW melter is to recycle it to the Pretreatment facility where it gets evaporated and processed into the LAW melter again. If the Pretreatment facility is not available, the baseline disposition pathway is not viable. Additionally, some components in the stream are volatile at melter temperatures, thereby accumulating to high concentrations in the scrubbed stream. It would be highly beneficial to divert this stream to an alternate disposition path to alleviate the close-coupled operation of the LAW vitrification and Pretreatment facilities, and to improve long-term throughput and efficiency of the WTP system. In order to determine an alternate disposition path for the LAW SBS/WESP Recycle stream, a range of options are being studied. A simulant of the LAW Off-Gas Condensate was developed, based on the projected composition of this stream, and comparison with pilot-scale testing. The primary radionuclide that vaporizes and accumulates in the stream is Tc-99, but small amounts of several other radionuclides are also projected to be present in this stream. The processes being investigated for managing this stream includes evaporation and radionuclide removal via precipitation and adsorption. During evaporation, it is of interest to investigate the formation of insoluble solids to avoid scaling and plugging of equipment. Key parameters for radionuclide removal include identifying effective precipitation or ion adsorption chemicals, solid-liquid separation methods, and achievable decontamination factors. Results of the radionuclide removal testing indicate that the radionuclides, including Tc-99, can be removed with inorganic sorbents and precipitating agents. Evaporation test results indicate that the simulant can be evaporated to fairly high concentration prior to formation of appreciable solids, but corrosion has not yet been examined.

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.; Taylor-Pashow, Kathryn M.; Adamson, Duane J.; Crawford, Charles L.; Morse, Megan M.

2014-01-07T23:59:59.000Z

289

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

290

Flowsheet model for the electrochemical treatment of liquid radioactive wastes. Final report  

SciTech Connect

The objective of this report is to describe the modeling and optimization procedure for the electrochemical removal of nitrates and nitrites from low level radioactive wastes. The simulation is carried out in SPEEDUP{trademark}, which is a state of the art flowsheet modeling package. The flowsheet model will provide a better understanding of the process and aid in the scale-up of the system. For example, the flowsheet model has shown that the electrochemical cell must be operated in batch mode to achieve 95 percent destruction. The flowsheet model is detailed in this report along with a systematic description of the batch optimization of the electrochemical cell. Results from two batch runs and one optimization run are also presented.

Hobbs, D.T. [Westinghouse Savannah River Co., Aiken, SC (United States); Prasad, S.; Farell, A.E.; Weidner, J.W.; White, R.E. [South Carolina Univ., Columbia, SC (United States). Dept. of Chemical Engineering

1995-12-31T23:59:59.000Z

291

Characterization of industrial process waste heat and input heat streams  

SciTech Connect

The nature and extent of industrial waste heat associated with the manufacturing sector of the US economy are identified. Industry energy information is reviewed and the energy content in waste heat streams emanating from 108 energy-intensive industrial processes is estimated. Generic types of process equipment are identified and the energy content in gaseous, liquid, and steam waste streams emanating from this equipment is evaluated. Matchups between the energy content of waste heat streams and candidate uses are identified. The resultant matrix identifies 256 source/sink (waste heat/candidate input heat) temperature combinations. (MHR)

Wilfert, G.L.; Huber, H.B.; Dodge, R.E.; Garrett-Price, B.A.; Fassbender, L.L.; Griffin, E.A.; Brown, D.R.; Moore, N.L.

1984-05-01T23:59:59.000Z

292

Evaluating the phase equilibria of liquid water + natural gas mixtures using cubic equations of state with asymmetric mixing rules  

Science Journals Connector (OSTI)

Based on a previously developed liquid–liquid mixing rule we present a modified and robust mixing rule for accurate prediction of water content of natural gas mixtures and the natural gas solubility in liquid water phase. The non-density dependent mixing rule (NDD) and the new mixing rule are incorporated into the Peng–Robinson (PR), Soave–Redlich–Kwong (SRK), and Nasrifar–Bolland (NB) equations of state to investigate their accuracies in estimating the water content of the gas phase as well as the gas solubility in the aqueous phase. For each binary system water + hydrocarbon, water + carbon dioxide, water + hydrogen sulfide, and water + nitrogen, three binary interaction parameters are required to describe the gas–liquid water equilibria. In this work, experimental data from literature were used to tune the parameters. The results are in good agreement with experimental data, demonstrating the reliability of the new mixing rule and the thermodynamic approach used in this work.

P. Reshadi; Kh. Nasrifar; M. Moshfeghian

2011-01-01T23:59:59.000Z

293

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

294

Development of low level liquid waste treatment systems: April-September 1981  

SciTech Connect

The pilot plant reverse osmosis system was demonstrated to be effective in removing large percentages of cobalt-60, iodine-125, and a mixture of cesium-137, cobalt-60, and iodine-125 from two types of aqueous streams. The effectiveness of three membrane porosities, 0, 50, and 97% salt rejection, were explored with each isotope. The 97% salt rejection membrane was the most effective in each experiment. Removals as high as 97.5% of the cobalt, 92.9% of the iodine and 95.1% of the combined isotopes were achieved. The effect of possibly interfering factors on the adsorbence of cobalt-60 and iodine-129 on selected ion exchange resins were investigated. The factors thought to affect cobalt-60 adsorption were (OH/sup -/), (NH/sub 4//sup +/), and (SO/sub 3//sup =/). None of the seven factors investigated had any effect on iodine-129 adsorption. Cesium-137 was removed from a 4600-gal aqueous waste containing a large amount of sodium hydroxide by treatment with sodium tetraphenyl boron. The cesium concentration of the supernatant portion was reduced from 570 to 4 counts/min/ml.

Williams, M.K.; Colvin, C.M.; Bond, W.H.

1982-03-05T23:59:59.000Z

295

Studies on fish waste management practices in Aroor Seafood Industrial Belt, Kerala and conversion of seafood waste into a liquid plant growth supplement.  

E-Print Network (OSTI)

??This study was materialized to analyze the management issues regarding the seafood processing waste generated including its impact on the coastal community in one of… (more)

Abhilash, S

2013-01-01T23:59:59.000Z

296

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network (OSTI)

DESCRIPTION DETAILS * Radioactive Waste Source Reduction 1,500 Radioactive Waste $6,000 $2,500 $6,000 Waste Yard Sorting Table surveying to sort clean waste from radioactive waste Radioactive Emissions Emission lives. Radioactive Waste generated through wet chemistry Waste Minimization 30 Mixed waste / Liquid

297

Ceramicrete stabilization of radioactive-salt-containing liquid waste and sludge water. Final CRADA report.  

SciTech Connect

It was found that the Ceramicrete Specimens incorporated the Streams 1 and 2 sludges with the adjusted loading about 41.6 and 31.6%, respectively, have a high solidity. The visible cracks in the matrix materials and around the anionite AV-17 granules included could not obtain. The granules mentioned above fixed by Ceramicrete matrix very strongly. Consequently, we can conclude that irradiation of Ceramecrete matrix, goes from the high radioactive elements, not result the structural degradation. Based on the chemical analysis of specimens No.462 and No.461 used it was shown that these matrix included the formation elements (P, K, Mg, O), but in the different samples their correlations are different. These ratios of the content of elements included are about {+-} 10%. This information shows a great homogeneity of matrix prepared. In the list of the elements founded, expect the matrix formation elements, we detected also Ca and Si (from the wollastonite - the necessary for Ceramicrete compound); Na, Al, S, O, Cl, Fe, Ni also have been detected in the Specimen No.642 from the waste forms: NaCl, Al(OH){sub 3}, Na{sub 2}SO{sub 4}. Fe(OH){sub 3}, nickel ferrocyanide and Ni(NO{sub 3})2. The unintelligible results also were found from analysis of an AV-17 granules, in which we obtain the great amount of K. The X-ray radiographs of the Ceramicrete specimens with loading 41.4 % of Stream 1 and 31.6% of Stream 2, respectively showed that the realization of the advance technology, created at GEOHKI, leads to formation of excellent ceramic matrix with high amount of radioactive streams up to 40% and more. Really, during the interaction with start compounds MgO and KH{sub 2}PO{sub 4} with the present of H{sub 3}BO{sub 3} and Wollastonite this process run with high speed under the controlled regimes. That fact that the Ceramicrete matrix with 30-40% of Streams 1 and 2 have a crystalline form, not amorphous matter, allows to permit that these matrix should be very stable, reliable for incorporation of a radionuclides.

Ehst, D.; Nuclear Engineering Division

2010-08-04T23:59:59.000Z

298

Numerical simulation of hydrothermal salt separation process and analysis and cost estimating of shipboard liquid waste disposal  

E-Print Network (OSTI)

Due to environmental regulations, waste water disposal for US Navy ships has become a requirement which impacts both operations and the US Navy's budget. In 2006, the cost for waste water disposal Navy-wide was 54 million ...

Hunt, Andrew Robert

2007-01-01T23:59:59.000Z

299

Gasification improvement of a poor quality solid recovered fuel (SRF). Effect of using natural minerals and biomass wastes blends  

Science Journals Connector (OSTI)

Abstract The need to produce energy from poor quality carbonaceous materials has increased, in order to reduce European dependency on imported fuels, diversify the use of new and alternative fuels and to guarantee secure energy production routes. The valorisation of a poor quality solid residual fuel (SRF), with high content of ash and volatile matter, through its conversion into fuel gas was studied. The rise of gasification temperature and equivalent ratio (ER) led to higher gas yields and to lower undesirable gaseous components, though higher ER values led to a gas with lower energetic content. To reduce the negative effect of SRF unfavourable characteristics and to diversify the feedstocks used, SRF blended with three different types of biomass wastes: forestry pine, almond shells and olive bagasse was co-gasified. The use of biomass wastes tested was valuable for SRF gasification, as there was an increase in the overall reactivity and in H2 production and a reduction of about 55% in tar released, without great changes in gas yield and in its HHV. The use of natural minerals mixed with silica sand was also studied with the aim of improving SRF gasification performance and fuel gas quality. The best results were obtained in presence of dolomite, as the lowest tar and H2S contents were obtained, while an increase in gas yield was observed. Co-gasification of this poor quality SRF blended with biomass wastes in presence of dolomite increased gas yield by 25% while tar contents decreased by 55%.

Filomena Pinto; Rui Neto André; Carlos Carolino; Miguel Miranda; Pedro Abelha; Daniel Direito; Nikos Perdikaris; Ioannis Boukis

2014-01-01T23:59:59.000Z

300

Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt  

SciTech Connect

Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.

Elders, W.A.; Cohen, L.H.

1983-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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

Trigeneration scheme for energy efficiency enhancement in a natural gas processing plant through turbine exhaust gas waste heat utilization  

Science Journals Connector (OSTI)

The performance of Natural Gas Processing Plants (NGPPs) can be enhanced with the integration of Combined Cooling, Heating and Power (CCHP) generation schemes. This paper analyzes the integration of a trigeneration scheme within a NGPP, that utilizes waste heat from gas turbine exhaust gases to generate process steam in a Waste Heat Recovery Steam Generator (WHRSG). Part of the steam generated is used to power double-effect water–lithium bromide (H2O–LiBr) absorption chillers that provide gas turbine compressor inlet air-cooling. Another portion of the steam is utilized to meet part furnace heating load, and supplement plant electrical power in a combined regenerative Rankine cycle. A detailed techno-economic analysis of scheme performance is presented based on thermodynamic predictions obtained using Engineering Equation Solver (EES). The results indicate that the trigeneration system could recover 79.7 MW of gas turbine waste heat, 37.1 MW of which could be utilized by three steam-fired H2O–LiBr absorption chillers to provide 45 MW of cooling at 5 °C. This could save approximately 9 MW of electric energy required by a typical compression chiller, while providing the same amount of cooling. In addition, the combined cycle generates 22.6 MW of additional electrical energy for the plant, while process heating reduces furnace oil consumption by 0.23 MSCM per annum. Overall, the trigeneration scheme would result in annual natural gas fuel savings of approximately 1879 MSCM, and annual operating cost savings of approximately US$ 20.9 million, with a payback period of 1 year. This study highlights the significant economical and environmental benefits that could be achieved through implementation of the proposed integrated cogeneration scheme in NGPPs, particularly in elevated ambient temperature and humidity conditions such as encountered in Middle East facilities.

Sahil Popli; Peter Rodgers; Valerie Eveloy

2012-01-01T23:59:59.000Z

302

Technology for Treatment of Liquid Radioactive Waste Generated during Uranium and Plutonium Chemical and Metallurgical Manufacturing in FSUE PO Mayak - 13616  

SciTech Connect

Created technological scheme for treatment of liquid radioactive waste generated while uranium and plutonium chemical and metallurgical manufacturing consists of: - Liquid radioactive waste (LRW) purification from radionuclides and its transfer into category of manufacturing waste; - Concentration of suspensions containing alpha-nuclides and their further conversion to safe dry state (calcinate) and moving to long controlled storage. The following technologies are implemented in LRW treatment complex: - Settling and filtering technology for treatment of liquid intermediate-level waste (ILW) with volume about 1500m{sup 3}/year and alpha-activity from 10{sup 6} to 10{sup 8} Bq/dm{sup 3} - Membrane and sorption technology for processing of low-level waste (LLW) of radioactive drain waters with volume about 150 000 m{sup 3}/year and alpha-activity from 10{sup 3} to 10{sup 4} Bq/dm{sup 3}. Settling and filtering technology includes two stages of ILW immobilization accompanied with primary settling of radionuclides on transition metal hydroxides with the following flushing and drying of the pulp generated; secondary deep after settling of radionuclides on transition metal hydroxides with the following solid phase concentration by the method of tangential flow ultrafiltration. Besides, the installation capacity on permeate is not less than 3 m{sup 3}/h. Concentrates generated are sent to calcination on microwave drying (MW drying) unit. Membrane and sorption technology includes processing of averaged sewage flux by the method of tangential flow ultrafiltration with total capacity of installations on permeate not less than 18 m{sup 3}/h and sorption extraction of uranium from permeate on anionite. According to radionuclide contamination level purified solution refers to general industrial waste. Concentrates generated during suspension filtering are evaporated in rotary film evaporator (RFE) in order to remove excess water, thereafter they are dried on infrared heating facility. Solid concentrate produced is sent for long controlled storage. Complex of the procedures carried out makes it possible to solve problems on treatment of LRW generated while uranium and plutonium chemical and metallurgical manufacturing in Federal State Unitary Enterprise (FSUE) Mayak and cease its discharge into open water reservoirs. (authors)

Adamovich, D. [SUE MosSIA Radon, 2/14 7th Rostovsky lane, Moscow, 119121 (Russian Federation)] [SUE MosSIA Radon, 2/14 7th Rostovsky lane, Moscow, 119121 (Russian Federation); Batorshin, G.; Logunov, M.; Musalnikov, A. [FSUE 'PO Mayak', 31 av. Lenin, Ozyorsk, Chelyabinsk region, 456780 (Russian Federation)] [FSUE 'PO Mayak', 31 av. Lenin, Ozyorsk, Chelyabinsk region, 456780 (Russian Federation)

2013-07-01T23:59:59.000Z

303

Low Cost Chemical Feedstocks Using an Improved and Energy Efficient Natural Gas Liquid (NGL) Removal Process, Final Technical Report  

