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Note: This page contains sample records for the topic "bulk waste removal" 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
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1

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

2

Removing nuclear waste, one shipment at a time  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way...

3

EM's SPRU Celebrates Waste Removal Success, Safety Milestone...  

Office of Environmental Management (EM)

EM's SPRU Celebrates Waste Removal Success, Safety Milestone EM's SPRU Celebrates Waste Removal Success, Safety Milestone February 27, 2014 - 12:00pm Addthis Members of the EM and...

4

1,153-ton Waste Vault Removed from 300 Area - Vault held waste...  

Energy Savers [EERE]

1,153-ton Waste Vault Removed from 300 Area - Vault held waste tanks with contamination from Hanford's former laboratory facilities 1,153-ton Waste Vault Removed from 300 Area -...

5

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

6

Lab sets new record for waste volume removed  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Lab Sets New Record for Waste Volume Removed Lab Sets New Record for Waste Volume Removed Community Connections: Our link to Northern New Mexico Communities Latest Issue:Dec. 2013 - Jan. 2014 All Issues » submit Lab sets new record for waste volume removed The Transuranic Waste Program has met its commitment to ship 800 cubic meters of TRU waste to the Waste Isolation Pilot Plant during fiscal year 2012. November 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office Kurt Steinhaus Email A lot of people worked together to make this happen, including our partners at the State of New Mexico and WIPP, as well as NNSA, the Los Alamos Site Office, and the Laboratory. The LANL Transuranic (TRU) Waste Program has met its commitment to ship 800 cubic meters of TRU waste to the Waste Isolation Pilot Plant (WIPP) during

7

Performance evaluation of the PITBULL{trademark} pump for the removal of hazardous waste  

SciTech Connect (OSTI)

One objective of the Waste Removal Project at the Department of Energy`s Savannah River Site (SRS) is to explore methods to successfully remove waste heels that will remain in the high-level waste tanks after bulk waste removal has been completed. Tank closure is not possible unless this residue is removed. As much as 151,000 liters of residue can remain after a conventional waste removal campaign. The waste heels can be comprised of sludge, zeolite, and silica. The heels are generally hardened or compacted insoluble particulate with relatively rapid settling velocities. A PITBULL{trademark} pump is being considered by SRS to retrieve sludge-type waste from Tank 19. Sections 1 through 4 of this report present the scope and objectives of the test program, describe the principles of operation of the PITBULL, and present the test approach, set-up, and instrumentation. Test results, including pumping rates with water and slurry, are provided in Section 5, along with considerations for remote operation. Conclusions and recommendations are provided in Section 6.

Hatchell, B.K.; Combs, W.H.; Hymas, C.R.; Powell, M.R.; Rinker, M.W.; White, M.

1998-09-01T23:59:59.000Z

8

Aluminum Removal from Photographic Waste Submitted to Dr. Tony Bi  

E-Print Network [OSTI]

Aluminum Removal from Photographic Waste Submitted to Dr. Tony Bi By: Kristen Favel, Tiffany Jung, and Kenny Tam CHBE 484 University of British Columbia April 15, 2009 #12;ii "Aluminum Removal from photographic waste has shown elevated levels of aluminum in the fixer, which exceed sewer discharge standards

9

Removing nuclear waste, one shipment at a time  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Stories » Stories » Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email "The milestone we're celebrating is one that has been a long-term environmental commitment." Removing nuclear waste, one shipment at a time Elected officials and other dignitaries recently gathered at Los Alamos

10

Microsoft PowerPoint - 3-03_pt 1_Davis_Waste Removal & Tank Closures.ppt  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Waste Removal & Tank Closure Waste Removal & Tank Closure New Technologies Neil Davis Deputy Program Manager Waste Removal & Tank Closure November 16, 2010 Print Close 2 * SRR baseline is to use 2 mechanical and 1 chemical technology on each tank - Large slurry mixer pumps - Hydrolancing/Robotic vacuum system - Oxalic acid * Technologies in hand * Incremental improvements to meet evolving mission needs and to have a defendable Maximum Extent Practical basis Point of View Print Close 3 Program Status Bulk Waste Removal Mechanical Heel Removal Chemical Cleaning Annulus Cleaning Isolation/Final Sampling Grout Tank Cooling Coil Flushing Tanks 4, 7, 9, 10, 11, 12, 13, 14, & 15 in progress 2 tanks closed 15 more in progress Tank 8 being prepped for chemical cleaning Tanks 5, 6 & 16 in progress Tanks 5&6 in progress

11

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

12

SPRU Removes High-Risk Radioactive Waste  

Broader source: Energy.gov [DOE]

NISKAYUNA, N.Y. EMs Separations Process Research Unit (SPRU) Disposition Project completed a significant waste-treatment campaign in February that involved the solidification of approximately 9,700 gallons of contaminated sludge and 14 shipments of the waste off-site for permanent disposal.

13

BULK VITRIFICATION TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect (OSTI)

This report is one of four reports written to provide background information regarding immobilization technologies under consideration for supplemental immobilization of Hanford's low-activity waste. This paper is intended to provide the reader with general understanding of Bulk Vitrification and how it might be applied to immobilization of Hanford's low-activity waste.

ARD KE

2011-04-11T23:59:59.000Z

14

TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 2 DF WASTE LINE REMOVAL, BNL  

SciTech Connect (OSTI)

5098-SR-02-0 PROJECT-SPECIFIC TYPE A VERIFICATION FOR THE HIGH FLUX BEAM REACTOR UNDERGROUND UTILITIES REMOVAL PHASE 2 DF WASTE LINE REMOVAL, BROOKHAVEN NATIONAL LABORATORY

P.C. Weaver

2010-07-09T23:59:59.000Z

15

Summary - Demonstration Bulk Vitrification System (DBVS) for Low-Actvity Waste at Hanford  

Broader source: Energy.gov (indexed) [DOE]

DBVS DBVS ETR Report Date: September 2006 ETR-3 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Demonstration Bulk Vitrification System (DBVS) for Low Activity Waste (LAW) at Hanford Why DOE-EM Did This Review The Department of Energy (DOE) is charged with the safe retrieval, treatment and disposal of 53 million gallons of Hanford radioactive waste. The Waste Treatment Plant (WTP) is being designed to treat and vitrify the High Level Waste (HLW) fraction in 20-25 years. The WTP is undersized for vitrifying the LAW fraction over the same time frame. The DOE is evaluating Bulk Vitrification as an alternative to increasing the size of the WTP LAW treatment process. Bulk vitrification is an in-container melting

16

Cesium removal from Savannah River Site radioactive waste using crystalline silicotitanate (IONSIV(R) IE-911)  

SciTech Connect (OSTI)

This study measured the ability of crystalline silicotitanate to remove cesium from Savannah River Site radioactive waste.

Walker, D.D.

1999-12-15T23:59:59.000Z

17

Laboratory simulation of salt dissolution during waste removal  

SciTech Connect (OSTI)

Laboratory experiments were performed to support the field demonstration of improved techniques for salt dissolution in waste tanks at the Savannah River Site. The tests were designed to investigate three density driven techniques for salt dissolution: (1) Drain-Add-Sit-Remove, (2) Modified Density Gradient, and (3) Continuous Salt Mining. Salt dissolution was observed to be a very rapid process as salt solutions with densities between 1.38-1.4 were frequently removed. Slower addition and removal rates and locating the outlet line at deeper levels below the top of the saltcake provided the best contact between the dissolution water and the saltcake. It was observed that dissolution with 1 M sodium hydroxide solution resulted in salt solutions that were within the current inhibitor requirements for the prevention of stress corrosion cracking. This result was independent of the density driven technique. However, if inhibited water (0.01 M sodium hydroxide and 0.011 M sodium nitrite) was utilized, the salt solutions were frequently outside the inhibitor requirements. Corrosion testing at conditions similar to the environments expected during waste removal was recommended.

Wiersma, B.J.; Parish, W.R.

1997-01-01T23:59:59.000Z

18

Evaluation of Technologies to Remove Suspended Solids from Waste Water  

SciTech Connect (OSTI)

The Effluent Treatment Facility (ETF) at the Savannah River Site utilizes pH adjustment, submicron filtration, Hg removal resin, activated carbon, reverse osmosis, cationic exchange, and evaporation to remove contaminants from radioactive waste water. After startup, the ETF had difficulty achieving design capacity. The primary problem was fouling of the ceramic microfilters. Typical filter flow rates were only 20 percent of design capacity.A research program was conducted to identify and evaluate technologies for improving suspended solids removal from radioactive wastewater at the Savannah River Site. Technolgies investigated were a ceramic microfilter, a tubular polymeric ultrafilter, two porous metal filters, a polymeric centrifugal ultrafilter, a deep bed filter, a backwashable cartridge filter, a fabric filter, and a centriguge.

Poirier, M.R.

1999-03-15T23:59:59.000Z

19

Mercury and tritium removal from DOE waste oils  

SciTech Connect (OSTI)

This work covers the investigation of vacuum extraction as a means to remove tritiated contamination as well as the removal via sorption of dissolved mercury from contaminated oils. The radiation damage in oils from tritium causes production of hydrogen, methane, and low-molecular-weight hydrocarbons. When tritium gas is present in the oil, the tritium atom is incorporated into the formed hydrocarbons. The transformer industry measures gas content/composition of transformer oils as a diagnostic tool for the transformers` condition. The analytical approach (ASTM D3612-90) used for these measurements is vacuum extraction of all gases (H{sub 2}, N{sub 2}, O{sub 2}, CO, CO{sub 2}, etc.) followed by analysis of the evolved gas mixture. This extraction method will be adapted to remove dissolved gases (including tritium) from the SRS vacuum pump oil. It may be necessary to heat (60{degrees}C to 70{degrees}C) the oil during vacuum extraction to remove tritiated water. A method described in the procedures is a stripper column extraction, in which a carrier gas (argon) is used to remove dissolved gases from oil that is dispersed on high surface area beads. This method appears promising for scale-up as a treatment process, and a modified process is also being used as a dewatering technique by SD Myers, Inc. (a transformer consulting company) for transformers in the field by a mobile unit. Although some mercury may be removed during the vacuum extraction, the most common technique for removing mercury from oil is by using sulfur-impregnated activated carbon (SIAC). SIAC is currently being used by the petroleum industry to remove mercury from hydrocarbon mixtures, but the sorbent has not been previously tested on DOE vacuum oil waste. It is anticipated that a final process will be similar to technologies used by the petroleum industry and is comparable to ion exchange operations in large column-type reactors.

Klasson, E.T. [Oak Ridge National Lab., TN (United States)

1997-10-01T23:59:59.000Z

20

Leach test of cladding removal waste grout using Hanford groundwater  

SciTech Connect (OSTI)

This report describes laboratory experiments performed during 1986-1990 designed to produce empirical leach rate data for cladding removal waste (CRW) grout. At the completion of the laboratory work, funding was not available for report completion, and only now during final grout closeout activities is the report published. The leach rates serve as inputs to computer codes used in assessing the potential risk from the migration of waste species from disposed grout. This report discusses chemical analyses conducted on samples of CRW grout, and the results of geochemical computer code calculations that help identify mechanisms involved in the leaching process. The semi-infinite solid diffusion model was selected as the most representative model for describing leaching of grouts. The use of this model with empirically derived leach constants yields conservative predictions of waste release rates, provided no significant changes occur in the grout leach processes over long time periods. The test methods included three types of leach tests--the American Nuclear Society (ANS) 16.1 intermittent solution exchange test, a static leach test, and a once-through flow column test. The synthetic CRW used in the tests was prepared in five batches using simulated liquid waste spiked with several radionuclides: iodine ({sup 125}I), carbon ({sup 14}C), technetium ({sup 99}Tc), cesium ({sup 137}Cs), strontium ({sup 85}Sr), americium ({sup 241}Am), and plutonium ({sup 238}Pu). The grout was formed by mixing the simulated liquid waste with dry blend containing Type I and Type II Portland cement, class F fly ash, Indian Red Pottery clay, and calcium hydroxide. The mixture was allowed to set and cure at room temperature in closed containers for at least 46 days before it was tested.

Serne, R.J.; Martin, W.J.; Legore, V.L.

1995-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron  

E-Print Network [OSTI]

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron John and reduction of pertechnetate anions (TcO4 -) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams

22

Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron  

E-Print Network [OSTI]

be to use a technetium ion- exchange or sorbent materialtechnetium problem is to remove pertechnetate from the waste using commercially available polymeric ion exchangetechnetium-containing eluate that would be generated in removing pertechnetate from the commercial ion-exchange

Darab, John

2008-01-01T23:59:59.000Z

23

Study on HCl removal for medical waste pyrolysis and combustion using a TG-FTIR analyzer  

Science Journals Connector (OSTI)

Under both pyrolysis and combustion condition, HCl removal efficiency for medical waste with Cabased additives was semi-quantitatively studied by means of ... TG-FTIR. Additionally, the difference of HCl removal ...

Hongmei Zhu; Weiying Chen; Xuguang Jiang

2014-02-01T23:59:59.000Z

24

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

SciTech Connect (OSTI)

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

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

2009-03-01T23:59:59.000Z

25

CHEMICAL REMOVAL OF BIOMASS FROM WASTE AIR BIOTRICKLING FILTERS: SCREENING OF CHEMICALS  

E-Print Network [OSTI]

CHEMICAL REMOVAL OF BIOMASS FROM WASTE AIR BIOTRICKLING FILTERS: SCREENING OF CHEMICALS for the removal of excess biomass from biotrickling ®lters for waste air treatment. Although the experiment/v) NaOH, 0.26 and 1.31% (w/v) NaClO and 11.3% (w/v) H2O2 resulted in a biomass removal signi

26

Bacterially mediated removal of phosphorus and cycling of nitrate and sulfate in the waste stream  

E-Print Network [OSTI]

with an increase in ammonia showing there had to be an additional P removal process at the same timeBacterially mediated removal of phosphorus and cycling of nitrate and sulfate in the waste stream sludge Phosphorus removal Denitrification Apatite formation Sulfur cycling a b s t r a c t Simultaneous

Benning, Liane G.

27

The Removal of Crude Oil in Waste Drilling Muds by a Constructed Microbial Consortium  

Science Journals Connector (OSTI)

Waste drilling muds (WDMs) contain serious pollutants produced by crude oil and gas well drilling. Bioremediation has been known as a useful ... enrichment of indigenous microorganisms, which can remove oil conta...

Yunkang Chang; Xingbiao Wang; Yifan Han

2014-01-01T23:59:59.000Z

28

Trichloroethene Removal From Waste Gases in Anaerobic Biotrickling Filters Through Reductive Dechlorination  

E-Print Network [OSTI]

reductive dechlorination of PCE. Environ. Sci. Technol 2003,588. Kim, J. O. Gaseous TCE and PCE removal by an activatedTsotsis, T. T. Degradation of PCE in an anaerobic waste gas

Popat, Sudeep Chandrakant

2010-01-01T23:59:59.000Z

29

Thiacrown polymers for removal of mercury from waste streams  

DOE Patents [OSTI]

Thiacrown polymers immobilized to a polystyrene-divinylbenzene matrix react with Hg.sup.2+ under a variety of conditions to efficiently and selectively remove Hg.sup.2+ ions from acidic aqueous solutions, even in the presence of a variety of other metal ions. The mercury can be recovered and the polymer regenerated. This mercury removal method has utility in the treatment of industrial wastewater, where a selective and cost-effective removal process is required.

Baumann, Theodore F. (Tracy, CA); Reynolds, John G. (San Ramon, CA); Fox, Glenn A. (Livermore, CA)

2002-01-01T23:59:59.000Z

30

Waste Biomass-Extracted Surfactants for Heavy Oil Removal  

Science Journals Connector (OSTI)

The potential synergism between biobased surfactants, produced from the alkaline extraction of waste biomass, and a synthetic surfactant was assessed. ... Since the principles of soil washing (critical Ca) were first developed for reservoir engineering, one expects that the ultralow (surfactant-enhanced oil recovery operations. ...

Matthew D. Baxter; Edgar Acosta; Enzo Montoneri; Silvia Tabasso

2014-02-03T23:59:59.000Z

31

Sequestering agents for the removal of actinides from waste streams  

SciTech Connect (OSTI)

The ultimate goal of this project is to develop new separation technologies to remove radioactive metal ions from contaminated DOE sites. To this end we are studying both the fundamental chemistry and the extractant properties of some chelators that are either found in nature or are closely related to natural materials. The work is a collaboration betwen Lawrence Berkeley National Laboratory-University of California, Berkeley, and the Glenn T. Seaborg Institute for Transactinium Science at Lawrence Livermore National Laboratory.

Raymond, K.; White, D. [Univ. of California, Berkeley, CA (United States); Whisenhunt, D. [Lawrence Livermore National Lab., CA (United States)

1996-10-01T23:59:59.000Z

32

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper (II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the orginal organic compounds, is subsequently blended with high level radioactive sludge and transferred to a virtrification facility for processing into borosilicate glass for long-term storage.

Doherty, Joseph P. (Elkton, MD); Marek, James C. (Augusta, GA)

1989-01-01T23:59:59.000Z

33

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper(II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the original organic compounds, is subsequently blended with high level radioactive sludge land transferred to a vitrification facility for processing into borosilicate glass for long-term storage. 2 figs., 3 tabs.

Doherty, J.P.; Marek, J.C.

1987-02-25T23:59:59.000Z

34

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

SciTech Connect (OSTI)

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

35

MODELING AN ION EXCHANGE PROCESS FOR CESIUM REMOVAL FROM ALKALINE RADIOACTIVE WASTE SOLUTIONS  

SciTech Connect (OSTI)

The performance of spherical Resorcinol-Formaldehyde ion-exchange resin for the removal of cesium from alkaline radioactive waste solutions has been investigated through computer modeling. Cesium adsorption isotherms were obtained by fitting experimental data using a thermodynamic framework. Results show that ion-exchange is an efficient method for cesium removal from highly alkaline radioactive waste solutions. On average, two 1300 liter columns operating in series are able to treat 690,000 liters of waste with an initial cesium concentration of 0.09 mM in 11 days achieving a decontamination factor of over 50,000. The study also tested the sensitivity of ion-exchange column performance to variations in flow rate, temperature and column dimensions. Modeling results can be used to optimize design of the ion exchange system.

Smith, F; Luther Hamm, L; Sebastian Aleman, S; Johnston Michael, J

2008-08-26T23:59:59.000Z

36

Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron  

SciTech Connect (OSTI)

The application of nanoparticles of predominantly zerovalent iron (nanoiron), either unsupported or supported, to the separation and reduction of pertechnetate anions (TcO4-) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams in general, the research discussed here was directed at two specific potential applications at the U.S. Department of Energy's Hanford Site: (1) the direct removal of pertechnetate from highly alkaline solutions, typical of those found in Hanford tank waste, and (2) the removal of dilute pertechnetate from near-neutral solutions, typical of the eluate streams from commercial organic ion-exchange resins that may be used to remediate Hanford tank wastes. It was envisioned that both applications would involve the subsequent encapsulation of the loaded sorbent material into a separate waste form. A high surface area (>200 M2/g) base-stable, nanocrystalline zirconia was used as a support for nanoiron for tests with highly alkaline solutions, while a silica gel support was used for tests with near-neutral solutions. It was shown that after 24 h of contact time, the high surface area zirconia supported nanoiron sorbent removed about 50percent (K-d = 370 L/kg) of the pertechnetate from a pH 14 tank waste simulant containing 0.51 mM TCO4- and large concentrations of Na+, OH-, NO3-, and CO32- for a phase ratio of 360 L simulant per kg of sorbent. It was also shown that after 18 h of contact time, the silica-supported nanoiron removed>95percent pertechnetate from a neutral pH eluate simulant containing 0.076 mM TcO4_ for a phase ratio of 290 L/kg. It was determined that in all cases, nanoiron reduced the Tc(VII) to Tc(IV), or possibly to Tc(V), through a redox reaction. Finally, it was demonstrated that a mixture of 20 mass percent of the solid reaction products obtained from contacting zirconia- supported nanoiron with an alkaline waste solution containing Re(VII), a surrogate for Tc(VII), with 80 mass percent alkali borosilicate based frit heat-treated at 700 degrees C for 4 h sintered into an easily handled glass composite waste form.

Darab, John; Amonette, Alexandra; Burke, Deborah; Orr, Robert; Ponder, Sherman; Schrick, Bettina; Mallouk, Thomas; Lukens, Wayne; Caulder, Dana; Shuh, David

2007-07-11T23:59:59.000Z

37

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

SciTech Connect (OSTI)

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

Jolly, R; Bruce Martin, B

2008-01-15T23:59:59.000Z

38

Characterization and Cadmium Ion-Removing Property of Adsorbents Synthesized from Inorganic Wastes  

Science Journals Connector (OSTI)

Adsorbents for removing cadmium ions from water were synthesized from inorganic wastes such as oyster shells, drinkingwater-treatment sludge (DWTS), and waste glass. The oyster shells and DWTS were pretreated by heating for 2 h at 1173 K before hydrothermal synthesis was started. The Al/(Al+Si) ratio was adjusted, and then, the mixture of pretreated materials was hydrothermally treated in a sodium hydroxide solution for 72 h at 423 K to synthesize the adsorbents. The synthesized adsorbent specimens were characterized by X-ray diffraction (XRD), thermogravimetric-differential thermal analysis (TG-DTA) measurements, and scanning electron microscopy (SEM). The main components of these specimens were aluminum-substituted tobermorite and sodalite. The formation of sodalite was dependent on the mass ratio of DWTS to glass. The maximum amount of cadmium ions were removed when the mass ratio of the pretreated material was 1:1:1. In the cadmium removal test, the adsorbent with this mass ratio removed almost 100% of the cadmium in a solution with a concentration of 10 mg L-1. Even in the presence of a 1000-fold excess of potassium ions or 10000-fold excess of sodium ions, approximately 80% of the cadmium ions were removed.

Kou Ooishi; Kana Ogino; Hiroshi Nishioka; Yasuji Muramatsu

2011-01-01T23:59:59.000Z

39

Hanford ETR Bulk Vitrification System - Demonstration Bulk Vitrification  

Broader source: Energy.gov (indexed) [DOE]

Bulk Vitrification System - Demonstration Bulk Bulk Vitrification System - Demonstration Bulk Vitrification System (DBVS) Review Report Hanford ETR Bulk Vitrification System - Demonstration Bulk Vitrification System (DBVS) Review Report Full Document and Summary Versions are available for download Hanford ETR Bulk Vitrification System - Demonstration Bulk Vitrification System (DBVS) Review Report Summary - Demonstration Bulk Vitrification System (DBVS) for Low-Actvity Waste at Hanford More Documents & Publications Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - November 2013 SRS Tank 48H Waste Treatment Project Technology Readiness Assessment External Technical Review for Evaluation of System Level Modeling and Simulation Tools in Support of Hanford Site Liquid Waste Process

40

REMOVAL OF CESIUM FROM SAVANNAH RIVER SITE WASTE WITH SPHERICAL RESORCINOL FORMALDEHYDE ION EXCHANGE RESIN EXPERIMENTAL TESTS  

SciTech Connect (OSTI)

A principal goal at the Savannah River Site (SRS) is to safely dispose of the large volume of liquid nuclear waste held in many storage tanks. In-tank ion exchange (IX) columns are being considered for cesium removal. The spherical form of resorcinol formaldehyde ion exchange resin (sRF) is being evaluated for decontamination of dissolved saltcake waste at SRS, which is generally lower in potassium and organic components than Hanford waste. The sRF performance with SRS waste was evaluated in two phases: resin batch contacts and IX column testing with both simulated and actual dissolved salt waste. The tests, equipment, and results are discussed.

Duignan, M.; Nash, C.

2010-03-31T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

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

SciTech Connect (OSTI)

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

42

PRELIMINARY ASSESSMENT OF THE LOW-TEMPERATURE WASTE FORM TECHNOLOGY COUPLED WITH TECHNETIUM REMOVAL  

SciTech Connect (OSTI)

The U.S. Department of Energy Office of Environmental Management (EM) is engaging the national laboratories to provide the scientific and technological rigor to support EM program and project planning, technology development and deployment, project execution, and assessment of program outcomes. As an early demonstration of this new responsibility, Pacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory (SRNL) have been chartered to implement a science and technology program addressing low-temperature waste forms for immobilization of DOE aqueous waste streams, including technetium removal as an implementing technology. As a first step, the laboratories examined the technical risks and uncertainties associated with the Cast Stone waste immobilization projects at Hanford. Science and technology needs were identified for work associated with 1) conducting performance assessments and risk assessments of waste form and disposal system performance, and 2) technetium chemistry in tank wastes and separations of technetium from waste processing streams. Technical approaches to address the science and technology needs were identified and an initial sequencing priority was suggested. The following table summarizes the most significant science and technology needs and associated approaches to address those needs. These approaches and priorities will be further refined and developed as strong integrated teams of researchers from national laboratories, contractors, industry, and academia are brought together to provide the best science and technology solutions. Implementation of a science and technology program that addresses these needs by pursuing the identified approaches will have immediate benefits to DOE in reducing risks and uncertainties associated with near-term decisions regarding supplemental immobilization at Hanford. Longer term, the work has the potential for cost savings and for providing a strong technical foundation for future performance assessments at Hanford and across the DOE complex.

Fox, K.

2014-05-13T23:59:59.000Z

43

Enhancement of sludge reduction and methane production by removing extracellular polymeric substances from waste activated sludge  

Science Journals Connector (OSTI)

Abstract The management of waste activated sludge (WAS) recycling is a concern that affects the development of the future low-carbon society, particularly sludge reduction and biomass utilization. In this study, we investigated the effect of removing extracellular polymeric substances (EPS), which play important roles in the adhesion and flocculation of WAS, on increased sludge disintegration, thereby enhancing sludge reduction and methane production by anaerobic digestion. EPS removal from WAS by ethylenediaminetetraacetic acid (EDTA) significantly enhanced sludge reduction, i.e., 495% compared with 271% of the control at the end the digestion process. Methane production was also improved in WAS without EPS by 8881109 CH4?molg?1 dry-weight of sludge. Microbial activity was determined by denaturing gradient gel electrophoresis and real-time polymerase chain reaction, which showed that the hydrolysis and acetogenesis stages were enhanced by pretreatment with 2% EDTA, with a larger methanogenic community and better methane production.

Minh Tuan Nguyen; Nazlina Haiza Mohd Yasin; Toshiki Miyazaki; Toshinari Maeda

2014-01-01T23:59:59.000Z

44

Assessment of commercially available ion exchange materials for cesium removal from highly alkaline wastes  

SciTech Connect (OSTI)

Approximately 61 million gallons of nuclear waste generated in plutonium production, radionuclide removal campaigns, and research and development activities is stored on the Department of Energy`s Hanford Site, near Richland, Washington. Although the pretreatment process and disposal requirements are still being defined, most pretreatment scenarios include removal of cesium from the aqueous streams. In many cases, after cesium is removed, the dissolved salt cakes and supernates can be disposed of as LLW. Ion exchange has been a leading candidate for this separation. Ion exchange systems have the advantage of simplicity of equipment and operation and provide many theoretical stages in a small space. The organic ion exchange material Duolite{trademark} CS-100 has been selected as the baseline exchanger for conceptual design of the Initial Pretreatment Module (IPM). Use of CS-100 was chosen because it is considered a conservative, technologically feasible approach. During FY 96, final resin down-selection will occur for IPM Title 1 design. Alternate ion exchange materials for cesium exchange will be considered at that time. The purpose of this report is to conduct a search for commercially available ion exchange materials which could potentially replace CS-100. This report will provide where possible a comparison of these resin in their ability to remove low concentrations of cesium from highly alkaline solutions. Materials which show promise can be studied further, while less encouraging resins can be eliminated from consideration.

Brooks, K.P.; Kim, A.Y.; Kurath, D.E.

1996-04-01T23:59:59.000Z

45

ALUMINUM REMOVAL FROM HANFORD WASTE BY LITHIUM HYDROTALCITE PRECIPITATION - LABORATORY SCALE VALIDATION ON WASTE SIMULANTS TEST REPORT  

SciTech Connect (OSTI)

To reduce the additional sodium hydroxide and ease processing of aluminum bearing sludge, the lithium hydrotalcite (LiHT) process has been invented by AREV A and demonstrated on a laboratory scale to remove alumina and regenerate/recycle sodium hydroxide prior to processing in the WTP. The method uses lithium hydroxide (LiOH) to precipitate sodium aluminate (NaAI(OH){sub 4}) as lithium hydrotalcite (Li{sub 2}CO{sub 3}.4Al(OH){sub 3}.3H{sub 2}O) while generating sodium hydroxide (NaOH). In addition, phosphate substitutes in the reaction to a high degree, also as a filterable solid. The sodium hydroxide enriched leachate is depleted in aluminum and phosphate, and is recycled to double-shell tanks (DSTs) to leach aluminum bearing sludges. This method eliminates importing sodium hydroxide to leach alumina sludge and eliminates a large fraction of the total sludge mass to be treated by the WTP. Plugging of process equipment is reduced by removal of both aluminum and phosphate in the tank wastes. Laboratory tests were conducted to verify the efficacy of the process and confirm the results of previous tests. These tests used both single-shell tank (SST) and DST simulants.