SciTech Connect

The overall objective of this project is to develop a new low-cost and energy efficient Natural Gas Liquid (NGL) recovery process - through a combination of theoretical, bench-scale and pilot-scale testing - so that it could be offered to the natural gas industry for commercialization. The new process, known as the IROA process, is based on U.S. patent No. 6,553,784, which if commercialized, has the potential of achieving substantial energy savings compared to currently used cryogenic technology. When successfully developed, this technology will benefit the petrochemical industry, which uses NGL as feedstocks, and will also benefit other chemical industries that utilize gas-liquid separation and distillation under similar operating conditions. Specific goals and objectives of the overall program include: (i) collecting relevant physical property and Vapor Liquid Equilibrium (VLE) data for the design and evaluation of the new technology, (ii) solving critical R&D issues including the identification of suitable dehydration and NGL absorbing solvents, inhibiting corrosion, and specifying proper packing structure and materials, (iii) designing, construction and operation of bench and pilot-scale units to verify design performance, (iv) computer simulation of the process using commercial software simulation platforms such as Aspen-Plus and HYSYS, and (v) preparation of a commercialization plan and identification of industrial partners that are interested in utilizing the new technology. NGL is a collective term for C2+ hydrocarbons present in the natural gas. Historically, the commercial value of the separated NGL components has been greater than the thermal value of these liquids in the gas. The revenue derived from extracting NGLs is crucial to ensuring the overall profitability of the domestic natural gas production industry and therefore of ensuring a secure and reliable supply in the 48 contiguous states. However, rising natural gas prices have dramatically reduced the economic incentive to extract NGLs from domestically produced natural gas. Successful gas processors will be those who adopt technologies that are less energy intensive, have lower capital and operating costs and offer the flexibility to tailor the plant performance to maximize product revenue as market conditions change, while maintaining overall system efficiency. Presently, cryogenic turbo-expander technology is the dominant NGL recovery process and it is used throughout the world. This process is known to be highly energy intensive, as substantial energy is required to recompress the processed gas back to pipeline pressure. The purpose of this project is to develop a new NGL separation process that is flexible in terms of ethane rejection and can reduce energy consumption by 20-30% from current levels, particularly for ethane recoveries of less than 70%. The new process integrates the dehydration of the raw natural gas stream and the removal of NGLs in such a way that heat recovery is maximized and pressure losses are minimized so that high-value equipment such as the compressor, turbo-expander, and a separate dehydration unit are not required. GTI completed a techno-economic evaluation of the new process based on an Aspen-HYSYS simulation model. The evaluation incorporated purchased equipment cost estimates obtained from equipment suppliers and two different commercial software packages; namely, Aspen-Icarus and Preliminary Design and Quoting Service (PDQ$). For a 100 MMscfd gas processing plant, the annualized capital cost for the new technology was found to be about 10% lower than that of conventional technology for C2 recovery above 70% and about 40% lower than that of conventional technology for C2 recovery below 50%. It was also found that at around 40-50% C2 recovery (which is economically justifiable at the current natural gas prices), the energy cost to recover NGL using the new technology is about 50% of that of conventional cryogenic technology.

Meyer, Howard, S.; Lu, Yingzhong

2012-08-10T23:59:59.000Z

304

Structural Integrity Program for the 300,000-Gallon Radioactive Liquid Waste Storage Tanks at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

This report provides a record of the Structural Integrity Program for the 300,000-gal liquid waste storage tanks and associated equipment at the Idaho Nuclear Technology and Engineering Center, as required by U.S. Department of Energy M 435.1-1, “Radioactive Waste Management Manual.” This equipment is known collectively as the Tank Farm Facility. This report is an update, and replaces the previous report by the same title issued April 2003. The conclusion of this report is that the Tank Farm Facility tanks, vaults, and transfer systems that remain in service for storage are structurally adequate, and are expected to remain structurally adequate over the remainder of their planned service life through 2012. Recommendations are provided for continued monitoring of the Tank Farm Facility.

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

305

Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 2: A Techno-economic Evaluation of the Production of Mixed Alcohols  

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

Biomass is a renewable energy resource that can be converted into liquid fuel suitable for transportation applications and thus help meet the Energy Independence and Security Act renewable energy goals (U.S. Congress 2007). However, biomass is not always available in sufficient quantity at a price compatible with fuels production. Municipal solid waste (MSW) on the other hand is readily available in large quantities in some communities and is considered a partially renewable feedstock. Furthermore, MSW may be available for little or no cost.

306

Resource-Limited Multiattribute Value Analysis of Alternatives for Immobilizing Radioactive Liquid Process Waste Stored in Saluggia, Italy  

Science Journals Connector (OSTI)

This large Italian public works project started with the development of engineering data to support the evaluation of three alternatives for processing nuclear waste. After an analysis of the alternatives' performance from an engineering perspective ... Keywords: EUREX, Sogin, alternatives, applications, decision analysis, decision making, decision theory, energy, environment, multiattribute value analysis, nuclear waste

Alan J. Brothers; Shas V. Mattigod; Denis M. Strachan; Gordon H. Beeman; Paul K. Kearns; Angelo Papa; Carlo Monti

2009-06-01T23:59:59.000Z

307

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect

The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

Charles M. Barnes; James B. Bosley; Clifford W. Olsen

2004-07-01T23:59:59.000Z

308

Comparative analysis of the production costs and life-cycle GHG emissions of FT liquid fuels from coal and natural gas  

SciTech Connect

Liquid transportation fuels derived from coal and natural gas could help the United States reduce its dependence on petroleum. The fuels could be produced domestically or imported from fossil fuel-rich countries. The goal of this paper is to determine the life-cycle GHG emissions of coal- and natural gas-based Fischer-Tropsch (FT) liquids, as well as to compare production costs. The results show that the use of coal- or natural gas-based FT liquids will likely lead to significant increases in greenhouse gas (GHG) emissions compared to petroleum-based fuels. In a best-case scenario, coal- or natural gas-based FT-liquids have emissions only comparable to petroleum-based fuels. In addition, the economic advantages of gas-to-liquid (GTL) fuels are not obvious: there is a narrow range of petroleum and natural gas prices at which GTL fuels would be competitive with petroleum-based fuels. CTL fuels are generally cheaper than petroleum-based fuels. However, recent reports suggest there is uncertainty about the availability of economically viable coal resources in the United States. If the U.S. has a goal of increasing its energy security, and at the same time significantly reducing its GHG emissions, neither CTL nor GTL consumption seem a reasonable path to follow. 28 refs., 2 figs., 4 tabs.

Paulina Jaramillo; W. Michael Griffin; H. Scott Matthews [Carnegie Mellon University, Pittsburgh, PA (USA). Civil and Environmental Engineering Department

2008-10-15T23:59:59.000Z

309

Feasibility study on the solidification of liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect

A literature survey was conducted to help determine the feasibility of solidifying a liquid low-level radioactive mixed waste in the inactive tank system at Oak Ridge National Laboratory (ORNL). The goal of this report is to facilitate a decision on the disposition of these wastes by identifying any waste constituents that might (1) compromise the strength or stability of the waste form or (2) be highly leachable. Furthermore, its goal is to identify ways to circumvent interferences and to decrease the leachability of the waste constituents. This study has sought to provide an understanding of inhibition of cement set by identifying the fundamental chemical mechanisms by which this inhibition takes place. From this fundamental information, it is possible to draw some conclusions about the potential effects of waste constituents, even in the absence of particular studies on specific compounds.

Trussell, S. [Texas A and M Univ., College Station, TX (United States). Dept. of Civil Engineering; Spence, R.D. [Oak Ridge National Lab., TN (United States)

1993-01-01T23:59:59.000Z

310

Increasing liquid hydrocarbon recovery from natural gas: Evaluation of the vortex-tube device  

SciTech Connect

The vortex-tube device provides a useful addition to the range of equipment available to the gas industry. It has been shown that the use of vortex-tube equipment permits improved separation in comparison with a Joule-Thomson system, without entering into the cost and complexity of a true isentropic system such as a turbo-expander unit. The comparative advantage of the vortex tube depends upon the inlet conditions of the gas and the pressure drop that is available. An optimum pressure drop of 25--35% of the inlet gas pressure has been confirmed in practice. Although not yet tested on operating plant, it is expected that a loss of performance of vortex-tube units will occur for inlet liquid-to-gas ratios of greater than 20%. Units with up to 5% liquid at the inlet have been successfully operated showing that a single phase gas at the unit inlet is not essential. It is expected that future application of vortex tube units will be concentrated where performance improvements over Joule-Thomson units, at low capital cost, are required.

Hajdik, B. [CBS Engineering, Houston, TX (United States); Steinle, J. [BEB Erdoel and Erdgas GmbH, Hannover (Germany); Lorey, M. [Filtan Analgenbau GmbH, Langenselbold (Germany); Thomas, K. [Falk and Thomas Engineering GmbH, Wettenberg (Germany)

1997-12-31T23:59:59.000Z

311

Low-Level Liquid Waste Processing Pilot Studies Using a Vibratory Shear Enhancing Process (VSEP) for Filtration  

SciTech Connect

A previous EPRI study evaluated potential treatment methods for the removal of iron from BWR waste streams. Of the methods investigated, high shear filtration using the vibratory shear-enhanced process (VSEP) showed the most promise to effectively and economically remove high iron concentrations from backwash receiving tank waste. A VSEP filter uses oscillatory vibration to create high shear at the surface of the filter membrane. This high shear force significantly improves the filter's resistance to fouling thereby enabling high throughputs with very little secondary waste generation. With a VSEP filter, the waste feed stream is split into two effluents- a permeate stream with little or no suspended solids and a concentrate stream with a suspended solids concentration much higher than that of the feed stream. To evaluate the feasibility of using a VSEP concept for processing typical high iron containing BWR radwaste, a surrogate feedstream containing up to 1,700 ppm iron oxide (as Fe2O3) was used. This surrogate waste simulates radioactive waste found at Exelon's Limerick and Peach Bottom (powdered resin condensate) plants, and in Hope Creek's (deep bed condensate) radwaste systems. Testing was done using a series L (laboratory scale) VSEP unit at the manufacturer's and contractor's laboratories. These tests successfully demonstrated the VSEP capability for producing highly concentrated waste streams with totally ''recyclable'' permeate (e.g., greater than 95% recovery).

Bushart, S.; Tran, P.; Asay, R.

2002-02-25T23:59:59.000Z

312

Enterprise Assessments Operational Awareness Record, Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

the melter handling system (LMH), the melter equipment support handling system (LSH), the radioactive solid waste handling system (RWH), and the radioactive liquid waste disposal...

313

Development of polymer concrete for dike insulation at LNG (Liquid Natural Gas) facilities. Final report, August 1983-July 1984  

SciTech Connect

An insulating polymer concrete (IPC) composite has been developed for possible use as a dike insulation material at Liquid Natural Gas (LNG) storage facilities. Using hermetically sealed glass nodules or expanded perlite aggregates and unsaturated polyester resins, a new class of lightweight polymer concretes can be manufactured. Two application procedures have been identified and shown to be feasible in laboratory studies. Precast IPC composite panels 1-in thick can be bonded to concrete substrates using epoxy gel type adhesives or mortars. Cast-in-place IPC to concrete substrates have been shown to have good bonding and insulating characteristics. Modifications of the mix design to improve the workability and sagging of the IPC for installation on vertical or sloped surfaces is necessary.

Fontana, J.J.; Steinberg, M.

1984-11-01T23:59:59.000Z

314

Assessment of fission product content of high-level liquid waste supernate on E-Area vault package criteria  

SciTech Connect

This report assesses the tank farm`s high level waste supernate to determine any potential impacts on waste certification for the E-Area vaults (EAV). The Waste Acceptance Criteria procedure (i.e., WAC 3.10 of the 1S manual) imposes administrative controls on radioactive material in waste packages sent to the EAV, specifically on six fission products. Waste tank supernates contain various fission products, so any waste package containing material contaminated with supernate will contain these radioactive isotopes. This report develops the process knowledge basis for characterizing the supernate composition for these isotopes, so that appropriate controls can be implemented to ensure that the EAV WAC is met. Six fission products are listed in the SRS 1S Manual WAC 3.10: Se-79, which decays to bromine; Sr-90, which decays to niobium; Tc-99, which decays to ruthenium; Sn-126, which decays to tellurium; I-129, which decays to xenon; and Cs-137, which decays to barium.

Brown, D.F.

1994-06-30T23:59:59.000Z

315

Evaluation of plasma melter technology for verification of high-sodium content low-level radioactive liquid wastes: Demonstration test No. 4 preliminary test report  

SciTech Connect

This document provides a preliminary report of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System Low-Level Waste (LLW) Vitrification Program. Phase I test conduct included 26 hours (24 hours steady state) of melting of simulated high-sodium low-level radioactive liquid waste. Average processing rate was 4.9 kg/min (peak rate 6.2 kg/min), producing 7330 kg glass product. Free-flowing glass pour point was 1250 C, and power input averaged 1530 kW(e), for a total energy consumption of 19,800 kJ/kg glass. Restart capability was demonstrated following a 40-min outage involving the scrubber liquor heat exchanger, and glass production was continued for another 2 hours. Some volatility losses were apparent, probably in the form of sodium borates. Roughly 275 samples were collected and forwarded for analysis. Sufficient process data were collected for heat/material balances. Recommendations for future work include lower boron contents and improved tuyere design/operation.

McLaughlin, D.F.; Gass, W.R.; Dighe, S.V.; D`Amico, N.; Swensrud, R.L.; Darr, M.F.

1995-01-10T23:59:59.000Z

316

Recovery of Wasted Mechanical Energy from the Reduction of Natural Gas Pressure  

Science Journals Connector (OSTI)

Abstract At the present time in Romania, the transition from the natural gas transportation system to the distribution system is done only thru the use of pressure reducing stations. Here the pressure drop is usually done by using throttle valves or pressure reducing valves, where the gas energy is spent without doing any work. In this article we propose the use of turbo-expanders in the pressure reducing stations, where the natural gas pressure from the transportation grid is high and needs to drop to lower levels to enter the distribution grids, in this way part of the energy consumed in the compression stations are recovered. The plans are made at this time for a pilot project at the pressure reducing station in the city of Onesti, Bacau County.

Iancu Andrei; Tudorache Valentin; Tarean Cristina; Toma Niculae

2014-01-01T23:59:59.000Z

317

The conversion of natural gas to liquid fuels using the Sasol Slurry Phase Distillate Process  

SciTech Connect

The natural gas and energy industries have long sought an economically attractive means of converting remote gas reserves into transportable products, such as fuels or petrochemicals. Applicable gas sources include: undeveloped gas fields in locations so remote that pipeline construction is prohibitively expensive and associated gas from oil wells that is either flared, which is becoming environmentally unacceptable in many parts of the world, or reinjected, which is costly. Projects which have been developed to exploit such feeds typically have converted the gas into one of the following: (1) liquefied natural gas (LNG)--the process plants for LNG production are expensive, need to be very large to be economically viable, have costly dedicated shipping requirements, and suffer from a limited market concentrated in few countries; (2) methanol--the market for petrochemical feedstock methanol is limited, for use as a fuel, further downstream processing is needed, for example in a methyl tertiary butyl ether (MTBE) or methanol to gasoline (MTG) unit. Clearly, there is a need for an alternative that produces high quality fuels or value added products that can be transported to far-off markets, while yielding an attractive return on the developers` investment. The Sasol Slurry Phase Distillate Process will fulfill this need.

Silverman, R.W. [Raytheon Engineers and Constructors, Cambridge, MA (United States); Hill, C.R. [Sastech, Johannesburg (South Africa)

1997-12-31T23:59:59.000Z

318

Cesium removal from liquid acidic wastes with the primary focus on ammonium molybdophosphate as an ion exchanger: A literature review  

SciTech Connect

Many articles have been written concerning the selective removal of cesium from both acidic and alkaline defense wastes. The majority of the work performed for cesium removal from defense wastes involves alkaline feed solutions. Several different techniques for cesium removal from acidic solutions have been evaluated such as precipitation, solvent extraction, and ion exchange. The purpose of this paper is to briefly review various techniques for cesium removal from acidic solutions. The main focus of the review will be on ion exchange techniques, particularly those involving ammonium molybdophosphate as the exchanger. The pertinent literature sources are condensed into a single document for quick reference. The information contained in this document was used as an aid in determining techniques to evaluate cesium removal from the acidic Idaho Chemical Processing Plant waste matrices. 47 refs., 2 tabs.

Miller, C.J.

1995-03-01T23:59:59.000Z

319

Savannah River Site Achieves Waste Transfer First  

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

AIKEN, S.C. – The EM program and its liquid waste contractor at the Savannah River Site (SRS) made history recently by safely transferring radioactive liquid waste from F Tank Farm to H Tank Farm using a central control room.

320

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

Note: This page contains sample records for the topic "liquid wastes natural" 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

Natural and Enhanced Attenuation of Soil and Groundwater at the Monument Valley, Arizona, DOE Legacy Waste Site—10281  

SciTech Connect

The U.S. Department of Energy (DOE), the Navajo Nation, and the University of Arizona are exploring natural and enhanced attenuation remedies for groundwater contamination at a former uranium-ore processing site near Monument Valley, Arizona. DOE removed radioactive tailings from the Monument Valley site in 1994. Nitrate and ammonium, waste products of the milling process, remain in an alluvial groundwater plume spreading from the soil source where tailings were removed. Planting and irrigating two native shrubs, fourwing saltbush and black greasewood, markedly reduced both nitrate and ammonium in the source area over an 8-year period. Total nitrogen dropped from 350 mg/kg in 2000 to less than 200 mg/kg in 2008. Most of the reduction is attributable to irrigation-enhanced microbial denitrification rather than plant uptake. However, soil moisture and percolation flux monitoring show that the plantings control the soil water balance in the source area, preventing additional leaching of nitrogen compounds. Enhanced denitrification and phytoremediation also look promising for plume remediation. Microcosm experiments, nitrogen isotopic fractionation analysis, and solute transport modeling results suggest that (1) up to 70 percent of nitrate in the plume has been lost through natural denitrification since the mill was closed in 1968, and (2) injection of ethanol may accelerate microbial denitrification in plume hot spots. A field-scale ethanol injection pilot study is underway. Landscape-scale remote sensing methods developed for the project suggest that transpiration from restored native phreatophyte populations rooted in the aquifer could limit further expansion of the plume. An evaluation of landfarm phytoremediation, the irrigation of native shrub plantings with high nitrate water pumped from the alluvial aquifer, is also underway.

Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, CO; Miller, D.E. [S.M. Stoller Corporation, Grand Junction, CO; Morris, S.A. [S.M. Stoller Corporation, Grand Junction, CO; Sheader, L.R. [S.M. Stoller Corporation, Grand Junction, CO; Glenn, E.P. [University of Arizona, Tucson, AZ; Moore, D. [University of Arizona, Tucson, AZ; Carroll, K.C. [University of Arizona, Tucson, AZ; Benally, L. [Navajo Nation, Window Rock, AZ; Roanhorse, M. [Navajo Nation, Window Rock, AZ; Bush, R.P. [U.S. Department of Energy, Grand Junction, CO; none,

2010-03-07T23:59:59.000Z

322

Municipal Solid Waste (MSW) to Liquid Fuels Synthesis, Volume 2: A Techno-economic Evaluation of the Production of Mixed Alcohols  

SciTech Connect

Biomass is a renewable energy resource that can be converted into liquid fuel suitable for transportation applications and thus help meet the Energy Independence and Security Act renewable energy goals (U.S. Congress 2007). However, biomass is not always available in sufficient quantity at a price compatible with fuels production. Municipal solid waste (MSW) on the other hand is readily available in large quantities in some communities and is considered a partially renewable feedstock. Furthermore, MSW may be available for little or no cost. This report provides a techno-economic analysis of the production of mixed alcohols from MSW and compares it to the costs for a wood based plant. In this analysis, MSW is processed into refuse derived fuel (RDF) and then gasified in a plant co-located with a landfill. The resulting syngas is then catalytically converted to mixed alcohols. At a scale of 2000 metric tons per day of RDF, and using current technology, the minimum ethanol selling price at a 10% rate of return is approximately $1.85/gallon ethanol (early 2008 $). However, favorable economics are dependent upon the toxicity characteristics of the waste streams and that a market exists for the by-product scrap metal recovered from the RDF process.

Jones, Susanne B.; Zhu, Yunhua; Valkenburt, Corinne

2009-05-01T23:59:59.000Z

323

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill  

E-Print Network (OSTI)

Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill Timothy D. Stark, F.ASCE1 landfills may contain aluminum from residential and commercial solid waste, industrial waste, and aluminum, may react with liquid in a landfill and cause uncontrolled temperature increases, significant changes

324

Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose............................................................................................................................................. 1 2.0 Scope................................................................................................................................................ 1 3.0 Background...................................................................................................................................... 2 4.0 Methodology....................................................................................................................................

325

Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012  

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

Waste Isolation Pilot Plant Waste Isolation Pilot Plant May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose............................................................................................................................................. 1 2.0 Scope................................................................................................................................................ 1 3.0 Background...................................................................................................................................... 2 4.0 Methodology....................................................................................................................................

326

New and Underutilized Technology: Liquid Desiccant Air Conditioner |  

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

Liquid Desiccant Air Conditioner Liquid Desiccant Air Conditioner New and Underutilized Technology: Liquid Desiccant Air Conditioner October 4, 2013 - 4:40pm Addthis The following information outlines key deployment considerations for liquid desiccant air conditioners (LDACs) within the Federal sector. Benefits Liquid desiccant air conditioners deeply dry air using natural gas, solar energy, waste heat, bio-fuel, or other fossil fuels to drive the system. By providing mostly latent cooling, the LDAC controls indoor humidity without overcooling and reheating. This unit is supplemented by an electric chiller or DX air conditioner that sensibly cools the building's recirculation air. The liquid desiccant is a concentrated salt solution that directly absorbs moisture. Application LDACs are applicable in hospital, office, prison, school, and service

327

WASTE DESCRIPTION TYPE OF PROJECT POUNDS REDUCED,  

E-Print Network (OSTI)

/spills and subsequent clean up costs ($20,000) Sewage Sludge Volume Reduction 234,000 Radioactive Waste $910,000 $193,400 $716,600 60,000 gallons of radioactive STP liquid waste could have been disposed of through,000) Digital Imaging System Substitution 282 Hazardous Waste / Radioactive Waste / Industrial Waste $25,000 $25

328

UBC Social Ecological Economic Development Studies (SEEDS) Student Report Diverting Waste, Conserving Natural Resources: Composting Toilets for the New SUB  

E-Print Network (OSTI)

..........................................................................................................................................13 Designing for sustainability: green buildingUBC Social Ecological Economic Development Studies (SEEDS) Student Report Diverting Waste­2008)........................................................................................................35 Appendix C: Maintenance manual for C.K. Choi Building at UBC .....................................41

329

Savannah River Site Achieves Transuranic Waste Disposition Goal...  

Office of Environmental Management (EM)

liquid waste contractor, Savannah River Remediation (SRR): Closed two more underground tanks containing radioactive waste, helping reduce a significant environmental risk to South...

330

Savannah River Site Waste Disposition Project  

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

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

331

HUMAN MACHINE INTERFACE (HMI) EVALUATION OF ROOMS TA-50-1-60/60A AT THE RADIOACTIVE LIQUID WASTE TREATMENT FACILITY (RLWTF)  

SciTech Connect

This effort addressed an evaluation of human machine interfaces (HMIs) in Room TA-50-1-60/60A of the Radioactive Liquid Waste Treatment Facility (RLWTF). The evaluation was performed in accordance with guidance outlined in DOE-STD-3009, DOE Standard Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, 2006 [DOE 2006]. Specifically, Chapter 13 of DOE 2006 highlights the 10 CFR 830, Nuclear Safety Management, 2012, [CFR 2012] and DOE G 421.1-2 [DOE 2001a] requirements as they relate to the human factors process and, in this case, the safety of the RLWTF. The RLWTF is a Hazard Category 3 facility and, consequently, does not have safety-class (SSCs). However, safety-significant SSCs are identified. The transuranic (TRU) wastewater tanks and associated piping are the only safety-significant SSCs in Rooms TA-50-1-60/60A [LANL 2010]. Hence, the human factors evaluation described herein is only applicable to this particular assemblage of tanks and piping.

Gilmore, Walter E. [Los Alamos National Laboratory; Stender, Kerith K. [Los Alamos National Laboratory

2012-08-29T23:59:59.000Z

332

Study on separation of platinum group metals from high level liquid waste using macroporous (MOTDGA-TOA)/SiO{sub 2}-P silica-based absorbent  

SciTech Connect

The recovery of platinum group metals (PGMs) from high level liquid waste (HLLW) by macroporous silica-based adsorbent, (MOTDGA-TOA)/SiO{sub 2}-P has been developed by impregnating two extractants of N,N'-dimethyl-N,N'-di-n-octyl-thio-diglycolamide (MOTDGA) and tri-n-octylamine (TOA) into a silica/polymer composite support (SiO{sub 2}-P). The adsorption of Ru(III), Rh(III) and Pd(II) have been investigated in simulated HLLW by batch method. The adsorbent has shown good uptake property for Pd(II). In addition, the combined use of MOTDGA and TOA improved the adsorption of Ru(III) and Rh(III) better than the individual use of them. The usability of adsorbent in radiation fields was further confirmed by irradiation experiments. The adsorbent remained to have the uptake capability for PGMs over the absorbed dose of 100 kGy, corresponding with one really adsorbed by the adsorbent, and showed good retention capability for Pd(II) even at the absorbed dose of 800 kGy. The chromatographic separation of metal ions was demonstrated with the adsorbent packed column, there is no influence of Re(VII) (instead of Tc) on the excellent separation behavior of Pd(II). (authors)

Ito, Tatsuya [Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aoba 6-6, Aramaki, Aoba-ku, Sendai, Miyagi 980-8579 (Japan); Japan Atomic Energy Agency, Tokai-mura Naka-gun, Ibarak319-1195 (Japan); Kim, Seong-Yun; Xu, Yuanlai; Hitomi, Keitaro [Cyclotron and Radioisotope Center, Tohoku University, Aoba 6-3, Aramaki, Aoba-ku, Sendai, Miyagi 980-8578 (Japan); Ishii, Keizo [Department of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aoba 6-6, Aramaki, Aoba-ku, Sendai, Miyagi 980-8579 (Japan); Nagaishi, Ryuji; Kimura, Takaumi [Japan Atomic Energy Agency, Tokai-mura Naka-gun, Ibarak319-1195 (Japan)

2013-07-01T23:59:59.000Z

333

Laboratory solvent reuse -- Liquid chromatography  

SciTech Connect

The objective of this work was to develop a method for reduction of waste solvent in the Process Engineering Chemistry Laboratory. The liquid chromatographs are the largest generators of explosive-contaminated waste in the laboratory. We developed a successful process for the reuse of solvents from the liquid chromatographs and demonstrated the utility of the process in the assay of hexanitrostilbene.

Quinlin, W.T.; Schaffer, C.L.

1992-11-01T23:59:59.000Z

334

SRS - Programs - Waste Solidification  

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

Waste Solidification Waste Solidification The two primary facilities operated within the Waste Solidification program are Saltstone and the Defense Waste Processing Facility (DWPF). Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. Each DWPF canister is 10 feet tall and 2 feet in diameter, and typically takes a little over a day to fill. The largest radioactive waste glassification plant in the world, DWPF converts the high-level liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for immobilizing high-level radioactive liquids into a more stable, manageable form until a federal

335

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

336

Missouri Hazardous Waste Management Law (Missouri)  

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

The Hazardous Waste Program, administered by the Hazardous Waste Management Commission in the Department of Natural Resources, regulates the processing, transportation, and disposal of hazardous...

337

Radioactive Waste Radioactive Waste  

E-Print Network (OSTI)

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

338

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

339

Waste-to-Energy Workshop  

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

The Waste to Energy Roadmapping Workshop was held on November 5, 2014, in Arlington, Virginia. This workshop gathered waste-to-energy experts to identify the key technical barriers to the commercial deployment of liquid transportation fuels from wet waste feedstocks.

340

Natural  

Gasoline and Diesel Fuel Update (EIA)

Summary of U.S. Natural Gas Imports and Exports, 1992-1996 Table 1992 1993 1994 1995 1996 Imports Volume (million cubic feet) Pipeline Canada............................. 2,094,387 2,266,751 2,566,049 2,816,408 2,883,277 Mexico .............................. 0 1,678 7,013 6,722 13,862 Total Pipeline Imports....... 2,094,387 2,268,429 2,573,061 2,823,130 2,897,138 LNG Algeria .............................. 43,116 81,685 50,778 17,918 35,325 United Arab Emirates ....... 0 0 0 0 4,949 Total LNG Imports............. 43,116 81,685 50,778 17,918 40,274 Total Imports......................... 2,137,504 2,350,115 2,623,839 2,841,048 2,937,413 Average Price (dollars per thousand cubic feet) Pipeline Canada............................. 1.84 2.02 1.86 1.48 1.96 Mexico .............................. - 1.94 1.99 1.53 2.25 Total Pipeline Imports.......

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


341

Permeability of natural rock salt from the Waste Isolation Pilot Plant (WIPP) during damage evolution and healing  

SciTech Connect

The US Department of Energy has developed the Waste Isolation Pilot Plant (WIPP) in the bedded salt of southeastern New Mexico to demonstrate the safe disposal of radioactive transuranic wastes. Four vertical shafts provide access to the underground workings located at a depth of about 660 meters. These shafts connect the underground facility to the surface and potentially provide communication between lithologic units, so they will be sealed to limit both the release of hazardous waste from and fluid flow into the repository. The seal design must consider the potential for fluid flow through a disturbed rock zone (DRZ) that develops in the salt near the shafts. The DRZ, which forms initially during excavation and then evolves with time, is expected to have higher permeability than the native salt. The closure of the shaft openings (i.e., through salt creep) will compress the seals, thereby inducing a compressive back-stress on the DRZ. This back-stress is expected to arrest the evolution of the DRZ, and with time will promote healing of damage. This paper presents laboratory data from tertiary creep and hydrostatic compression tests designed to characterize damage evolution and healing in WIPP salt. Healing is quantified in terms of permanent reduction in permeability, and the data are used to estimate healing times based on considerations of first-order kinetics.

Pfeifle, T.W. [RE/SPEC Inc., Rapid City, SD (United States); Hurtado, L.D. [Sandia National Lab., Albuquerque, NM (United States)

1998-06-01T23:59:59.000Z

342

Basis for Section 3116 Determination for Salt Waste Disposal...  

Office of Environmental Management (EM)

gallons 1 2 (Mgal) of liquid radioactive waste stored in underground waste storage tanks at SRS. Much of this waste resulted from the reprocessing of spent nuclear fuel for...

343

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

344

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

345

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

346

Waste Heat Boilers for Incineration Applications  

E-Print Network (OSTI)

Incineration is a widely used process for disposing of solid, liquid and gaseous wastes generated in various types of industries. In addition to destroying pollutants, energy may also be recovered from the waste gas streams in the form of steam...

Ganapathy, V.

347

LNG liquid-liquid immiscibility  

SciTech Connect

Although natural gas species rarely exhibit liquid-liquid immiscibility in binary systems, the presence of additional components can extend the domain of immiscibility in those few binary systems where it already exists or produce immiscibility in binary systems where it had not existed. If the solute has the proper molecular relation to the solvent mixture background, liquid-liquid-vapor (LLV) behavior will occur; such phenomena greatly complicate the design of LNG processing equipment. To aid LNG engineers, researchers mapped the thermodynamic behavior of four ternary LLV systems and examined the effects of the second solvents - ethane, propane, n-butane, and CO/sub 2/ - on the binary methane + n-octane system.

Luks, K.D.; Kohn, J.P.

1981-09-01T23:59:59.000Z

348

natural gasoline  

Science Journals Connector (OSTI)

natural gasoline, condensate, distillate [Liquid hydrocarbons, generally clear or pale straw-coloured and of high API gravity (above 6o°), that are produced with wet gas] ? Gasbenzin n, Gasolin n ...