SAMS T; HAGERTY K

2011-01-27T23:59:59.000Z

46

Removal and recovery of radionuclides and toxic metals from wastes, soils and materials  

SciTech Connect (OSTI)

A process has been developed at Brookhaven National Laboratory (BNL) for the removal of metals and radionuclides from contaminated materials, soils, and waste sites (Figure 1). In this process, citric acid, a naturally occurring organic complexing agent, is used to extract metals such as Ba, Cd, Cr, Ni, Zn, and radionuclides Co, Sr, Th, and U from solid wastes by formation of water soluble, metal-citrate complexes. Citric acid forms different types of complexes with the transition metals and actinides, and may involve formation of a bidentate, tridentate, binuclear, or polynuclear complex species. The extract containing radionuclide/metal complex is then subjected to microbiological degradation followed by photochemical degradation under aerobic conditions. Several metal citrate complexes are biodegraded and the metals are recovered in a concentrated form with the bacterial biomass. Uranium forms binuclear complex with citric acid and is not biodegraded. The supernatant containing uranium citrate complex is separated and upon exposure to light, undergoes rapid degradation resulting in the formation of an insoluble, stable polymeric form of uranium. Uranium is recovered as a precipitate (uranium trioxide) in a concentrated form for recycling or for appropriate disposal. This treatment process, unlike others which use caustic reagents, does not create additional hazardous wastes for disposal and causes little damage to soil which can then be returned to normal use.

Francis, A.J.

1993-07-01T23:59:59.000Z

47

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering  

DOE Patents [OSTI]

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved. 1 fig.

Vijayan, S.; Wong, C.F.; Buckley, L.P.

1994-11-22T23:59:59.000Z

48

Waste treatment process for removal of contaminants from aqueous, mixed-waste solutions using sequential chemical treatment and crossflow microfiltration, followed by dewatering  

DOE Patents [OSTI]

In processes of this invention aqueous waste solutions containing a variety of mixed waste contaminants are treated to remove the contaminants by a sequential addition of chemicals and adsorption/ion exchange powdered materials to remove the contaminants including lead, cadmium, uranium, cesium-137, strontium-85/90, trichloroethylene and benzene, and impurities including iron and calcium. Staged conditioning of the waste solution produces a polydisperse system of size enlarged complexes of the contaminants in three distinct configurations: water-soluble metal complexes, insoluble metal precipitation complexes, and contaminant-bearing particles of ion exchange and adsorbent materials. The volume of the waste is reduced by separation of the polydisperse system by cross-flow microfiltration, followed by low-temperature evaporation and/or filter pressing. The water produced as filtrate is discharged if it meets a specified target water quality, or else the filtrate is recycled until the target is achieved.

Vijayan, Sivaraman (Deep River, CA); Wong, Chi F. (Pembroke, CA); Buckley, Leo P. (Deep River, CA)

1994-01-01T23:59:59.000Z

49

1,153-ton Waste Vault Removed from 300 Area- Vault held waste tanks with contamination from Hanfords former laboratory facilities  

Broader source: Energy.gov [DOE]

Today, the Department of Energys (DOEs) Richland Operations Office announced the removal of a massive concrete vault that once held two 15,000-gallon stainless steel tanks used to collect highly contaminated waste from Hanfords 300 Area laboratories as part of the River Corridor Closure project.

50

E-Print Network 3.0 - accelerating waste removal Sample Search...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

SOLID WASTE IN CALIFORNIA: NEEDS AND CHALLENGES Alexander E. Helou... , such as gasification, pyrolysis, waste-to-energy (WTE), and advanced thermal ... Source: Columbia...

51

Waste management plan for the removal action at the former YS-860 Firing Ranges, Oak Ridge Y-12 Plant, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

This waste management plan defines the procedures for control and management of waste generated as a result of the removal action of the YS-86O Firing Ranges site at the Oak Ridge Y-12 Plant. This document includes plan objectives; remediation activities; key personnel; waste generation activities; and waste treatment, storage, transportation, and disposal. Methods of control and characterization of waste generated as a result of remediation activities will be within the guidelines and procedures outlined herein. ENTECH personnel will make every effort when conducting remediation and decontamination activities to minimize the amount of generated waste.

NONE

1998-03-01T23:59:59.000Z

52

The removal of mercury from solid mixed waste using chemical leaching processes  

SciTech Connect (OSTI)

The focus of this research was to evaluate chemical leaching as a technique to treat soils, sediments, and glass contaminated with either elemental mercury or a combination of several mercury species. Potassium iodide/iodine solutions were investigated as chemical leaching agents for contaminated soils and sediments. Clean, synthetic soil material and surrogate storm sewer sediments contaminated with mercury were treated with KI/I{sub 2} solutions. It was observed that these leaching solutions could reduce the mercury concentration in soil and sediments by 99.8%. Evaluation of selected posttreatment sediment samples revealed that leachable mercury levels in the treated solids exceeded RCRA requirements. The results of these studies suggest that KI/I{sub 2} leaching is a treatment process that can be used to remove large quantities of mercury from contaminated soils and sediments and may be the only treatment required if treatment goals are established on Hg residual concentrations in solid matrices. Fluorescent bulbs were used to simulate mercury contaminated glass mixed waste. To achieve mercury contamination levels similar to those found in larger bulbs such as those used in DOE facilities a small amount of Hg was added to the crushed bulbs. The most effective agents for leaching mercury from the crushed fluorescent bulbs were KI/I{sub 2}, NaOCl, and NaBr + acid. Radionuclide surrogates were added to both the EPA synthetic soil material and the crushed fluorescent bulbs to determine the fate of radionuclides following chemical leaching with the leaching agents determined to be the most promising. These experiments revealed that although over 98% of the dosed mercury solubilized and was found in the leaching solution, no Cerium was measured in the posttreatment leaching solution. This finding suggest that Uranium, for which Ce was used as a surrogate, would not solubilize during leaching of mercury contaminated soil or glass.

Gates, D.D.; Chao, K.K.; Cameron, P.A.

1995-07-01T23:59:59.000Z

53

Removing Phosphate from Hanford High-Phosphate Tank Wastes: FY 2010 Results  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) is responsible for environmental remediation at the Hanford Site in Washington State, a former nuclear weapons production site. Retrieving, processing, immobilizing, and disposing of the 2.2 105 m3 of radioactive wastes stored in the Hanford underground storage tanks dominates the overall environmental remediation effort at Hanford. The cornerstone of the tank waste remediation effort is the Hanford Tank Waste Treatment and Immobilization Plant (WTP). As currently designed, the capability of the WTP to treat and immobilize the Hanford tank wastes in the expected lifetime of the plant is questionable. For this reason, DOE has been pursuing supplemental treatment options for selected wastes. If implemented, these supplemental treatments will route certain waste components to processing and disposition pathways outside of WTP and thus will accelerate the overall Hanford tank waste remediation mission.

Lumetta, Gregg J.; Braley, Jenifer C.; Edwards, Matthew K.; Qafoku, Odeta; Felmy, Andrew R.; Carter, Jennifer C.; MacFarlan, Paul J.

2010-09-22T23:59:59.000Z

54

Nanostructured High Temperature Bulk Thermoelectric Energy Conversion...  

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

Efficient Automotive Waste Heat Recovery Multi-physics modeling of thermoelectric generators for waste heat recovery applications Nanostructured High-Temperature Bulk...

55

Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126  

SciTech Connect (OSTI)

Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it was used for the column testing to obtain breakthrough curves under various conditions of pH and brine concentration. The breakthrough point had a dependency on pH and the brine concentration. We found that when the pH was higher or the brine concentration was lower, the longer it took to reach the breakthrough point. The inhibition of strontium adsorption by alkali earth metals would be diminished for conditions of higher pH and lower brine concentration. (authors)

Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan)] [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan); Asano, Takashi; Tamata, Shin [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)] [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)

2013-07-01T23:59:59.000Z

56

ALUMINUM READINESS EVALUATION FOR ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENRATION FROM HANFORD TANK WASTE BY LITHIUM HYDROTALCITE PRECIPITATION  

SciTech Connect (OSTI)

A Technology Readiness Evaluation (TRE) performed by AREV A Federal Services, LLC (AFS) for Washington River Protection Solutions, LLC (WRPS) shows the lithium hydrotalcite (LiHT) process invented and patented (pending) by AFS has reached an overall Technology Readiness Level (TRL) of 3. The LiHT process removes aluminum and regenerates sodium hydroxide. The evaluation used test results obtained with a 2-L laboratory-scale system to validate the process and its critical technology elements (CTEs) on Hanford tank waste simulants. The testing included detailed definition and evaluation for parameters of interest and validation by comparison to analytical predictions and data quality objectives for critical subsystems. The results of the TRE would support the development of strategies to further mature the design and implementation of the LiHT process as a supplemental pretreatment option for Hanford tank waste.

SAMS TL; MASSIE HL

2011-01-27T23:59:59.000Z

57

FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL ACTIONS AT THE TECHNICAL AREA III CLASSIFIED WASTE LANDFILL, SANDIA NATIONAL LABORATORIES, NEW MEXICO - DOE/EA-1729  

Broader source: Energy.gov (indexed) [DOE]

FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL FINAL ENVIRONMENTAL ASSESSMENT FOR REMOVAL ACTIONS AT THE TECHNICAL AREA III CLASSIFIED WASTE LANDFILL, SANDIA NATIONAL LABORATORIES, NEW MEXICO DOE/EA-1729 August 2010 National Nuclear Security Administration Sandia Site Office P.O. Box 5400 Albuquerque, New Mexico 87185-5400 DOE/EA-1729: Environmental Assessment for Removal Actions at the Technical Area III August 2010 Classified Waste Landfill, Sandia National Laboratories, New Mexico i TABLE OF CONTENTS Section 1.0 PURPOSE AND NEED FOR AGENCY ACTION .................................................................... Page 1 1.1 Background .................................................................................................................................. 1

58

Pyrolysis of Mixed Plastic Wastes for the Recovery of Benzene, Toluene, and Xylene (BTX) Aromatics in a Fluidized Bed and Chlorine Removal by Applying Various Additives  

Science Journals Connector (OSTI)

It seems that the char removal system, which was composed of a cyclone and a hot filter, almost perfectly removed the char particles. ... To absorb the hydrogen chloride that was formed from the degradation of the polyvinyl chloride (PVC) in the mixed plastic wastes, additives (calcium oxide, calcium hydroxide, crushed oyster shells, and rice straw) were added to a fraction of the mixed plastic wastes. ... For different additives, different Ca/Cl ratios should be chosen based on the cost, HCl removal efficiency and utilization efficiency of additive. ...

Min-Hwan Cho; Su-Hwa Jung; Joo-Sik Kim

2009-12-15T23:59:59.000Z

59

Development of a Fuel Containing Material Removal and Waste Management Strategy for the Chernobyl Unit 4 Shelter  

SciTech Connect (OSTI)

A study was performed to develop a strategy for the removal of fuel-containing material (FCM) from the Chernobyl Unit 4 Shelter and for the related waste management. This study was performed during Phase 1 of the Shelter Implementation Plan (SIP) and was funded by the Chernobyl Shelter Fund. The main objective for Phase 2 of the SIP is to stabilize the Shelter and to construct a New Confinement (NC) by the year 2007. In addition, the SIP includes studies on the strategy and on the conceptual design implications of the removal of FCM from the Shelter. This is considered essential for the ultimate goal, the transformation of the Shelter into an environmentally safe system.

Tokarevsky, V. V.; Shibetsky, Y. A.; Leister, P.; Davison, W. R.; Follin, J. F.; McNair, J.; Lins, W.; Edler, G.

2002-02-27T23:59:59.000Z

60

Removal of pertechnetate from simulated nuclear waste streams using supported zerovalent iron  

E-Print Network [OSTI]

3. ?? TM/JD 2. Westinghouse Hanford Co. , Report WHC-SD-WM-Department of Energys Hanford Site: (1) the direct removaltypical of those found in Hanford tank waste; and (2) the

Darab, John

2008-01-01T23:59:59.000Z

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


61

Idaho Cold War Waste Removal Advancing as Work on Eighth Area...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Carlsbad, New Mexico. The waste was generated during nuclear weapons production at the Rocky Flats Plant near Denver, Colorado, and was buried in Idaho from 1954 to 1970. In...

62

Removal of {sup 14}C from Irradiated Graphite for Graphite Recycle and Waste Volume Reduction  

SciTech Connect (OSTI)

The aim of the research presented here was to identify the checmical from of {sup 14}C inirradiated graphite. A greater understanding of the chemical form of this longest-lived isotope in irradiated graphite will inform not only management of legacy waste, but also development of next generation gas-cooled reactors. Approimately 250,000 metric tons of irradiated graphite waste exists worldwide, with the largest single quantity originating in the Magnox and AGR reactors of UK. The waste quantity is expected to increase with decommissioning of Generation II reactors and deployment of Generation I gas-cooled, graphite moderated reactors. Of greatest concern for long-term disposal of irradiated graphite is carbon-14 ({sup 14}C), with a half-life of 5730 years.

Dunzik-Gougar, Mary Lou; Windes, Will; Marsden, Barry

2014-06-10T23:59:59.000Z

63

ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENERATION FROM HANFORD TANK WASTE BY LITHIUM HYDROTALCITE PRECIPITATION SUMMARY OF PRIOR LAB-SCALE TESTING  

SciTech Connect (OSTI)

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

SAMS TL; GUILLOT S

2011-01-27T23:59:59.000Z

64

DISSOLUTION & RESUSPENSION OF STORED RADIOACTIVE WASTE & ON SITE TRANSPORT & HANDLING FOR CONDITIONING FOR WASTE RETRIEVAL  

SciTech Connect (OSTI)

The four primary functions in a waste retrieval system are as follows: accessing all of the waste within the tank configuration; mobilizing all of the waste, which can have varying physical properties; removing the bulk and residual mobilized waste; and transferring the waste to storage or processing equipment. Selection of retrieval and transfer systems must include all of these functions. Limitations on any one of these areas affect the whole process. This section categorizes according to function many available retrieval and transfer processes, with positive attributes and limitations. Additional information on these systems is referenced in the annexes.

GIBBONS, P.W.

2001-08-13T23:59:59.000Z

65

Preliminary Ion Exchange Modeling for Removal of Cesium from Hanford Waste Using SuperLig 644 Resin  

SciTech Connect (OSTI)

A proposed facility is being designed for the immobilization of Hanford high-level radioactive waste. One unit process in the facility is designed to remove radioactive cesium by ion-exchange from the strongly alkaline aqueous phase. A resin specifically designed with high selectivity of cesium under alkaline conditions is being investigated. The resin also is elutable under more acidic conditions. The proposed design of the facility consists of two sets of two packed columns placed in series (i.e., a lead column followed by a lag (guard) column configuration). During operation, upon reaching a specified cesium concentration criterion at the exit of the lag column, operation is switched to the second set of lead and lag columns. The cesium-loaded lead column is processed (i.e., washed and eluted) and switched to the lag position. the previous lag column is then placed in the lead position (without eluting) and the system is ready for use in the next cycle. For a well designed process, the loading and elution processes result in significant volume reductions in aqueous high-level waste.

Hamm, L.L.

2000-08-23T23:59:59.000Z

66

Removal and recovery of metal ions from process and waste streams using polymer filtration  

SciTech Connect (OSTI)

Polymer Filtration (PF) is an innovative, selective metal removal technology. Chelating, water-soluble polymers are used to selectively bind the desired metal ions and ultrafiltration is used to concentrate the polymer-metal complex producing a permeate with low levels of the targeted metal ion. When applied to the treatment of industrial metal-bearing aqueous process streams, the permeate water can often be reused within the process and the metal ions reclaimed. This technology is applicable to many types of industrial aqueous streams with widely varying chemistries. Application of PF to aqueous streams from nuclear materials processing and electroplating operations will be described.

Jarvinen, G.D.; Smith, B.F.; Robison, T.W.; Kraus, K.M.; Thompson, J.A.

1999-06-13T23:59:59.000Z

67

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion...  

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

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion for Efficient Automotive Waste Heat Recovery Nanostructured High-Temperature Bulk Thermoelectric Energy...

68

SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATION  

SciTech Connect (OSTI)

This report describes experimental results for the selective removal of strontium and cesium from simulated waste solutions using monosodium titanate (MST) and crystalline silicotitanate (CST)-laden filter cartridges. Four types of ion exchange cartridge media (CST and MST designed by both 3M and POROX{reg_sign}) were evaluated. In these proof-of-principle tests effective uptake of both Sr-85 and Cs-137 was observed. However, the experiments were not performed long enough to determine the saturation levels or breakthrough curve for each filter cartridge. POREX{reg_sign} MST cartridges, which by design were based on co-sintering of the active titanates with polyethylene particles, seem to perform as well as the 3M-designed MST cartridges (impregnated filter membrane design) in the uptake of strontium. At low salt simulant conditions (0.29 M Na{sup +}), the instantaneous decontamination factor (D{sub F}) for Sr-85 with the 3M-design MST cartridge measured 26, representing the removal of 96% of the Sr-85. On the other hand, the Sr-85 instantaneous D{sub F} with the POREX{reg_sign} design MST cartridge measured 40 or 98% removal of the Sr-85. Strontium removal with the 3M-design MST and CST cartridges placed in series filter arrangement produced an instantaneous decontamination factor of 41 or 97.6% removal compared to an instantaneous decontamination factor of 368 or 99.7% removal of the strontium with the POREX{reg_sign} MST and CST cartridge design placed in series. At high salt simulant conditions (5.6 M Na{sup +}), strontium removal with 3M-designed MST cartridge only and with 3M-designed MST and CST cartridges operated in a series configuration were identical. The instantaneous decontamination factor and the strontium removal efficiency, under the above configuration, averaged 8.6 and 88%, respectively. There were no POREX{reg_sign} cartridge experiments using the higher ionic strength simulant solution. At low salt simulant conditions, the uptake of Cs-137 with POREX{reg_sign} CST cartridge out performed the 3M-designed CST cartridges. The POREX{reg_sign} CST cartridge, with a Cs-137 instantaneous decontamination factor of 55 and a Cs-137 removal efficiency of 98% does meet the Cs-137 decontamination goals in the low salt simulant liquor. The Cs-137 removal with 3M-designed CST cartridge produced a decontamination factor of 2 or 49% removal efficiency. The Cs-137 performance graph for the 3M-designed CST cartridge showed an early cessation in the uptake of cesium-137. This behavior was not observed with the POREX{reg_sign} CST cartridges. No Cs-137 uptake tests were performed with the POREX{reg_sign} CST cartridges at high salt simulant conditions. The 3M-designed CST cartridges, with an instantaneous Cs-137 decontamination factor of less than 3 and a Cs-137 removal efficiency of less than 50% failed to meet the Cs-137 decontamination goals in both the low and high salt simulant liquors. This poor performance in the uptake of Cs-137 by the 3M CST cartridges may be attributed to fabrication flaws for the 3M-designed CST cartridges. The reduced number of CST membrane wraps per cartridge during the cartridge design phase, from 3-whole wraps to about 1.5, may have contributed to Cs-137 laden simulant channeling/by-pass which led to the poor performance in terms of Cs-137 sorption characteristics for the 3M designed CST cartridges. The grinding of CST ion exchange materials, to reduce the particle size distribution and thus enhance their easy incorporation into the filter membranes and the co-sintering of MST with polyethylene particles, did not adversely affect the sorption kinetics of both CST and MST in the uptake of Cs-137 and Sr-85, respectively. In general, the POREX{reg_sign} based cartridges showed more resistance to simulant flow through the filter cartridges as evidenced by higher pressure differences across the cartridges. Based on these findings they conclude that incorporating MST and CST sorbents into filter membranes represent a promising method for the semi-continuous removal of radioisotopes of strontium a

Oji, L.; Martin, K.; Hobbs, D.

2011-05-26T23:59:59.000Z

69

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion...  

Broader source: Energy.gov (indexed) [DOE]

More Documents & Publications Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion for Efficient Automotive Waste Heat Recovery Vehicle Technologies Office...

70

Preliminary engineering report waste area grouping 5, Old Hydrofracture Facility Tanks content removal project, Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facilities Agreement (FFA) for federal facilities placed on the National Priorities List. The Oak Ridge Reservation was placed on that list on December 21, 1989, and the agreement was signed in November 1991 by the U.S. Department of Energy (DOE) Oak Ridge Operations Office, the U.S. Environmental Protection Agency (EPA) Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA is January 1, 1992. One objective of the FFA is to ensure that liquid low-level waste (LLLW) tanks that are removed from service are evaluated and remediated through the CERCLA process. Five inactive LLLW tanks, designated T-1, T-2, T-3, T-4, and T-9, located at the Old Hydrofracture (OHF) Facility in the Melton Valley area of Oak Ridge National Laboratory (ORNL) have been evaluated and are now entering the remediation phase. As a precursor to final remediation, this project will remove the current liquid and sludge contents of each of the five tanks (System Requirements Document, Appendix A). It was concluded in the Engineering Evaluation/Cost Analysis [EE/CA] for the Old Hydrofracture Facility Tanks (DOE 1996) that sluicing and pumping the contaminated liquid and sludge from the five OHF tanks was the preferred removal action. Evaluation indicated that this alternative meets the removal action objective and can be effective, implementable, and cost-effective. Sluicing and removing the tank contents was selected because this action uses (1) applicable experience, (2) the latest information about technologies and techniques for removing the wastes from the tanks, and (3) activities that are currently acceptable for storage of transuranic (TRU) mixed waste.

NONE

1996-06-01T23:59:59.000Z

71

RADIOLOGICAL CONTROLS FOR PLUTONIUM CONTAMINATED PROCESS EQUIPMENT REMOVAL FROM 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINSHING PLANT (PFP)  

SciTech Connect (OSTI)

The 232-Z facility at Hanford's Plutonium Finishing Plant operated as a plutonium scrap incinerator for 11 years. Its mission was to recover residual plutonium through incinerating and/or leaching contaminated wastes and scrap material. Equipment failures, as well as spills, resulted in the release of radionuclides and other contamination to the building, along with small amounts to external soil. Based on the potential threat posed by the residual plutonium, the U.S. Department of Energy (DOE) issued an Action Memorandum to demolish Building 232-2, Comprehensive Environmental Response Compensation, and Liability Act (CERC1.A) Non-Time Critical Removal Action Memorandum for Removal of the 232-2 Waste Recovery Process Facility at the Plutonium Finishing Plant (04-AMCP-0486).

MINETTE, M.J.

2007-05-30T23:59:59.000Z

72

Evaluation of an alkaline-side solvent extraction process for cesium removal from SRS tank waste using laboratory-scale centrifugal contactors  

SciTech Connect (OSTI)

An alkaline-side solvent extraction process for cesium removal from Savannah River Site (SRS) tank waste was evaluated experimentally using a laboratory-scale centrifugal contactor. Single-stage and multistage tests were conducted with this contactor to determine hydraulic performance, stage efficiency, and general operability of the process flowsheet. The results and conclusions of these tests are reported along with those from various supporting tests. Also discussed is the ability to scale-up from laboratory- to plant-scale operation when centrifugal contractors are used to carry out the solvent extraction process. While some problems were encountered, a promising solution for each problem has been identified. Overall, this alkaline-side cesium extraction process appears to be an excellent candidate for removing cesium from SRS tank waste.

Leonard, R. A.; Conner, C.; Liberatore, M. W.; Sedlet, J.; Aase, S. B.; Vandegrift, G. F.

1999-11-29T23:59:59.000Z

73

CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE D&D OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT (PFP)  

SciTech Connect (OSTI)

This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place.

HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

2007-01-25T23:59:59.000Z

74

Development and Demonstration of Waste Heat Integration with Solvent Process for More Efficient CO2 Removal from Coal-Fired Flue Gas  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

and Demonstration of and Demonstration of Waste Heat Integration with Solvent Process for More Efficient CO 2 Removal from Coal-Fired Flue Gas Background The mission of the U.S. Department of Energy/National Energy Technology Laboratory (DOE/NETL) Existing Plants, Emissions, & Capture (EPEC) Research & Development (R&D) Program is to develop innovative environmental control technologies to enable full use of the nation's vast coal reserves, while at the same time allowing the current fleet of coal-

75

Preparation of sorbents containing ettringite phase from concrete sludge and their performance in removing borate and fluoride ions from waste water  

Science Journals Connector (OSTI)

Concrete sludge is an industrial waste slurry containing hydrated cement, aggregates and water. Solid sorbents containing ettringite, Ca6Al2(SO4)3(OH)1226H2O, were prepared from concrete sludge by adding various amounts of aluminum sulfate to enhance ettringite formation. Anion exchange performance of the sorbents was examined using model waste waters containing boron or fluoride ions. The removal behavior depended on the calcium/aluminum ratio and the heat treatment temperature after drying. For the same Ca/Al ratio, improved removal performance was observed for sorbents treated at higher temperatures. The highest removal capacity was found when the sorbent was prepared with a molar ratio of Ca/Al of 3.2 and heat treatment at 175C. The final concentrations of boron and fluoride were 6.3mg-B/L, and less than 4mg-F/L for initial concentrations of 100mg-B/L and 300mg-F/L. Treatment of the sorbents at higher temperature dehydrated the ettringite phase to form metaettringite phase. The sorbents prepared in the present study can be used in a boron and fluoride removal process that meets the effluent standard in Japan.

Yusuke Tsunashima; Atsushi Iizuka; Junichiro Akimoto; Teruhisa Hongo; Akihiro Yamasaki

2012-01-01T23:59:59.000Z

76

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

Broader source: Energy.gov (indexed) [DOE]

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

77

SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092  

SciTech Connect (OSTI)

Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate and crystalline silicotitanate laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both strontium-85 and cesium-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor for strontium-85 with monosodium titanate impregnated filter membrane cartridges measured 26, representing 96% strontium-85 removal efficiency. On the other hand, the strontium-85 instantaneous decontamination factor with co-sintered active monosodium titanate cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the monosodium titanate impregnated membrane cartridges and crystalline silicotitanate impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active monosodium titanate cartridges and co-sintered active crystalline silicotitanate cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of cesium-137 with co-sintered crystalline silicotitanate cartridges. Tests results with crystalline silicotitanate impregnated membrane cartridges for cesium-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating monosodium titanate and crystalline silicotitanate sorbents into membranes represent a promising method for the semicontinuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

Oji, L.; Martin, K.; Hobbs, D.

2012-01-03T23:59:59.000Z

78

SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092  

SciTech Connect (OSTI)

Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate (MST) and crystalline silicotitanate (CST) laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both Sr-85 and Cs-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor (D{sub F}) for Sr-85 with MST impregnated filter membrane cartridges measured 26, representing 96% Sr-85 removal efficiency. On the other hand, the Sr-85 instantaneous D{sub F} with co-sintered active MST cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the MST impregnated membrane cartridges and CST impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active MST cartridges and co-sintered active CST cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of Cs-137 with co-sintered CST cartridges. Tests results with CST impregnated membrane cartridges for Cs-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating MST and CST sorbents into membranes represent a promising method for the semi-continuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

Oji, L.; Martin, K.; Hobbs, D.

2011-11-10T23:59:59.000Z

79

Evaluation of packed-bed and fluidized-bed cell technology for the destruction and removal of contaminants in alkaline waste solutions. Final report  

SciTech Connect (OSTI)

Disposing of the large quantity of nuclear waste that has been produced within the DOE complex is an area of active research and development. Electrochemical processes have been reported for the treatment of alkaline wastes including the destruction of nitrate and nitrite and the removal of metals such as Tc and Ru. Electrolytic recovery of metals from dilute solution has been reported using conventional porous electrodes such as felt electrode and reticulated electrode, but use of such electrodes is limited. The pores of such electrodes become blocked as a consequence of metal deposition. If an attempt is made to regenerate these electrodes by dissolution of the deposited metals, oxygen evolution on the matrix competes with dissolution of metals deposited within the pores. On the other hand, the use of three dimensional packed-bed and fluidized-bed electrodes having large surface area per unit volume would offer an improvement on felt or reticulated system because of the greater ease of regeneration.