2014-08-01T23:59:59.000Z

349

Waste Management | Department of Energy  

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

Management Management Waste Management Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing The Department has approximately 88 million gallons of liquid waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

350

Heavy-Duty Waste Hauler with Chemically Correct Natural Gas Engine Diluted with EGR and Using a Three-Way Catalyst: Final Report, 24 February 2004 -- 23 February 2006  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Heavy-Duty Waste Hauler with Heavy-Duty Waste Hauler with Chemically Correct Natural Gas Engine Diluted with EGR and Using a Three-Way Catalyst Final Report February 24, 2004 - February 23, 2006 T. Reppert Mack Trucks, Inc. Allentown, Pennsylvania J. Chiu Southwest Research Institute San Antonio, Texas Subcontract Report NREL/SR-540-38222 September 2005 Heavy-Duty Waste Hauler with Chemically Correct Natural Gas Engine Diluted with EGR and Using a Three-Way Catalyst Final Report February 24, 2004 - February 23, 2006 T. Reppert Mack Trucks, Inc. Allentown, Pennsylvania J. Chiu Southwest Research Institute San Antonio, Texas NREL Technical Monitor: R. Parish Prepared under Subcontract No. ZCI-4-32049-01 Subcontract Report NREL/SR-540-38222 September 2005 National Renewable Energy Laboratory

351

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network (OSTI)

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

352

Separation, Concentration, and Immobilization of Technetium and Iodine from Alkaline Supernate Waste  

SciTech Connect

Development of remediation technologies for the characterization, retrieval, treatment, concentration, and final disposal of radioactive and chemical tank waste stored within the Department of Energy (DOE) complex represents an enormous scientific and technological challenge. A combined total of over 90 million gallons of high-level waste (HLW) and low-level waste (LLW) are stored in 335 underground storage tanks at four different DOE sites. Roughly 98% of this waste is highly alkaline in nature and contains high concentrations of nitrate and nitrite salts along with lesser concentrations of other salts. The primary waste forms are sludge, saltcake, and liquid supernatant with the bulk of the radioactivity contained in the sludge, making it the largest source of HLW. The saltcake (liquid waste with most of the water removed) and liquid supernatant consist mainly of sodium nitrate and sodium hydroxide salts. The main radioactive constituent in the alkaline supernatant is cesium-137, but strontium-90, technetium-99, and transuranic nuclides are also present in varying concentrations. Reduction of the radioactivity below Nuclear Regulatory Commission (NRC) limits would allow the bulk of the waste to be disposed of as LLW. Because of the long half-life of technetium-99 (2.1 x 10 5 y) and the mobility of the pertechnetate ion (TcO 4 - ) in the environment, it is expected that technetium will have to be removed from the Hanford wastes prior to disposal as LLW. Also, for some of the wastes, some level of technetium removal will be required to meet LLW criteria for radioactive content. Therefore, DOE has identified a need to develop technologies for the separation and concentration of technetium-99 from LLW streams. Eichrom has responded to this DOE-identified need by demonstrating a complete flowsheet for the separation, concentration, and immobilization of technetium (and iodine) from alkaline supernatant waste.

James Harvey; Michael Gula

1998-12-07T23:59:59.000Z

353

Physical characterization of magmatic liquids. [Ultrasonic and Brillouin Scattering Studies of Natural and Synthetic Silicates and Oxides  

SciTech Connect

This report describes a research project that was conducted from August 15, 1985 to February 28, 1992. The project was based on the ultrasonic studies of natural and synthetic silicate melts, and the study of Brillouin scattering of synthetic silicates and oxides. Measurements of the compressional wave velocity and attenuation can be established using the ultrasonic methods. Temperature dependences of silicates can be established by the Brillouin scattering. (MB)

Manghnani, M.H.

1992-06-05T23:59:59.000Z

354

Nationwide, Regional, and Statewide Energy Supply Chain Optimization for Natural Gas to Liquid Transportation Fuel (GTL) Systems  

Science Journals Connector (OSTI)

When data on the well-specific production are available, the figures are grouped on the basis of the county of the wells. ... The states that have major natural gas productions are Alabama, Arkansas, California, Colorado, Kansas, Kentucky, Louisiana, Michigan, Mississippi, Montana, New Mexico, Ohio, Oklahoma, Pennsylvania, Texas, Utah, Virginia, West Virginia, and Wyoming. ... State of California Department of Conservation, Division of Oil, Gas & Geothermal Resources ...

Josephine A. Elia; Richard C. Baliban; Christodoulos A. Floudas

2013-09-05T23:59:59.000Z

355

E-Print Network 3.0 - aqueous tank waste Sample Search Results  

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

Summary: by tank truck. The various wastes, when received, are pumped to storage tanks, then blended to produce... of Liquid Fluid Wastes General Description Light...

356

Tank Waste Committee Page 1  

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

immobilizing liquid and slurry waste. Steve said bulk vitrification has a TRL of five, meaning there have been lab experiments and a similar system has been validated in a relevant...

357

Liquid natural gas as a transportation fuel in the heavy trucking industry. Final technical report, May 10, 1994--December 30, 1995  

SciTech Connect

This report encompasses the first year of a proposed three year project with emphasis focused on LNG research issues in Use of Liquid Natural Gas as a Transportation Fuel in the Heavy Trucking Industry. These issues may be categorized as (i) direct diesel replacement with LNG fuel, and (ii) long term storage/utilization of LNG vent gases produced by tank storage and fueling/handling operation. Since this work was for fundamental research in a number of related areas to the use of LNG as a transportation fuel for long haul trucking, many of those results have appeared in numerous refereed journal and conference papers, and significant graduate training experiences (including at least one M.S. thesis and one Ph.D. dissertation) in the first year of this project. In addition, a potential new utilization of LNG fuel has been found, as a part of this work on the fundamental nature of adsorption of LNG vent gases in higher hydrocarbons; follow on research for this and other related applications and transfer of technology are proceeding at this time.

Sutton, W.H.

1995-12-31T23:59:59.000Z

358

Salt Waste Processing Facility Fact Sheet | Department of Energy  

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

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications EIS-0082-S2: Amended Record of Decision Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report EIS-0082-S2: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)

359

Summary of Natural Resources that Potentially Influence Human Intrusion at the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nye County, Nevada  

SciTech Connect

In 1993, Raytheon Services Nevada completed a review of natural resource literature and other sources to identify potentially exploitable resources and potential future land uses near the Area 5 Radioactive Waste Management Site (RWMS) of the Nevada Test Site (NTS), Nye County, Nevada, that could lead to future inadvertent human intrusion and subsequent release of radionuclides to the accessible environment. National Security Technologies, LLC, revised the original limited-distribution document to conform to current editorial standards and U.S. Department of Energy requirements for public release. The researchers examined the potential for future development of sand, gravel, mineral, petroleum, water resources, and rural land uses, such as agriculture, grazing, and hunting. The study was part of the performance assessment for Greater Confinement Disposal boreholes. Sand and gravel are not considered exploitable site resources because the materials are common throughout the area and the quality at the Area 5 RWMS is not ideal for typical commercial uses. Site information also indicates a very low mineral potential for the area. None of the 23 mining districts in southern Nye County report occurrences of economic mineral deposits in unconsolidated alluvium. The potential for oil and natural gas is low for southern Nye County. No occurrences of coal, tar sand, or oil shale on the NTS are reported in available literature. Several potential future uses of water were considered. Agricultural irrigation is impractical due to poor soils and existing water supply regulations. Use of water for geothermal energy development is unlikely because temperatures are too low for typical commercial applications using current technology. Human consumption of water has the most potential for cause of intrusion. The economics of future water needs may create a demand for the development of deep carbonate aquifers in the region. However, the Area 5 RWMS is not an optimal location for extraction of groundwater from the deep carbonate aquifer. Grazing and hunting are unlikely to be potential causes for inadvertent human intrusion into waste areas because of vegetation characteristics and lack of significant game animal populations.

NSTec Environmental Management

2007-06-01T23:59:59.000Z

360

Waste Inspection Tomography (WIT)  

SciTech Connect

Waste Inspection Tomography (WIT) provides mobile semi-trailer mounted nondestructive examination (NDE) and assay (NDA) for nuclear waste drum characterization. WIT uses various computed tomography (CT) methods for both NDE and NDA of nuclear waste drums. Low level waste (LLW), transuranic (TRU), and mixed radioactive waste can be inspected and characterized without opening the drums. With externally transmitted x-ray NDE techniques, WIT has the ability to identify high density waste materials like heavy metals, define drum contents in two- and three-dimensional space, quantify free liquid volumes through density and x-ray attenuation coefficient discrimination, and measure drum wall thickness. With waste emitting gamma-ray NDA techniques, WIT can locate gamma emitting radioactive sources in two- and three-dimensional space, identify gamma emitting isotopic species, identify the external activity levels of emitting gamma-ray sources, correct for waste matrix attenuation, provide internal activity approximations, and provide the data needed for waste classification as LLW or TRU. The mobile feature of WIT allows inspection technologies to be brought to the nuclear waste drum storage site without the need to relocate drums for safe, rapid, and cost-effective characterization of regulated nuclear waste. The combination of these WIT characterization modalities provides the inspector with an unprecedented ability to non-invasively characterize the regulated contents of waste drums as large as 110 gallons, weighing up to 1,600 pounds. Any objects that fit within these size and weight restrictions can also be inspected on WIT, such as smaller waste bags and drums that are five and thirty-five gallons.

Bernardi, R.T.

1995-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes  

SciTech Connect

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D`Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D`Amico, N. [ed.

1994-10-20T23:59:59.000Z

362

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

363

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site  

SciTech Connect

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01T23:59:59.000Z

364

Process removes Sr from nuclear wastes  

Science Journals Connector (OSTI)

Process removes Sr from nuclear wastes ... Scientists at Argonne National Laboratory have devised a chemical process for extracting and recovering strontium-90 from liquid nuclear wastes. ... Argonne chemist E. Philip Horwitz, head of the team, says it could be a significant aid in managing such radioactive wastes. ...

WARD WORTHY

1990-09-10T23:59:59.000Z

365

Waste-to-wheel analysis of anaerobic-digestion-based renewable natural gas pathways with the GREET model.  

SciTech Connect

In 2009, manure management accounted for 2,356 Gg or 107 billion standard cubic ft of methane (CH{sub 4}) emissions in the United States, equivalent to 0.5% of U.S. natural gas (NG) consumption. Owing to the high global warming potential of methane, capturing and utilizing this methane source could reduce greenhouse gas (GHG) emissions. The extent of that reduction depends on several factors - most notably, how much of this manure-based methane can be captured, how much GHG is produced in the course of converting it to vehicular fuel, and how much GHG was produced by the fossil fuel it might displace. A life-cycle analysis was conducted to quantify these factors and, in so doing, assess the impact of converting methane from animal manure into renewable NG (RNG) and utilizing the gas in vehicles. Several manure-based RNG pathways were characterized in the GREET (Greenhouse gases, Regulated Emissions, and Energy use in Transportation) model, and their fuel-cycle energy use and GHG emissions were compared to petroleum-based pathways as well as to conventional fossil NG pathways. Results show that despite increased total energy use, both fossil fuel use and GHG emissions decline for most RNG pathways as compared with fossil NG and petroleum. However, GHG emissions for RNG pathways are highly dependent on the specifics of the reference case, as well as on the process energy emissions and methane conversion factors assumed for the RNG pathways. The most critical factors are the share of flared controllable CH{sub 4} and the quantity of CH{sub 4} lost during NG extraction in the reference case, the magnitude of N{sub 2}O lost in the anaerobic digestion (AD) process and in AD residue, and the amount of carbon sequestered in AD residue. In many cases, data for these parameters are limited and uncertain. Therefore, more research is needed to gain a better understanding of the range and magnitude of environmental benefits from converting animal manure to RNG via AD.

Han, J.; Mintz, M.; Wang, M. (Energy Systems)

2011-12-14T23:59:59.000Z

366

Enterprise Assessments Operational Awareness Record, Waste Treatment and Immobilization Plant – December 2014  

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

Operational Awareness Record for the Observation of Waste Treatment and Immobilization Plant High Level Waste Facility Radioactive Liquid Waste Disposal System Hazards Analysis Activities (EA-WTP-HLW-2014-08-18(a))

367

Ferrocyanide tank waste stability  

SciTech Connect

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

368

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

The most influential national and international bodies providing recommendations on radiation protection are described, including the International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA). Protection philosophies and the ICRP general principles of radiation protection are discussed. Radioactive material regulations and sources of radiation are explained. Criteria of exemption from regulatory control are discussed with examples of exemption levels for naturally occurring and radioactive waste radionuclides. Clearance of both moderate and bulk amounts of materials from regulatory control is also explained, including examples of EU and the UK regulations. Dose limits recommended by the ICRP are given, as well as the main principles of control of radiation hazards. Nuclear waste classification schemes are outlined, including the IAEA classification scheme. A brief explanation of nuclear waste classes including exempt waste, very short-lived waste, very low-level waste, low-level waste, intermediate-level waste and high-level waste is given. Examples of waste classification schemes are given, including that of the UK.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

369

EIA responds to Nature article on shale gas projections  

Annual Energy Outlook 2012 (EIA)

Crude oil, gasoline, heating oil, diesel, propane, and other liquids including biofuels and natural gas liquids. Natural Gas Exploration and reserves, storage, imports and...

370

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

371

NDAA Section 3116 Waste Determinations with Related Disposal...  

Office of Environmental Management (EM)

The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste) are Office of River Protection and...

372

The Gibbs free energy of mixing of natural silicate liquids; an expanded regular solution approximation for the calculation of magmatic intensive variables  

Science Journals Connector (OSTI)

The compositions of liquids coexisting with experimentally grown crystals of olivine, plagioclase, clinopyroxene, orthopyroxene, leucite, spinel, rhombohedral oxide, melilite and potassium feldspar are used to de...

Mark S. Ghiorso; Ian S. E. Carmichael…

1983-11-01T23:59:59.000Z

373

Secondary Waste Forms and Technetium Management  

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

Secondary Waste Forms and Secondary Waste Forms and Technetium Management Joseph H. Westsik, Jr. Pacific Northwest National Laboratory EM HLW Corporate Board Meeting November 18, 2010 What are Secondary Wastes? Process condensates and scrubber and/or off-gas treatment liquids from the pretreatment and ILAW melter facilities at the Hanford WTP. Sent from WTP to the Effluent Treatment Facility (ETF) for treatment and disposal Treated liquid effluents under the ETF State Wastewater Discharge Permit Solidified liquid effluents under the Dangerous Waste Permit for disposal at the Integrated Disposal Facility (IDF) Solidification Treatment Unit to be added to ETF to provide capacity for WTP secondary liquid wastes 2 Evaporator Condensate Solution Evaporator Pretreatment Melter SBS/ WESP Secondary

374

Natural Gas Liquids Reserves Sales  

Gasoline and Diesel Fuel Update (EIA)

03 442 440 931 670 282 2000-2008 03 442 440 931 670 282 2000-2008 Federal Offshore U.S. 84 59 35 104 41 27 2000-2008 Pacific (California) 0 0 0 0 0 0 2000-2008 Louisiana & Alabama 77 57 34 84 40 27 2000-2008 Texas 7 2 1 20 1 0 2000-2008 Alaska 0 0 0 0 0 0 2000-2008 Lower 48 States 403 442 440 931 670 282 2000-2008 Alabama 4 5 14 17 4 0 2000-2008 Arkansas 0 0 0 0 0 0 2000-2008 California 2 5 8 17 7 0 2000-2008 Coastal Region Onshore 0 0 0 7 0 0 2000-2008 Los Angeles Basin Onshore 1 0 0 2 0 0 2000-2008 San Joaquin Basin Onshore 1 5 8 8 7 0 2000-2008 State Offshore 0 0 0 0 0 0 2000-2008 Colorado 10 71 33 70 22 21 2000-2008 Florida 0 0 0 0 1 0 2000-2008 Kansas 12 8 2 1 3 1 2000-2008 Kentucky 0 0 0 21 0 0 2000-2008

375

Natural Gas Plant Liquids Production  

Gasoline and Diesel Fuel Update (EIA)

Production Production (Million Barrels) Period: Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes 2006 2007 2008 2009 2010 2011 View History U.S. 629 650 667 714 745 784 1979-2011 Alabama 3 2 7 5 6 6 1979-2011 Alaska 14 13 13 13 11 11 1979-2011 Arkansas 0 0 0 0 0 0 1979-2011 California 11 11 11 11 10 10 1979-2011 Coastal Region Onshore 1 1 1 1 1 1 1979-2011 Los Angeles Basin Onshore 0 0 0 0 0 0 1979-2011 San Joaquin Basin Onshore 10 10 10 10 9 9 1979-2011 State Offshore 0 0 0 0 0 0 1979-2011 Colorado 26 27 38 48 58 63 1979-2011 Florida 0 0 0 0 0 0 1979-2011 Kansas 18 18 18 16 16 16 1979-2011 Kentucky 3 3 3 4 5 4 1979-2011 Louisiana

376

Natural Gas Liquids Estimated Production  

Gasoline and Diesel Fuel Update (EIA)

802 827 788 811 831 840 1979-2008 802 827 788 811 831 840 1979-2008 Federal Offshore U.S. 148 155 123 125 127 94 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 120 127 98 102 108 80 1981-2008 Texas 28 28 25 23 19 14 1981-2008 Alaska 18 18 17 14 13 13 1979-2008 Lower 48 States 784 809 771 797 818 827 1979-2008 Alabama 5 4 5 5 4 9 1979-2008 Arkansas 0 0 0 0 0 0 1979-2008 California 10 10 11 11 11 11 1979-2008 Coastal Region Onshore 1 1 1 1 1 1 1979-2008 Los Angeles Basin Onshore 0 0 0 0 0 0 1979-2008 San Joaquin Basin Onshore 9 9 10 10 10 10 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 29 32 31 32 33 45 1979-2008 Florida 1 0 0 0 0 0 1979-2008 Kansas 23 22 20 19 19 19 1979-2008

377

Natural Gas Liquids Reserves Extensions  

Gasoline and Diesel Fuel Update (EIA)

629 734 863 924 1,030 956 1979-2008 629 734 863 924 1,030 956 1979-2008 Federal Offshore U.S. 33 44 29 31 36 29 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 30 43 27 26 25 24 1981-2008 Texas 3 1 2 5 11 5 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States 629 734 863 924 1,030 956 1979-2008 Alabama 5 2 1 3 2 2 1979-2008 Arkansas 0 0 0 0 1 0 1979-2008 California 2 5 5 8 1 4 1979-2008 Coastal Region Onshore 0 1 0 1 0 0 1979-2008 Los Angeles Basin Onshore 0 2 0 0 0 0 1979-2008 San Joaquin Basin Onshore 2 2 5 7 1 4 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 33 29 51 54 67 70 1979-2008 Florida 0 0 0 0 0 0 1979-2008 Kansas 4 3 5 6 7 4 1979-2008 Kentucky 2 4 3 1 13 7 1979-2008

378

Natural Gas Liquids Reserves Extensions  

Gasoline and Diesel Fuel Update (EIA)

629 734 863 924 1,030 956 1979-2008 629 734 863 924 1,030 956 1979-2008 Federal Offshore U.S. 33 44 29 31 36 29 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 30 43 27 26 25 24 1981-2008 Texas 3 1 2 5 11 5 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States 629 734 863 924 1,030 956 1979-2008 Alabama 5 2 1 3 2 2 1979-2008 Arkansas 0 0 0 0 1 0 1979-2008 California 2 5 5 8 1 4 1979-2008 Coastal Region Onshore 0 1 0 1 0 0 1979-2008 Los Angeles Basin Onshore 0 2 0 0 0 0 1979-2008 San Joaquin Basin Onshore 2 2 5 7 1 4 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 33 29 51 54 67 70 1979-2008 Florida 0 0 0 0 0 0 1979-2008 Kansas 4 3 5 6 7 4 1979-2008 Kentucky 2 4 3 1 13 7 1979-2008

379

Natural Gas Liquids Reserves Adjustments  

Gasoline and Diesel Fuel Update (EIA)

-338 273 -89 173 -139 76 1979-2008 -338 273 -89 173 -139 76 1979-2008 Federal Offshore U.S. -101 119 26 47 -7 -29 1981-2008 Pacific (California) 0 0 0 1 0 1 1979-2008 Louisiana & Alabama -93 118 29 44 -3 -32 1981-2008 Texas -8 1 -3 2 -4 2 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States -338 273 -89 173 -139 76 1979-2008 Alabama -2 -5 0 9 -13 76 1979-2008 Arkansas -1 0 0 2 -2 -1 1979-2008 California 11 9 -6 8 0 5 1979-2008 Coastal Region Onshore 1 1 -3 5 -7 1 1979-2008 Los Angeles Basin Onshore -1 0 0 0 1 2 1979-2008 San Joaquin Basin Onshore 11 8 -3 3 6 2 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado -38 55 -19 -14 -23 120 1979-2008 Florida 4 -5 -5 -2 -2 -1 1979-2008 Kansas 3 32 -25 8 -9 5 1979-2008

380

Natural Gas Liquids Reserves Acquisitions  

Gasoline and Diesel Fuel Update (EIA)

33 554 596 1,048 771 332 2000-2008 33 554 596 1,048 771 332 2000-2008 Federal Offshore U.S. 61 68 41 97 45 26 2000-2008 Pacific (California) 0 0 0 0 0 0 2000-2008 Louisiana & Alabama 58 66 37 72 44 25 2000-2008 Texas 3 2 4 25 1 1 2000-2008 Alaska 0 0 0 0 0 0 2000-2008 Lower 48 States 433 554 596 1,048 771 332 2000-2008 Alabama 4 0 28 5 16 1 2000-2008 Arkansas 0 0 0 0 0 0 2000-2008 California 2 7 10 18 10 1 2000-2008 Coastal Region Onshore 0 1 0 6 0 0 2000-2008 Los Angeles Basin Onshore 1 0 1 5 0 0 2000-2008 San Joaquin Basin Onshore 1 6 9 7 10 1 2000-2008 State Offshore 0 0 0 0 0 0 2000-2008 Colorado 13 69 49 62 10 40 2000-2008 Florida 0 0 0 0 0 0 2000-2008 Kansas 12 11 3 1 3 1 2000-2008 Kentucky 0 0 0 26 0 0 2000-2008

Note: This page contains sample records for the topic "liquid wastes natural" 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

Natural Gas Liquids Estimated Production  

Gasoline and Diesel Fuel Update (EIA)

802 827 788 811 831 840 1979-2008 802 827 788 811 831 840 1979-2008 Federal Offshore U.S. 148 155 123 125 127 94 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 120 127 98 102 108 80 1981-2008 Texas 28 28 25 23 19 14 1981-2008 Alaska 18 18 17 14 13 13 1979-2008 Lower 48 States 784 809 771 797 818 827 1979-2008 Alabama 5 4 5 5 4 9 1979-2008 Arkansas 0 0 0 0 0 0 1979-2008 California 10 10 11 11 11 11 1979-2008 Coastal Region Onshore 1 1 1 1 1 1 1979-2008 Los Angeles Basin Onshore 0 0 0 0 0 0 1979-2008 San Joaquin Basin Onshore 9 9 10 10 10 10 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 29 32 31 32 33 45 1979-2008 Florida 1 0 0 0 0 0 1979-2008 Kansas 23 22 20 19 19 19 1979-2008

382

Natural Gas Liquids Reserves Sales  

Gasoline and Diesel Fuel Update (EIA)

03 442 440 931 670 282 2000-2008 03 442 440 931 670 282 2000-2008 Federal Offshore U.S. 84 59 35 104 41 27 2000-2008 Pacific (California) 0 0 0 0 0 0 2000-2008 Louisiana & Alabama 77 57 34 84 40 27 2000-2008 Texas 7 2 1 20 1 0 2000-2008 Alaska 0 0 0 0 0 0 2000-2008 Lower 48 States 403 442 440 931 670 282 2000-2008 Alabama 4 5 14 17 4 0 2000-2008 Arkansas 0 0 0 0 0 0 2000-2008 California 2 5 8 17 7 0 2000-2008 Coastal Region Onshore 0 0 0 7 0 0 2000-2008 Los Angeles Basin Onshore 1 0 0 2 0 0 2000-2008 San Joaquin Basin Onshore 1 5 8 8 7 0 2000-2008 State Offshore 0 0 0 0 0 0 2000-2008 Colorado 10 71 33 70 22 21 2000-2008 Florida 0 0 0 0 1 0 2000-2008 Kansas 12 8 2 1 3 1 2000-2008 Kentucky 0 0 0 21 0 0 2000-2008

383

The effect of concentration on the structure and crystallinity of a cementitious waste form for caustic wastes  

SciTech Connect

Cement-based waste forms have long been considered economical technologies for disposal of various types of waste. A solidified cementitious waste form, Cast Stone, was developed to immobilize the radioactive secondary waste from vitrification processes. In this work, Cast Stone was considered for a Na-based caustic liquid waste, and its physical properties were analyzed as a function of liquid waste loading up to 2 M Na. Differences in crystallinity (phase composition), microstructure, mesostructure (pore size distribution, surface area), and macrostructure (density, compressive strength) were investigated using various analytical techniques, in order to assess the suitability of Cast Stone as a chemically durable waste. It was found that the concentration of secondary waste simulant (caustic waste) had little effect on the relevant engineering properties of Cast Stone, showing that Cast Stone could be an effective and tolerant waste form for a wide range of concentrations of high sodium waste.

Chung, Chul-Woo; Turo, Laura A.; Ryan, Joseph V.; Johnson, Bradley R.; McCloy, John S.

2013-06-01T23:59:59.000Z

384

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...4). Although disposal of HLW remains...for long-term disposal is through deep...successful waste-disposal program has eluded...geologic repository at Yucca Mountain, Nevada. Authorized...Administration withdrew funding for Yucca Mountain...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

385

In: . Proceedings of the 91st Annual Meeting (held June 14-18 in San Diego, CA), Air and Waste Management Association, Pittsburgh, Pennsylvania, June 1998 (CD-ROM). 1998 H.C. Frey  

E-Print Network (OSTI)

natural gas, petroleum residuals, petroleum coke, refinery wastes, and coal as inputs. In recent years 27695-7908 ABSTRACT Gasification systems, such as coal-based integrated gasification combined cycle there is currently a lack of high-value markets for low-value liquid residues and coke.(2) Integrated Gasification

Frey, H. Christopher

386

Natural convection in high heat flux tanks at the Hanford Waste Site / [by] Mark van der Helm and Mujid S. Kazimi  

E-Print Network (OSTI)

A study was carried out on the potential for natural convection and the effect of natural convection in a High Heat Flux Tank, Tank 241-C-106, at the Hanford Reservation. To determine the existence of natural convection, ...

Van der Helm, Mark Johan, 1972-

1996-01-01T23:59:59.000Z

387

HLW Glass Waste Loadings  

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

HLW HLW Glass Waste Loadings Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC Overview Overview  Vitrification - general background  Joule heated ceramic melter (JHCM) technology  Factors affecting waste loadings  Waste loading requirements and projections  WTP DWPF  DWPF  Yucca Mountain License Application requirements on waste loading  Summary Vitrification  Immobilization of waste by conversion into a glass  Internationally accepted treatment for HLW  Why glass?  Amorphous material - able to incorporate a wide spectrum of elements over wide ranges of composition; resistant to radiation damage  Long-term durability - natural analogs Relatively simple process - amenable to nuclearization at large  Relatively simple process - amenable to nuclearization at large scale  There

388

Lab optimizes burning of hazardous wastes  

Science Journals Connector (OSTI)

A new thermal destruction laboratory has gone into operation at Midwest Research Institute, Kansas City, Mo. The bench-scale facility, which can accommodate gram quantities of hazardous wastes in liquid, slurry, or solid forms, is used to determine ...

WARD WORTHY

1981-08-31T23:59:59.000Z

389

Estimating Waste Inventory and Waste Tank Characterization |...  

Office of Environmental Management (EM)

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

390

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a “nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

391

Waste Isolation Pilot Plant - Reports  

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

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

392

Radiation Chemistry of Ionic Liquids  

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

Liquids Liquids James F. Wishart, Alison M. Funston, and Tomasz Szreder in "Molten Salts XIV" Mantz, R. A., et al., Eds.; The Electrochemical Society, Pennington, NJ, (2006) pp. 802-813. [Information about the volume (look just above this link)] Abstract: Ionic liquids have potentially important applications in nuclear fuel and waste processing, energy production, improving the efficiency and safety of industrial chemical processes, and pollution prevention. Successful use of ionic liquids in radiation-filled environments will require an understanding of ionic liquid radiation chemistry. For example, characterizing the primary steps of ionic liquid radiolysis will reveal radiolytic degradation pathways and suggest ways to prevent them or mitigate their effects on the properties of the material

393

Review of High Level Waste Tanks Ultrasonic Inspection Data  

SciTech Connect

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

Wiersma, B

2006-03-09T23:59:59.000Z

394

Waste Treatment Plant - 12508  

SciTech Connect

The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration equipment, cesium-ion exchange columns, evaporator boilers and recirculation pumps, and various mechanical process pumps for transferring process fluids. During the first phase of pretreatment, the waste will be concentrated using an evaporation process. Solids will be filtered out, and the remaining soluble, highly radioactive isotopes will be removed using an ion-exchange process. The high-level solids will be sent to the High-Level Waste (HLW) Vitrification Facility, and the low activity liquids will be sent to the Low-Activity Waste (LAW) Vitrification Facility for further processing. The high-level waste will be transferred via underground pipes to the HLW Facility from the Pretreatment Facility. The waste first arrives at the wet cell, which rests inside a black-cell area. The pretreated waste is transferred through shielded pipes into a series of melter preparation and feed vessels before reaching the melters. Liquids from various facility processes also return to the wet cell for interim storage before recycling back to the Pretreatment Facility. (authors)

Harp, Benton; Olds, Erik [US DOE (United States)

2012-07-01T23:59:59.000Z

395

ENVIROCARE OF UTAH: EXPANDING WASTE ACCEPTANCE CRITERIA TO PROVIDE LOW-LEVEL AND MIXED WASTE DISPOSAL OPTIONS  

SciTech Connect

Envirocare of Utah operates a low-level radioactive waste disposal facility 80 miles west of Salt Lake City in Clive, Utah. Accepted waste types includes NORM, 11e2 byproduct material, Class A low-level waste, and mixed waste. Since 1988, Envirocare has offered disposal options for environmental restoration waste for both government and commercial remediation projects. Annual waste receipts exceed 12 million cubic feet. The waste acceptance criteria (WAC) for the Envirocare facility have significantly expanded to accommodate the changing needs of restoration projects and waste generators since its inception, including acceptable physical waste forms, radiological acceptance criteria, RCRA requirements and treatment capabilities, PCB acceptance, and liquids acceptance. Additionally, there are many packaging, transportation, and waste management options for waste streams acceptable at Envirocare. Many subcontracting vehicles are also available to waste generators for both government and commercial activities.

Rogers, B.; Loveland, K.