Hobbs, D.T. [Westinghouse Savannah River Co., Aiken, SC (United States); Bockris, J.O.M.; Kim, Jinseong [Texas A& M Univ., College Station, TX (United States). Surface Electrochemistry Laboratory

1995-12-31T23:59:59.000Z

80

Small Column Ion Exchange Testing of Superlig 644 for Removal of 137Cs from Hanford Tank Waste Envelope C (Tank 241-AN-107)  

SciTech Connect (OSTI)

The current BNFL Inc. flowsheet for the pretreatment of the Hanford high-level tank wastes includes the use of Superlig{reg_sign} materials for removing {sup 137}Cs from the aqueous fraction of the waste. The Superlig materials applicable to cesium removal include the cesium-selective Superlig 632and Superlig 644. These materials have been developed and supplied by IBC Advanced Technologies, Inc., American Fork, Utah. This report describes the testing of the Superlig 644 ion exchange material in a small dual-column system. The bed volume of the lead column was 18.6 mL (L/D = 7), and the bed volume of the lag column was 15.9 mL (L/D = 6) during the loading phase. The sample processed was approximately 1.6 L of diluted waste ([Na{sup +}] = 4.84 M) from Tank 241-AN-107 (Envelope C). This sample had been previously treated for removal of Sr/transuranic (TRU) values and clarified in a single tube cross-flow filtration unit. All ion exchange process steps were tested, including resin-bed preparation, loading, feed displacement, water rinse, elution, eluant rinse, and resin regeneration. A summary of performance measures for both columns is shown in Table S1. The Cs {lambda} values represent a measure of the effective capacity of the SL-644 resin. The Cs {lambda} of 20 for the lead column is much lower than the estimated 150 obtained by the Savannah River Technology Center during Phase 1A testing. Equilibrium data obtained with batch contacts using the AN-107 Cs IX feed predicts a Cs {lambda} of 183. A Cs {lambda} for the lag column could not be determined due to insufficient breakthrough, but it appeared to work well and removed nearly all of the cesium not removed by the lead column. The low value for the lead column indicates that it did not perform as expected. This may have been due to air or gas in the bed that caused fluid channeling or blinding of the resin. The maximum decontamination factor (DF) for {sup 137}Cs listed in Table S1 is based on {sup 137}Cs concentration in the first samples collected from each column and the {sup 137}Cs concentration in the feed. The composite DF for {sup 137}Cs was 1,760, which provided an effluent with a {sup 137}Cs concentration of 8.7E-02 Ci/m{sup 3}. The {sup 137}Cs concentration is below the basis of design limit and is 7.2% of the contract limit for {sup 137}Cs.

DE Kurath; DL Blanchard; JR Bontha

2000-06-28T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

TECHNOLOGY MATURATION PLAN FOR ALUMINUM REMOVAL AND SODIUM HYDROXIDE REGENERATION FROM HANFORD WASTE BY LITHIUM HYDROTALCITE PRECIPITATION  

SciTech Connect (OSTI)

This Technology Maturation Plan schedules the development process that will bring the Lithium Hydrotalcite waste pretreatment process from its current estimated Technology Readiness Level of 3, to a level of 6. This maturation approach involves chemical and engineering research and development work, from laboratory scale to pilot scale testing, to incrementally make the process progress towards its integration in a fully qualified industrial system.

SAMS TL; GUILLOT S

2011-01-27T23:59:59.000Z

82

Preliminary evaluation of the effectiveness of moisture removal and energy usage in pretreatment module of waste cooking oil for biodiesel production  

Science Journals Connector (OSTI)

Waste Cooking Oil (WCO) is a plausible low cost biodiesel feedstock but it exhibits few unfavorable parameters for conversion into biodiesel. One of the parameter is the presence of high moisture content which will inhibit or retard catalyst during the acid esterification or base transesterification causing lower purity and yield of biodiesel. This will effect the post processing and escalate production cost making WCO a not favorable biodiesel feedstock. Therefore, it is important to have an effective moisture removal method to reduce the moisture content below 0.05%wt or 500 ppm in WCO for an efficient biodiesel production. In this work, the effectiveness of moisture removal and the energy usage of a newly develop innovative pretreatment module has been evaluated and reported. Results show that the pretreatment module is able to reduce up to 85% to effectively reduce the moisture content to below 500ppm of the initial moisture content of WCO and only consume 157 Wh/l energy compared to conventional heating that consume 386 Wh/l and only remove 67.6% moisture in 2 hours.

K Palanisamy; M K Idlan; N Saifudin

2013-01-01T23:59:59.000Z

83

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion...  

Broader source: Energy.gov (indexed) [DOE]

High Temperature Bulk Thermoelectric Energy Conversion for Efficient Waste Heat Recovery Project Overview 2 * Start: October 2011 * End: September 2015 * Percent complete -...

84

RECENT PROGRESS IN DOE WASTE TANK CLOSURE  

SciTech Connect (OSTI)

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

Langton, C

2008-02-01T23:59:59.000Z

85

Selective Removal of Cs+, Sr2+, and Ni2+ by K2xMgxSn3xS6 (x = 0.51) (KMS-2) Relevant to Nuclear Waste Remediation  

Science Journals Connector (OSTI)

Selective Removal of Cs+, Sr2+, and Ni2+ by K2xMgxSn3xS6 (x = 0.51) (KMS-2) Relevant to Nuclear Waste Remediation ... Materials Science Division, Argonne National Laboratory, Argonne, Illinois 60439, United States ...

Joshua L. Mertz; Zohreh Hassanzadeh Fard; Christos D. Malliakas; Manolis J. Manos; Mercouri G. Kanatzidis

2013-05-15T23:59:59.000Z

86

High vacuum indirectly-heated rotary kiln for the removal and recovery of mercury from air pollution control scrubber waste  

SciTech Connect (OSTI)

SepraDyne corporation (Denton, TX, US) has conducted pilot-scale treatability studies of dewatered acid plant blowdown sludge generated by a copper smelter using its recently patented high temperature and high vacuum indirectly-heated rotary retort technology. This unique rotary kiln is capable of operating at internal temperatures up to 850 C with an internal pressure of 50 torr and eliminates the use of sweep gas to transport volatile substances out of the retort. By removing non-condensables such as oxygen and nitrogen at relatively low temperatures and coupling the process with a temperature ramp-up program and low temperature condensation, virtually all of the retort off-gases produced during processing can be condensed for recovery. The combination of rotation, heat and vacuum produce the ideal environment for the rapid volatilization of virtually all organic compounds, water and low-to-moderate boiling point metals such as arsenic, cadmium and mercury.

Hawk, G.G.; Aulbaugh, R.A. [Scientific Consulting Labs., Inc., Farmers Branch, TX (United States)] [Scientific Consulting Labs., Inc., Farmers Branch, TX (United States)

1998-12-31T23:59:59.000Z

87

Ion Exchange Studies for Removal of Sulfate from Hanford Tank Waste Envelope C (241-AN-107) Using SuperLig 655 Resin  

SciTech Connect (OSTI)

BNFL Inc. is evaluating various pretreatment technologies to mitigate the impacts of sulfate on the LAW vitrification system. One pretreatment technology for separating sulfate from LAW solutions involves the use of SuperLig{reg_sign} 655 (SL-655), a proprietary ion exchange material developed and supplied by IBC Advanced Technologies, Inc., American Fork, UT. This report describes testing of SL-655 with diluted ([Na] {approximately} 5 M) waste from Hanford Tank 241-AN-107 at Battelle, Pacific Northwest Division. Batch contact studies were conducted from 4 to 96 hours to determine the sulfate distribution coefficient and reaction kinetics. A small-scale ion exchange column test was conducted to evaluate sulfate removal, loading, breakthrough, and elution from the SL-655. In all of these tests, an archived 241-AN-107 tank waste sample (pretreated to remove Cs, Sr, and transuranics elements) was used. The experimental details and results are described in this report. Under the test conditions, SL-655 was found to have no significant ion exchange affinity for sulfate in this matrix. The batch contact study resulted in no measurable difference in the aqueous sulfate concentration following resin contact (K{sub d} {approximately} 0). The column test also demonstrated SL-655 had no practical affinity for sulfate in the tested matrix. Within experimental error, the sulfate concentration in the column effluent was equal to the concentration in the feed after passing 3 bed volumes of sample through the columns. Furthermore, some, if not all, of the decreased sulfate concentration in these first three column volumes of effluent can be ascribed to mixing and dilution of the 241-AN-107 feed with the interstitial liquid present in the column at the start of the loading cycle. Finally, ICP-AES measurements on the eluate solutions showed the presence of barium as soon as contact with the feed solution is completed. Barium is a metal not detected in the feed solution. Should the loss of barium be correlated with the resin's ability to selectively complex sulfate, then maintaining even the current limited resin characteristics for sulfate complexation over multiple cycles becomes questionable.

DE Kurath; JR Bontha; DL Blanchard; SK Fiskum; BM Rapko

2000-08-23T23:59:59.000Z

88

Process development for remote-handled mixed-waste treatment  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

1990-01-01T23:59:59.000Z

89

Robotic Inspection System for Bulk Liquid Storage Tanks  

E-Print Network [OSTI]

for aboveground storage tanks (ASTs) requires: drainage of the product; cleaning of the vessel with water or solvents; physical removal, collection and containment of petroleum and chemical waste residues, including the waste streams created by the cleaning...

Hartsell, D. R.; Hakes, K. J.

90

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation of Sodium Salts  

SciTech Connect (OSTI)

The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high-level nuclear waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 10,000-fold by ordinary inorganic chemicals. Quite simply, if the radioactive matter and bulk inorganic chemicals could be separated into separate streams, large cost savings would accrue, because the latter stream is much cheaper to dispose of. In principle, one could remove the radionuclides from the waste, leaving behind the bulk of the waste; or one could remove certain bulk chemicals from the waste, leaving behind the radionuclides. The preponderance of effort over the past two decades has focused on the former approach, which produces a high-level stream for vitrification and a low-activity stream for either vitrification (Hanford) or grout (Savannah River). At Hanford, a particular concern arises in that vitrification of a large volume of low-activity waste will be unacceptably expensive. To make matters worse, a projected future deficit of tank space may necessitate construction of expensive new tanks. These problems have raised questions as to whether a solution could be devised based on separation of sodium from the waste, resulting in the reduction of the total volume of waste that must be vitrified.

Moyer, Bruce A.; Lumetta, Gregg J.; Marchand, Alan P.

2002-06-01T23:59:59.000Z

91

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation of Sodium Salts  

SciTech Connect (OSTI)

The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid- liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high- level nuclear waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 10,000-fold by ordinary inorganic chemicals.1 Quite simply, if the radioactive matter and bulk inorganic chemicals could be separated into separate streams, large cost savings would accrue, because the latter stream is much cheaper to dispose of. In principle, one could remove the radionuclides from the waste, leaving behind the bulk of the waste; or one could remove certain bulk chemicals from the waste, leaving behind a mixture of radionuclides and minor inorganic salts. The preponderance of effort over the past two decades has focused on the former approach, which produces a high- level stream for vitrification and a low-activity stream for either vitrification (Hanford) or grout (Savannah River). At Hanford, a particular concern arises in that vitrification of a large volume of low-activity waste will be unacceptably expensive. To make matters worse, a projected future deficit of tank space may necessitate construction of expensive new tanks. These problems have raised questions as to whether a solution could be devised based on separation of sodium from the waste, resulting in the reduction of the total volume of waste that must be vitrified.

Moyer, Bruce A; Lumetta, Gregg J.; Marchand, Alan P.

2003-06-01T23:59:59.000Z

92

Separation, Concentration, and Immobilization of Technetium and Iodine from Alkaline Supernate Waste  

SciTech Connect (OSTI)

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

93

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

1999-07-09T23:59:59.000Z

94

Results of Hazardous and Mixed Waste Excavation from the Chemical Waste Landfill  

SciTech Connect (OSTI)

This paper describes the results of the excavation of a 1.9-acre hazardous and mixed waste landfill operated for 23 years at Sandia National Laboratories, Albuquerque, New Mexico. Excavation of the landfill was completed in 2 1/2 years without a single serious accident or injury. Approximately 50,000 cubic yards of soil contaminated with volatile and semi-volatile organics, metals, polychlorinated biphenyl compounds, and radioactive constituents was removed. In addition, over 400 cubic yards of buried debris was removed, including bulk debris, unknown chemicals, compressed gas cylinders, thermal and chemical batteries, explosive and ordnance debris, pyrophoric materials and biohazardous waste. Removal of these wastes included negotiation of multiple regulations and guidances encompassed in the Resource Conservation and Recovery Act (RCRA), the Toxic Substances Control Act (TSCA), and risk assessment methodology. RCRA concepts that were addressed include the area of contamination, permit modification, emergency treatment provision, and listed waste designation. These regulatory decisions enabled the project to overcome logistical and programmatic needs such as increased operational area, the ability to implement process improvements while maintaining a record of decisions and approvals.

Young, S. G.; Schofield, D. P.; Kwiecinski, D.; Edgmon, C. L.; Methvin, R.

2002-02-27T23:59:59.000Z

95

Processing results of 1,800 gallons of mercury and radioactively contaminated mixed waste rinse solution  

SciTech Connect (OSTI)

The mercury-contaminated rinse solution (INEL waste ID{number_sign} 123; File 8 waste) was successfully treated at the Idaho National Engineering Laboratory (INEL). This waste was generated during the decontamination of the Heat Transfer Reactor Experiment 3 (HTRE-3) reactor shield tank. Approximately 1,800 gal of waste was generated and was placed into 33 drums. Each drum contained precipitated sludge material ranging from 1--10 in. in depth, with the average depth of about 2.5 in. The pH of each drum varied from 3--11. The bulk liquid waste had a mercury level of 7.0 mg/l, which exceeded the Resource Conservation and Recovery Act (RCRA) limit of 0.2 mg/l. The average liquid bulk radioactivity was about 2.1 pCi/ml, while the average sludge contamination was about 13,800 pci/g. Treatment of the waste required separation of the liquid from the sludge, filtration, pH adjustment, and ion exchange. Because of difficulties in processing, three trials were required to reduce the mercury levels to below the RCRA limit. In the first trial, insufficient filtration of the waste allowed solid particulate produced during pH adjustment to enter into the ion exchange columns and ultimately the waste storage tank. In the second trial, the waste was filtered down to 0.1 {mu} to remove all solid mercury compounds. However, before filtration could take place, a solid mercury complex dissolved and mercury levels exceeded the RCRA limit after filtration. In the third trial, the waste was filtered through 0.3-A filters and then passed through the S-920 resin to remove the dissolved mercury. The resulting solution had mercury levels at 0.0186 mg/l and radioactivity of 0.282 pCi/ml. This solution was disposed of at the TAN warm waste pond, TAN782, TSF-10.

Thiesen, B.P.

1993-01-01T23:59:59.000Z

96

Waste-to-Energy using Refuse-Derived Fuel  

Science Journals Connector (OSTI)

At a mass-burn incinerator, Municipal Solid Waste (MSW) is ... vehicles or waste collection vehicles into a deep pit. There is no processing of the waste. Waste is removed from the pit by overhead crane and fed i...

Floyd Hasselriis MME; Dr. Patrick F. Mahoney

2012-01-01T23:59:59.000Z

97

Waste-to-Energy using Refuse-Derived Fuel  

Science Journals Connector (OSTI)

At a mass-burn incinerator, Municipal Solid Waste (MSW) is ... vehicles or waste collection vehicles into a deep pit. There is no processing of the waste. Waste is removed from the pit by overhead crane and fed i...

Floyd Hasselriis MME; Dr. Patrick F. Mahoney

2013-01-01T23:59:59.000Z

98

Two-stage air gasification of mixed plastic waste: Olivine as the bed material and effects of various additives and a nickel-plated distributor on the tar removal  

Science Journals Connector (OSTI)

Abstract Air gasification of mixed plastic waste was conducted in a two-stage gasifier. The effects of the combination of olivine as the fluidized bed material and activated carbon with or without other additives for tar cracking, as well as a Ni-plated distributor, the use of steam as a gasifying agent, and the calcination of olivine on the producer gas compositions and tar production, were also investigated. The maximum H2 concentration (27.3vol%) was obtained with 900g of activated carbon in the tar-cracking zone, and through the use of calcined olivine as the bed material. In the experiments, the maximum tar removal efficiency calculated using a base case reached 98.2%. The \\{LHVs\\} of the producer gases were in the range of 6.19.0MJ/Nm3. The increase in the activated carbon amount led to an enhanced H2 production, as well as a decrease in tar production. The Ni-plated distributor was found to be effective for tar removal. In the application of dolomite in the tar-cracking zone and the use of steam as a fluidizing medium resulted in a high rate of \\{HCl\\} removal. The minimum \\{HCl\\} concentration in the producer gases was under 1ppm.

Min-Hwan Cho; Tae-Young Mun; Young-Kon Choi; Joo-Sik Kim

2014-01-01T23:59:59.000Z

99

Low temperature thermal treatment for petroleum refinery waste sludges  

SciTech Connect (OSTI)

Treatment requirements for waste sludges generated by petroleum refinery operations and designated as waste codes K048, K049, K050, K051 and K052 under the Resource Conservation and Recovery Act (RCRA) became effective in November, 1990 under the Landban regulations. An experimental program evaluated low temperature thermal treatment of filter cakes produced from these sludges using laboratory and pilot-scale equipment. One set of experiments on waste samples from two different refineries demonstrated the effective removal of organics of concern from the sludges to meet the RCRA Best Demonstrated Available Technology (BDAT) treatment standards. Cyanides were also within the acceptable limit. Combined with stabilization of heavy metals in the treatment residues, low temperature thermal treatment therefore provides an effective and efficient means of treating refinery sludges, with most hydrocarbons recovered and recycled to the refinery. A milder thermal treatment was used to remove the bulk of the water from a previously filtered waste sludge, providing effective waste minimization through a 40% decrease in the mass of sludge to be disposed. The heating value of the sludge was increased simultaneously by one-third, thereby producing a residue of greater value in an alternative fuels program. A process based on this approach was successfully designed and commercialized.

Ayen, R.J.; Swanstrom, C.P. (Geneva Research Center, IL (United States))

1992-05-01T23:59:59.000Z

100

THE RETRIEVAL KNOWLEDGE CENTER EVALUATION OF LOW TANK LEVEL MIXING TECHNOLOGIES FOR DOE HIGH LEVEL WASTE TANK RETRIEVAL 10516  

SciTech Connect (OSTI)

The Department of Energy (DOE) Complex has over two-hundred underground storage tanks containing over 80-million gallons of legacy waste from the production of nuclear weapons. The majority of the waste is located at four major sites across the nation and is planned for treatment over a period of almost forty years. The DOE Office of Technology Innovation & Development within the Office of Environmental Management (DOE-EM) sponsors technology research and development programs to support processing advancements and technology maturation designed to improve the costs and schedule for disposal of the waste and closure of the tanks. Within the waste processing focus area are numerous technical initiatives which included the development of a suite of waste removal technologies to address the need for proven equipment and techniques to remove high level radioactive wastes from the waste tanks that are now over fifty years old. In an effort to enhance the efficiency of waste retrieval operations, the DOE-EM Office of Technology Innovation & Development funded an effort to improve communications and information sharing between the DOE's major waste tank locations as it relates to retrieval. The task, dubbed the Retrieval Knowledge Center (RKC) was co-lead by the Savannah River National Laboratory (SRNL) and the Pacific Northwest National Laboratory (PNNL) with core team members representing the Oak Ridge and Idaho sites, as well as, site contractors responsible for waste tank operations. One of the greatest challenges to the processing and closure of many of the tanks is complete removal of all tank contents. Sizeable challenges exist for retrieving waste from High Level Waste (HLW) tanks; with complications that are not normally found with tank retrieval in commercial applications. Technologies currently in use for waste retrieval are generally adequate for bulk removal; however, removal of tank heels, the materials settled in the bottom of the tank, using the same technology have proven to be difficult. Through the RKC, DOE-EM funded an evaluation of adaptable commercial technologies that could assist with the removal of the tank heels. This paper will discuss the efforts and results of developing the RKC to improve communications and discussion of tank waste retrieval through a series of meetings designed to identify technical gaps in retrieval technologies at the DOE Hanford and Savannah River Sites. This paper will also describe the results of an evaluation of commercially available technologies for low level mixing as they might apply to HLW tank heel retrievals.

Fellinger, A.

2009-12-08T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Characterization, Leaching, and Filtration Testing for Tributyl Phosphate (TBP, Group 7) Actual Waste Sample Composites  

SciTech Connect (OSTI)

.A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. The actual waste-testing program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. The tributyl phosphate sludge (TBP, Group 7) is the subject of this report. The Group 7 waste was anticipated to be high in phosphorus as well as aluminum in the form of gibbsite. Both are believed to exist in sufficient quantities in the Group 7 waste to address leaching behavior. Thus, the focus of the Group 7 testing was on the removal of both P and Al. The waste-type definition, archived sample conditions, homogenization activities, characterization (physical, chemical, radioisotope, and crystal habit), and caustic leaching behavior as functions of time, temperature, and hydroxide concentration are discussed in this report. Testing was conducted according to TP-RPP-WTP-467.

Edwards, Matthew K.; Billing, Justin M.; Blanchard, David L.; Buck, Edgar C.; Casella, Amanda J.; Casella, Andrew M.; Crum, J. V.; Daniel, Richard C.; Draper, Kathryn E.; Fiskum, Sandra K.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Snow, Lanee A.; Swoboda, Robert G.

2009-03-09T23:59:59.000Z

102

Bulk Power Transmission Study  

E-Print Network [OSTI]

, obsolete power plants. The freedom to locate these facilities at the fuel source or at the site of large thermal demand makes real economic and environmental sense. The use of renewable or waste fuels allows something that would otherwise be wasted...

John, T.

103

Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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...

104

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

105

Nuclear waste solutions  

DOE Patents [OSTI]

High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

Walker, Darrel D. (1684 Partridge Dr., Aiken, SC 29801); Ebra, Martha A. (129 Hasty Rd., Aiken, SC 29801)

1987-01-01T23:59:59.000Z

106

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

The objective of this research is to explore new liquid-liquid extraction approaches to the selective separation of major sodium salts from alkaline high-level wastes stored in underground tanks at Hanford, Savannah River, and Oak Ridge sites. Disposal of high level waste is horrendously expensive, in large part because the actual radioactive matter in the tanks has been diluted over 1000-fold by ordinary inorganic chemicals. Since the residual bulk chemicals must still undergo expensive treatment and disposal after most of the hazardous radionuclides have been removed, large cost savings will result from processes that reduce the overall waste volume. It is proposed that major cost savings can be expected if sodium hydroxide needed for sludge washing can be obtained from the waste itself, thus avoiding the addition of yet another bulk chemical to the waste and still further increase of the waste volume and disposal cost. Secondary priority is given to separating potassium an d abundant anions, including nitrate, nitrite, aluminate, and carbonate. Salts of these ions represent possible additional value for recycle, alternative disposal, or even use as commodity chemicals. A comprehensive approach toward understanding the extractive chemistry of these salts is envisioned, involving systems of varying complexity, from use of simple solvents to new bifunctional host molecules for ion-pair recognition. These extractants will ideally require no adjustment of the waste composition and will release the extracted salt into water, thereby consuming no additional chemicals and producing no additional waste volume. The overall goal of this research is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated.

Moyer, Bruce A.; Marchand, Alan P.; Bryan, Jeffrey C.; Bonnesen, Peter V.

1999-06-01T23:59:59.000Z

107

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

SciTech Connect (OSTI)

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

108

Method for aqueous radioactive waste treatment  

DOE Patents [OSTI]

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

Bray, Lane A. (Richland, WA); Burger, Leland L. (Richland, WA)

1994-01-01T23:59:59.000Z

109

Bulk Hydrogen Strategic Directions for  

E-Print Network [OSTI]

Bulk Hydrogen Storage Strategic Directions for Hydrogen Delivery Workshop May 7-8, 2003 Crystal City, Virginia #12;Breakout Session - Bulk Hydrogen Storage Main Themes/Caveats Bulk Storage = Anything storage is an economic solution to address supply/demand imbalance #12;Breakout Session - Bulk Hydrogen

110

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

111

Auctioning Bulk Mobile Messages  

Science Journals Connector (OSTI)

The search for enablers of continued growth of SMS traffic, as well as the take-off of the more diversified MMS message contents, open up for enterprises the potential of bulk use of mobile messaging, instead of essentially one-by-one use. In parallel, ... Keywords: EMS, MMS, SMS, auctions, mobile commerce, mobile operators, multi-attribute auctions

S. Meij; L. -F. Pau

2006-05-01T23:59:59.000Z

112

Hanford ETR Bulk Vitrification System - Demonstration Bulk Vitrification System (DBVS) Review Report  

Broader source: Energy.gov (indexed) [DOE]

A Comprehensive Technical A Comprehensive Technical Review of the Demonstration Bulk Vitrification System Technical Assessment Conducted by an Independent and External Team of Experts Volume 1 September 28, 2006 Chartered by CH2M HILL Hanford Group, Inc. Richland, Washington 99352 RPP-31314 Executive Summary In May 2006, CH2M HILL Hanford Group, Inc. chartered an Expert Review Panel (ERP) to review the current status of the Demonstration Bulk Vitrification System (DBVS). It is the consensus of the ERP that bulk vitrification is a technology that requires further development and evaluation to determine its potential for meeting the Hanford waste stabilization mission. No fatal flaws (issues that would jeopardize the overall DBVS mission that cannot be mitigated) were found, given the current state of the project.

113

Petroleum Chemicals: Bulk Detergents  

Science Journals Connector (OSTI)

... One of the largest users of detergents is the textile industry. For example, raw wool, either used alone or blended with synthetic fibres, must be ... , either used alone or blended with synthetic fibres, must be scoured to remove dirt and ...

H. B. MILNER

1964-02-29T23:59:59.000Z

114

Waste Encapsulation and Storage Facility - Hanford Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

of heat were removed from the high level waste tanks at Hanford. Called cesium and strontium, these elements had to be taken out of single shell waste tanks to reduce the...

115

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

116

High Level Waste ManagemenfDivision ..  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

B.2 Environmental Documentation C. Regulatory Waste Removal Schedule (Type I, II and IV Tanks) D. Process Logic Diagram E. Process Logic Interactive Matrix F. HLW Integrated...

117

Stabilization of compactible waste  

SciTech Connect (OSTI)

This report summarizes the results of series of experiments performed to determine the feasibility of stabilizing compacted or compactible waste with polymers. The need for this work arose from problems encountered at disposal sites attributed to the instability of this waste in disposal. These studies are part of an experimental program conducted at Brookhaven National Laboratory (BNL) investigating methods for the improved solidification/stabilization of DOE low-level wastes. The approach taken in this study was to perform a series of survey type experiments using various polymerization systems to find the most economical and practical method for further in-depth studies. Compactible dry bulk waste was stabilized with two different monomer systems: styrene-trimethylolpropane trimethacrylate (TMPTMA) and polyester-styrene, in laboratory-scale experiments. Stabilization was accomplished by wetting or soaking compactible waste (before or after compaction) with monomers, which were subsequently polymerized. Three stabilization methods are described. One involves the in-situ treatment of compacted waste with monomers in which a vacuum technique is used to introduce the binder into the waste. The second method involves the alternate placement and compaction of waste and binder into a disposal container. In the third method, the waste is treated before compaction by wetting the waste with the binder using a spraying technique. A series of samples stabilized at various binder-to-waste ratios were evaluated through water immersion and compression testing. Full-scale studies were conducted by stabilizing two 55-gallon drums of real compacted waste. The results of this preliminary study indicate that the integrity of compacted waste forms can be readily improved to ensure their long-term durability in disposal environments. 9 refs., 10 figs., 2 tabs.

Franz, E.M.; Heiser, J.H. III; Colombo, P.

1990-09-01T23:59:59.000Z

118

Creating bulk nanocrystalline metal.  

SciTech Connect (OSTI)

Nanocrystalline and nanostructured materials offer unique microstructure-dependent properties that are superior to coarse-grained materials. These materials have been shown to have very high hardness, strength, and wear resistance. However, most current methods of producing nanostructured materials in weapons-relevant materials create powdered metal that must be consolidated into bulk form to be useful. Conventional consolidation methods are not appropriate due to the need to maintain the nanocrystalline structure. This research investigated new ways of creating nanocrystalline material, new methods of consolidating nanocrystalline material, and an analysis of these different methods of creation and consolidation to evaluate their applicability to mesoscale weapons applications where part features are often under 100 {micro}m wide and the material's microstructure must be very small to give homogeneous properties across the feature.