2003-02-27T23:59:59.000Z

396

HEAT TRANSFER ANALYSIS FOR NUCLEAR WASTE SOLIDIFICATION CONTAINER  

SciTech Connect

The Nuclear Nonproliferation Programs Design Authority is in the design stage of the Waste Solidification Building (WSB) for the treatment and solidification of the radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility (PDCF) and Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The waste streams will be mixed with a cementitious dry mix in a 55-gallon waste container. Savannah River National Laboratory (SRNL) has been performing the testing and evaluations to support technical decisions for the WSB. Engineering Modeling & Simulation Group was requested to evaluate the thermal performance of the 55-gallon drum containing hydration heat source associated with the current baseline cement waste form. A transient axi-symmetric heat transfer model for the drum partially filled with waste form cement has been developed and heat transfer calculations performed for the baseline design configurations. For this case, 65 percent of the drum volume was assumed to be filled with the waste form, which has transient hydration heat source, as one of the baseline conditions. A series of modeling calculations has been performed using a computational heat transfer approach. The baseline modeling results show that the time to reach the maximum temperature of the 65 percent filled drum is about 32 hours when a 43 C initial cement temperature is assumed to be cooled by natural convection with 27 C external air. In addition, the results computed by the present model were compared with analytical solutions. The modeling results will be benchmarked against the prototypic test results. The verified model will be used for the evaluation of the thermal performance for the WSB drum. Detailed results and the cases considered in the calculations will be discussed here.

Lee, S.

2009-06-01T23:59:59.000Z

397

Example of a Risk-Based Disposal Approval: Solidification of Hanford Site Transuranic Waste  

SciTech Connect

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26, 2005 to June 9, 2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP. (authors)

Barnes, B.M.; Hyatt, J.E.; Martin, P.W.; Prignano, A.L. [Fluor Hanford, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

398

Liquid Fuels Market Module  

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

Liquid Fuels Market Module Liquid Fuels Market Module This page inTenTionally lefT blank 145 U.S. Energy Information Administration | Assumptions to the Annual Energy Outlook 2013 Liquid Fuels Market Module The NEMS Liquid Fuels Market Module (LFMM) projects petroleum product prices and sources of supply for meeting petroleum product demand. The sources of supply include crude oil (both domestic and imported), petroleum product imports, unfinished oil imports, other refinery inputs (including alcohols, ethers, esters, corn, biomass, and coal), natural gas plant liquids production, and refinery processing gain. In addition, the LFMM projects capacity expansion and fuel consumption at domestic refineries. The LFMM contains a linear programming (LP) representation of U.S. petroleum refining

399

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams  

SciTech Connect

This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)] [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States)] [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)] [Univ. of Tennessee, Knoxville, TN (United States)

1994-01-01T23:59:59.000Z

400

Process for removing sulfate anions from waste water  

DOE Patents (OSTI)

A liquid emulsion membrane process for removing sulfate anions from waste water is disclosed. The liquid emulsion membrane process includes the steps of: (a) providing a liquid emulsion formed from an aqueous strip solution and an organic phase that contains an extractant capable of removing sulfate anions from waste water; (b) dispersing the liquid emulsion in globule form into a quantity of waste water containing sulfate anions to allow the organic phase in each globule of the emulsion to extract and absorb sulfate anions from the waste water and (c) separating the emulsion including its organic phase and absorbed sulfate anions from the waste water to provide waste water containing substantially no sulfate anions.

Nilsen, David N. (Lebanon, OR); Galvan, Gloria J. (Albany, OR); Hundley, Gary L. (Corvallis, OR); Wright, John B. (Albany, OR)

1997-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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

Estimating heat of combustion for waste materials  

SciTech Connect

Describes a method of estimating the heat of combustion of hydrocarbon waste (containing S,N,Q,C1) in various physical forms (vapor, liquid, solid, or mixtures) when the composition of the waste stream is known or can be estimated. Presents an equation for predicting the heat of combustion of hydrocarbons containing some sulfur. Shows how the method is convenient for estimating the heat of combustion of a waste profile as shown in a sample calculation.

Chang, Y.C.

1982-11-01T23:59:59.000Z

402

Convergence of Regional Liquid Natural Gas (LNG) Prices : A review of regional LNG import prices using Engle Granger’s Cointegration approach.  

E-Print Network (OSTI)

??This thesis investigates the bivariate long term stochastic relationship between the import Liquefied Natural Gas (LNG) prices in Japan, USA and EU. The bivariate testing… (more)

Eliston, Anton Jayanand

2009-01-01T23:59:59.000Z

403

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents (OSTI)

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

404

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2  

SciTech Connect

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

Jacobsen, P.H.

1997-09-23T23:59:59.000Z

405

Experimental and modeling results for reconsolidation of crushed natural rock salt under varying physical conditions: Applications to nuclear waste isolation in bedded and domal salt formations  

SciTech Connect

Mined salt from the underground facility at the Waste Isolation Pilot Plant (WIPP) Project is a candidate material for use as backfill around the waste packages and in the underground openings during and after the operational phase. We have conducted a series of hydrostatic and triaxial compression experiments on the time-dependent compaction behavior of crushed salt under nominally dry, damp,'' (0.5-5 wt % added water), and brine-saturated conditions. Though the compaction of dry crushed salt is very slow in the laboratory, damp salt is likely to compact as rapidly as the mine walls can converge. Drained tests on brine-saturated crushed salt indicate that, though effects associated with saturation do retard consolidation rates slightly, high fractional densities ({ge}0.95) can still be obtained on laboratory times scales at pressures below lithostatic at the WIPP. Triaxial compression experiments indicate that small deviatoric stresses have little impact on consolidation rates. Micromechanical models for the compaction of dry and damp crushed salt, based on isostatic hot-pressing models, are discussed. 14 refs., 4 figs.

Zeuch, D.H.; Holcomb, D.J.

1991-01-01T23:59:59.000Z

406

Revision 08 (08/10) Form G Radioactive Waste Disposal Form  

E-Print Network (OSTI)

Revision 08 (08/10) Form G Radioactive Waste Disposal Form RS - 19g Proc. 9290, 9501 General Instructions: 1. Do not mix different waste forms together. Keep dry, liquid, and scintillation vials separate. 2. Do not mix waste of different isotopes. 3. Entries are to be made on this form each time waste

Nair, Sankar

407

Synthesis of three advanced biofuels from ionic liquid-pretreated switchgrass using engineered Escherichia coli  

Science Journals Connector (OSTI)

...and yard waste, respectively...for yard waste control strain...pCellulose on plant biomass treated...liquid pre-treatment . Biofuel...Insights into plant cell wall degradation...bioenergy systems . Biofuels Bioprod...2010 ) An integrated catalytic approach...

Gregory Bokinsky; Pamela P. Peralta-Yahya; Anthe George; Bradley M. Holmes; Eric J. Steen; Jeffrey Dietrich; Taek Soon Lee; Danielle Tullman-Ercek; Christopher A. Voigt; Blake A. Simmons; Jay D. Keasling

2011-01-01T23:59:59.000Z

408

Hanford Site waste management and environmental restoration integration plan  

SciTech Connect

The Hanford Site Waste Management and Environmental Restoration Integration Plan'' describes major actions leading to waste disposal and site remediation. The primary purpose of this document is to provide a management tool for use by executives who need to quickly comprehend the waste management and environmental restoration programs. The Waste Management and Environmental Restoration Programs have been divided into missions. Waste Management consists of five missions: double-shell tank (DST) wastes; single-shell tank (SST) wastes (surveillance and interim storage, stabilization, and isolation); encapsulated cesium and strontium; solid wastes; and liquid effluents. Environmental Restoration consists of two missions: past practice units (PPU) (including characterization and assessment of SST wastes) and surplus facilities. For convenience, both aspects of SST wastes are discussed in one place. A general category of supporting activities is also included. 20 refs., 14 figs., 7 tabs.

Merrick, D.L.

1990-04-30T23:59:59.000Z

409

Waste-to-Energy Workshop Agenda  

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

The Bioenergy Technologies Office (BETO) at the Department of Energy aims to identify and address key technical barriers to the commercial deployment of liquid transportation fuels from waste feedstocks. As a part of this effort, BETO is organizing a Waste-to-Energy Roadmapping workshop. Workshop participants will join facilitated breakout sessions to discuss anaerobic digestion, hydrothermal liquefaction, and other processes that make productive use of wastewater residuals, biosolids, foodstuffs, and organic municipal solid waste. These discussions will be synthesized and used in developing a waste-to-energy technology roadmap.

410

VALUING FLARED NATURAL GAS  

Science Journals Connector (OSTI)

LAST YEAR , enough natural gas to supply 27% of U.S. needs was burned off as waste around the world, according to a new report by the World Bank. Flared natural gas is a by-product of petroleum production and is not generally considered worth capture and ...

2007-09-10T23:59:59.000Z

411

Appendix C Selected Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

Recurring Recurring Natural Gas Reports * Natural Gas Monthly, DOE/EIA-0130. Published monthly. Other Reports Covering Natural Gas, Natural Gas Liquids, and Other Energy Sources * Monthly Energy Review, DOE/EIA-0035. Published monthly. Provides national aggregate data for natural gas, natural gas liquids, and other energy sources. * Short-Term Energy Outlook, DOE/EIA-0202. Published quarterly. Provides forecasts for next six quarters for natural gas and other energy sources. * Natural Gas 1996: Issues and Trends, DOE/EIA- 0560(96), December 1996. * U.S. Crude Oil, Natural Gas, and Natural Gas Liquids Reserves -1996 Annual Report, DOE/EIA-0216(96)/Ad- vance Summary, September 1997. * Annual Energy Review 1996, DOE/ EIA-0384(96), July 1997. Published annually. * State Energy Data Report, Consumption Estimates, 1960- 1994, DOE/EIA-0214(94), October 1996. * Annual

412

Method for solidification of radioactive and other hazardous waste  

DOE Patents (OSTI)

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

413

E-Print Network 3.0 - acid liquid radioactive Sample Search Results  

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

WASHINGTON, D.C. 20460 Summary: radioactive wastes in liquid or solid forms. Oil and gas production, as an example, also results... a radioactive source, plus radioactive...

414

ProClim-Flash | No 57, June 201318 Figure 1: Swiss CH4 fluxes from (a) anthropogenic (agriculture, energy, waste) and (b) natural contributors (wetlands, lakes and  

E-Print Network (OSTI)

April 2013 under the United Nations Framework Convention on Climate Change and under the Kyoto Protocol layers representing CH4 emissions from wastewater treatment and natural sources and sinks (Figure 1b by the CCES projects ENHANCE, www.cces.ethz.ch/ projects/sulu/ENHANCE, and BioChange, www.cces.ethz.ch/projects/clench/BioChange

415

A Case for Molecular Recognition in Nuclear Separations: Sulfate Separation from Nuclear Wastes  

Science Journals Connector (OSTI)

In this paper, we present the case for molecular-recognition approaches for sulfate removal from radioactive wastes via the use of anion-sequestering systems selective for sulfate, using either liquid–liquid extraction or crystallization. Potential ...

Bruce A. Moyer; Radu Custelcean; Benjamin P. Hay; Jonathan L. Sessler; Kristin Bowman-James; Victor W. Day; Sung-Ok Kang

2012-11-07T23:59:59.000Z

416

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect

This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

VOLKMAN, D.D.

1999-10-27T23:59:59.000Z

417

TRU waste-sampling program  

SciTech Connect

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of /sup 238/Pu- and /sup 239/Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with /sup 239/Pu-contaminated waste, but three 8-month-old drums of /sup 238/Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs.

Warren, J.L.; Zerwekh, A.

1985-08-01T23:59:59.000Z

418

Displacing Natural Gas Consumption and Lowering Emissions  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

fuels and thereby reduce their natural gas consumption. Opportunity gas fuels include biogas from animal and agri- cultural wastes, wastewater plants, and landfills, as well as...

419

Categorical Exclusion 4565, Waste Management Construction Support  

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

FornI FornI Project Title: Waste Management Construction Support (4565) Program or Program Office: Y -12 Site Office Location: Oak Ridge Tennessee Project Description: This work scope is an attempt to cover the general activities that construction would perform in support of Waste Management activities. Work includes construction work performed in support of Waste Management Sustainability and Stewardship projects and programs to include: load waste into containers; open, manipulate containers; empty containers; decommission out-of-service equipment (includes removal of liquids, hazardous, and universal wastes); apply fabric and gravel to ground; transport equipment; transport materials; transport waste; remove vegetation; place barriers; place erosion controls; operate wheeled and tracked equipment; general carpentry. Work will be performed on dirt, vegetated, graveled, or paved surfaces in

420

Thermal Pretreatment For TRU Waste Sorting  

SciTech Connect

Japan Atomic Energy Agency conducted a study on thermal treatment of TRU waste to develop a removal technology for materials that are forbidden for disposal. The thermal pretreatment in which hot nitrogen and/or air is introduced to the waste is a process of removing combustibles, liquids, and low melting point metals from PVC wrapped TRU waste. In this study, thermal pretreatment of simulated waste was conducted using a desktop thermal treatment vessel and a laboratory scale thermal pretreatment system. Combustibles and low melting point metals are effectively separated from wastes by choosing appropriate temperature of flowing gases. Combustibles such as papers, PVC, oil, etc. were removed and low melting point metals such as zinc, lead, and aluminum were separated from the simulated waste by the thermal pretreatment. (authors)

Sasaki, T.; Aoyama, Y.; Miyamoto, Y.; Yamaguchi, H. [Japan Atomic Energy Agency, Tokai-mura, Ibaraki (Japan)

2008-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes natural" 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.


421

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect

A study of a database system that can manage radioactive waste collectively on a network has been carried out. A conceptual data modeling that is based on the theory of information engineering (IE), which is the first step of the whole database development, has been studied to manage effectively information and data related to radioactive waste. In order to establish the scope of the database, user requirements and system configuration for radioactive waste management were analyzed. The major information extracted from user requirements are solid waste, liquid waste, gaseous waste, and waste related to spent fuel. The radioactive waste management system is planning to share information with associated companies.

Park, H.S; Shon, J.S; Kim, K.J; Park, J.H; Hong, K.P; Park, S.H

2003-02-27T23:59:59.000Z

422

The Venezuelan natural gas industry  

SciTech Connect

Venezuela's consumption energy of comes from three primary sources: hydroelectricity, liquid hydrocarbons and natural gas. In 1986, the energy consumption in the internal market was 95.5 thousand cubic meters per day of oil equivalent, of which 32% was natural gas, 46% liquid hydrocarbons and 22% hydroelectricity. The Venezuelan energy policy established natural gas usage after hydroelectricity, as a substitute of liquid hydrocarbons, in order to increase exports of these. This policy permits a solid development of the natural gas industry, which is covered in this paper.

Silva, P.V.; Hernandez, N.

1988-01-01T23:59:59.000Z

423

Waste Reduction plan for Oak Ridge National Laboratory  

SciTech Connect

Oak Ridge National Laboratory (ORNL) is a multipurpose research and development (R D) facility owned and operated by the Department of Energy (DOE) and managed under subcontract by Martin Marietta Energy Systems (Energy Systems), Inc. ORNL R D activities generate numerous small waste streams. In the hazardous waste category alone, over 300 streams of a diverse nature exist. Generation avoidance, reduction or recycling of wastes is an important goal in maintaining efficiency of ORNL R D activities and protection of workers, the public, and the environment. Waste minimization is defined as any action that minimizes or eliminates the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution and inventory management, process modification, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction activities.

Not Available

1991-12-01T23:59:59.000Z

424

Waste Reduction plan for Oak Ridge National Laboratory  

SciTech Connect

Oak Ridge National Laboratory (ORNL) is a multipurpose research and development (R&D) facility owned and operated by the Department of Energy (DOE) and managed under subcontract by Martin Marietta Energy Systems (Energy Systems), Inc. ORNL R&D activities generate numerous small waste streams. In the hazardous waste category alone, over 300 streams of a diverse nature exist. Generation avoidance, reduction or recycling of wastes is an important goal in maintaining efficiency of ORNL R&D activities and protection of workers, the public, and the environment. Waste minimization is defined as any action that minimizes or eliminates the volume or toxicity of waste by avoiding its generation or recycling. This is accomplished by material substitution and inventory management, process modification, or recycling wastes for reuse. Waste reduction is defined as waste minimization plus treatment which results in volume or toxicity reduction. The ORNL Waste Reduction Program will include both waste minimization and waste reduction activities.