Fredenburg, D. Anthony (Georgia Institute of Technology, Atlanta, GA); Saldana, Christopher J. (Purdue University, West Lafayette, IN); Gill, David D.; Hall, Aaron Christopher; Roemer, Timothy John (Ktech Corporation, Albuquerque, NM); Vogler, Tracy John; Yang, Pin

2008-10-01T23:59:59.000Z

119

Ferrocyanide tank waste stability  

SciTech Connect (OSTI)

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

Fowler, K.D.

1993-01-01T23:59:59.000Z

120

Silica Scaling Removal Process  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Silica Scaling Removal Process Silica Scaling Removal Process Scientists at Los Alamos National Laboratory have developed a novel technology to remove both dissolved and colloidal...

Note: This page contains sample records for the topic "bulk waste removal" 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

Method for processing aqueous wastes  

DOE Patents [OSTI]

A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

122

Bulk Heterojunction Polymer Solar Cells  

Science Journals Connector (OSTI)

Recent developments on bulk-heterojunction polymer photovoltaic diodes will be presented, focusing on the mechanism of charge generation, low bandgap polymers for increased photon...

Janssen, Ren

123

Salt Waste Processing Initiatives  

Broader source: Energy.gov (indexed) [DOE]

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%)

124

Los Alamos exceeds waste shipping goal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

125

Los Alamos exceeds waste shipping goal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

126

Characterization, Leaching, and Filtration Testing for Bismuth Phosphate Sludge (Group 1) and Bismuth Phosphate Saltcake (Group 2) Actual Waste Sample Composites  

SciTech Connect (OSTI)

A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan.() The test program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. The actual waste-testing program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. Two of the eight defined groupsbismuth phosphate sludge (Group 1) and bismuth phosphate saltcake (Group2)are the subjects of this report. The Group 1 waste was anticipated to be high in phosphorus and was implicitly assumed to be present as BiPO4 (however, results presented here indicate that the phosphate in Group 1 is actually present as amorphous iron(III) phosphate). The Group 2 waste was also anticipated to be high in phosphorus, but because of the relatively low bismuth content and higher aluminum content, it was anticipated that the Group 2 waste would contain a mixture of gibbsite, sodium phosphate, and aluminum phosphate. Thus, the focus of the Group 1 testing was on determining the behavior of P removal during caustic leaching, and the focus of the Group 2 testing was on the removal of both P and Al. The waste-type definition, archived sample conditions, homogenization activities, characterization (physical, chemical, radioisotope, and crystal habit), and caustic leaching behavior as functions of time, temperature, and hydroxide concentration are discussed in this report. Testing was conducted according to TP-RPP-WTP-467.

Lumetta, Gregg J.; Buck, Edgar C.; Daniel, Richard C.; Draper, Kathryn; Edwards, Matthew K.; Fiskum, Sandra K.; Hallen, Richard T.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Shimskey, Rick W.; Sinkov, Sergey I.; Snow, Lanee A.

2009-02-19T23:59:59.000Z

127

DOE/LX/07-0267&D1 Secondary Document DMSA C-337-35 Solid Waste...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

WASTE QUANTITY: Currently 0 ft 3 ; waste quantity removed 278 ft 3 SUMMARY OF ENVIRONMENTAL SAMPLING DATA: No sampling of environmental media has occurred. DESCRIPTION OF...

128

Strontium and cesium release mechanisms during unsaturated flow through waste-weathered Hanford sediments  

E-Print Network [OSTI]

Plutonium from Simulated Hanford Tank-Waste Sludges. Separ.Containing Tank Waste at Hanford. Separ. Sci. Technol. 2005,T. B. , Sr/TRU Removal from Hanford High Level Waste. Separ.

Chang, H.

2013-01-01T23:59:59.000Z

129

Optimization of Waste Disposal - 13338  

SciTech Connect (OSTI)

From 2009 through 2011, remediation of areas of a former fuel cycle facility used for government contract work was conducted. Remediation efforts were focused on building demolition, underground pipeline removal, contaminated soil removal and removal of contaminated sediments from portions of an on-site stream. Prior to conducting the remediation field effort, planning and preparation for remediation (including strategic planning for waste characterization and disposal) was conducted during the design phase. During the remediation field effort, waste characterization and disposal practices were continuously reviewed and refined to optimize waste disposal practices. This paper discusses strategic planning for waste characterization and disposal that was employed in the design phase, and continuously reviewed and refined to optimize efficiency. (authors)

Shephard, E.; Walter, N.; Downey, H. [AMEC E and I, Inc., 511 Congress Street, Suite 200, Portland, ME 04101 (United States)] [AMEC E and I, Inc., 511 Congress Street, Suite 200, Portland, ME 04101 (United States); Collopy, P. [AMEC E and I, Inc., 9210 Sky Park Court, Suite 200, San Diego, CA 92123 (United States)] [AMEC E and I, Inc., 9210 Sky Park Court, Suite 200, San Diego, CA 92123 (United States); Conant, J. [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)] [ABB Inc., 5 Waterside Crossing, Windsor, CT 06095 (United States)

2013-07-01T23:59:59.000Z

130

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)  

SciTech Connect (OSTI)

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

131

THE PERFORMANCE AND MODIFICATION OF RECYCLED ELECTRONIC WASTE PLASTICS FOR THE IMPROVEMENT OF ASPHALT PAVEMENT MATERIALS.  

E-Print Network [OSTI]

?? Bulk electric waste plastics were recycled and reduced in size into plastic chips before pulverization or cryogenic grinding into powders. Two major types of (more)

Colbert, Baron W.

2012-01-01T23:59:59.000Z

132

Radioactive waste management and decommissioning of accelerator facilities  

Science Journals Connector (OSTI)

......the removed radioactive waste shall be treated and processed for either long-term storage or disposal. delayed...facility itself becomes a long-term storage that shall be...dismantling resources, waste storage space or development......

Luisa Ulrici; Matteo Magistris

2009-11-01T23:59:59.000Z

133

bulk power | OpenEI  

Open Energy Info (EERE)

bulk power bulk power Dataset Summary Description The Form EIA-411, "Coordinated Bulk Power Supply Program Report," collects information from the Nation's power system planners about the electricity supply, both capacity and energy, that is needed to serve current demand and for future growth. Source Energy Information Administration (EIA) Date Released December 03rd, 2010 (3 years ago) Date Updated December 03rd, 2010 (3 years ago) Keywords bulk power EIA Electricity Generation Data application/vnd.ms-excel icon Net Energy for Load - Historic, Actual and Projected Five-Years (xls, 26.1 KiB) application/vnd.ms-excel icon Noncoincident Peak Load - Historic, Actual and Projected Five-Years (xls, 25.6 KiB) application/vnd.ms-excel icon Noncoincident Peak Load - Historic, Actual and Projected Five-Years (xls, 0 bytes)

134

Bulk Hauling Equipment for CHG  

Broader source: Energy.gov (indexed) [DOE]

load of CHG Semitrailer Mass Trailer or ModuleChassis Module Mass Hydrogen Gas Mass CAPITAL EXPENDITURE FOR BULK HAULING EQUIPMENT For large consumption, total CapEx for...

135

Lab sets new record for waste shipments  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

New record for waste shipments New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall cleanup." Each shipment moves LANL closer to cleanup LOS ALAMOS, New Mexico, August 20, 2010-Los Alamos National Laboratory set a new LANL record on Friday by completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment eclipsed last year's

136

Thermal Pretreatment For TRU Waste Sorting  

SciTech Connect (OSTI)

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

137

High Level Waste Management Division . H L W System Plan  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

and Regulatory Documentation C. Regulatory Waste Removal Schedule (Type I, II and IV Tanks) D. Process Logic Diagram E. Process Logic Interactive Matrix F. HLW Integrated...

138

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams  

SciTech Connect (OSTI)

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

139

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

140

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect (OSTI)

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Treatment requirements for decontamination of ORNL low-level liquid waste  

SciTech Connect (OSTI)

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

142

Bulk Viscosity of Interacting Hadrons  

E-Print Network [OSTI]

We show that first approximations to the bulk viscosity $\\eta_v$ are expressible in terms of factors that depend on the sound speed $v_s$, the enthalpy, and the interaction (elastic and inelastic) cross section. The explicit dependence of $\\eta_v$ on the factor $(\\frac 13 - v_s^2)$ is demonstrated in the Chapman-Enskog approximation as well as the variational and relaxation time approaches. The interesting feature of bulk viscosity is that the dominant contributions at a given temperature arise from particles which are neither extremely nonrelativistic nor extremely relativistic. Numerical results for a model binary mixture are reported.

A. Wiranata; M. Prakash

2009-06-30T23:59:59.000Z

143

Charm contribution to bulk viscosity  

E-Print Network [OSTI]

In the range of temperatures reached in future heavy ion collision experiments, hadronic pair annihilations and creations of charm quarks may take place within the lifetime of the plasma. As a result, charm quarks may increase the bulk viscosity affecting the early stages of hydrodynamic expansion. Assuming thermalization, we estimate the charm contribution to bulk viscosity within the same effective kinetic theory framework in which the light parton contribution has been computed previously. The time scale at which this physics becomes relevant is related to the width of the transport peak associated with the trace anomaly correlator, and is found to be 600 MeV.

Laine, M

2014-01-01T23:59:59.000Z

144

Charm contribution to bulk viscosity  

E-Print Network [OSTI]

In the range of temperatures reached in future heavy ion collision experiments, hadronic pair annihilations and creations of charm quarks may take place within the lifetime of the plasma. As a result, charm quarks may increase the bulk viscosity affecting the early stages of hydrodynamic expansion. Assuming thermalization, we estimate the charm contribution to bulk viscosity within the same effective kinetic theory framework in which the light parton contribution has been computed previously. The time scale at which this physics becomes relevant is related to the width of the transport peak associated with the trace anomaly correlator, and is found to be 600 MeV.

M. Laine; Kiyoumars A. Sohrabi

2014-10-24T23:59:59.000Z

145

Technologies for Boron Removal  

Science Journals Connector (OSTI)

Tests were performed to examine the removal of boron from aqueous solution either with polyvinyl alcohol (PVA) alone or by both PVA and other inorganic additives under room temperature. ... Added calcium hydroxide increased the co-removal of borate with PVA, and this offers a polishing treatment after borate removal by liming. ... As boron removal can be achieved by chemical precipitation and coagulation, it is logical to assume that the EC could remove boron from water and industrial effluent. ...

Yonglan Xu; Jia-Qian Jiang

2007-11-23T23:59:59.000Z

146

NETL: Gasification Systems - Warm Gas Multi-Contaminant Removal System  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Warm Gas Multi-Contaminant Removal System Warm Gas Multi-Contaminant Removal System Project Number: DE-SC00008243 TDA Research, Inc. is developing a high-capacity, low-cost sorbent that removes anhydrous ammonia (NH3), mercury (Hg), and trace contaminants from coal- and coal/biomass-derived syngas. The clean-up system will be used after the bulk warm gas sulfur removal step, and remove NH3 and Hg in a regenerable manner while irreversibly capturing all other trace metals (e.g., Arsenic, Selenium) reducing their concentrations to sub parts per million (ppm) levels. Current project plans include identifying optimum chemical composition and structure that provide the best sorbent performance for removing trace contaminants, determining the effect of operating parameters, conducting multiple-cycle experiments to test the life of the sorbent for NH3 and Hg removal, and conducting a preliminary design of the sorbent reactor.

147

Treatment of halogen-containing waste and other waste materials  

DOE Patents [OSTI]

A process is described for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1997-03-18T23:59:59.000Z

148

Treatment of halogen-containing waste and other waste materials  

DOE Patents [OSTI]

A process for treating a halogen-containing waste material. The process provides a bath of molten glass containing a sacrificial metal oxide capable of reacting with a halogen in the waste material. The sacrificial metal oxide is present in the molten glass in at least a stoichiometric amount with respect to the halogen in the waste material. The waste material is introduced into the bath of molten glass to cause a reaction between the halogen in the waste material and the sacrificial metal oxide to yield a metal halide. The metal halide is a gas at the temperature of the molten glass. The gaseous metal halide is separated from the molten glass and contacted with an aqueous scrubber solution of an alkali metal hydroxide to yield a metal hydroxide or metal oxide-containing precipitate and a soluble alkali metal halide. The precipitate is then separated from the aqueous scrubber solution. The molten glass containing the treated waste material is removed from the bath as a waste glass. The process of the invention can be used to treat all types of waste material including radioactive wastes. The process is particularly suited for separating halogens from halogen-containing wastes.

Forsberg, Charles W. (Oak Ridge, TN); Beahm, Edward C. (Oak Ridge, TN); Parker, George W. (Concord, TN)

1997-01-01T23:59:59.000Z

149

Bulk viscosity and deflationary universes  

E-Print Network [OSTI]

We analyze the conditions that make possible the description of entropy generation in the new inflationary model by means of a nearequilibrium process. We show that there are situations in which the bulk viscosity cannot describe particle production during the coherent field oscillations phase.

J. A. S. Lima; R. Portugal; I. Waga

2007-08-24T23:59:59.000Z

150

Handbook of industrial and hazardous wastes treatment. 2nd ed.  

SciTech Connect (OSTI)

This expanded Second Edition offers 32 chapters of industry- and waste-specific analyses and treatment methods for industrial and hazardous waste materials - from explosive wastes to landfill leachate to wastes produced by the pharmaceutical and food industries. Key additional chapters cover means of monitoring waste on site, pollution prevention, and site remediation. Including a timely evaluation of the role of biotechnology in contemporary industrial waste management, the Handbook reveals sound approaches and sophisticated technologies for treating: textile, rubber, and timber wastes; dairy, meat, and seafood industry wastes; bakery and soft drink wastes; palm and olive oil wastes; pesticide and livestock wastes; pulp and paper wastes; phosphate wastes; detergent wastes; photographic wastes; refinery and metal plating wastes; and power industry wastes. This final chapter, entitled 'Treatment of power industry wastes' by Lawrence K. Wang, analyses the stream electric power generation industry, where combustion of fossil fuels coal, oil, gas, supplies heat to produce stream, used then to generate mechanical energy in turbines, subsequently converted to electricity. Wastes include waste waters from cooling water systems, ash handling systems, wet-scrubber air pollution control systems, and boiler blowdown. Wastewaters are characterized and waste treatment by physical and chemical systems to remove pollutants is presented. Plant-specific examples are provided.

Lawrence Wang; Yung-Tse Hung; Howard Lo; Constantine Yapijakis (eds.)

2004-06-15T23:59:59.000Z

151

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...

152

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

153

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.

154

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

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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).

155

Turbomachinery debris remover  

DOE Patents [OSTI]

An apparatus for removing debris from a turbomachine. The apparatus includes housing and remotely operable viewing and grappling mechanisms for the purpose of locating and removing debris lodged between adjacent blades in a turbomachine.

Krawiec, Donald F. (Pittsburgh, PA); Kraf, Robert J. (North Huntingdon, PA); Houser, Robert J. (Monroeville, PA)

1988-01-01T23:59:59.000Z

156

Measurement of radioactive contaminated wastes  

SciTech Connect (OSTI)

At Los Alamos, a comprehensive program is underway for the development of sensitive, practical, nondestructive assay techniques for the quantification of low-level transuranics in bulk solid wastes. The program encompasses a broad range of techniques, including sophisticated active and passive gamma-ray spectroscopy, passive neutron detection systems, pulsed portable neutron generator interrogation systems, and electron accelerator-based techniques. The techniques can be used with either low-level or high-level beta-gamma wastes in either low-density or high-density matrices. The techniques are quite sensitive (< 10 nCi/g detection) and, in many cases, isotopic specific. Waste packages range in size from small cardboard boxes to large metal or wooden crates. Considerable effort is being expended on waste matrix identification to improve assay accuracy.

Caldwell, J.T.; Close, D.A.; Crane, T.W.

1983-01-01T23:59:59.000Z

157

Bulk Hauling Equipment for CHG  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

BULK HAULING EQUIPMENT FOR CHG BULK HAULING EQUIPMENT FOR CHG Don Baldwin Director of Product Development - Hexagon Lincoln HEXAGON LINCOLN TITAN(tm) Module System Compressed Hydrogen Gas * Capacity 250 bar - 616 kg 350 bar - 809 kg 540 bar - 1155 kg * Gross Vehicle Weight (with prime mover) 250 bar - 28 450 kg 350 bar - 30 820 kg 540 bar - 39 440 kg * Purchase Cost 250 bar - $510,000 350 bar - $633,750 540 bar - $1,100,000 Compressed Natural Gas * Capacity (250 bar at 15 C) - 7412 kg * GVW (With prime mover) - 35 250 kg * Purchase Cost (+/- 5%) - $510,000 HEXAGON LINCOLN TITAN(tm) V Magnum Trailer System Compressed Hydrogen Gas * Capacity 250 bar - 800 kg 350 bar - 1050 kg 540 bar - 1500 kg * Gross Vehicle Weight (with prime mover) 250 bar - 31 000 kg 350 bar - 34 200 kg 540 bar - 45 700 kg * Purchase Cost (+/-

158

Bulk viscosity in hybrid stars  

Science Journals Connector (OSTI)

We compute the bulk viscosity of a mixed quark-hadron phase. In the first scenario to be discussed, the mixed phase occurs at large densities and we assume that it is composed of a mixing of hyperonic matter and quarks in the Color Flavor Locked phase. In a second scenario, the mixed phase occurs at lower densities and it is composed of a mixing of nucleons and unpaired quark matter. We have also investigated the effect of a nonvanishing surface tension at the interface between hadronic and quark matter. In both scenarios, the bulk viscosity is large when the surface tension is absent, while the value of the viscosity reduces in the second scenario when a finite value for the surface tension is taken into account. In all cases, the r-mode instabilities of the corresponding hybrid star are suppressed.

A. Drago; A. Lavagno; G. Pagliara

2005-05-16T23:59:59.000Z

159

Categorical Exclusion 4565, Waste Management Construction Support  

Broader source: Energy.gov (indexed) [DOE]

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

160

ENVIRONMENTAL ASSESSMENT Waste Water Treatment Modifications for  

E-Print Network [OSTI]

Actions - Isolate and restore sand filter beds (~10 acres) - Remove UV light sanitation system ­ evaluateENVIRONMENTAL ASSESSMENT FOR Waste Water Treatment Modifications for Improved Effluent Compliance adhering to them. · Develop recharge basins for disposal of treated waste water. Polythiocarbonate

Homes, Christopher C.

Note: This page contains sample records for the topic "bulk waste removal" 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

Bulk Vitrification Performance Enhancement: Refractory Lining Protection Against Molten Salt Penetration  

SciTech Connect (OSTI)

Bulk vitrification (BV) is a process that heats a feed material that consists of glass-forming solids and dried low-activity waste (LAW) in a disposable refractory-lined metal box using electrical power supplied through carbon electrodes. The feed is heated to the point that the LAW decomposes and combines with the solids to generate a vitreous waste form. This study supports the BV design and operations by exploring various methods aimed at reducing the quantities of soluble Tc in the castable refractory block portion of the refractory lining, which limits the effectiveness of the final waste form.

Hrma, Pavel R.; Bagaasen, Larry M.; Schweiger, Michael J.; Evans, Michael B.; Smith, Benjamin T.; Arrigoni, Benjamin M.; Kim, Dong-Sang; Rodriguez, Carmen P.; Yokuda, Satoru T.; Matyas, Josef; Buchmiller, William C.; Gallegos, Autumn B.; Fluegel, Alexander

2007-08-06T23:59:59.000Z

162

The WIPP Hazardous Waste Facility Permit Improvements--2007 Update  

SciTech Connect (OSTI)

The most significant changes to the Waste Isolation Pilot Plant Hazardous Waste Facility Permit to date were completed during the past year with the implementation of significant revisions to the Waste Analysis Plan and the authorization to dispose of remote-handled transuranic waste. The modified Permit removes the requirement for reporting headspace gas sampling and analysis results for every container of transuranic mixed waste and provides for the use of radiography and visual examination to confirm a statistically representative subpopulation of the waste stream in each waste shipment as well as other changes that streamline the analytical data management process. Implementation began on November 17, 2006. (authors)

Kehrman, R.; Most, W. [Washington Regulatory and Environmental Services, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

163

ACCEPTED BY WATER ENVIRONMENT RESEARCH ODOR AND VOC REMOVAL FROM WASTEWATER TREATMENT PLANT  

E-Print Network [OSTI]

of their high rates of chemical consumption. Additionally, chemical scrubbers are ineffective for the removalACCEPTED BY WATER ENVIRONMENT RESEARCH _______ ODOR AND VOC REMOVAL FROM WASTEWATER TREATMENT PLANT of biofilters for sequential removal of H2S and VOCs from wastewater treatment plant waste air. The biofilter

164

Transuranium Removal from Hanford AN-107 Simulants using Sodium Permanganate and Calcium  

SciTech Connect (OSTI)

Removal of strontium from the complexant-containing wastes (AN-102 and AN-107) had previously been acceptably accomplished by isotopic dilution. Actinide removal using ferric co-precipitation, however, was very problematic from both a processing and a decontamination standpoint. Therefore, a series of tests were performed to identify other potential actinide removal agents and to test these agents at various concentrations.

Wilmarth, W.

2000-08-30T23:59:59.000Z

165

Diffusive shielding stabilizes bulk nanobubble clusters  

E-Print Network [OSTI]

Using molecular dynamics, we study the nucleation and stability of bulk nanobubble clusters. We study the formation, growth, and final size of bulk nanobubbles. We find that, as long as the bubble-bubble interspacing is small enough, bulk nanobubbles are stable against dissolution. Simple diffusion calculations provide an excellent match with the simulation results, giving insight into the reason for the stability: nanobubbles in a cluster of bulk nanobubbles "protect" each other from diffusion by a shielding effect.

Weijs, Joost H; Lohse, D

2011-01-01T23:59:59.000Z

166

HANFORD MEDIUM & LOW CURIE WASTE PRETREATMENT PROJECT PHASE 1 LAB REPORT  

SciTech Connect (OSTI)

A fractional crystallization (FC) process is being developed to supplement tank waste pretreatment capabilities provided by the Waste Treatment and Immobilization Plant (WTP). FC can process many tank wastes, separating wastes into a low-activity fraction (LAW) and high-activity fraction (HLW). The low-activity fraction can be immobilized in a glass waste form by processing in the bulk vitrification (BV) system.

HAMILTON, D.W.

2006-01-30T23:59:59.000Z

167

Waste Treatment Plant - 12508  

SciTech Connect (OSTI)

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

168

RADIATION PROTECTION, RADIOACTIVE WASTE MANAGEMENT AND SITE MONITORING AT THE NUCLEAR SCIENTIFIC EXPERIMENTAL AND EDUCATIONAL CENTRE IRT-SOFIA AT INRNE-BAS  

Science Journals Connector (OSTI)

......related to radioactive waste treatments and interim...site to the temporary storage of radioactive waste operated by SE . Removal...The comprehensive long-term monitoring of the IRT...protection and radioactive waste management in the design......

Al. Mladenov; D. Stankov; Tz. Nonova; K. Krezhov

2014-07-01T23:59:59.000Z

169

USE OF AN EQUILIBRIUM MODEL TO FORECAST DISSOLUTION EFFECTIVENESS, SAFETY IMPACTS, AND DOWNSTREAM PROCESSABILITY FROM OXALIC ACID AIDED SLUDGE REMOVAL IN SAVANNAH RIVER SITE HIGH LEVEL WASTE TANKS 1-15  

SciTech Connect (OSTI)

This thesis details a graduate research effort written to fulfill the Magister of Technologiae in Chemical Engineering requirements at the University of South Africa. The research evaluates the ability of equilibrium based software to forecast dissolution, evaluate safety impacts, and determine downstream processability changes associated with using oxalic acid solutions to dissolve sludge heels in Savannah River Site High Level Waste (HLW) Tanks 1-15. First, a dissolution model is constructed and validated. Coupled with a model, a material balance determines the fate of hypothetical worst-case sludge in the treatment and neutralization tanks during each chemical adjustment. Although sludge is dissolved, after neutralization more is created within HLW. An energy balance determines overpressurization and overheating to be unlikely. Corrosion induced hydrogen may overwhelm the purge ventilation. Limiting the heel volume treated/acid added and processing the solids through vitrification is preferred and should not significantly increase the number of glass canisters.

KETUSKY, EDWARD

2005-10-31T23:59:59.000Z

170

Risk Removal | Department of Energy  

Energy Savers [EERE]

Risk Removal Risk Removal Workers safely remove old mercury tanks from the Y-12 National Security Complex. Workers safely remove old mercury tanks from the Y-12 National Security...

171

Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation and Recycle of Sodium Hydroxide and Sodium Nitrate  

SciTech Connect (OSTI)

This research has focused on new liquid-liquid extraction chemistry applicable to separation of major sodium salts from alkaline tank waste. It was the overall goal to provide the scientific foundation upon which the feasibility of liquid-liquid extraction chemistry for bulk reduction of the volume of tank waste can be evaluated. Sodium hydroxide represented the initial test case and primary focus. It is a primary component of the waste1 and has the most value for recycle. A full explanation of the relevance of this research to USDOE Environmental Management needs will be given in the Relevance, Impact, and Technology Transfer section below. It should be noted that this effort was predicated on the need for sodium removal primarily from low-activity waste, whereas evolving needs have shifted attention to volume reduction of the high-activity waste. The results of the research to date apply to both applications, though treatment of high-activity wastes raises new questions that will be addressed in the renewal period. Toward understanding the extractive chemistry of sodium hydroxide and other sodium salts, it was the intent to identify candidate extractants and determine their applicable basic properties regarding selectivity, efficiency, speciation, and structure. A hierarchical strategy was to be employed in which the type of liquid-liquid-extraction system varied in sophistication from simple, single-component solvents to solvents containing designer host molecules. As an aid in directing this investigation toward addressing the fundamental questions having the most value, a conceptualization of an ideal process was advanced. Accordingly, achieving adequate selectivity for sodium hydroxide represented a primary goal, but this result is worthwhile for waste applications only if certain conditions are met.

Moyer, Bruce A.; Marchand, Alan P.; Bonnesen, Peter V.; Bryan, Jeffrey C.; Haverlock, Tamara J.

2002-03-30T23:59:59.000Z

172

RAPID/BulkTransmission/Siting/California | Open Energy Information  

Open Energy Info (EERE)

Information Desktop Toolkit BETA RAPID Toolkit About Bulk Transmission Geothermal Solar Resources Contribute Contact Us RAPID Bulk Transmission Siting California Bulk...

173

Bulk Hydrogen Storage - Strategic Directions for Hydrogen Delivery...  

Broader source: Energy.gov (indexed) [DOE]

Bulk Hydrogen Storage Strategic Directions for Hydrogen Delivery Workshop May 7-8, 2003 Crystal City, Virginia Breakout Session - Bulk Hydrogen Storage Main ThemesCaveats Bulk...

174

RAPID/BulkTransmission/Power Plant | Open Energy Information  

Open Energy Info (EERE)

BulkTransmissionPower Plant < RAPID | BulkTransmission Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA RAPID Toolkit About Bulk...

175

Savannah River Tank Waste Residuals  

Broader source: Energy.gov (indexed) [DOE]

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

176

Environmental Solutions, A Summary of Contributions for CY04: Battelle Contributions to the Waste Treatment Plant  

SciTech Connect (OSTI)

In support of the Waste Treatment Plant (WTP), Battelle conducted tests on mixing specific wastes within the plant, removing troublesome materials from the waste before treatment, and determining if the final waste forms met the established criteria. In addition, several Battelle experts filled full-time positions in WTP's Research and Testing and Process and Operations departments.

Beeman, Gordon H.

2005-03-08T23:59:59.000Z

177

Process for treating waste water having low concentrations of metallic contaminants  

DOE Patents [OSTI]

A process for treating waste water having a low level of metallic contaminants by reducing the toxicity level of metallic contaminants to an acceptable level and subsequently discharging the treated waste water into the environment without removing the treated contaminants.

Looney, Brian B; Millings, Margaret R; Nichols, Ralph L; Payne, William L

2014-12-16T23:59:59.000Z

178

Operability test procedure [Tank] 241-SY-101 equipment removal system  

SciTech Connect (OSTI)

The 241-SY-101 equipment removal system (ERS) consists of components, equipment, instrumentation and procedures that will provide the means to disconnect, retrieve, contain, load and transport the Mitigation Pump Assembly (MPA) from waste Tank 241-SY-101 to the Central Waste Complex (CWC). The Operability Test Procedure (OTP) will test the interfaces between ERS components and will rehearse the procedure for MPA removal and transportation to the extent they can be mocked-up at the CTF (Cold Test Facility). At the conclusion of the OTP, the ERS components and equipment will be removed from the CTF, entered into the Component Based Recall System (CBRS), and stored until needed for actual MPA removal and transportation.