Not Available

1991-12-01T23:59:59.000Z

425

A fermi liquid electric structure and the nature of the carriers in high-T/sub c/ cuprates: A photoemission study  

SciTech Connect

We have performed angle-integrated and angle-resolved photoemission measurements at 20 K on well-characterized single crystals of high-T/sub c/ cuprates (both 1:2:3-type and 2:2:1:2-type) cleaved in situ, and find a relatively large, resolution limited Fermi edge which shows large amplitude variations with photon energy, indicative of band structure final state effects. The lineshapes of the spectra of the 1:2:3 materials as a function of photon energy are well reproduced by band structure predictions, indicating a correct mix of 2p and 3d orbitals on the calculations, while the energy positions of the peaks agree with calculated bands only to within /approx/0.5 eV. This may yet prove to reflect the effects of Coulomb correlation. We nevertheless conclude that a Fermi liquid approach to conductivity is appropriate. Angle-resolved data, while still incomplete, suggest agreement with the Fermi surface predicted by the LDA calculations. A BCS-like energy gap is observed in the 2:2:1:2 materials, whose magnitude is twice the weak coupling BCS value (i.e., 2/Delta/ = 7 KT/sub c/). 49 refs., 11 figs.

Arko, A.J.; List, R.S.; Bartlett, R.J.; Cheong, S.W.; Fisk, Z.; Thompson, J.D.; Olson, C.G.; Yang, A.B.; Liu, R.; Gu, C.; Veal, B.W.; Liu, J.Z.; Paulikas, A.P.; Vandervoort, K.; Claus, H.; Campuzano, J.C.; Schirber, J.E.; Shinn, N.D.

1989-01-01T23:59:59.000Z

426

Microsoft PowerPoint - S05-05_Zapp_Liquid Air Interface.ppt  

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

Liquid-Air Interface Corrosion Studies at SRS Liquid-Air Interface Corrosion Studies at SRS EM Waste Processing Technical Exchange 2010 Philip E. Zapp Savannah River National Laboratory November 17, 2010 SRNL-STI-2010-00695 Print Close 2 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Introduction Pitting Corrosion in Carbon Steel Waste Tanks Pitting Induced by Dilute Waste Solutions Dilution for feed preparation for vitrification; waste removal Focus: Pitting Susceptibility at Liquid-Air Interface Service Experience Hydroxide Depletion Model Type III tanks under constr. Tank with ventilation & cooling equip. Print Close 3 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Background Pitting in carbon steel at and above liquid-air interface in dilute wastes ([Nitrate] < 1 M)

427

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH){sub 4} to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set. 4 figs.

Wagh, A.S.; Singh, D.

1997-07-08T23:59:59.000Z

428

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH).sub.4 to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set.

Wagh, Arun S. (Joliet, IL); Singh, Dileep (Westmont, IL)

1997-01-01T23:59:59.000Z

429

Liquid natural gas as a transportation fuel in the heavy trucking industry. Fourth quarterly progress report, April 1, 1995--June 30, 1995  

SciTech Connect

This project encompasses the first year of a proposed three year project with emphasis focused on LNG research issues that may be categorized as direct diesel replacement with LNG fuel, and long term storage/utilization of LNG vent gases produced by tank storage and fueling/handling operation. In addition, a potential new utilization of LNG fuel has been found, as a part of this work on the fundamental nature of adsorption of LNG vent gases in higher hydrocarbons; follow on research for this and other related applications and transfer of technology are proceeding at this time.

Sutton, W.H.

1995-09-01T23:59:59.000Z

430

Integrated plant for treatment of liquid radwaste  

SciTech Connect

In the early 1980`s, AECL Research, at its Chalk River Laboratories (CRL) site, built a Waste Treatment Centre for managing low-level radioactive aqueous liquid wastes. At present, two industrial liquid waste streams are being routinely treated. One stream originates from the central Decontamination Centre (DC), where reactor components, protective plastic clothing, and respirators are cleaned. The other Active Drain (AD) stream is produced from a large and diverse number of research laboratories and radioisotope production facilities. The two waste streams, totalling about 2500 m per year (0.66 million US gallons), are volume reduced by a combination of continuous crossflow microfiltration (MF), spiral wound reverse osmosis (SWRO), and tubular reverse osmosis (TRO) membrane technologies; two thin-film evaporators (TFE) are employed for (i) the final volume reduction step, and (ii) the subsequent solidification of evaporator bottom with bitumen for containment of the radioactivity.

Sen Gupta, S.K. [Chalk River Laboratories, Ontario (Canada)

1995-05-01T23:59:59.000Z

431

Preventing Alzheimer's disease by means of natural selection  

Science Journals Connector (OSTI)

...Alzheimer's disease|natural selection|neuroenergetics...context of the amyloid cascade model. These features...solids, liquids and gases). Thermodynamic entropy...process, thus turning natural selection to our patients...matter-solid, liquid or gas. The quantity describes...

2015-01-01T23:59:59.000Z

432

liquids | EMSL  

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

leads are available at this time. Iodine Solubility in Low-Activity Waste Borosilicate Glass at 1000 °C. Abstract: The purpose of this study was to determine the solubility of...

433

Utilization of waste heat stream in distillation  

SciTech Connect

Cost of separation can be reduced by utilizing all available energy streams at various temperature levels. In the simplest case a waste energy heat stream can be used to partially vaporize a liquid feed stream. A more beneficial process involves an entire evaporation of a portion of the feed and introducing it into a column below the liquid portion of the feed. One can also use the waste energy stream as a heating medium in an intermediate reboiler in the column. There is, however, a limit to the amount of the waste energy that can be utilized in each case, beyond which this approach is no longer beneficial. Detailed analysis of the waste heat utilization enables one to determine this limit and compare each of these flowsheet options.

Fidkowski, Z.T.; Agrawal, R. [Air Products and Chemicals, Inc., Allentown, PA (United States)

1995-04-01T23:59:59.000Z

434

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton...

435

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

436

Imaging and Characterizing the Waste Materials Inside an Underground Storage Tank Using Seismic Normal Modes  

SciTech Connect

It is necessary to know something about the nature of the wastes in a Hanford underground storage tank (UST) so that the correct hardware can be inserted into a tank for sampling, sluicing, or pumping operations. It is also important to know if a layer of gas exists beneath solid and liquid layers of waste. Given that the tank will have only one liquid observation well (LOW), the authors examined the information that could be obtained from the natural seismic vibrations of a tank as a whole; that is, the normal modes of that tank. As in the case of a bell, the natural vibration, or normal modes, of a tank depend on many things, including the construction of the tank, the kinds of waste materials in the tank, the amount of each material in the tank, and where the energy is placed that excites the vibrations (i.e., where you will ''hit'' the tank). The nature of a normal mode of vibration can be given by its frequency and amplitude. For any given frequency, the amplitude of vibration can be given as a function of position in and around the tank. Since they assumed that one would be ''listening'' to a tank from locations along a LOW, they show their computed amplitudes as a function of position inside and around the tank, and in the case of the physical models they display the observations along various lines inside the tank model. This allowed us to see the complex geometry of each mode of oscillation as a function of increasing frequency.

M. N. Toksoz; R. M. Turpening

1999-09-14T23:59:59.000Z

437

Recycling of CdTe photovoltaic waste  

DOE Patents (OSTI)

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate and electrolyzing the leachate to separate Cd from Te, wherein the Te is deposits onto a cathode while the Cd remains in solution.

Goozner, Robert E. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Drinkard, Jr., William F. (Charlotte, NC)

1999-01-01T23:59:59.000Z

438

H-Tank Farm Waste Determination | Department of Energy  

Office of Environmental Management (EM)

(SRS) in South Carolina to complete cleanup and closure of the underground liquid waste tanks in the H Tank Farm as they are emptied and cleaned. The action marked a major...

439

Office of Enterprise Assessments Review of the Hanford Site Waste...  

Energy Savers (EERE)

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

440

Independent Oversight Review of the Hanford Site Waste Treatment...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

of liquid or semi-solid radioactive and chemical waste stored in 177 underground tanks at the Hanford Site. ORP serves as DOE line management for two functions: the Tank...

Note: This page contains sample records for the topic "liquid wastes natural" 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.


441

Integrated Waste Treatment Facility Fact Sheet | Department of...  

Office of Environmental Management (EM)

is designed to treat 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility located at DOE's Idaho...

442

Drilling Waste Management Fact Sheet: Slurry Injection of Drilling Wastes  

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

Slurry Injection Slurry Injection Fact Sheet - Slurry Injection of Drilling Wastes Underground Injection of Drilling Wastes Several different approaches are used for injecting drilling wastes into underground formations for permanent disposal. Salt caverns are described in a separate fact sheet. This fact sheet focuses on slurry injection technology, which involves grinding or processing solids into small particles, mixing them with water or some other liquid to make a slurry, and injecting the slurry into an underground formation at pressures high enough to fracture the rock. The process referred to here as slurry injection has been given other designations by different authors, including slurry fracture injection (this descriptive term is copyrighted by a company that provides slurry injection services), fracture slurry injection, drilled cuttings injection, cuttings reinjection, and grind and inject.

443

Tank Waste Corporate Board Meeting 11/06/08 | Department of Energy  

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

11/06/08 11/06/08 Tank Waste Corporate Board Meeting 11/06/08 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 6th, 2008. Note: (Please contact Steven Ross at steven.ross@em.doe.gov for a HLW Glass Waste Loadings version with animations on slide 6). Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop The Way Ahead - West Valley Demonstration Project High-Level Liquid Waste Tank Integrity Workshop - 2008 Savannah River Tank Waste Residuals Hanford Tank Waste Residuals HLW Glass Waste Loadings High-Level Waste Corporate Board Performance Assessment Subcommittee More Documents & Publications Tank Waste Corporate Board Meeting 11/18/10 System Planning for Low-Activity Waste at Hanford Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

444

Independent Oversight Review, Waste Isolation Pilot Plant - November...  

Energy Savers (EERE)

Safety and Security (HSS), conducted an independent review of the U.S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) preparedness for severe natural phenomena...

445

Regulation of Natural Gas (Texas)  

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

This legislation provides for the protection of public and private interests with regards to natural gas production, prohibits waste, and compels ratable production to enable owners of gas in a...

446

Chapter 30 Waste Management: General Administrative Procedures (Kentucky) |  

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

Chapter 30 Waste Management: General Administrative Procedures Chapter 30 Waste Management: General Administrative Procedures (Kentucky) Chapter 30 Waste Management: General Administrative Procedures (Kentucky) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Retail Supplier Rural Electric Cooperative State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Solar Buying & Making Electricity Wind Program Info State Kentucky Program Type Environmental Regulations Provider Department for Environmental Protection The waste management administrative regulations apply to the disposal of solid waste and the management of all liquid, semisolid, solid, or gaseous

447

WASTE TO WATTS Waste is a Resource!  

E-Print Network (OSTI)

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From Waste to Energy To Energy from Waste #12;9.00-9.30: Registration 9.30-9.40: Chairman Ella Stengler opens

Columbia University

448

Oversight Reports - Waste Isolation Pilot Plant | Department of Energy  

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

Oversight Reports - Waste Isolation Pilot Plant Oversight Reports - Waste Isolation Pilot Plant Oversight Reports - Waste Isolation Pilot Plant April 22, 2013 Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities November 28, 2012 Independent Oversight Review, Waste Isolation Pilot Plant - November 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant September 28, 2011 Independent Activity Report, Waste Isolation Pilot Plant - September 2011 Orientation Visit to the Waste Isolation Pilot Plant [HIAR-WIPP-2011-09-07] October 2, 2002 Independent Oversight Inspection, Waste Isolation Pilot Plant, Summary Report - August 2002 Inspection of Environment, Safety, and Health and Emergency Management at

449

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01T23:59:59.000Z

450

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31T23:59:59.000Z

451

November 8, 1983: Defense Waste Processing Facility | Department of Energy  

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

November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983 The Department begins construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant in South Carolina. DWPF is designed to make high-level nuclear waste into a glass-like substance, which will then be shipped to a repository. DWPF will mix borosilicate glass with the waste, heat it to 2000 degrees F, and pour the mixture into stainless steel canisters. The mixture will cool into solid glass that can be permanently stored. DWPF will immobilize the more than 34 million gallons of liquid high-level waste that have accumulated from producing defense-related nuclear materials

452

Solid Waste Program (Alabama) | Department of Energy  

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

Program (Alabama) Program (Alabama) Solid Waste Program (Alabama) < Back Eligibility Commercial Construction Developer General Public/Consumer Industrial Residential Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations This article states the authority of the department, regulations for the control of unauthorized dumping, disposal fees, violations and penalties. Solid waste refers to any garbage, rubbish, construction or demolition debris, ash, or sludge from a waste treatment facility, water supply plant, or air pollution control facility, and any other discarded materials, including solid, liquid, semisolid, or contained gaseous material resulting

453

Waste management project fiscal year 1998 multi-year work plan WBS 1.2  

SciTech Connect

The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

Slaybaugh, R.R.

1997-08-29T23:59:59.000Z

454

Savannah River Site sample and analysis plan for Clemson Technical Center waste  

SciTech Connect

The purpose of this sampling and analysis plan is to determine the chemical, physical and radiological properties of the SRS radioactive Polychlorinated Biphenyl (PCB) liquid waste stream, to verify that it conforms to Waste Acceptance Criteria of the Department of Energy (DOE) East Tennessee Technology Park (ETTP) Toxic Substance Control Act (TSCA) Incineration Facility. Waste being sent to the ETTP TSCA Incinerator for treatment must be sufficiently characterized to ensure that the waste stream meets the waste acceptance criteria to ensure proper handling, classification, and processing of incoming waste to meet the Waste Storage and Treatment Facility`s Operating Permits. This sampling and analysis plan is limited to WSRC container(s) of homogeneous or multiphasic radioactive PCB contaminated liquids generated in association with a treatability study at Clemson Technical Center (CTC) and currently stored at the WSRC Solid Waste Division Mixed Waste Storage Facility (MWSF).

Hagstrom, T.

1998-04-01T23:59:59.000Z

455

Aluminum Reactions and Problems in Municipal Solid Waste Landfills  

E-Print Network (OSTI)

Aluminum Reactions and Problems in Municipal Solid Waste Landfills G. Vincent Calder, Ph.D.1 ; and Timothy D. Stark, Ph.D., P.E., F.ASCE2 Abstract: Aluminum enters municipal solid waste MSW landfills from problematic for landfill operations by generating undesirable heat, liquid leachate, and gases

456

A3. Natural Gas  

Gasoline and Diesel Fuel Update (EIA)

Natural Natural Gas Processed and Liquids Extracted at Natural Gas Processing Plants by State, 1996 Table Plant Location Volume of Natural Gas Delivered to Processing Plants a (million cubic feet) Total Liquids Extracted b (thousand barrels) Extraction Loss (million cubic feet) State Production Out of State Production Natural Gas Processed Alabama..................................... 111,656 1,212 112,868 4,009 5,361 Alaska ........................................ 2,987,364 0 2,987,364 33,346 38,453 Arkansas.................................... 214,868 4,609 219,477 383 479 California.................................... 240,566 0 240,566 9,798 12,169 Colorado .................................... 493,748 215 493,963 16,735 23,362 Florida........................................ 5,900 2,614 8,514 1,630 1,649 Illinois.........................................

457

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970`s, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-12-31T23:59:59.000Z

458

DWPF waste form compliance plan (Draft Revision)  

SciTech Connect

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan.

Plodinec, M.J.; Marra, S.L.

1991-01-01T23:59:59.000Z

459

EIS-0063: Waste Management Operations, Double-Shell Tanks for Defense High Level Radioactive Waste Storage, Hanford Site, Richland, Washington  

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

The U.S. Department of Energy developed this statement to evaluate the existing tank design and consider additional specific design and safety feature alternatives for the thirteen tanks being constructed for storage of defense high-level radioactive liquid waste at the Hanford Site in Richland, Washington. This statement supplements ERDA-1538, "Final Environmental Statement on Waste Management Operation."