Mast, J.C.

1994-12-08T23:59:59.000Z

179

A reclamation approach for mined prime farmland by adding organic wastes and lime to the subsoil  

SciTech Connect (OSTI)

Surface mined prime farmland may be reclaimed by adding organic wastes and lime to subsoil thus improving conditions in root zone. In this study, sewage sludge, poultry manure, horse bedding, and lime were applied to subsoil (15-30 cm) during reclamation. Soil properties and plant growth were measured over two years. All organic amendments tended to lower the subsoil bulk density and increase organic matter and total nitrogen. Liming raised exchangeable calcium, slightly increased pH, but decreased exchangeable magnesium and potassium. Corn ear-leaf and forage tissue nitrogen, yields, and nitrogen removal increased in treatments amended with sewage sludge and poultry manure, but not horse bedding. Subsoil application of sewage sludge or poultry manure seems like a promising method in the reclamation of surface mined prime farmland based on the improvements observed in the root zone environment.

Zhai, Qiang; Barnhisel, R.I. [Univ. of Kentucky, Lexington, KY (United States)

1996-12-31T23:59:59.000Z

180

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

SciTech Connect (OSTI)

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

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


181

Nanofluidics, from bulk to interfaces  

E-Print Network [OSTI]

Nanofluidics has emerged recently in the footsteps of microfluidics, following the quest of scale reduction inherent to nanotechnologies. By definition, nanofluidics explores transport phenomena of fluids at the nanometer scales. Why is the nanometer scale specific ? What fluid properties are probed at nanometric scales ? In other words, why 'nanofluidics' deserves its own brand name ? In this critical review, we will explore the vast manifold of length scales emerging for the fluid behavior at the nanoscales, as well as the associated mechanisms and corresponding applications. We will in particular explore the interplay between bulk and interface phenomena. The limit of validity of the continuum approaches will be discussed, as well as the numerous surface induced effects occuring at these scales, from hydrodynamic slippage to the various electro-kinetic phenomena originating from the couplings between hydrodynamics and electrostatics. An enlightening analogy between ion transport in nanochannels and transport in doped semi-conductors will be discussed.

Lyderic Bocquet; Elisabeth Charlaix

2009-09-03T23:59:59.000Z

182

In-situ vitrification of waste materials  

DOE Patents [OSTI]

A method for the in-situ vitrification of waste materials in a disposable can that includes an inner container and an outer container is disclosed. The method includes the steps of adding frit and waste materials to the inner container, removing any excess water, heating the inner container such that the frit and waste materials melt and vitrify after cooling, while maintaining the outer container at a significantly lower temperature than the inner container. The disposable can is then cooled to ambient temperatures and stored. A device for the in-situ vitrification of waste material in a disposable can is also disclosed. 7 figs.

Powell, J.R.; Reich, M.; Barletta, R.

1997-10-14T23:59:59.000Z

183

Silica Scaling Removal Process  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Silica Scaling Removal Process Silica Scaling Removal Process Silica Scaling Removal Process Scientists at Los Alamos National Laboratory have developed a novel technology to remove both dissolved and colloidal silica using small gel particles. Available for thumbnail of Feynman Center (505) 665-9090 Email Silica Scaling Removal Process Applications: Cooling tower systems Water treatment systems Water evaporation systems Potential mining applications (produced water) Industry applications for which silica scaling must be prevented Benefits: Reduces scaling in cooling towers by up to 50% Increases the number of cycles of concentration substantially Reduces the amount of antiscaling chemical additives needed Decreases the amount of makeup water and subsequent discharged water (blowdown) Enables considerable cost savings derived from reductions in

184

Technical basis for classification of low-activity waste fraction from Hanford site tanks  

SciTech Connect (OSTI)

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Petersen, C.A.

1996-09-20T23:59:59.000Z

185

Synthesis and Characterization of Bulk Vitreous Cadmium Germanium...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Bulk Vitreous Cadmium Germanium Arsenide. Synthesis and Characterization of Bulk Vitreous Cadmium Germanium Arsenide. Abstract: Abstract Cadmium-germanium-diarsenide...

186

241-AZ-101 pump removal trough analysis  

SciTech Connect (OSTI)

As part of the current Hanford mission of environmental cleanup, various long length equipment must be removed from highly radioactive waste tanks. The removal of equipment will utilize portions of the Equipment Removal System for Project W320 (ERS-W320), specifically the 50 ton hydraulic trailer system. Because the ERS-W320 system was designed to accommodate much heavier equipment it is adequate to support the dead weight of the trough, carriage and related equipment for 241AZ101 pump removal project. However, the ERS-W320 components when combined with the trough and its` related components must also be analyzed for overturning due to wind loads. Two troughs were designed, one for the 20 in. diameter carriage and one for the 36 in. diameter carriage. A proposed 52 in. trough was not designed and, therefore is not included in this document. In order to fit in the ERS-W320 strongback the troughs were design with the same widths. Structurally, the only difference between the two troughs is that more material was removed from the stiffener plates on the 36 in trough. The reduction in stiffener plate material reduces the allowable load. Therefore, only the 36 in. trough was analyzed.

Coverdell, B.L.

1995-10-17T23:59:59.000Z

187

Biochemical Removal of HAP Precursors from Coal  

SciTech Connect (OSTI)

Column biooxidation tests with Kentucky coal confirmed results of earlier shake flask tests showing significant removal from the coal of arsenic, selenium, cobalt, manganese, nickel and cadmium. Rates of pyrite biooxidation in Kentucky coal were only slightly more than half the rates found previously for Indiana and Pittsburgh coals. Removal of pyrite from Pittsburgh coal by ferric ion oxidation slows markedly as ferrous ions accumulate in solution, requiring maintenance of high redox potentials in processes designed for removal of pyrite and hazardous air pollutant (HAP) precursors by circulation of ferric solutions through coal. The pyrite oxidation rates obtained in these tests were used by Unifield Engineering to support the conceptual designs for alternative pyrite and HAP precursor bioleaching processes for the phase 2 pilot plant. Thermophilic microorganisms were tested to determine if mercury could be mobilized from coal under elevated growth temperatures. There was no evidence for mercury removal from coal under these conditions. However, the activity of the organisms may have liberated mercury physically. It is also possible that the organisms dissolved mercury and it readsorbed to the clay preferentially. Both of these possibilities are undergoing further testing. The Idaho National Engineering and Environmental Laboratory?s (INEEL) slurry column reactor was operated and several batches of feed coal, product coal, waste solids and leach solutions were submitted to LBL for HAP precursor analysis. Results to date indicate significant removal of mercury, arsenic and other HAP precursors in the combined physical-biological process.

Gregory J. Olson

1997-05-12T23:59:59.000Z

188

Bulk viscosity of a pion gas  

Science Journals Connector (OSTI)

We compute the bulk viscosity of a gas of pions at temperatures below the QCD crossover temperature, for the physical value of m?, to lowest order in chiral perturbation theory. Bulk viscosity is controlled by number-changing processes which become exponentially slow at low temperatures when the pions become exponentially dilute, leading to an exponentially large bulk viscosity ?~(F08/m?5)exp(2m?/T), where F0?93?MeV is the pion decay constant.

Egang Lu and Guy D. Moore

2011-04-07T23:59:59.000Z

189

Hyperon bulk viscosity in strong magnetic fields  

SciTech Connect (OSTI)

We study the bulk viscosity of neutron star matter including {lambda} hyperons in the presence of quantizing magnetic fields. Relaxation time and bulk viscosity due to both the nonleptonic weak process involving {lambda} hyperons and direct Urca processes are calculated here. In the presence of a strong magnetic field of 10{sup 17} G, the hyperon bulk viscosity coefficient is reduced, whereas bulk viscosity coefficients due to direct Urca processes are enhanced compared with their field free cases when many Landau levels are populated by protons, electrons, and muons.

Sinha, Monika; Bandyopadhyay, Debades [Theory Division and Centre for Astroparticle Physics, Saha Institute of Nuclear Physics, 1/AF Bidhannagar, Kolkata-700064 (India)

2009-06-15T23:59:59.000Z

190

Bulk viscosity in kaon condensed matter  

E-Print Network [OSTI]

We investigate the effect of $K^-$ condensed matter on bulk viscosity and r-mode instability in neutron stars. The bulk viscosity coefficient due to the non-leptonic process $n \\rightleftharpoons p + K^-$ is studied here. In this connection, equations of state are constructed within the framework of relativistic field theoretical models where nucleon-nucleon and kaon-nucleon interactions are mediated by the exchange of scalar and vector mesons. We find that the bulk viscosity coefficient due to the non-leptonic weak process in the condensate is suppressed by several orders of magnitude. Consequently, kaon bulk viscosity may not damp the r-mode instability in neutron stars.

Debarati Chatterjee; Debades Bandyopadhyay

2007-02-09T23:59:59.000Z

191

Oxygen penetration into the bulk of palladium  

Science Journals Connector (OSTI)

Oxygen penetration into the bulk of palladium ... During heating, the reaction rate exhibited an activity maximum at 650 K, whereas no activity maximum was found during the ... ...

C. T. Campbell; D. C. Foyt; J. M. White

1977-01-01T23:59:59.000Z

192

Commercialization of Bulk Thermoelectric Materials for Power...  

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

& Publications Commercialization of Bulk Thermoelectric Materials for Power Generation Hydrogen Embrittlement of Pipeline Steels: Causes and Remediation Distributed Bio-Oil...

193

Applications of bulk high-temperature superconductors  

SciTech Connect (OSTI)

The development of high-temperature superconductors (HTSs) can be broadly generalized into thin-film electronics, wire applications, and bulk applications. We consider bulk HTSs to include sintered or crystallized forms that do not take the geometry of filaments or tapes, and we discuss major applications for these materials. For the most part applications may be realized with the HTSs cooled to 77 K, and the properties of the bulk HTSs are often already sufficient for commercial use. A non-exhaustive list of applications for bulk HTSs includes trapped field magnets, hysteresis motors, magnetic shielding, current leads, and magnetic bearings. These applications are briefly discussed in this paper.

Hull, J.R.

1995-06-01T23:59:59.000Z

194

Recent Device Developments with Advanced Bulk Thermoelectric...  

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

at RTI Reviews work in engineered thin-film nanoscale thermoelectric materials and nano-bulk materials with high ZT undertaken by RTI in collaboration with its research...

195

Summary of Laboratory Capabilities Fact Sheets Waste Sampling and Characterization Facility and 222-S Laboratory Complex  

SciTech Connect (OSTI)

This summary of laboratory capabilities is provided to assist prospective responders to the CH2M HILL Hanford Group, Inc. (CHG) Requests for Proposal (RFP) issued or to be issued. The RFPs solicit development of treatment technologies as categorized in the CHG Requests for Information (RFI): Solid-Liquid Separations Technology - SOL: Reference-Number-CHG01; Cesium and Technetium Separations Technology - SOL: Reference-Number-CHG02; Sulfate Removal Technology - SOL: Reference-Number-CHG03; Containerized Grout Technology - SOL: Reference-Number-CHG04; Bulk Vitrification Technology - SOL: Reference-Number-CHG05; and TRU Tank Waste Solidification for Disposal at the Waste Isolation Pilot Plant - SOL: Reference-Number-CHG06 Hanford Analytical Services, Technology Project Management (TPM), has the capability and directly related experience to provide breakthrough innovations and solutions to the challenges presented in the requests. The 222-S Complex includes the 70,000 sq ft 222-S Laboratory, plus several support buildings. The laboratory has 11 hot cells for handling and analyzing highly radioactive samples, including tank farm waste. Inorganic, organic, and radiochemical analyses are performed on a wide variety of air, liquid, soil, sludge, and biota samples. Capabilities also include development of process technology and analytical methods, and preparation of analytical standards. The TPM staff includes many scientists with advanced degrees in chemistry (or closely related fields), over half of which are PhDs. These scientists have an average 20 years of Hanford experience working with Hanford waste in a hot cell environment. They have hundreds of publications related to Hanford tank waste characterization and process support. These would include, but are not limited to, solid-liquid separations engineering, physical chemistry, particle size analysis, and inorganic chemistry. TPM has had revenues in excess of $1 million per year for the past decade in above technology or similar related work. The abbreviated Bibliography, which follows, is an example of experience for Solicitations 1,2 and 3.

HADLEY, R.M.

2002-09-12T23:59:59.000Z

196

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

Practical disposal of nuclear waste requires high-throughput separation techniques. The most dangerous part of nuclear waste is the fission product, which contains the most active and mobile radioisotopes and produces most of the heat. We suggest that the fission products could be separated as a group from nuclear waste using plasma mass filters. Plasmabased processes are well suited to separating nuclear waste, because mass rather than chemical properties are used for separation. A single plasma stage can replace several stages of chemical separation, producing separate streams of bulk elements, fission products, and actinoids. The plasma mass filters may have lower cost and produce less auxiliary waste than chemical processing plants. Three rotating plasma configurations are considered that act as mass filters: the plasma centrifuge, the Ohkawa filter, and the asymmetric centrifugal trap.

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

197

Small-Scale Ion Exchange Removal of Cesium and Technetium from Envelope B Hanford Tank 241-AZ-102  

SciTech Connect (OSTI)

The pretreatment process for the Hanford River Protection Project Waste Treatment Plant is to provide decontaminated Low-Activity Waste and concentrated elute streams for vitrification into low- and high-activity waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, strontium, transuranics, cesium, and technetium.

King, W.D.

2001-02-15T23:59:59.000Z

198

BIO?REFINERIES: BIOPROCESS TECHNOLOGIES FOR WASTE?WATER TREATMENT, ENERGY AND PRODUCT VALORIZATION  

Science Journals Connector (OSTI)

Increasing pressure is being exerted on communities and nations to source energy from forms other than fossil fuels. Also potable water is becoming a scarce resource in many parts of the world and there remains a large divide in the demand and utilization of plant products derived from genetically modified organisms (GMOs) and non?GMOs. The most extensive user and manager of terrestrial ecosystems is agriculture which is also the de facto steward of natural resources. As stated by Miller (2008) no other industry or institution comes close to the comparative advantage held for this vital responsibility while simultaneously providing food fiber and other biology?based products including energy. Since modern commercial agriculture is transitioning from the production of bulk commodities to the provision of standardized products and specific?attribute raw materials for differentiated markets we can argue that processes such as mass cultivation of microalgae and the concept of bio?refineries be seen as part of a new agronomy. EBRU is currently exploring the integration of bioprocess technologies using microalgae as biocatalysts to achieve waste?water treatment water polishing and endocrine disruptor (EDC) removal sustainable energy production and exploitation of the resultant biomass in agriculture as foliar fertilizer and seed coatings and for commercial extraction of bulk commodities such as bio?oils and lecithin. This presentation will address efforts to establish a fully operational solar?driven microalgae bio?refinery for use not only in waste remediation but to transform waste and biomass to energy fuels and other useful materials (valorisation) with particular focus on environmental quality and sustainability goals.

A. Keith Cowan

2010-01-01T23:59:59.000Z

199

Continuous sulfur removal process  

DOE Patents [OSTI]

A continuous process for the removal of hydrogen sulfide from a gas stream using a membrane comprising a metal oxide deposited on a porous support is disclosed. 4 figures.

Jalan, V.; Ryu, J.

1994-04-26T23:59:59.000Z

200

Removing arsenic from aqueous solution and long-term product storage  

Science Journals Connector (OSTI)

The removal of arsenic from hydrometallurgical solutions, waste waters, and acid drainage mine waters has ... and co-precipitation processes; and, on the long-term outdoor storage of the arsenic bearing products.

L. G. Twidwell; J. W. McCloskey

2011-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

DOE Achieves Second TRU Waste Cleanup | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Achieves Second TRU Waste Cleanup Achieves Second TRU Waste Cleanup DOE Achieves Second TRU Waste Cleanup October 6, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. -The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE, ANL is the country's first science and engineering research national laboratory. This milestone was supported by $83,000 provided to the National Transuranic Waste Program as part of a $172 million American Recovery and Reinvestment Act investment to expedite legacy TRU waste disposal activities across the DOE complex.

202

West Valley Demonstration Project High-Level Waste Management  

Broader source: Energy.gov (indexed) [DOE]

DRAFT_19507_1 DRAFT_19507_1 High-Level Waste Management Bryan Bower, DOE Director - WVDP DOE High-Level Waste Corporate Board Meeting Savannah River Site April 1, 2008 West Valley Demonstration Project West Valley Demonstration Project DRAFT_19507_2 West Valley High-Level Waste To solidify the radioactive material from approximately 600,000 gallons of high-level radioactive waste into a durable, high-quality glass, both a pretreatment system to remove salts and sulfates from the waste and a vitrification system/process were designed. To solidify the radioactive material from approximately 600,000 gallons of high-level radioactive waste into a durable, high-quality glass, both a pretreatment system to remove salts and sulfates from the waste and a vitrification system/process were designed.

203

DOE Achieves Second TRU Waste Cleanup | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

Achieves Second TRU Waste Cleanup Achieves Second TRU Waste Cleanup DOE Achieves Second TRU Waste Cleanup October 6, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. -The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE, ANL is the country's first science and engineering research national laboratory. This milestone was supported by $83,000 provided to the National Transuranic Waste Program as part of a $172 million American Recovery and Reinvestment Act investment to expedite legacy TRU waste disposal activities across the DOE complex.

204

Fast pyrolysis of a waste fraction of high impact polystyrene (HIPS) containing brominated flame retardants in a fluidized bed reactor: The effects of various Ca-based additives (CaO, Ca(OH)2 and oyster shells) on the removal of bromine  

Science Journals Connector (OSTI)

A waste fraction of high impact polystyrene (HIPS) containing brominated flame retardants and antimony trioxide (Sb2O3) as a synergist was pyrolyzed in a bench-scale system equipped with a fluidized bed and char separation system. Experiments were carried out to observe the effects of the reaction temperature and three additives (CaO, Ca(OH)2, oyster shells) on the removal of bromine. An analysis of the pyrolysis oils obtained showed the oils were mainly composed of toluene, ethyl-benzene, styrene, cumene, ?-methylstyrene, 1,3-diphenylpropane, 1,3-diphenylbutane and (1-bromoethyl)-benzene. When the Ca-based additives were used, the concentration of styrene was markedly increased; whereas, those of ethlybenzene and cumene were reduced. The total bromine content of pyrolysis oil produced without any additive at 459C was about 5wt.%. When Ca(OH)2 and oyster shells were applied, the total bromine contents of the pyrolysis oils were decreased to 1.3 and 2.7wt.%, respectively. The antimony content in the pyrolysis oil was relatively small due to the efficient operation of the char separation system.

Su-Hwa Jung; Seon-Jin Kim; Joo-Sik Kim

2012-01-01T23:59:59.000Z

205

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2009  

SciTech Connect (OSTI)

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2009 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2009 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per LWO-LWE-2008-00423, HLW Tank Farm Inspection Plan for 2009, were completed. All Ultrasonic measurements (UT) performed in 2009 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 1, and WSRC-TR-2002-00061, Rev.4. UT inspections were performed on Tank 29 and the findings are documented in SRNL-STI-2009-00559, Tank Inspection NDE Results for Fiscal Year 2009, Waste Tank 29. Post chemical cleaning UT measurements were made in Tank 6 and the results are documented in SRNL-STI-2009-00560, Tank Inspection NDE Results Tank 6, Including Summary of Waste Removal Support Activities in Tanks 5 and 6. A total of 6669 photographs were made and 1276 visual and video inspections were performed during 2009. Twenty-Two new leaksites were identified in 2009. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.4. Fifteen leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. Five leaksites at Tank 6 were documented during tank wall/annulus cleaning activities. Two new leaksites were identified at Tank 19 during waste removal activities. Previously documented leaksites were reactivated at Tanks 5 and 12 during waste removal activities. Also, a very small amount of additional leakage from a previously identified leaksite at Tank 14 was observed.

West, B.; Waltz, R.

2010-06-21T23:59:59.000Z

206

Inorganic Nitrogen Removal from Wastewater: Effect on Phytoplankton Growth in Coastal Marine Waters  

Science Journals Connector (OSTI)

...secondarily treated wastewater and controlling eutrophication...PRODUCTION FROM SEA BY RECYCLING HUMAN WASTES, BIOSCIENCE...nitrogen removal from wastewater: effect on phytoplankton...depending on the type of wastewater used, there may be...re-moval and waste recycling. JOEL C. GOLDMAN...

Joel C. Goldman; Kenneth R. Tenore; Helen I. Stanley

1973-06-01T23:59:59.000Z

207

OFFICE WASTE DATA 2010 Recyclable Materials 1680 tons / 62%  

E-Print Network [OSTI]

is used to stabilise temperatures within conventional Energy from Waste incineration plants as well materials and to produce a combustible product. This involves the removal of inert and compostable materials

Guillas, Serge

208

Ferrocyanide tank waste stability. Supplement 2  

SciTech Connect (OSTI)

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

Fowler, K.D.

1993-01-01T23:59:59.000Z

209

Waste Hoist  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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...

210

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

211

Drum lid removal tool  

DOE Patents [OSTI]

A tool for removing the lid of a metal drum wherein the lid is clamped over the drum rim without protruding edges, the tool having an elongated handle with a blade carried by an angularly positioned holder affixed to the midsection of the handle, the blade being of selected width to slice between lid lip and the drum rim and, when the blade is so positioned, upward motion of the blade handle will cause the blade to pry the lip from the rim and allow the lid to be removed.

Pella, Bernard M. (Martinez, GA); Smith, Philip D. (North Augusta, SC)

2010-08-24T23:59:59.000Z

212

Bulk viscosity of a pion gas  

SciTech Connect (OSTI)

We compute the bulk viscosity of a gas of pions at temperatures below the QCD crossover temperature, for the physical value of m{sub {pi}}, to lowest order in chiral perturbation theory. Bulk viscosity is controlled by number-changing processes which become exponentially slow at low temperatures when the pions become exponentially dilute, leading to an exponentially large bulk viscosity {zeta}{approx}(F{sub 0}{sup 8}/m{sub {pi}}{sup 5})exp(2m{sub {pi}}/T), where F{sub 0}{approx_equal}93 MeV is the pion decay constant.

Lu Egang; Moore, Guy D. [Department of Physics, McGill University, 3600 rue University, Montreal, Quebec, H3A 2T8 (Canada)

2011-04-15T23:59:59.000Z

213

The Bulk Viscosity of a Pion Gas  

E-Print Network [OSTI]

We compute the bulk viscosity of a gas of pions at temperatures below the QCD crossover temperature, for the physical value of pion mass, to lowest order in chiral perturbation theory. Bulk viscosity is controlled by number-changing processes which become exponentially slow at low temperatures when the pions become exponentially dilute, leading to an exponentially large bulk viscosity zeta ~ (F_0^8/m_\\pi^5) exp(2m_\\pi/T), where F_0 = 93 MeV is the pion decay constant.

Egang Lu; Guy D. Moore

2011-01-31T23:59:59.000Z

214

Tunable Biopolymers for Heavy Metal Removal Jan Kostal, Ashok Mulchandani, and Wilfred Chen*  

E-Print Network [OSTI]

persistent nature, heavy metal ions are major contributors to pollution of the biosphere.1,2 These metalsTunable Biopolymers for Heavy Metal Removal Jan Kostal, Ashok Mulchandani, and Wilfred Chen synthesized for the removal of heavy metals from dilute waste streams. Protein-protein interaction

Chen, Wilfred

215

Results from evaporation tests to support the MWTF heat removal system design  

SciTech Connect (OSTI)

An experimental tests program was conducted to measure the evaporative heat removal from the surface of a tank of simulated waste. The results contained in this report constitute definition design data for the latest heat removal function of the MWTF primary ventilation system.

Crea, B.A.

1994-12-22T23:59:59.000Z

216

System for chemically digesting low level radioactive, solid waste material  

DOE Patents [OSTI]

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01T23:59:59.000Z

217

Condensate removal device  

DOE Patents [OSTI]

A condensate removal device is disclosed which incorporates a strainer in unit with an orifice. The strainer is cylindrical with its longitudinal axis transverse to that of the vapor conduit in which it is mounted. The orifice is positioned inside the strainer proximate the end which is remoter from the vapor conduit.

Maddox, James W. (Newport News, VA); Berger, David D. (Alexandria, VA)

1984-01-01T23:59:59.000Z

218

Definition: Bulk Electric System | Open Energy Information  

Open Energy Info (EERE)

Bulk Electric System Bulk Electric System Jump to: navigation, search Dictionary.png Bulk Electric System As defined by the Regional Reliability Organization, the electrical generation resources, transmission lines, interconnections with neighboring systems, and associated equipment, generally operated at voltages of 100 kV or higher. Radial transmission facilities serving only load with one transmission source are generally not included in this definition.[1] Related Terms Regional Reliability Organization, transmission lines, transmission line References ↑ Glossary of Terms Used in Reliability Standards An in LikeLike UnlikeLike You like this.Sign Up to see what your friends like. line Glossary Definition Retrieved from "http://en.openei.org/w/index.php?title=Definition:Bulk_Electric_System&oldid=48030

219

Bulk Viscosity of a Pion Gas  

SciTech Connect (OSTI)

We calculate the bulk viscosity of a pion gas at low energies within the kinetic theory approach and show the importance of dealing properly with the zero modes of this transport coefficient.

Dobado, Antonio; Torres-Rincon, Juan M. [Dpto. Fisica Teorica I, Universidad Complutense de Madrid, 28040 Madrid (Spain)

2011-05-23T23:59:59.000Z

220

Effects of bulk viscosity at freezeout  

SciTech Connect (OSTI)

We investigate particle spectra and elliptic flow coefficients in relativistic heavy-ion collisions by taking into account the distortion of phase space distributions by bulk viscosity at freezeout. We first calculate the distortion of phase space distributions in a multicomponent system with Grad's 14-moment method. We find some subtle issues when macroscopic variables are matched with microscopic momentum distributions in a multicomponent system, and we develop a consistent procedure to uniquely determine the corrections to the phase space distributions. Next, we calculate particle spectra by using the Cooper-Frye formula to see the effect of the bulk viscosity. Despite the relative smallness of the bulk viscosity, we find that it is likely to have a visible effect on particle spectra and elliptic flow coefficients. This indicates the importance of taking into account bulk viscosity together with shear viscosity to constrain the transport coefficients with better accuracy from comparison with experimental data.

Monnai, Akihiko; Hirano, Tetsufumi [Department of Physics, University of Tokyo, Tokyo 113-0033 (Japan)

2009-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Inorganic Nanocrystal Bulk Heterojunctions - Energy Innovation...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

This Technology

Schematic illustration of a nanocrystal bulk heterojunction solar cell with an active layer in which the concentration of n-type and p-type nanocrystals is...

222

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

223

Heat treatment of bulk gallium arsenide using a phosphosilicate glass cap  

SciTech Connect (OSTI)

n-type bulk GaAs crystals, capped with chemically vapor-deposited phosphosilicate glass, were heat treated at temperatures in the range of 600 to 950 /sup 0/C. Measurements on Schottky diodes and solar cells fabricated on the heat-treated material, after removal of a damaged surface layer, show an increase in free-carrier concentration, in minority-carrier-diffusion length, and in solar-cell short-circuit current. The observed changes are attributed to a removal of lifetime-reducing acceptorlike impurities, defects, or their complexes.

Mathur, G.; Wheaton, M.L.; Borrego, J.M.; Ghandhi, S.K.

1985-05-15T23:59:59.000Z

224

Texas Bulk Power Study-- An Overview  

E-Print Network [OSTI]

TEXAS BULK POWER STUDY -- AN OVERVIEW BIll MOORE Economist Publ ic Utility Commission of Texas Austin, Texas ABSTRACT In the 1980' s, several signi ficant changes have evolved in markets for electric power in Texas. Cogeneration, fuel... of bulk power transactions may reduce some uncertainty and result in cost savings to the util ities involved. However, both the transactions potential and any corresponding changes in operating costs are quite sensitive to assumptions about the price...

Moore, B.

225

Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned  

Broader source: Energy.gov (indexed) [DOE]

Los Alamos National Laboratory Transuranic Waste Program Exceeds Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal May 1, 2012 - 12:00pm Addthis LOS ALAMOS, N.M. - Los Alamos National Laboratory's (LANL) Transuranic (TRU) Waste Program is looking at another record-setting month for the amount of TRU waste leaving Material Disposal Area G, headed to the Waste Isolation Pilot Plant (WIPP) for permanent disposal. LANL exceeded its planned removal of TRU waste from Area G in April, shipping more than 91 cubic meters of waste to WIPP - more than the Lab has ever shipped there in a single month. The Lab is headed for an even more successful May, with 99 cubic meters shipped to WIPP as of May 22. "Our shipping performance reflects the acceleration that began last

226

Method for forming microspheres for encapsulation of nuclear waste  

DOE Patents [OSTI]

Microspheres for nuclear waste storage are formed by gelling droplets containing the waste in a gelation fluid, transferring the gelled droplets to a furnace without the washing step previously used, and heating the unwashed gelled droplets in the furnace under temperature or humidity conditions that result in a substantially linear rate of removal of volatile components therefrom.

Angelini, Peter (Oak Ridge, TN); Caputo, Anthony J. (Knoxville, TN); Hutchens, Richard E. (Knoxville, TN); Lackey, Walter J. (Oak Ridge, TN); Stinton, David P. (Knoxville, TN)

1984-01-01T23:59:59.000Z

227

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

Johnson, Terry R. (Wheaton, IL); Ackerman, John P. (Downers Grove, IL); Tomczuk, Zygmunt (Orland Park, IL); Fischer, Donald F. (Glen Ellyn, IL)

1989-01-01T23:59:59.000Z

228

Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh:  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh: Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh: Recent Fieldwork Results & Policy Implications Title Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh: Recent Fieldwork Results & Policy Implications Publication Type Report Year of Publication 2009 Authors Mathieu, Johanna L., Ashok J. Gadgil, Kristin Kowolik, and Susan E. Addy Publisher Lawrence Berkeley National Laboratory City Berkeley Abstract of arsenic from drinking water in Bangladesh. During fieldwork in four sub-districts of the country, ARUBA reduced arsenic levels ranging from 200 to 900 ppb to below the Bangladesh standard of 50 ppb. The technology is cost-effective because the substrate-bottom ash from coal fired power plants-is a waste material readily available in South Asia. In comparison to similar technologies, ARUBA uses less media for arsenic removal due to its high surface area to volume ratio. Hence, less waste is produced. A number of experiments were conducted in Bangladesh to determine the effectiveness of various water treatment protocols. It was found that (1) ARUBA removes more thanhalf of the arsenic from water within five minutes of treatment, (2) ARUBA, that has settled at the bottom of a treatment vessel, continues to remove arsenic for 2-3 days, (3) ARUBA's arsenic removal efficiency can be improved through sequential partial dosing (adding a given amount of ARUBA in fractions versus all at once), and (4) allowing water to first stand for two to three days followed by treatment with ARUBA produced final arsenic levels ten times lower than treating water directly out of the well. Our findings imply a number of tradeoffs between ARUBA's effective arsenic removal capacity, treatment system costs, and waste output. These tradeoffs, some a function of arsenic-related policies in Bangladesh (e.g., waste disposal regulations), must be considered when designing anarsenic removal system. We propose that the most attractive option is to use ARUBA in communityscale water treatment centers, installed as public-private partnerships, in Bangladeshi villages

229

DOE Removes Brookhaven Contractor  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

DOE Removes DOE Removes Brookhaven Contractor Peña sends a message to DOE facilities nationwide INSIDE 2 Accelerator Rx 4 FermiKids 6 Spring at Fermilab Photos courtesy of Brookhaven National Laboratory by Judy Jackson, Office of Public Affairs Secretary of Energy Federico Peña announced on Thursday, May 1, that the Department of Energy would immediately terminate the current management contract with Associated Universities, Inc. at Brookhaven National Laboratory in Upton, New York. Peña said that he made the decision after receiving the results of a laboratory safety management review conducted by the independent oversight arm of DOE's Office of Environment, Safety and Health. In addition, the Secretary said he found unacceptable "the continued on page 8 Volume 20 Friday, May 16, 1997

230

Pneumatic soil removal tool  

DOE Patents [OSTI]

A soil removal tool is provided for removing radioactive soil, rock and other debris from the bottom of an excavation, while permitting the operator to be located outside of a containment for that excavation. The tool includes a fixed jaw, secured to one end of an elongate pipe, which cooperates with a movable jaw pivotably mounted on the pipe. Movement of the movable jaw is controlled by a pneumatic cylinder mounted on the pipe. The actuator rod of the pneumatic cylinder is connected to a collar which is slidably mounted on the pipe and forms part of the pivotable mounting assembly for the movable jaw. Air is supplied to the pneumatic cylinder through a handle connected to the pipe, under the control of an actuator valve mounted on the handle, to provide movement of the movable jaw. 3 figs.

Neuhaus, J.E.

1992-10-13T23:59:59.000Z

231

RAPID/BulkTransmission/Land Access | Open Energy Information  

Open Energy Info (EERE)

Information Desktop Toolkit BETA RAPID Toolkit About Bulk Transmission Geothermal Solar Tools Contribute Contact Us RAPID Bulk Transmission Land Access Regulatory...

232

RAPID/BulkTransmission/Siting/New Mexico | Open Energy Information  

Open Energy Info (EERE)

Solar Resources Contribute Contact Us RAPID Bulk Transmission Siting New Mexico Bulk Transmission Siting in New Mexico Regulatory Information Overviews Search for...

233

High Heat Flux Thermoelectric Module Using Standard Bulk Material...  

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

Heat Flux Thermoelectric Module Using Standard Bulk Material High Heat Flux Thermoelectric Module Using Standard Bulk Material Presents high heat flux thermoelectric module design...

234

RAPID/Overview/BulkTransmission/Siting/Colorado | Open Energy...  

Open Energy Info (EERE)

Colorado < RAPID | Overview | BulkTransmission | Siting(Redirected from RAPIDAtlasBulkTransmissionSitingColorado) Redirect page Jump to: navigation, search REDIRECT...

235

Bulk Hydrogen Storage - Strategic Directions for Hydrogen Delivery...  

Broader source: Energy.gov (indexed) [DOE]

Bulk Hydrogen Storage - Strategic Directions for Hydrogen Delivery Workshop Bulk Hydrogen Storage - Strategic Directions for Hydrogen Delivery Workshop Targets, barriers and...

236

The influence of molecular orientation on organic bulk heterojunction...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

The influence of molecular orientation on organic bulk heterojunction solar cells The influence of molecular orientation on organic bulk heterojunction solar cells Print Monday, 28...

237

RAPID/BulkTransmission/Water Use | Open Energy Information  

Open Energy Info (EERE)

RAPIDBulkTransmissionWater Use < RAPID | BulkTransmission Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA RAPID Toolkit About Bulk...

238

Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites |  

Broader source: Energy.gov (indexed) [DOE]

Evaluation of Removing Used Nuclear Fuel From Shutdown Evaluation of Removing Used Nuclear Fuel From Shutdown Sites Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America's Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. Shutdown sites are defined as those commercial nuclear power reactor sites where the

239

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, Lien-Mow (North Augusta, SC); Kilpatrick, Lester L. (Aiken, SC)

1984-01-01T23:59:59.000Z

240

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, L.M.; Kilpatrick, L.L.

1982-05-19T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Waste Disposal (Illinois)  

Broader source: Energy.gov [DOE]

This article lays an outline of waste disposal regulations, permits and fees, hazardous waste management and underground storage tank requirements.

242

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

243

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

244

2401-W Waste storage building closure plan  

SciTech Connect (OSTI)

This plan describes the performance standards met and closure activities conducted to achieve clean closure of the 2401-W Waste Storage Building (2401-W) (Figure I). In August 1998, after the last waste container was removed from 2401-W, the U.S. Department of Energy, Richland Operations Office (DOE-RL) notified Washington State Department of Ecology (Ecology) in writing that the 2401-W would no longer receive waste and would be closed as a Resource Conservation and Recovery Act (RCRA) of 1976 treatment, storage, and/or disposal (TSD) unit (98-EAP-475). Pursuant to this notification, closure activities were conducted, as described in this plan, in accordance with Washington Administrative Code (WAC) 173-303-610 and completed on February 9, 1999. Ecology witnessed the closure activities. Consistent with clean closure, no postclosure activities will be necessary. Because 2401-W is a portion of the Central Waste Complex (CWC), these closure activities become the basis for removing this building from the CWC TSD unit boundary. The 2401-W is a pre-engineered steel building with a sealed concrete floor and a 15.2-centimeter concrete curb around the perimeter of the floor. This building operated from April 1988 until August 1998 storing non-liquid containerized mixed waste. All waste storage occurred indoors. No potential existed for 2401-W operations to have impacted soil. A review of operating records and interviews with cognizant operations personnel indicated that no waste spills occurred in this building (Appendix A). After all waste containers were removed, a radiation survey of the 2401-W floor for radiological release of the building was performed December 17, 1998, which identified no radiological contamination (Appendix B).

LUKE, S.M.

1999-07-15T23:59:59.000Z

245

Development of catalyst free carbon nanotubes from coal and waste plastics  

SciTech Connect (OSTI)

DC-Arc technique has been used to synthesize carbon nanotubes from super clean coal, chemically cleaned coal, original coal and waste plastics instead of using high purity graphite in the presence of metal catalysts. The results obtained are compared in terms of yield, purity and type of carbon nanotubes produced from different types of raw material used. In the present study different types of raw materials have been prepared i.e. chemically cleaned coal and super clean coal, and the carbon nanotubes have been synthesized by DC Arc discharge method. Taking in account the present need of utilizing coal as a cheaper raw material for bulk production of carbon nanotubes and utilization of waste plastics (which itself is a potential environmental threat) for production of such an advance material the present work was undertaken. Since the process does not involve presence of any kind of metal catalyst, it avoids the cost intensive process of removal of these metal particles. The residual coal obtained after refining has major fuel potential and can be utilized for various purposes.

Dosodia, A.; Lal, C.; Singh, B.P.; Mathur, R.B.; Sharma, D.K. [Indian Institute of Technology, New Delhi (India). Centre of Energy Studies

2009-07-01T23:59:59.000Z

246

Removal of sulfur and nitrogen containing pollutants from discharge gases  

DOE Patents [OSTI]

Oxides of sulfur and of nitrogen are removed from waste gases by reaction with an unsupported copper oxide powder to form copper sulfate. The resulting copper sulfate is dissolved in water to effect separation from insoluble mineral ash and dried to form solid copper sulfate pentahydrate. This solid sulfate is thermally decomposed to finely divided copper oxide powder with high specific surface area. The copper oxide powder is recycled into contact with the waste gases requiring cleanup. A reducing gas can be introduced to convert the oxide of nitrogen pollutants to nitrogen.

Joubert, James I. (Pittsburgh, PA)

1986-01-01T23:59:59.000Z

247

Method of waste stabilization via chemically bonded phosphate ceramics  

DOE Patents [OSTI]

A method for regulating the reaction temperature of a ceramic formulation process is provided comprising supplying a solution containing a monovalent alkali metal; mixing said solution with an oxide powder to create a binder; contacting said binder with bulk material to form a slurry; and allowing the slurry to cure. A highly crystalline waste form is also provided consisting of a binder containing potassium and waste substrate encapsulated by the binder. 3 figs.

Wagh, A.S.; Singh, D.; Jeong, S.Y.

1998-11-03T23:59:59.000Z

248

Material Recycling and Waste Disposal Document Control  

E-Print Network [OSTI]

of pollution, compliance with legislative requirements and continual improvement. The list of parties involved managers. Legislation referenced by this document. Environmental protection Act 1990 (EPA 1990). Waste. The clear bag bin liners are removed by the O&G Cleaners, tied closed, and taken to the building

Guillas, Serge

249

SLUDGE HEEL REMOVAL BY ALUMINUM DISSOLUTION AT SAVANNAH RIVER SITE 12390  

SciTech Connect (OSTI)

High Level Waste (HLW) at the Savannah River Site (SRS) is currently stored in aging underground storage tanks. This waste is a complex mixture of insoluble solids, referred to as sludge, and soluble salts. Continued long-term storage of these radioactive wastes poses an environmental risk. Operations are underway to remove and disposition the waste, clean the tanks and fill with grout for permanent closure. Heel removal is the intermediate phase of the waste retrieval and tank cleaning process at SRS, which is intended to reduce the volume of waste prior to treatment with oxalic acid. The goal of heel removal is to reduce the residual amount of radioactive sludge wastes to less than 37,900 liters (10,000 gallons) of wet solids. Reducing the quantity of residual waste solids in the tank prior to acid cleaning reduces the amount of acid required and reduces the amount of excess acid that could impact ongoing waste management processes. Mechanical heel removal campaigns in Tank 12 have relied solely on the use of mixing pumps that have not been effective at reducing the volume of remaining solids. The remaining waste in Tank 12 is known to have a high aluminum concentration. Aluminum dissolution by caustic leaching was identified as a treatment step to reduce the volume of remaining solids and prepare the tank for acid cleaning. Dissolution was performed in Tank 12 over a two month period in July and August, 2011. Sample results indicated that 16,440 kg of aluminum oxide (boehmite) had been dissolved representing 60% of the starting inventory. The evolution resulted in reducing the sludge solids volume by 22,300 liters (5900 gallons), preparing the tank for chemical cleaning with oxalic acid.

Keefer, M.

2012-01-12T23:59:59.000Z

250

Tank Farms and Waste Feed Delivery - 12507  

SciTech Connect (OSTI)

The mission of the Department of Energy's Office of River Protection (ORP) is to safely retrieve and treat the 56 million gallons of Hanford's tank waste and close the Tank Farms to protect the Columbia River. Our discussion of the Tank Farms and Waste Feed Delivery will cover progress made to date with Base and Recovery Act funding in reducing the risk posed by tank waste and in preparing for the initiation of waste treatment at Hanford. The millions of gallons of waste are a by-product of decades of plutonium production. After irradiated fuel rods were taken from the nuclear reactors to the processing facilities at Hanford they were exposed to a series of chemicals designed to dissolve away the rod, which enabled workers to retrieve the plutonium. Once those chemicals were exposed to the fuel rods they became radioactive and extremely hot. They also couldn't be used in this process more than once. Because the chemicals are caustic and extremely hazardous to humans and the environment, underground storage tanks were built to hold these chemicals until a more permanent solution could be found. The underground storage tanks range in capacity from 55,000 gallons to more than 1 million gallons. The tanks were constructed with carbon steel and reinforced concrete. There are eighteen groups of tanks, called 'tank farms', some having as few as two tanks and others up to sixteen tanks. Between 1943 and 1964, 149 single-shell tanks were built at Hanford in the 200 West and East Areas. Heat generated by the waste and the composition of the waste caused an estimated 67 of these single-shell tanks to leak into the ground. Washington River Protection Solutions is the prime contractor responsible for the safe management of this waste. WRPS' mission is to reduce the risk to the environment that is posed by the waste. All of the pumpable liquids have been removed from the single-shell tanks and transferred to the double-shell tanks. What remains in the single-shell tanks are solid and semi-solid wastes. Known as salt-cakes, they have the consistency of wet beach sand. Some of the waste resembles small broken ice, or whitish crystals. Because the original pumps inside the tanks were designed to remove only liquid waste, other methods have been developed to reach the remaining waste. Access to the tank waste is through long, typically skinny pipes, called risers, extending out of the tanks. It is through these pipes that crews are forced to send machines and devices into the tanks that are used to break up the waste or push it toward a pump. These pipes range in size from just a few inches to just over a foot in diameter because they were never intended to be used in this manner. As part of the agreement regulating Hanford cleanup, crews must remove at least 99% of the material in every tank on the site, or at least as much waste that can be removed based on available technology. To date, seven single-shell tanks have been emptied, and work is underway in another 10 tanks in preparation for additional retrieval activities. Two barriers have been installed over single-shell tanks to prevent the intrusion of surface water down to the tanks, with additional barriers planned for the future. Single and double-shell tank integrity analyses are ongoing. Because the volume of the waste generated through plutonium production exceeded the capacity of the single-shell tanks, between 1968 and 1986 Hanford engineers built 28 double-shell tanks. These tanks were studied and made with a second shell to surround the carbon steel and reinforced concrete. The double-shell tanks have not leaked any of their waste. (authors)

Fletcher, Thomas; Charboneau, Stacy; Olds, Erik [US DOE (United States)

2012-07-01T23:59:59.000Z

251

4 - Bulk high temperature superconductor (HTS) materials  

Science Journals Connector (OSTI)

Abstract: This chapter concentrates on bulk materials. A bulk superconductor is one in which the superconductor has been formed into a lump, usually cylindrically shaped, but can also be hexagonal, rectangular or even square. Bulk superconductors are typically 35cm across and 1cm thick. They have many uses but the principal one is as extremely compact high-field permanent magnets in superconducting machines. A 2.6cm (RE)BCO puck has been magnetised to 17.24 T: this is an order of magnitude greater than the flux density available from a conventional permanent magnet. This chapter describes the materials, manufacturing process, magnetisation process and some examples of machines.

T. Coombs

2012-01-01T23:59:59.000Z

252

Characterization and Leach Testing for PUREX Cladding Waste Sludge (Group 3) and REDOX Cladding Waste Sludge (Group 4) Actual Waste Sample Composites  

SciTech Connect (OSTI)

A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan.(a) The testing program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. The actual wastetesting program included homogenizing the samples by group, characterizing the solids and aqueous phases, and performing parametric leaching tests. Two of the eight defined groupsplutonium-uranium extraction (PUREX) cladding waste sludge (Group 3, or CWP) and reduction-oxidation (REDOX) cladding waste sludge (Group 4, or CWR)are the subjects of this report. Both the Group 3 and 4 waste composites were anticipated to be high in gibbsite, requiring caustic leaching. Characterization of the composite Group 3 and Group 4 waste samples confirmed them to be high in gibbsite. The focus of the Group 3 and 4 testing was on determining the behavior of gibbsite during caustic leaching. The waste-type definition, archived sample conditions, homogenization activities, characterization (physical, chemical, radioisotope, and crystal habit), and caustic leaching behavior as functions of time, temperature, and hydroxide concentration are discussed in this report. Testing was conducted according to TP-RPP-WTP-467.

Snow, Lanee A.; Buck, Edgar C.; Casella, Amanda J.; Crum, Jarrod V.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Fiskum, Sandra K.; Jagoda, Lynette K.; Jenson, Evan D.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Swoboda, Robert G.

2009-02-13T23:59:59.000Z

253

Ordered Vertex Removal Subgraph Problems  

E-Print Network [OSTI]

of the vertex removal and subgraph problems are shown to be P­complete. In addition, a natural lex­ icographicOrdered Vertex Removal and Subgraph Problems Ray Greenlaw Department of Computer Science University­8703196. #12; Vertex Removal and Graph Problems Ray Greenlaw Department of Computer Science FR­35

Greenlaw, Ray

254

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...

255

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

256

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

Broader source: Energy.gov (indexed) [DOE]

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

257

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

Broader source: Energy.gov (indexed) [DOE]

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

258

Method and apparatus for incinerating hazardous waste  

DOE Patents [OSTI]

An incineration apparatus and method for disposal of infectious hazardous waste including a fluidized bed reactor containing a bed of granular material. The reactor includes a first chamber, a second chamber, and a vertical partition separating the first and second chambers. A pressurized stream of air is supplied to the reactor at a sufficient velocity to fluidize the granular material in both the first and second chambers. Waste materials to be incinerated are fed into the first chamber of the fluidized bed, the fine waste materials being initially incinerated in the first chamber and subsequently circulated over the partition to the second chamber wherein further incineration occurs. Coarse waste materials are removed from the first chamber, comminuted, and recirculated to the second chamber for further incineration. Any partially incinerated waste materials and ash from the bottom of the second chamber are removed and recirculated to the second chamber for further incineration. This process is repeated until all infectious hazardous waste has been completely incinerated.

Korenberg, Jacob (York, PA)

1990-01-01T23:59:59.000Z

259

Disposal of Rocky Flats residues as waste  

SciTech Connect (OSTI)

Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

Dustin, D.F.; Sendelweck, V.S. [EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant; Rivera, M.A. [Lamb Associates, Inc., Rockville, MD (United States)

1993-03-01T23:59:59.000Z

260

Disposal of Rocky Flats residues as waste  

SciTech Connect (OSTI)

Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

Dustin, D.F.; Sendelweck, V.S. (EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant); Rivera, M.A. (Lamb Associates, Inc., Rockville, MD (United States))

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Radioactive waste processing apparatus  

DOE Patents [OSTI]

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

262

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

SciTech Connect (OSTI)

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

Thaxton, D; Timothy Baughman, T

2008-01-16T23:59:59.000Z

263

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...

264

GEOTECHNICAL/GEOCHEMICAL CHARACTERIZATION OF ADVANCED COAL PROCESS WASTE STREAMS  

SciTech Connect (OSTI)

Thirteen solid wastes, six coals and one unreacted sorbent produced from seven advanced coal utilization processes were characterized for task three of this project. The advanced processes from which samples were obtained included a gas-reburning sorbent injection process, a pressurized fluidized-bed coal combustion process, a coal-reburning process, a SO{sub x}, NO{sub x}, RO{sub x}, BOX process, an advanced flue desulfurization process, and an advanced coal cleaning process. The waste samples ranged from coarse materials, such as bottom ashes and spent bed materials, to fine materials such as fly ashes and cyclone ashes. Based on the results of the waste characterizations, an analysis of appropriate waste management practices for the advanced process wastes was done. The analysis indicated that using conventional waste management technology should be possible for disposal of all the advanced process wastes studied for task three. However, some wastes did possess properties that could present special problems for conventional waste management systems. Several task three wastes were self-hardening materials and one was self-heating. Self-hardening is caused by cementitious and pozzolanic reactions that occur when water is added to the waste. All of the self-hardening wastes setup slowly (in a matter of hours or days rather than minutes). Thus these wastes can still be handled with conventional management systems if care is taken not to allow them to setup in storage bins or transport vehicles. Waste self-heating is caused by the exothermic hydration of lime when the waste is mixed with conditioning water. If enough lime is present, the temperature of the waste will rise until steam is produced. It is recommended that self-heating wastes be conditioned in a controlled manner so that the heat will be safely dissipated before the material is transported to an ultimate disposal site. Waste utilization is important because an advanced process waste will not require ultimate disposal when it is put to use. Each task three waste was evaluated for utilization potential based on its physical properties, bulk chemical composition, and mineral composition. Only one of the thirteen materials studied might be suitable for use as a pozzolanic concrete additive. However, many wastes appeared to be suitable for other high-volume uses such as blasting grit, fine aggregate for asphalt concrete, road deicer, structural fill material, soil stabilization additives, waste stabilization additives, landfill cover material, and pavement base course construction.

Edwin S. Olson; Charles J. Moretti

1999-11-01T23:59:59.000Z

265

Bulk viscosity in a cold CFL superfluid  

E-Print Network [OSTI]

We compute one of the bulk viscosity coefficients of cold CFL quark matter in the temperature regime where the contribution of mesons, quarks and gluons to transport phenomena is Boltzmann suppressed. In that regime dissipation occurs due to collisions of superfluid phonons, the Goldstone modes associated to the spontaneous breaking of baryon symmetry. We first review the hydrodynamics of relativistic superfluids, and remind that there are at least three bulk viscosity coefficients in these systems. We then compute the bulk viscosity coefficient associated to the normal fluid component of the superfluid. In our analysis we use Son's effective field theory for the superfluid phonon, amended to include scale breaking effects proportional to the square of the strange quark mass m_s. We compute the bulk viscosity at leading order in the scale breaking parameter, and find that it is dominated by collinear splitting and joining processes. The resulting transport coefficient is zeta=0.011 m_s^4/T, growing at low temperature T until the phonon fluid description stops making sense. Our results are relevant to study the rotational properties of a compact star formed by CFL quark matter.

Cristina Manuel; Felipe Llanes-Estrada

2007-05-26T23:59:59.000Z

266

Waste Hoist  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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).

267

Photoactivated metal removal  

SciTech Connect (OSTI)

The authors propose the use of photochromic dyes as light activated switches to bind and release metal ions. This process, which can be driven by solar energy, can be used in environmental and industrial processes to remove metals from organic and aqueous solutions. Because the metals can be released from the ligands when irradiated with visible light, regeneration of the ligands and concentration of the metals may be easier than with conventional ion exchange resins. Thus, the process has the potential to be less expensive than currently used metal extraction techniques. In this paper, the authors report on their studies of the metal binding of spirogyran dyes and the hydrolytic stability of these dyes. They have prepared a number of spirogyrans and measured their binding constants for calcium and magnesium. They discuss the relationship of the structure of the dyes to their binding strengths. These studies are necessary towards determining the viability of this technique.

Nimlos, M.R.; Filley, J.; Ibrahim, M.A.; Watt, A.S.; Blake, D.M.

1999-07-01T23:59:59.000Z

268

Categorical Exclusion 4566, Ash Removal Project  

Broader source: Energy.gov (indexed) [DOE]

FOrnI FOrnI Project Title: Ash Removal Project (4566) Program or Program Office: Y -12 Site Office Location: Oak Ridge Tennessee Project Description: This work scope is to split, containerize, package, transport and disposition one hundred and two (102) cans of mixed waste. General Administration/Management OA I - Routine business actions OA2 * Administrative contract amendments OA4 - Interpretations/rulings for existing regulations OA5 - Regulatory interpretations without environmental effect OA6 - Procedural rule makings upgrade OA 7 - Transfer of property, use unchanged OA8 . Award of technical supportlM&O/personal service contracts OA9 - Info gathering, analysis, documentation, dissemination, and training OA 10 - Reports on non-DOE legislation OA II -

269

AX Tank Farm tank removal study  

SciTech Connect (OSTI)

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

SKELLY, W.A.

1998-10-14T23:59:59.000Z

270

Hanford Waste Physical and Rheological Properties: Data and Gaps  

SciTech Connect (OSTI)

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 Protections (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 Hanfords 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

271

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect (OSTI)

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

272

Ozone removal by HVAC filters  

Science Journals Connector (OSTI)

Residential and commercial HVAC filters that have been loaded with particles during operation in the field can remove ozone from intake or recirculated air. However, knowledge of the relative importance of HVAC filters as a removal mechanism for ozone in residential and commercial buildings is incomplete. We measured the ozone removal efficiencies of clean (unused) fiberglass, clean synthetic filters, and field-loaded residential and commercial filters in a controlled laboratory setting. For most filters, the ozone removal efficiency declined rapidly but converged to a non-zero (steady-state) value. This steady-state ozone removal efficiency varied from 0% to 9% for clean filters. The mean steady-state ozone removal efficiencies for loaded residential and commercial filters were 10% and 41%, respectively. Repeated exposure of filters to ozone following a 24-h period of no exposure led to a regeneration of ozone removal efficiency. Based on a theoretical scaling analysis of mechanisms that are involved in the ozone removal process, we speculate that the steady-state ozone removal efficiency is limited by reactant diffusion out of particles, and that regeneration is due to internal diffusion of reactive species to sites available to ozone for reaction. Finally, by applying our results to a screening model for typical residential and commercial buildings, HVAC filters were estimated to contribute 22% and 95%, respectively, of total ozone removal in HVAC systems.

P. Zhao; J.A. Siegel; R.L. Corsi

2007-01-01T23:59:59.000Z

273

Metalworkers clean up their waste  

SciTech Connect (OSTI)

This article describes how using methods such as chemical precipitation, filtration, and ion exchange, metal parts manufacturers are reducing the pollutants in their wastewater so it can be reused or safely discharged. Metalworking manufacturer are recovering useful materials, lowering their disposal costs, and reducing pollution by treating their wastewater with methods such as chemical precipitation and ion exchange so that it can be reused or safely discharged. They are also reducing wastes by recycling metalworking coolants. The major wastewater treatment technologies identified by the Environmental Protection Agency are chemical precipitation, or adding flocculants to bind waste particles together; membrane ultrafiltration and reverse osmosis, in which waste is trapped when the water passes through a membrane; and ion exchange, in which specially formulated resins capture dissolved metal salts. Other treatment techniques cited by Elwood Forsht, chief of the chemicals and metals branch at the EPA, include electrowinning, which uses electrolysis to concentrate metallic ions in wastewater, and coolant recycling, a method that removes metal particles by centrifugal force and kills bacteria by pasteurization. Many metalworking operations create wastewater, including drilling, welding, soldering, surface finishing, electroplating, acid treatment, anodizing, assembly, and machining. Companies use wastewater treatment technologies to recycle their wastewater or clean it so that it meets EPA standards and can be discharged into a municipal waste system, thus avoiding high disposal costs.

Valenti, M.