460

Waste Disposal (Illinois)  

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

This article lays an outline of waste disposal regulations, permits and fees, hazardous waste management and underground storage tank requirements.

Note: This page contains sample records for the topic "liquid wastes natural" 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.


461

Solid Waste Policies (Iowa) | Department of Energy  

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

Policies (Iowa) Policies (Iowa) Solid Waste Policies (Iowa) < Back Eligibility Agricultural Commercial Fuel Distributor Industrial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Tribal Government Utility Program Info State Iowa Program Type Environmental Regulations Provider Iowa Department of Natural Resources This statute establishes the support of the state for alternative waste management practices that reduce the reliance upon land disposal and incorporate resource recovery. Cities and counties are required to establish and operate a comprehensive solid waste reduction program. These regulations discuss land application of processed wastes as well as requirements for sanitary landfills and for groundwater monitoring near land disposal sites

462

Waste minimization/pollution prevention study of high-priority waste streams  

SciTech Connect

Although waste minimization has been practiced by the Metals and Ceramics (M&C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division`s pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M&C staff members empowered by the Division Director to study specific waste streams.

Ogle, R.B. [comp.

1994-03-01T23:59:59.000Z

463

Idaho National Engineering Laboratory nonradiological waste management information for 1994 and record to date  

SciTech Connect

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1994. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

French, D.L.; Lisee, D.J.; Taylor, K.A.

1995-08-01T23:59:59.000Z

464

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1992 and record to date  

SciTech Connect

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1992. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

Randall, V.C.; Sims, A.M.

1993-08-01T23:59:59.000Z

465

Idaho National Engineering Laboratory Nonradiological Waste Management Information for 1993 and record to date  

SciTech Connect

This document provides detailed data and graphics on airborne and liquid effluent releases, fuel oil and coal consumption, water usage, and hazardous and mixed waste generated for calendar year 1993. This report summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Nonradiological Waste Management Information System.

Sims, A.M.; Taylor, K.A.

1994-08-01T23:59:59.000Z

466

Synergic and conflicting issues in planning underground use to produce energy in densely populated countries, as Italy: Geological storage of CO2, natural gas, geothermics and nuclear waste disposal  

Science Journals Connector (OSTI)

In densely populated countries there is a growing and compelling need to use underground for different and possibly coexisting technologies to produce “low carbon” energy. These technologies include (i) clean coal combustion merged with CO2 Capture and Storage (CCS); (ii) last-generation nuclear power or, in any case, safe nuclear wastes disposal, both “temporary” and “geological” somewhere in Europe (at least in one site): Nuclear wastes are not necessarily associated to nuclear power plants; (iii) safe natural gas (CH4) reserves to allow consumption also when the foreign pipelines are less available or not available for geopolitical reasons and (iv) “low-space-consuming” renewables in terms of Energy Density Potential in Land (EDPL measured in [GW h/ha/year]) as geothermics. When geothermics is exploited as low enthalpy technology, the heat/cool production could be associated, where possible, to increased measures of “building efficiency”, low seismic risks building reworking and low-enthalpy heat managing. This is undispensable to build up “smart cities”. In any case the underground geological knowledge is prerequisite. All these technologies have been already proposed and defined by the International Energy Agency (IEA) Road Map 2009 as priorities for worldwide security: all need to use underground in a rational and safe manner. The underground is not renewable in most of case histories [10,11]. IEA recently matched and compared different technologies in a unique “Clean Energy Economy” improved document (Paris, November 16–17, 2011), by the contribution of this vision too (see reference). In concert with “energy efficiency” improvement both for plants and buildings, in the frame of the “smart cities” scenarios, and the upstanding use of “energy savings”, the energetic planning on regional scale where these cities are located, are strategic for the year 2050: this planning is strongly depending by the underground availability and typology. Therefore, if both literature and European Policy are going fast to improve the concept of “smart cities” this paper stresses the concept of “smart regions”, more strategic than “smart cities”, passing throughout a discussion on the synergic and conflicting use of underground to produce energy for the “smart regions” as a whole. The paper highlights the research lines which are urgent to plan the soundest energy mix for each region by considering the underground performances case by case: a worldwide mapping, by GIS tools of this kind of information could be strategic for all the “world energy management” authorities, up to ONU, with its Intergovernmental Panel on Climate Change (IPCC), the G20, the Carbon Sequestration Leadership Forum (CSLF) and the European Platforms such as the “Zero Emissions Fossil Fuel Power Plants” (EU-ZEP Platform), the Steel Platform, the Biomass Platform too. All of these organizations agree on the need for synergistic and coexistent uses of underground for geological storage of CO2, CH4, nuclear waste and geothermic exploitation. The paper is therefore a discussion of the tools, methods and approaches to these underground affecting technologies, after a gross view of the different uses of underground to produce energy for each use, with their main critical issues (i.e. public acceptance in different cases). The paper gives some gross evaluation for the Lazio Region and some hints from the Campania Region, located in Central Italy. Energy Density Potential in Land (EDPL), is calculated for each renewable energy technology (solar, wind, geothermal) highlighting the potentiality of the last. Why the Italian case history among the densely populated countries? on the Italian territory is hard to find suitable areas (mostly if greenfields) to use the own underground, with respect to other European countries, due to the presence of seismotectonic activity and many faulted areas characterized by Diffuse Degassing Structures (DDSs, which are rich in CO2 and CH4). In this cases, public acceptan

Fedora Quattrocchi; Enzo Boschi; Angelo Spena; Mauro Buttinelli; Barbara Cantucci; Monia Procesi

2013-01-01T23:59:59.000Z

467

Geochemical aspects of radioactive waste disposal  

SciTech Connect

The book addresses various topics related to the geochemistry of waste disposal: natural radioactivity, kinds of radioactive waste, details of possible disposal sites, low-level waste, uranium mill tailing, natural analogs, waste forms, and engineered barriers. Emphasis throughout is on the importance of natural analogs, the behavior of elements resembling those to be put in a waste repository as they occur in natural situations where the temperature, pressure, and movement of ground water are similar to those expected near a repository. The author is convinced that conclusions drawn from the study of analog elements are directly applicable to predictions about radionuclide behavior, and that the observed near-immobility of most of these elements in comparable geologic environments is good evidence that radioactive waste can be disposed of underground with negligible effects on the biosphere. Much of his own research has been in this area, and the best parts of the book are the descriptions of his work on trace elements in the salt minerals at the Waste Isolation Pilot Plant in southeastern New Mexico, on the movement of radionuclides and their daughter elements from the famous Precambrian reactor at Oklahoma in Gabon, and on the distribution of analog elements in rocks near the contacts of igneous intrusions.

Brookins, D.G.

1984-01-01T23:59:59.000Z

468

Technology of high-level nuclear waste disposal. Advances in the science and engineering of the management of high-level nuclear wastes. Volume 1  

SciTech Connect

The papers in this volume cover the following subjects: waste isolation and the natural geohydrologic system; repository perturbations of the natural system; radionuclide migration through the natural system; and repository design technology. Individual papers are abstracted.

Hofmann, P.L.; Breslin, J.J. (eds.)

1981-01-01T23:59:59.000Z

469

Waste Treatment and Immobilation Plant HLW Waste Vitrification...  

Office of Environmental Management (EM)

Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Full Document and Summary Versions...

470

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency left intentionally blank.] #12;Prepared for the U.S. Department of Energy PNNL-SA-69994 under Contract DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL

471

Ferrocyanide tank waste stability. Supplement 2  

SciTech Connect

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

472

Hanford Waste Physical and Rheological Properties: Data and Gaps  

SciTech Connect

The Hanford Site in Washington State manages 177 underground storage tanks containing approximately 250,000 m3 of waste generated during past defense reprocessing and waste management operations. These tanks contain a mixture of sludge, saltcake and supernatant liquids. The insoluble sludge fraction of the waste consists of metal oxides and hydroxides and contains the bulk of many radionuclides such as the transuranic components and 90Sr. The saltcake, generated by extensive evaporation of aqueous solutions, consists primarily of dried sodium salts. The supernates consist of concentrated (5-15 M) aqueous solutions of sodium and potassium salts. The 177 storage tanks include 149 single-shell tanks (SSTs) and 28 double -hell tanks (DSTs). Ultimately the wastes need to be retrieved from the tanks for treatment and disposal. The SSTs contain minimal amounts of liquid wastes, and the Tank Operations Contractor is continuing a program of moving solid wastes from SSTs to interim storage in the DSTs. The Hanford DST system provides the staging location for waste feed delivery to the Department of Energy (DOE) Office of River Protection’s (ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP is being designed and constructed to pretreat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks.

Wells, Beric E.; Kurath, Dean E.; Mahoney, Lenna A.; Onishi, Yasuo; Huckaby, James L.; Cooley, Scott K.; Burns, Carolyn A.; Buck, Edgar C.; Tingey, Joel M.; Daniel, Richard C.; Anderson, K. K.

2011-08-01T23:59:59.000Z

473

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

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

NDAA Section NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Section 3116 is currently only applicable to Idaho National Laboratory (INL) and the Savannah River Site (SRS). The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste)

474

Oklahoma Hazardous Waste Management Act (Oklahoma) | Department of Energy  

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

Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) < Back Eligibility Agricultural Construction Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Oklahoma Program Type Environmental Regulations Provider Oklahoma Department of Environmental Quality A hazardous waste facility permit from the Department of Environmental Quality is required to store, treat or dispose of hazardous waste materials, or to construct, own or operate any facility engaged in the operation of storing, treating or disposing of hazardous waste or storing recyclable materials. The Department shall not issue a permit for the treatment, disposal or temporary storage of any liquid hazardous waste in a

475

EIS-0217: Savannah River Site Waste Management | Department of Energy  

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

17: Savannah River Site Waste Management 17: Savannah River Site Waste Management EIS-0217: Savannah River Site Waste Management Summary This EIS evaluates the potential environmental impacts and costs of storing, treating, and/or disposing of liquid high-level radioactive, low-level radioactive, hazardous, mixed (radioactive and hazardous), and transuranic wastes at SRS. Public Comment Opportunities None available at this time. Documents Available for Download June 28, 2001 EIS-0217: Amended Record of Decision Savannah River Site Waste Management, Savannah River Operations Office, Aiken, South Carolina May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management, Savannah River Operations Office,

476

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

477

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

478

Natural Gas Liquids New Field Discoveries  

Gasoline and Diesel Fuel Update (EIA)

35 26 32 16 30 65 1979-2008 35 26 32 16 30 65 1979-2008 Federal Offshore U.S. 25 7 21 6 24 22 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 25 7 21 6 13 22 1981-2008 Texas 0 0 0 0 11 0 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States 35 26 32 16 30 65 1979-2008 Alabama 0 0 0 0 0 0 1979-2008 Arkansas 0 0 0 0 0 0 1979-2008 California 0 0 0 0 0 0 1979-2008 Coastal Region Onshore 0 0 0 0 0 0 1979-2008 Los Angeles Basin Onshore 0 0 0 0 0 0 1979-2008 San Joaquin Basin Onshore 0 0 0 0 0 0 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 0 4 1 0 0 0 1979-2008 Florida 0 0 0 0 0 0 1979-2008 Kansas 0 0 0 0 0 0 1979-2008 Kentucky 0 0 1 0 0 0 1979-2008 Louisiana 0 0 0 1 0 3 1981-2008

479

Natural Gas Liquids New Field Discoveries  

Gasoline and Diesel Fuel Update (EIA)

35 26 32 16 30 65 1979-2008 35 26 32 16 30 65 1979-2008 Federal Offshore U.S. 25 7 21 6 24 22 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 25 7 21 6 13 22 1981-2008 Texas 0 0 0 0 11 0 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States 35 26 32 16 30 65 1979-2008 Alabama 0 0 0 0 0 0 1979-2008 Arkansas 0 0 0 0 0 0 1979-2008 California 0 0 0 0 0 0 1979-2008 Coastal Region Onshore 0 0 0 0 0 0 1979-2008 Los Angeles Basin Onshore 0 0 0 0 0 0 1979-2008 San Joaquin Basin Onshore 0 0 0 0 0 0 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 0 4 1 0 0 0 1979-2008 Florida 0 0 0 0 0 0 1979-2008 Kansas 0 0 0 0 0 0 1979-2008 Kentucky 0 0 1 0 0 0 1979-2008 Louisiana 0 0 0 1 0 3 1981-2008

480

Natural Gas Liquids Reserves Revision Increases  

Gasoline and Diesel Fuel Update (EIA)

882 1,232 968 845 1,187 1,192 1979-2008 882 1,232 968 845 1,187 1,192 1979-2008 Federal Offshore U.S. 118 148 114 118 116 85 1981-2008 Pacific (California) 0 0 0 0 0 0 1979-2008 Louisiana & Alabama 89 104 89 99 90 71 1981-2008 Texas 29 44 25 19 26 14 1981-2008 Alaska 0 0 0 0 0 0 1979-2008 Lower 48 States 882 1,232 968 845 1,187 1,192 1979-2008 Alabama 8 4 2 5 2 9 1979-2008 Arkansas 0 0 0 0 0 0 1979-2008 California 12 22 31 8 16 12 1979-2008 Coastal Region Onshore 1 3 2 3 2 1 1979-2008 Los Angeles Basin Onshore 1 0 1 0 1 0 1979-2008 San Joaquin Basin Onshore 10 19 28 5 13 11 1979-2008 State Offshore 0 0 0 0 0 0 1979-2008 Colorado 51 72 55 34 105 93 1979-2008 Florida 0 0 0 0 2 0 1979-2008 Kansas 11 44 12 44 22 19 1979-2008

Note: This page contains sample records for the topic "liquid wastes natural" 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.


481

Waste Processing | Department of Energy  

Office of Environmental Management (EM)

Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Centers Cask Processing Enclosure. Workers process and repackage waste at...

482

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

483

Thermal Predictions of the Cooling of Waste Glass Canisters  

SciTech Connect

Radioactive liquid waste from five decades of weapons production is slated for vitrification at the Hanford site. The waste will be mixed with glass forming additives and heated to a high temperature, then poured into canisters within a pour cave where the glass will cool and solidify into a stable waste form for disposal. Computer simulations were performed to predict the heat rejected from the canisters and the temperatures within the glass during cooling. Four different waste glass compositions with different thermophysical properties were evaluated. Canister centerline temperatures and the total amount of heat transfer from the canisters to the surrounding air are reported.

Donna Post Guillen

2014-11-01T23:59:59.000Z

484

Secondary Waste Form Development and Optimization—Cast Stone  

SciTech Connect

Washington River Protection Services is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF is a Resource Conservation and Recovery Act-permitted, multi-waste, treatment and storage unit and can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid wastes generated during operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The STU to ETF will provide the additional capacity needed for ETF to process the increased volume of secondary wastes expected to be produced by WTP.

Sundaram, S. K.; Parker, Kent E.; Valenta, Michelle M.; Pitman, Stan G.; Chun, Jaehun; Chung, Chul-Woo; Kimura, Marcia L.; Burns, Carolyn A.; Um, Wooyong; Westsik, Joseph H.

2011-07-14T23:59:59.000Z

485

Co-processing of agricultural and biomass waste with coal  

SciTech Connect

A major thrust of our research program is the use of waste materials as co-liquefaction agents for the first-stage conversion of coal to liquid fuels. By fulfilling one or more of the roles of an expensive solvent in the direct coal liquefaction (DCL) process, the waste material is disposed off ex-landfill, and may improve the overall economics of DCL. Work in our group has concentrated on co-liquefaction with waste rubber tires, some results from which are presented elsewhere in these Preprints. In this paper, we report on preliminary results with agricultural and biomass-type waste as co-liquefaction agents.

Stiller, A.H.; Dadyburjor, D.B.; Wann, Ji-Perng [West Virginia Univ., Morgantown, WV (United States)] [and others

1995-12-31T23:59:59.000Z