1994-10-01T23:59:59.000Z

274

Removal of Heavy Metals from Industrial Effluent Using Bacteria  

E-Print Network [OSTI]

Industrial development results in the generation of industrial effluents, and if untreated results in water, sediment and soil pollution. (Fakayode and Onianwa, 2002 ? Fakayode, 2005). Industrial wastes and emission contain toxic and hazardous substances, most of which are detrimental to human health (Jimena et al.,2008 ? Ogunfowokan et al.,2005 ? Rajaram et al.,2008). The key pollutants include heavy metals, chemical wastes and oil spills etc. Heavy metal resistant bacteria have significant role in bioremediation of heavy metals in wastewater. The objective of this work is to study the role of bacteria in removing the heavy metals present in the industrial effluent.Five effluent samples out of nine were selected for this study due to high content of heavy metals. The heavy metals Hg and Cu were removed by Bacillus sp. The average Hg reduction was 45 % and Cu reduction was recorded as 62%. The heavy metals Cd, As and Co were removed by Pseudomonas sp. The average Cd reduction was 56%, average As reduction was 34 % and average Co reduction was recorded as 53%. The heavy metals Cd and Cu were removed by Staphylococcus sp. The average Cd reduction was 44 % and average Cu reduction was recorded as 34 %.

Manisha N; Dinesh Sharma; Arun Kumar

275

Heavy metal removal and recovery using microorganisms  

SciTech Connect (OSTI)

Microorganisms -- bacteria, fungi, and microalgae -- can accumulate relatively large amounts of toxic heavy metals and radionuclides from the environment. These organisms often exhibit specificity for particular metals. The metal content of microbial biomass can be a substantial fraction of total dry weight with concentration factors (metal in dry biomass to metal in solution) exceeding one million in some cases. Both living and inert (dead) microbial biomass can be used to reduce heavy metal concentrations in contaminated waters to very low levels -- parts per billion and even lower. In many respects (e.g. specificity, residual metal concentrations, accumulation factors, and economics) microbial bioremoval processes can be superior to conventional processes, such as ion exchange and caustic (lime or hydroxide) precipitation for heavy metals removal from waste and contaminated waters. Thus, bioremoval could be developed to contribute to the clean-up of wastes at the Savannah River Site (SRS) and other DOE facilities. However, the potential advantages of bioremoval processes must still be developed into practical operating systems. A detailed review of the literature suggests that appropriate bioremoval processes could be developed for the SRS. There is great variability from one biomass source to another in bioremoval capabilities. Bioremoval is affected by pH, other ions, temperature, and many other factors. The biological (living vs. dead) and physical (immobilized vs. dispersed) characteristics of the biomass also greatly affect metal binding. Even subtle differences in the microbial biomass, such as the conditions under which it was cultivated, can have major effects on heavy metal binding.

Wilde, E.W. (Westinghouse Savannah River Co., Aiken, SC (United States)); Benemann, J.R. (Benemann (J.R.), Pinole, CA (United States))

1991-02-01T23:59:59.000Z

276

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

ELLEFSON, M.D.

1999-12-01T23:59:59.000Z

277

Removal Action Plan for the Accelerated Retrieval Project for a Described Area within Pit 4  

SciTech Connect (OSTI)

This Removal Action Plan documents the plan for implementation of the Comprehensive Environmental Response, Compenstion, and Liability Act non-time-critical removal action to be performed by the Accelerated Retrieval Project. The focus of the action is the limited excavation and retrieval of selected waste streams from a designated portion of the Radioactive Waste Management Complex Subsurface Disposal Area that are contaminated with volatile organic compounds, isotopes of uranium, or transuranic radionuclides. The selected retrieval area is approximately 0.2 ha (1/2 acre) and is located in the eastern portion of Pit 4. The proposed project is referred to as the Accelerated Retrieval Project. This Removal Action Plan details the major work elements, operations approach, and schedule, and summarizes the environmental, safety and health, and waste management considerations associated with the project.

A. M. Tyson

2006-08-01T23:59:59.000Z

278

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [DOE]

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

279

WASTE PACKAGE REMEDIATION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect (OSTI)

The Waste Package Remediation System remediates waste packages (WPs) and disposal containers (DCs) in one of two ways: preparation of rejected DC closure welds for repair or opening of the DC/WP. DCs are brought to the Waste Package Remediation System for preparation of rejected closure welds if testing of the closure weld by the Disposal Container Handling System indicates an unacceptable, but repairable, welding flaw. DC preparation of rejected closure welds will require removal of the weld in such a way that the Disposal Container Handling System may resume and complete the closure welding process. DCs/WPs are brought to the Waste Package Remediation System for opening if the Disposal Container Handling System testing of the DC closure weld indicates an unrepairable welding flaw, or if a WP is recovered from the subsurface repository because suspected damage to the WP or failure of the WP has occurred. DC/WP opening will require cutting of the DC/WP such that a temporary seal may be installed and the waste inside the DC/WP removed by another system. The system operates in a Waste Package Remediation System hot cell located in the Waste Handling Building that has direct access to the Disposal Container Handling System. One DC/WP at a time can be handled in the hot cell. The DC/WP arrives on a transfer cart, is positioned within the cell for system operations, and exits the cell without being removed from the cart. The system includes a wide variety of remotely operated components including a manipulator with hoist and/or jib crane, viewing systems, machine tools for opening WPs, and equipment used to perform pressure and gas composition sampling. Remotely operated equipment is designed to facilitate DC/WP decontamination and hot cell equipment maintenance, and interchangeable components are provided where appropriate. The Waste Package Remediation System interfaces with the Disposal Container Handling System for the receipt and transport of WPs and DCs. The Waste Handling Building System houses the system, and provides the facility, safety, and auxiliary systems required to support operations. The system receives power from the Waste Handling Building Electrical System. The system also interfaces with the various DC systems.

N.D. Sudan

2000-06-22T23:59:59.000Z

280

Bulk viscosity in heavy ion collision  

E-Print Network [OSTI]

The effect of a temperature dependent bulk viscosity to entropy density ratio~($\\zeta/s$) along with a constant shear viscosity to entropy density ratio~($\\eta/s$) on the space time evolution of the fluid produced in high energy heavy ion collisions have been studied in a relativistic viscous hydrodynamics model. The boost invariant Israel-Stewart theory of causal relativistic viscous hydrodynamics is used to simulate the evolution of the fluid in 2 spatial and 1 temporal dimension. The dissipative correction to the freezeout distribution for bulk viscosity is calculated using Grad's fourteen moment method. From our simulation we show that the method is applicable only for $\\zeta/s<0.004$.

Victor Roy; A. K. Chaudhuri

2012-01-20T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Removing Arsenic from Drinking Water  

ScienceCinema (OSTI)

See how INL scientists are using nanotechnology to remove arsenic from drinking water. For more INL research, visit http://www.facebook.com/idahonationallaboratory

None

2013-05-28T23:59:59.000Z

282

Removing Arsenic from Drinking Water  

SciTech Connect (OSTI)

See how INL scientists are using nanotechnology to remove arsenic from drinking water. For more INL research, visit http://www.facebook.com/idahonationallaboratory

None

2011-01-01T23:59:59.000Z

283

Structural Dimensions, Fabrication, Materials, and Operational History for Types I and II Waste Tanks  

SciTech Connect (OSTI)

Radioactive waste is confined in 48 underground storage tanks at the Savannah River Site. The waste will eventually be processed and transferred to other site facilities for stabilization. Based on waste removal and processing schedules, many of the tanks, including those with flaws and/or defects, will be required to be in service for another 15 to 20 years. Until the waste is removed from storage, transferred, and processed, the materials and structures of the tanks must maintain a confinement function by providing a leak-tight barrier to the environment and by maintaining acceptable structural stability during design basis event which include loading from both normal service and abnormal conditions.

Wiersma, B.J.

2000-08-16T23:59:59.000Z

284

Fluid-bed combustion of solid wastes  

SciTech Connect (OSTI)

For over ten years combustion Power Company has been conducting experimental programs and developing fluid bed systems for agencies of the federal government and for private industry and institutions. Many of these activities have involved systems for the combustion of solid waste materials. Discussed here will be three categories of programs, development of Municipal Solid Waste (MSW) fired fluid beds, development of wood waste fired fluid beds, and industrial installations. Research and development work on wood wastes has led to the design and construction of two large industrial fluid bed combustors. In one of these, a fluid bed is used for the generation of steam with a fuel that was previously suited only for landfill. Rocks and inerts are continuously removed from this combustor using a patented system. The second FBC is designed to use a variety of fuels as the source of energy to dry hog fuel for use in a high performance power boiler. Here the FBC burns green hog fuel, log yard debris, fly ash (char) from the boiler, and dried wood fines to produce a hot gas system for the wood dryer. A significant advantage of the fluidized bed reactor over conventional incinerators is its ability to reduce noxious gas emission and, finally, the fluidized bed is unique in its ability to efficiently consume low quality fuels. The relatively high inerts and moisture content of solid wastes pose no serious problem and require no associated additional devices for their removal.

Vander Molen, R.H.

1980-01-01T23:59:59.000Z

285

Radioactive Waste Management  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

286

Transuranic Waste Requirements  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

1999-07-09T23:59:59.000Z

287

Waste?to?Energy  

Broader source: Energy.gov [DOE]

Waste?to?Energy Roadmapping Workshop Waste?to?Energy Presentation by Jonathan Male, Director of the Bioenery Technolgies Office, Department of Energy

288

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

The term nuclear waste...embraces all residues from the use of radioactive materials, including uses in medicine and industry. The most highly radioactive of these are the spent fuel or reprocessed wastes from co...

2005-01-01T23:59:59.000Z

289

Behavior of hydrophobic ionic liquids as liquid membranes on phenol removal: Experimental study and optimization  

E-Print Network [OSTI]

Room temperature ionic liquids show potential as an alternative to conventional organic membrane solvents mainly due to their properties of low vapor pressure, low volatility and they are often stable. In the present work, the technical feasibilities of room temperature ionic liquids as bulk liquid membranes for phenol removal were investigated experimentally. Three ionic liquids with high hydrophobicity were used and their phenol removal efficiency, membrane stability and membrane loss were studied. Besides that, the effects of several parameters, namely feed phase pH, feed concentration, NaOH concentration and stirring speeds on the performance of best ionic liquid membrane were also evaluated. Lastly, an optimization study on bulk ionic liquid membrane was conducted and the maximum phenol removal efficiency was compared with the organic liquid membranes. The preliminary study shows that high phenol extraction and stripping efficiencies of 96.21% and 98.10%, respectively can be achieved by ionic liquid memb...

Ng, Y S; Hashim, M A

2014-01-01T23:59:59.000Z

290

Intense femtosecond photoexcitation of bulk and monolayer MoS2  

E-Print Network [OSTI]

The effect of femtosecond laser irradiation on bulk and single-layer MoS2 on silicon oxide is studied. Optical, Field Emission Scanning Electron Microscopy (FESEM) and Raman microscopies were used to quantify the damage. The intensity of A1g and E2g1 vibrational modes was recorded as a function of the number of irradiation pulses. The observed behavior was attributed to laser-induced bond breaking and subsequent atoms removal due to electronic excitations. The single-pulse optical damage threshold was determined for the monolayer and bulk under 800nm and 1030nm pulsed laser irradiation and the role of two-photon versus one photon absorption effects is discussed.

Paradisanos, I; Fotakis, C; Kioseoglou, G; Stratakis, E

2015-01-01T23:59:59.000Z

291

Treatability study of Tank E-3-1 waste: mixed waste stream SR-W049  

SciTech Connect (OSTI)

Treatability studies were conducted for tank E-3-1 waste which was previously characterized in WSRC-RP-87-0078. The waste was determined to be mixed waste because it displayed the characteristic of metal toxicity for Hg and Cr and was also contaminated with low levels of radionuclides. Two types of treatments for qualifying this waste suitable for land disposal were evaluated: ion exchange and stabilization with hydraulic materials (portland cement, slag and magnesium phosphate cement). These treatments were selected for testing because: (1) Both treatments can be carried out as in-drum processes., (2) Cement stabilization is the RCRA/LDR best developed available technology (BDAT) for Hg (less than 280 mg/L) and for Cr., and (3) Ion exchange via Mag-Sep is a promising alternative technology for in drum treatment of liquid wastes displaying metal toxicity. Cement stabilization of the E-3-1 material ( supernate and settled solids) resulted in waste forms which passed the TCLP test for both Hg and Cr. However, the ion exchange resins tested were ineffective in removing the Hg from this waste stream. Consequently, cement stabilization is recommended for a treatment of the five drums of the actual waste.

Langton, C.A. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-08-21T23:59:59.000Z

292

DOE Issues Salt Waste Determination for the Savannah River Site |  

Broader source: Energy.gov (indexed) [DOE]

Issues Salt Waste Determination for the Savannah River Site Issues Salt Waste Determination for the Savannah River Site DOE Issues Salt Waste Determination for the Savannah River Site January 18, 2006 - 10:49am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today issued the waste determination for the treatment and stabilization of low activity salt-waste at the Savannah River Site allowing for significant reductions in environmental and health risks posed by the material. Stored in forty-nine underground tanks, approximately 36 million gallons of radioactive waste is left over from plutonium production during the Cold War. In addition, the department issued an amended Record of Decision and Implementation Plan to the Defense Nuclear Facilities Safety Board. "Today's announcement clears the way for the removal and treatment of this

293

Identification of potential transuranic waste tanks at the Hanford Site  

SciTech Connect (OSTI)

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

Colburn, R.P.

1995-05-05T23:59:59.000Z

294

A Full-scale Study on the Partitioning of Trace Elements in Municipal Solid Waste IncinerationEffects of Firing Different Waste Types  

Science Journals Connector (OSTI)

The changes in waste composition were applied by adding (one-by-one): dedicated waste fractions, comprising road salt (NaCl), household batteries, automotive shredder waste, CCA (copper?chromate?arsenate)-impregnated wood, PVC, and, shoes, to a base-load waste. ... What is left after removing recyclables from vehicles is shredded. ... Automotive shredder waste (residues) is then the light shredder fraction from the airflow separator that separates it from the heavier metallic fraction, which is fully recyclable as a secondary raw material. ...

Anne J. Pedersen; Flemming J. Frandsen; Christian Riber; Thomas Astrup; Sren N. Thomsen; Kasper Lundtorp; Leif F. Mortensen

2009-03-23T23:59:59.000Z

295

WasteTraining Booklet Waste & Recycling Impacts  

E-Print Network [OSTI]

WasteTraining Booklet #12;Waste & Recycling Impacts Environment: The majority of our municipal jobs while recycling 10,000 tons of waste creates 36 jobs. Environment: Recycling conserves resources. It takes 95% less energy to make aluminum from recycled aluminum than from virgin materials, 60% less

Saldin, Dilano

296

High-Quality, Low-Cost Bulk Gallium Nitride Substrates  

Broader source: Energy.gov [DOE]

To develop ESG into a viable bulk growth process for GaN that is more scalable to large-area wafer manufacturing and able to produce cost-effective, high-quality bulk GaN substrates.

297

Removing Arsenic from Contaminated Drinking Water in Rural Bangladesh: Recent Fieldwork Results and Policy Implications  

SciTech Connect (OSTI)

ARUBA (Arsenic Removal Using Bottom Ash) has proven effective at removing high concentrations of arsenic from drinking water in Bangladesh. During fieldwork in four sub-districts of the country, ARUBA reduced arsenic levels ranging from 200 to 900 ppb to below the Bangladesh standard of 50 ppb. The technology is cost-effective because the substrate--bottom ash from coal fired power plants--is a waste material readily available in South Asia. In comparison to similar technologies, ARUBA uses less media for arsenic removal due to its high surface area to volume ratio. Hence, less waste is produced. A number of experiments were conducted in Bangladesh to determine the effectiveness of various water treatment protocols. It was found that (1) ARUBA removes more than half of the arsenic from water within five minutes of treatment, (2) ARUBA, that has settled at the bottom of a treatment vessel, continues to remove arsenic for 2-3 days, (3) ARUBA's arsenic removal efficiency can be improved through sequential partial dosing (adding a given amount of ARUBA in fractions versus all at once), and (4) allowing water to first stand for two to three days followed by treatment with ARUBA produced final arsenic levels ten times lower than treating water directly out of the well. Our findings imply a number of tradeoffs between ARUBA's effective arsenic removal capacity, treatment system costs, and waste output. These tradeoffs, some a function of arsenic-related policies in Bangladesh (e.g., waste disposal regulations), must be considered when designing an arsenic removal system. We propose that the most attractive option is to use ARUBA in communityscale water treatment centers, installed as public-private partnerships, in Bangladeshi villages.

Mathieu, Johanna L.; Gadgil, Ashok J.; Kowolik, Kristin; Addy, Susan E.A.

2009-09-17T23:59:59.000Z

298

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

SciTech Connect (OSTI)

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

299

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix conditions and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

DOE Carlsbad Field Office

2001-04-06T23:59:59.000Z

300

The Economic Case for Bulk Energy Storage in Transmission Systems  

E-Print Network [OSTI]

The Economic Case for Bulk Energy Storage in Transmission Systems with High Percentages to Engineer the Future Electric Energy System #12;#12;The Economic Case for Bulk Energy Storage Economic Case for Bulk Energy Storage in Transmission Sys- tems with High Percentages of Renewable

Note: This page contains sample records for the topic "bulk waste removal" 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

Bulk viscosity and r-modes of neutron stars  

E-Print Network [OSTI]

The bulk viscosity due to the non-leptonic process involving hyperons in $K^-$ condensed matter is discussed here. We find that the bulk viscosity is modified in a superconducting phase. Further, we demonstrate how the exotic bulk viscosity coefficient influences $r$-modes of neutron stars which might be sources of detectable gravitational waves.

Debarati Chatterjee; Debades Bandyopadhyay

2008-08-08T23:59:59.000Z

302

Bulk viscosity of gauge theory plasma at strong coupling  

E-Print Network [OSTI]

We propose a lower bound on bulk viscosity of strongly coupled gauge theory plasmas. Using explicit example of the N=2^* gauge theory plasma we show that the bulk viscosity remains finite at a critical point with a divergent specific heat. We present an estimate for the bulk viscosity of QGP plasma at RHIC.

Alex Buchel

2007-08-27T23:59:59.000Z

303

Rescheduling Bulk Gas Production and Distribution Wasu Glankwamdee  

E-Print Network [OSTI]

customer demand at minimum cost? #12;Bulk Gas Wrinkles Production Most sites operate in two modes: RegularRescheduling Bulk Gas Production and Distribution Wasu Glankwamdee Jackie Griffin Jeff Linderoth March 15, 2006 #12;Liquid Bulk Gas Production-Distribution Sites S Products P = {LOX, LNI} Customers C

Grossmann, Ignacio E.

304

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect (OSTI)

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

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

305

Overview of resuspension model: application to low level waste management  

SciTech Connect (OSTI)

Resuspension is one of the potential pathways to man for radioactive or chemical contaminants that are in the biosphere. In waste management, spills or other surface contamination can serve as a source for resuspension during the operational phase. After the low-level waste disposal area is closed, radioactive materials can be brought to the surface by animals or insects or, in the long term, the surface can be removed by erosion. Any of these methods expose the material to resuspension in the atmosphere. Intrusion into the waste mass can produce resuspension of potential hazard to the intruder. Removal of items from the waste mass by scavengers or archeologists can result in potential resuspension exposure to others handling or working with the object. The ways in which resuspension can occur are wind resuspension, mechanical resuspension and local resuspension. While methods of predicting exposure are not accurate, they include the use of the resuspension factor, the resuspension rate and mass loading of the air.

Healy, J.W.

1980-01-01T23:59:59.000Z

306

Recycling of sodium waste  

Science Journals Connector (OSTI)

Recycling of sodium waste ... Methods for handling and recycling a dangerous and costly chemical. ...

Bettina Hubler-Blank; Michael Witt; Herbert W. Roesky

1993-01-01T23:59:59.000Z

307

Central Waste Complex (CWC) Waste Analysis Plan  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly.

ELLEFSON, M.D.

2000-01-06T23:59:59.000Z

308

Method for the Removal of Ultrafine Particulates from an Aqueous Suspension  

SciTech Connect (OSTI)

A method of separating ultra-fine particulate from an aqueous suspension such as a process stream or a waste stream. The method involves the addition of alkali silicate and an organic gelling agent to a volume of liquid, from the respective process or waste stream, to form a gel. The gel then undergoes syneresis to remove water and soluble salts from the gel-containing the particulate, thus, forming a silica monolith. The silica monolith is then sintered to form a hard, nonporous waste form.

Chaiko, David J.; Kopasz, John P.; Ellison, Adam J.G.

1999-03-05T23:59:59.000Z

309

Short mechanical biological treatment of municipal solid waste allows landfill impact reduction saving waste energy content  

Science Journals Connector (OSTI)

Abstract The aim of this work was to evaluate the effects of full scale MBT process (28 d) in removing inhibition condition for successive biogas (ABP) production in landfill and in reducing total waste impact. For this purpose the organic fraction of MSW was treated in a full-scale MBT plant and successively incubated vs. untreated waste, in simulated landfills for one year. Results showed that untreated landfilled-waste gave a total ABP reduction that was null. On the contrary MBT process reduced ABP of 44%, but successive incubation for one year in landfill gave a total ABP reduction of 86%. This ABP reduction corresponded to a MBT process of 22weeks length, according to the predictive regression developed for ABP reduction vs. MBT-time. Therefore short MBT allowed reducing landfill impact, preserving energy content (ABP) to be produced successively by bioreactor technology since pre-treatment avoided process inhibition because of partial waste biostabilization.

Barbara Scaglia; Silvia Salati; Alessandra Di Gregorio; Alberto Carrera; Fulvia Tambone; Fabrizio Adani

2013-01-01T23:59:59.000Z

310

Bulk viscosity effects on elliptic flow  

E-Print Network [OSTI]

The effects of bulk viscosity on the elliptic flow $v_{2}$ are studied using realistic equation of state and realistic transport coefficients. We find that thebulk viscosity acts in a non trivial manner on $v_{2}$. At low $p_{T}$, the reduction of $v_{2}$ is even more effective compared to the case of shear viscosity, whereas at high $p_{T}$, an enhancement of $v_{2}$ compared to the ideal case is observed. We argue that this is caused by the competition of the critical behavior of the equation of state and the transport coefficients.

G. S. Denicol; T. Kodama; T. Koide; Ph. Mota

2009-07-24T23:59:59.000Z

311

A New Approach to Cosmological Bulk Viscosity  

E-Print Network [OSTI]

We examine the cosmological consequences of an alternative to the standard expression for bulk viscosity, one which was proposed to avoid the propagation of superluminal signals without the necessity of extending the space of variables of the theory. The Friedmann equation is derived for this case, along with an expression for the effective pressure. We find solutions for the evolution of the density of a viscous component, which differs markedly from the case of conventional Eckart theory; our model evolves toward late-time phantom-like behavior with a future singularity. Entropy production is addressed, and some similarities and differences to approaches based on the Mueller-Israel-Stewart theory are discussed.

Disconzi, Marcelo M; Scherrer, Robert J

2014-01-01T23:59:59.000Z

312

Magnetic structures of hcp bulk gadolinium  

Science Journals Connector (OSTI)

We present results of self-consistent linear-muffin-tin-orbital calculations with the atomic-sphere approximation for hcp bulk Gd, using the local spin-density approximation (LSDA) and gradient correction (GC) for the description of exchange and correlation. In the LSDA calculation antiferromagnetic order is favored over the ferromagnetic, and experimentally observed, structure. The GC weakens the bonding, leading to a higher equilibrium lattice parameter. At the new equilibrium volume the ground state is ferromagnetic. Our results point towards a magnetic phase transition under pressure.

Martina Heinemann and Walter M. Temmerman

1994-02-01T23:59:59.000Z

313

Infectious waste feed system  

DOE Patents [OSTI]

An infectious waste feed system for comminuting infectious waste and feeding the comminuted waste to a combustor automatically without the need for human intervention. The system includes a receptacle for accepting waste materials. Preferably, the receptacle includes a first and second compartment and a means for sealing the first and second compartments from the atmosphere. A shredder is disposed to comminute waste materials accepted in the receptacle to a predetermined size. A trough is disposed to receive the comminuted waste materials from the shredder. A feeding means is disposed within the trough and is movable in a first and second direction for feeding the comminuted waste materials to a combustor.

Coulthard, E. James (York, PA)

1994-01-01T23:59:59.000Z

314

Vit Plant receives and sets key air filtration equipment for Low Activity Waste Facility  

Broader source: Energy.gov [DOE]

WTP lifted a nearly 100-ton carbon bed absorber into the Low-Activity Waste Facility. This key piece of air-filtration equipment will remove mercury and acidic gases before air is channeled through...

315

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 liquidliquid 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

316

HLW-OVP-94-00n High Level Waste Management Division HLW System...  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

B.2 Environmental Documentation C. Waste Removal Schedule C. 1 Type I, II and IV Tanks C. 2 Type III Tanks D. Process Logic Diagram E. Process Logic Interactive Matrix F....

317

Molten Salt Oxidation of mixed wastes  

SciTech Connect (OSTI)

Molten Salt Oxidation (MSO) can be characterized as a simple noncombustion process; the basic concept is to introduce air and wastes into a bed of molten salt, oxidize the organic wastes in the molten salt, use the heat of oxidation to keep the salt molten and remove the salt for disposal or processing and recycling. The process has been developed through bench-scale and pilot-scale testing, with successful destruction demonstration of a wide variety of hazardous and mixed (radioactive and hazardous) wastes including chemical warfare agents, combustible solids, halogenated solvents, polychlorinated biphenyls, plutonium-contaminated solids, uranium-contaminated solvents and fission product-contaminated oil. The MSO destruction efficiency of the hazardous organic constituents in the wastes exceeds 99.9999%. Radioactive species, such as actinides and rare earth fission products, are retained in the salt bath. These elements can be recovered from the spent salt using conventional chemical processes, such as ion exchange, to render the salt as nonradioactive and nonhazardous. This paper reviews the principles and capabilities of MSO, previous mixed waste studies, and a new US Department of Energy program to demonstrate the process for the treatment of mixed wastes.

Gay, R.L.; Navratil, J.D.; Newman, C. [Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.

1993-12-31T23:59:59.000Z

318

Practical guidelines for small-volume additions of uninhibited water to waste storage tanks  

SciTech Connect (OSTI)

Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick`s second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem.

Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A.

1994-12-01T23:59:59.000Z

319

Practical guidelines for small volume additions of uninhibited water to waste storage tanks  

SciTech Connect (OSTI)

Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick`s second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem.

Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A. [Westinghouse Savannah River Co., Aiken, SC (United States)

1995-11-01T23:59:59.000Z

320

Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility  

SciTech Connect (OSTI)

The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

2003-02-26T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

The Bulk Channel in Thermal Gauge Theories  

E-Print Network [OSTI]

We investigate the thermal correlator of the trace of the energy-momentum tensor in the SU(3) Yang-Mills theory. Our goal is to constrain the spectral function in that channel, whose low-frequency part determines the bulk viscosity. We focus on the thermal modification of the spectral function, $\\rho(\\omega,T)-\\rho(\\omega,0)$. Using the operator-product expansion we give the high-frequency behavior of this difference in terms of thermodynamic potentials. We take into account the presence of an exact delta function located at the origin, which had been missed in previous analyses. We then combine the bulk sum rule and a Monte-Carlo evaluation of the Euclidean correlator to determine the intervals of frequency where the spectral density is enhanced or depleted by thermal effects. We find evidence that the thermal spectral density is non-zero for frequencies below the scalar glueball mass $m$ and is significantly depleted for $m\\lesssim\\omega\\lesssim 3m$.

Harvey B. Meyer

2010-02-17T23:59:59.000Z

322

Electromagnetic mixed waste processing system for asbestos decontamination  

SciTech Connect (OSTI)

DOE sites contain a broad spectrum of asbestos materials (cloth, pipe lagging, sprayed insulation and other substances) which are contaminated with a combination of hazardous and radioactive wastes due to its use during the development of the US nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCBs, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay, and fission products of DOE operations. To allow disposal, the asbestos must be converted chemically, followed by removing and separating the hazardous and radioactive materials to prevent the formation of mixed wastes and to allow for both sanitary disposal and effective decontamination. Currently, no technology exists that can meet these sanitary and other objectives. An attempt was made to apply techniques that have already proved successful in the mining, oil, and metals processing industries to the development of a multi-stage process to remove and separate hazardous chemical radioactive materials from asbestos. This process uses three methods: ABCOV chemicals which converts the asbestos to a sanitary waste; dielectric heating to volatilize the organic materials; and electrochemical processing for the removal of heavy metals, RCRA wastes and radionuclides. This process will result in the destruction of over 99% of the asbestos; limit radioactive metal contamination to 0.2 Bq alpha per gram and 1 Bq beta and gamma per gram; reduce hazardous organics to levels compatible with current EPA policy for RCRA delisting; and achieve TCLP limits for all solidified waste.

Kasevich, R.S.; Nocito, T.; Vaux, W.G.; Snyder, T.

1994-12-31T23:59:59.000Z

323

WCH Removes Massive Test Reactor  

Broader source: Energy.gov [DOE]

RICHLAND, WA -- Hanford's River Corridor contractor, Washington Closure Hanford, has met a significant cleanup challenge on the U.S. Department of Energy's (DOE) Hanford Site by removing a 1,082...

324

Organoclay Sorbent for Removal of Carbon Dioxide from Gas Streams at Low Temperatures  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Organoclay Sorbent for Removal of Carbon Dioxide from Gas Organoclay Sorbent for Removal of Carbon Dioxide from Gas Streams at Low Temperatures Contact NETL Technology Transfer Group techtransfer@netl.doe.gov October 2012 Significance * Energy mixing is maximized * Mobilizing of the particulates is complete * No "dead zones" exist * Packing of material is minimized * Eroding effects are significantly reduced Applications * Mixing nuclear waste at Hanford * Any similar industrial process involving heavy solids in a carrier fluid Opportunity Research is currently active on the patent-pending technology "Organoclay Sorbent for Removal of Carbon Dioxide from

325

Thermal and chemical remediation of mixed wastes  

DOE Patents [OSTI]

A process is described for treating organic waste materials without venting gaseous emissions to the atmosphere which includes oxidizing the organic waste materials at an elevated temperature not less than about 500 C with a gas having an oxygen content in the range of from about 20% to about 70% to produce an oxidation product containing CO{sub 2} gas. The gas is then filtered to remove particulates, and then contacted with an aqueous absorbent solution of alkali metal carbonates or alkanolamines to absorb a portion of the CO{sub 2} gas from the particulate-free oxidation product. The CO{sub 2} absorbent is thereafter separated for further processing. A process and system are also disclosed in which the waste materials are contacted with a reactive medium such as lime and product treatment as described. 8 figs.

Nelson, P.A.; Swift, W.M.

1997-12-16T23:59:59.000Z

326

Thermal and chemical remediation of mixed wastes  

DOE Patents [OSTI]

A process for treating organic waste materials without venting gaseous emissions to the atmosphere which includes oxidizing the organic waste materials at an elevated temperature not less than about 500.degree. C. with a gas having an oxygen content in the range of from about 20% to about 70% to produce an oxidation product containing CO.sub.2 gas. The gas is then filtered to remove particulates, and then contacted with an aqueous absorbent solution of alkali metal carbonates or alkanolamines to absorb a portion of the CO.sub.2 gas from the particulate-free oxidation product. The CO.sub.2 absorbent is thereafter separated for further processing. A process and system are also disclosed in which the waste materials are contacted with a reactive medium such as lime and product treatment as described.

Nelson, Paul A. (Wheaton, IL); Swift, William M. (Downers Grove, IL)

1997-01-01T23:59:59.000Z

327

Debate over waste imperils 3-Mile cleanup  

SciTech Connect (OSTI)

The cleanup is a task of extraordinary proportions. Every step in the cleanup must be taken in a highly sensitive political and regulatory environment. A demineralizer or ion exchange filtration unit was installed in order that the fission products could be removed from the water spilled in the auxiliary and fuel handling buildings. GPU later vented krypton gas. Twice now engineers have made cautions entries into the containment building as part of the effort to size up the job. Cleanup will be costly, requiring many workers. Some wastes will require special packaging in hundreds of containers with shielded overpacks, plus bulky items of hardware and equipment that cannot be easily packaged. There will be the damaged fuel assemblies from the reactor core. Removing the fuel from the reactor may be difficult. A troublesome waste disposal question has to do with the material to be generated in cleaning up the containment building's sump water. GPU's man in charge of clean-up strategy is to collect the wastes in a form that permits maximum flexibility with respect to their stage, packaging, transport, and ultimate disposal. If plans for disposal of all the wastes from the cleanup are to be completed, an early commitment by Pennsylvania and other northeastern states to establish a burial ground for low level waste generated within the region is needed. Also a speedy commitment by NRC, DOE, and Congress to a plan for disposal of the first-stage zeolites is needed. Should there be a failure to cope with the wastes that Three Mile Island cleanup generates, the whole nuclear enterprise may suffer.

Carter, L.J.

1980-10-10T23:59:59.000Z

328

Microsoft PowerPoint - EM SSAB Chairs Webinar - Marcinowski Waste Strategies.042413  

Broader source: Energy.gov (indexed) [DOE]

Chair's Meeting Chair's Meeting Waste Disposition Strategies Update www.energy.gov/EM 1 Waste Disposition Strategies Update Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management April 25, 2013 * Recent Program Accomplishments * FY13 Waste Management Priorities * FY14 Waste Management Priorities * Los Alamos Update * LLW/MLLW Disposition Options Discussion Outline www.energy.gov/EM 2 * Hanford TRU Tank Disposition Initiative * GTCC EIS * Mercury Supplemental EIS * Excess Material and Metal Recycling * DOE Order 435.1, Radioactive Waste Management * Blue Ribbon Commission Related Activities Recent Program Accomplishments * Continued progress towards removal of Los Alamos TRU waste, in accord with Framework Agreement * Submitted WIPP Hazardous Waste Facility permit modification for

329

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

330

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

331

CERAMIC WASTE FORM DATA PACKAGE  

SciTech Connect (OSTI)

The purpose of this data package is to provide information about simulated crystalline waste forms that can be used to select an appropriate composition for a Cold Crucible Induction Melter (CCIM) proof of principle demonstration. Melt processing, viscosity, electrical conductivity, and thermal analysis information was collected to assess the ability of two potential candidate ceramic compositions to be processed in the Idaho National Laboratory (INL) CCIM and to guide processing parameters for the CCIM operation. Given uncertainties in the CCIM capabilities to reach certain temperatures throughout the system, one waste form designated 'Fe-MP' was designed towards enabling processing and another, designated 'CAF-5%TM-MP' was designed towards optimized microstructure. Melt processing studies confirmed both compositions could be poured from a crucible at 1600{degrees}C although the CAF-5%TM-MP composition froze before pouring was complete due to rapid crystallization (upon cooling). X-ray diffraction measurements confirmed the crystalline nature and phase assemblages of the compositions. The kinetics of melting and crystallization appeared to vary significantly between the compositions. Impedance spectroscopy results indicated the electrical conductivity is acceptable with respect to processing in the CCIM. The success of processing either ceramic composition will depend on the thermal profiles throughout the CCIM. In particular, the working temperature of the pour spout relative to the bulk melter which can approach 1700{degrees}C. The Fe-MP composition is recommended to demonstrate proof of principle for crystalline simulated waste forms considering the current configuration of INL's CCIM. If proposed modifications to the CCIM can maintain a nominal temperature of 1600{degrees}C throughout the melter, drain, and pour spout, then the CAF-5%TM-MP composition should be considered for a proof of principle demonstration.

Amoroso, J.; Marra, J.

2014-06-13T23:59:59.000Z

332

Waste-to-Energy: Waste Management and Energy Production Opportunities...  

Office of Environmental Management (EM)

Waste-to-Energy: Waste Management and Energy Production Opportunities Waste-to-Energy: Waste Management and Energy Production Opportunities July 24, 2014 9:00AM to 3:30PM EDT U.S....

333

On bulk viscosity and moduli decay  

E-Print Network [OSTI]

This pedagogically intended lecture, one of four under the header "Basics of thermal QCD", reviews an interesting relationship, originally pointed out by Bodeker, that exists between the bulk viscosity of Yang-Mills theory (of possible relevance to the hydrodynamics of heavy ion collision experiments) and the decay rate of scalar fields coupled very weakly to a heat bath (appearing in some particle physics inspired cosmological scenarios). This topic serves, furthermore, as a platform on which a number of generic thermal field theory concepts are illustrated. The other three lectures (on the QCD equation of state and the rates of elastic as well as inelastic processes experienced by heavy quarks) are recapitulated in brief encyclopedic form.

M. Laine

2010-07-15T23:59:59.000Z

334

Electron transport in the bulk photovoltaic effect  

Science Journals Connector (OSTI)

The spontaneous motion of electrons in the bulk photovoltaic effect in pyroelectric materials may be explained by separating the processes into two steps: the generation of photoelectrons whose distribution is asymmetric in momentum and a subsequent normal diffusion of the carriers. Asymmetric generation violates time-reversal symmetry and is shown to be only possible for local states in polar systems. Transport properties are calculated for the short-circuit and the open-end case. It is shown that in high-resistivity materials the short-circuit current is not affected by impurities other than those supplying the asymmetric photoelectrons. The open-end saturation field is proportional to the short-circuit current Es=Jsc?, where ? is the photoconductivity. Both results agree with experiment.

H. Heyszenau

1978-08-15T23:59:59.000Z

335

Organic hybrid planar-nanocrystalline bulk heterojunctions  

DOE Patents [OSTI]

A photosensitive optoelectronic device having an improved hybrid planar bulk heterojunction includes a plurality of photoconductive materials disposed between the anode and the cathode. The photoconductive materials include a first continuous layer of donor material and a second continuous layer of acceptor material. A first network of donor material or materials extends from the first continuous layer toward the second continuous layer, providing continuous pathways for conduction of holes to the first continuous layer. A second network of acceptor material or materials extends from the second continuous layer toward the first continuous layer, providing continuous pathways for conduction of electrons to the second continuous layer. The first network and the second network are interlaced with each other. At least one other photoconductive material is interspersed between the interlaced networks. This other photoconductive material or materials has an absorption spectra different from the donor and acceptor materials.

Forrest, Stephen R. (Ann Arbor, MI); Yang, Fan (Piscataway, NJ)

2011-03-01T23:59:59.000Z

336

Organic hybrid planar-nanocrystalline bulk heterojunctions  

DOE Patents [OSTI]

A photosensitive optoelectronic device having an improved hybrid planar bulk heterojunction includes a plurality of photoconductive materials disposed between the anode and the cathode. The photoconductive materials include a first continuous layer of donor material and a second continuous layer of acceptor material. A first network of donor material or materials extends from the first continuous layer toward the second continuous layer, providing continuous pathways for conduction of holes to the first continuous layer. A second network of acceptor material or materials extends from the second continuous layer toward the first continuous layer, providing continuous pathways for conduction of electrons to the second continuous layer. The first network and the second network are interlaced with each other. At least one other photoconductive material is interspersed between the interlaced networks. This other photoconductive material or materials has an absorption spectra different from the donor and acceptor materials.

Forrest, Stephen R.; Yang, Fan

2013-04-09T23:59:59.000Z

337

DEPLOYMENT OF THE BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect (OSTI)

A new Bulk Tritium Shipping Package (BTSP) was designed by the Savannah River National Laboratory to be a replacement for a package that has been used to ship tritium in a variety of content configurations and forms since the early 1970s. The BTSP was certified by the National Nuclear Safety Administration in 2011 for shipments of up to 150 grams of Tritium. Thirty packages were procured and are being delivered to various DOE sites for operational use. This paper summarizes the design features of the BTSP, as well as associated engineered material improvements. Fabrication challenges encountered during production are discussed as well as fielding requirements. Current approved tritium content forms (gas and tritium hydrides), are reviewed, as well as, a new content, tritium contaminated water on molecular sieves. Issues associated with gas generation will also be discussed.

Blanton, P.

2013-10-10T23:59:59.000Z

338

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

Broader source: Energy.gov (indexed) [DOE]

and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes Air Products and Chemicals, Inc. - Allentown, PA A microbial reverse electrodialysis...

339

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

Broader source: Energy.gov (indexed) [DOE]

(ex: organic Rankine cycle) High installed KW capital Low temperature waste heat (<100C) is not practicable Further efficiency loss in electrolytic conversion to...

340

Radioactive Waste Management Manual  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Geotechnical/geochemical characterization of advanced coal process waste streams: Task 2  

SciTech Connect (OSTI)

Successful disposal practices for solid wastes produced from advanced coal combustion and coal conversion processes must provide for efficient management of relatively large volumes of wastes in a cost-effective and environmentally safe manner. At present, most coal-utilization solid wastes are disposed of using various types of land-based systems, and it is probable that this disposal mode will continue to be widely used in the future for advanced process wastes. Proper design and operation of land-based disposal systems for coal combustion wastes normally require appropriate waste transfer, storage, and conditioning subsystems at the plant to prepare the waste for transport to an ultimate disposal site. Further, the overall waste management plan should include a by-product marketing program to minimize the amount of waste that will require disposal. In order to properly design and operate waste management systems for advanced coal-utilization processes, a fundamental understanding of the physical properties, chemical and mineral compositions, and leaching behaviors of the wastes is required. In order to gain information about the wastes produced by advanced coal-utilization processes, 55 waste samples from 16 different coal gasification, fluidized-bed coal combustion (FBC), and advanced flue gas scrubbing processes were collected. Thirty-four of these wastes were analyzed for their bulk chemical and mineral compositions and tested for a detailed set of disposal-related physical properties. The results of these waste characterizations are presented in this report. In addition to the waste characterization data, this report contains a discussion of potentially useful waste management practices for advanced coal utilization processes.

Moretti, C.J.; Olson, E.S.

1992-09-01T23:59:59.000Z

342

Microsoft Word - EC Sodium coolant removal.doc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

1 1 SECTION A. Project Title: MFC - EBR-II Sodium Removal/RCRA Closure Activities SECTION B . Project Description The proposed action will remove the sodium from the Experimental Breeder Reactor (EBR)-II piping system and tanks to achieve clean-closure for eventual decommissioning, deactivation and demolition (DD&D). The clean-closure will be completed in compliance with the EBR-II Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) Storage and Treatment Permit PER-120, which includes the closure plan. EBR-II is located at the Materials and Fuels Complex at the Idaho National Laboratory. The EBR-II DD&D actions will be addressed under the Comprehensive Environmental Response Compensation, and Liability Act, specifically, the Engineering Evaluation/Cost

343

Apparatus for removing hydrocarbon contaminants from solid materials  

DOE Patents [OSTI]

A system for removing hydrocarbons from solid materials. Contaminated solids are combined with a solvent (preferably terpene based) to produce a mixture. The mixture is washed with water to generate a purified solid product (which is removed from the system) and a drainage product. The drainage product is separated into a first fraction (consisting mostly of contaminated solvent) and a second fraction (containing solids and water). The first fraction is separated into a third fraction (consisting mostly of contaminated solvent) and a fourth fraction (containing residual solids and water). The fourth fraction is combined with the second fraction to produce a sludge which is separated into a fifth fraction (containing water which is ultimately reused) and a sixth fraction (containing solids). The third fraction is then separated into a seventh fraction (consisting of recovered solvent which is ultimately reused) and an eighth fraction (containing hydrocarbon waste).

Bala, Gregory A. (Idaho Falls, ID); Thomas, Charles P. (Idaho Falls, ID)

1996-01-01T23:59:59.000Z

344

Method for removing hydrocarbon contaminants from solid materials  

DOE Patents [OSTI]

A system for removing hydrocarbons from solid materials. Contaminated solids are combined with a solvent (preferably terpene based) to produce a mixture. The mixture is washed with water to generate a purified solid product (which is removed from the system) and a drainage product. The drainage product is separated into a first fraction (consisting mostly of contaminated solvent) and a second fraction (containing solids and water). The first fraction is separated into a third fraction (consisting mostly of contaminated solvent) and a fourth fraction (containing residual solids and water). The fourth fraction is combined with the second fraction to produce a sludge which is separated into a fifth fraction (containing water which is ultimately reused) and a sixth fraction (containing solids). The third fraction is then separated into a seventh fraction (consisting of recovered solvent which is ultimately reused) and an eighth fraction (containing hydrocarbon waste).

Bala, Gregory A. (Idaho Falls, ID); Thomas, Charles P. (Idaho Falls, ID)

1995-01-01T23:59:59.000Z

345

Recommendation 199: Recommendation to Remove Uncontaminated Areas...  

Office of Environmental Management (EM)

9: Recommendation to Remove Uncontaminated Areas of the Oak Ridge Reservation from the National Priorities List Recommendation 199: Recommendation to Remove Uncontaminated Areas of...

346

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

347

Evaluation of asbestos-abatement techniques. Phase 1. Removal. Final report  

SciTech Connect (OSTI)

Airborne asbestos levels were measured by transmission electron microscopy (TEM), scanning electron microscopy (SEM) and phase constrast microscopy (PCM) before, during, and after removal of sprayed-on acoustical plaster from the ceilings of four suburban schools. Air samples were collected at three types of sites: indoor sites with asbestos-containing material (ACM), indoor sites without ACM (indoor control), and sites outside the building (outdoor control). Bulk samples of the ACM were collected prior to the removal and analyzed by polarized light microscopy (PLM). A vigorous quality-assurance program was applied to all aspects of the study. Airborne asbestos levels were low before and after removal. Elevated, but still relatively low levels were measured outside the work area during removal. This emphasizes the need for careful containment of the work area.

Chesson, J.; Margeson, D.P.; Ogden, J.; Reichenbach, N.G.; Bauer, K.

1985-10-01T23:59:59.000Z

348

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING In general, building materials contain low levels of radioactivity. For example, the range of  

E-Print Network [OSTI]

4.0 RISK FROM URANIUM MINING WASTE IN BUILDING MATERIALS In general, building materials contain low, especially in buildings constructed with materials containing uranium TENORM mine wastes. In the Grand the wastes from uranium mines have been removed from mining sites and used in local and nearby communities

349

Mercury removal in utility wet scrubber using a chelating agent  

DOE Patents [OSTI]

A method for capturing and reducing the mercury content of an industrial flue gas such as that produced in the combustion of a fossil fuel or solid waste adds a chelating agent, such as ethylenediaminetetraacetic acid (EDTA) or other similar compounds like HEDTA, DTPA and/or NTA, to the flue gas being scrubbed in a wet scrubber used in the industrial process. The chelating agent prevents the reduction of oxidized mercury to elemental mercury, thereby increasing the mercury removal efficiency of the wet scrubber. Exemplary tests on inlet and outlet mercury concentration in an industrial flue gas were performed without and with EDTA addition. Without EDTA, mercury removal totaled 42%. With EDTA, mercury removal increased to 71%. The invention may be readily adapted to known wet scrubber systems and it specifically provides for the removal of unwanted mercury both by supplying S.sup.2- ions to convert Hg.sup.2+ ions into mercuric sulfide (HgS) and by supplying a chelating agent to sequester other ions, including but not limited to Fe.sup.2+ ions, which could otherwise induce the unwanted reduction of Hg.sup.2+ to the form, Hg.sup.0.

Amrhein, Gerald T. (Louisville, OH)

2001-01-01T23:59:59.000Z

350

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

from tank waste. * Decreases the volume of water to create room in double-shell tanks, allowing them to accept waste from noncompliant single- shell tanks. * Treats up to 1...

351

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

trucks for scale. The DSTs have limited capacity and are aging. Maintaining these tanks is important to ensure that waste is ready to supply the Waste Treatment Plant. The...

352

Hazardous Waste Management (Oklahoma)  

Broader source: Energy.gov [DOE]

This article states regulations for the disposal of hazardous waste. It also provides information about permit requirements for the transport, treatment and storage of such waste. It also mentions...

353

Nuclear waste solids  

Science Journals Connector (OSTI)

Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since releas...

L. L. Hench; D. E. Clark; A. B. Harker

1986-05-01T23:59:59.000Z

354

Removal of mercury from solids using the potassium iodide/iodine leaching process  

SciTech Connect (OSTI)

Potassium iodide (KI) and iodine (I{sub 2}) leaching solutions have been evaluated for use in a process for removing mercury from contaminated mixed waste solids. Most of the experimental work was completed using surrogate waste. During the last quarter of fiscal year 1995, this process was evaluated using an actual mixed waste (storm sewer sediment from the Oak Ridge Y-12 Site). The mercury content of the storm sewer sediment was measured and determined to be approximately 35,000 mg/kg. A solution consisting of 0.2 M I{sub 2} and 0.4 M KI proved to be the most effective leachant used in the experiments when applied for 2 to 4 h at ambient temperature. Over 98% of the mercury was removed from the storm sewer sediment using this solution. Iodine recovery and recycle of the leaching agent were also accomplished successfully. Mathematical model was used to predict the amount of secondary waste in the process. Both surrogate waste and actual waste were used to study the fate of radionuclides (uranium) in the leaching process.

Klasson, K.T.; Koran, L.J. Jr.; Gates, D.D.; Cameron, P.A.

1997-12-01T23:59:59.000Z

355

RAPID/BulkTransmission/General Construction | Open Energy Information  

Open Energy Info (EERE)

RAPIDBulkTransmissionGeneral Construction < RAPID | BulkTransmission Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA RAPID Toolkit...

356

On Eling-Oz formula for the holographic bulk viscosity  

E-Print Network [OSTI]

Recently Eling and Oz [1] proposed a simple formula for the bulk viscosity of holographic plasma. They argued that the formula is valid in the high temperature (near-conformal) regime, but is expected to break down at low temperatures. We point out that the formula is in perfect agreement with the previous computations of the bulk viscosity of the cascading plasma [2,3], as well as with the previous computations of the bulk viscosity of N=2^* plasma [4,5]. In the latter case it correctly reproduces the critical behaviour of the bulk viscosity in the vicinity of the critical point with the vanishing speed of sound.

Alex Buchel

2011-03-19T23:59:59.000Z

357

Bulk viscosity of QCD matter near the critical temperature  

E-Print Network [OSTI]

Kubo's formula relates bulk viscosity to the retarded Green's function of the trace of the energy-momentum tensor. Using low energy theorems of QCD for the latter we derive the formula which relates the bulk viscosity to the energy density and pressure of hot matter. We then employ the available lattice QCD data to extract the bulk viscosity as a function of temperature. We find that close to the deconfinement temperature bulk viscosity becomes large, with viscosity-to-entropy ratio zeta/s about 1.

D. Kharzeev; K. Tuchin

2007-05-29T23:59:59.000Z

358

Innovative approaches to improve bulk heterojuction organic photovoltaic device performance.  

E-Print Network [OSTI]

??In this thesis we studied the electrical properties of bulk heterojunction organic photovoltaic (OPV) devices fabricated using a variety of conjugated polymers, including regioregular P3HT, (more)

Zhang, Ye

2010-01-01T23:59:59.000Z

359

Regulatory Roadmap Workshop for Federal Bulk Transmission Regulations...  

Open Energy Info (EERE)

Regulatory Roadmapping Pgower's picture Submitted by Pgower(45) Member 7 August, 2014 - 13:19 One-day workshop to review regulatory roadmaps for bulk transmission. Date:...

360

RAPID/BulkTransmission/Arizona | Open Energy Information  

Open Energy Info (EERE)

Entity responsible for coordinating and promoting Bulk Electric System reliability in the Western Interconnection, including Arizona. WECC also provides an environment for...

Note: This page contains sample records for the topic "bulk waste removal" 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

Light-Emitting Diodes on Semipolar Bulk Gallium Nitride Substrate  

Broader source: Energy.gov [DOE]

This project is producing high-efficiency semipolar light-emitting diodes (LEDs) on low-defect bulk gallium nitride (GaN) substrates.

362

RAPID/BulkTransmission/New Mexico | Open Energy Information  

Open Energy Info (EERE)

Information Desktop Toolkit BETA RAPID Toolkit About Bulk Transmission Geothermal Solar Resources Contribute Contact Us Regulatory Information Overviews Search for other...

363

Bulk Fuel Procurement Process & Alternative Drop-in Fuel  

Broader source: Energy.gov [DOE]

Jeanne Binder, DLA Energy, presentation on Bulk Fuel Procurement Process & Alternative Drop-in Fuel at the Advanced Biofuels Industry Roundtable.

364

Strategies for High Thermoelectric zT in Bulk Materials  

Broader source: Energy.gov [DOE]

Zintl principle in chemistry, complex electronic band structures, and incorporation of nanometer sized particles were used to explore, optimize and improve bulk thermoelectric materials

365

Recent Device Developments with Advanced Bulk Thermoelectric Materials at RTI  

Broader source: Energy.gov [DOE]

Reviews work in engineered thin-film nanoscale thermoelectric materials and nano-bulk materials with high ZT undertaken by RTI in collaboration with its research partners

366

High Heat Flux Thermoelectric Module Using Standard Bulk Material  

Broader source: Energy.gov [DOE]

Presents high heat flux thermoelectric module design for cooling using a novel V-shaped shunt configuration with bulk TE elements achieving high area packing fractions

367

Control Center and Data Management Improvements Modernize Bulk...  

Broader source: Energy.gov (indexed) [DOE]

Operations Corporation's (GSOC) Smart Grid Investment Grant (SGIG) project modernized bulk power management and control center operations for 38 electric membership...

368

RAPID/BulkTransmission/Air Quality | Open Energy Information  

Open Energy Info (EERE)

RAPIDBulkTransmissionAir Quality < RAPID | BulkTransmission Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA RAPID Toolkit About...

369

RAPID/BulkTransmission/About | Open Energy Information  

Open Energy Info (EERE)

Contribute Contact Us About Bulk Transmission Lattice.jpg High-voltage transmission lines form the backbone of electricity systems. Transmission lines are designed to carry...

370

RAPID/BulkTransmission/Water Quality | Open Energy Information  

Open Energy Info (EERE)

RAPIDBulkTransmissionWater Quality < RAPID | BulkTransmission Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA RAPID Toolkit About...

371

Analysis of a hypothetical criticality accident in a waste supercompactor  

SciTech Connect (OSTI)

A hypothetical nuclear criticality accident in a waste supercompactor is examined. The material being compressed in the compactor is a homogeneous mixture of beryllium and {sup 239}Pu. The point-kinetics equations with simple thermal-hydraulic feedback are used to model the transient behavior of the system. A computer code has been developed to solve the model equations. The computer code calculates the fission power history, fission yield, bulk temperature of the system, and several other thermal-hydraulic parameters of interest. Calculations have been performed for the waste supercompactor for various material misloading configurations. The peak power for the various accident scenarios varies from 1.04 {times} 10{sup 17} to 4.85 {times} 10{sup 20} fissions per second (fps). The total yield varies from 8.21 {times} 10{sup 17} to 7.73 {times} 10{sup 18} fissions, and the bulk temperature of the system varies from 412 to >912 K.

Plaster, M.J.; Basoglu, B.; Bentley, C.L.; Dunn, M.E.; Ruggles, A.E.; Wilkinson, A.D.; Yamamoto, T.; Dodds, H.L. [Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.

1995-08-01T23:59:59.000Z

372

Thermoelectric recovery of waste heat -- Case studies  

SciTech Connect (OSTI)

The use of waste heat as an energy source for thermoelectric generation largely removes the constraint for the wide scale application of this technology imposed by its relatively low conversion efficiency (typically about 5%). Paradoxically, in some parasitic applications, a low conversion efficiency can be viewed as a distinct advantage. However, commercially available thermoelectric modules are designed primarily for refrigerating applications and are less reliable when operated at elevated temperatures. Consequently, a major factor which determines the economic competitiveness of thermoelectric recovery of waste heat is the cost per watt divided by the mean-time between module failures. In this paper is reported the development of a waste, warm water powered thermoelectric generator, one target in a NEDO sponsored project to economically recover waste heat. As an application of this technology case studies are considered in which thermoelectric generators are operated in both active and parasitic modes to generate electrical power for a central heating system. It is concluded that, in applications when the supply of heat essentially is free as with waste heat, thermoelectrics can compete economically with conventional methods of electrical power generation. Also, in this situation, and when the generating system is operated in a parasitic mode, conversion efficiency is not an important consideration.

Rowe, M.D.; Min, G.; Williams, S.G.K.; Aoune, A. [Cardiff School of Engineering (United Kingdom). Div. of Electronic Engineering; Matsuura, Kenji [Osaka Univ., Suita, Osaka (Japan). Dept. of Electrical Engineering; Kuznetsov, V.L. [Ioffe Physical-Technical Inst., St. Petersburg (Russian Federation); Fu, L.W. [Tsinghua Univ., Beijing (China). Microelectronics Inst.

1997-12-31T23:59:59.000Z

373

Removing Stains from Washable Fabrics.  

E-Print Network [OSTI]

of May 8, 1914, as amended, and June 30, 1914, in cooperation with the United States Department of Agriculture. Zerle L. Carpenter, Director, Texas Agricultural Extension Service, The Texas A&M University System. lOM-1l-88, New CLO ...I UUL. Z TA24S.7 8873 NO.1616 B.1616 / Texas Agricultural Extension Service LIBRARY FEB 0 1 1989 Texas A&M University Removing Stains from Washable Fabrics Ann Vanderpoorten 8eard* Most spots and stains can be removed by prompt...

Beard, Ann Vanderpoorten

1988-01-01T23:59:59.000Z

374

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

SciTech Connect (OSTI)

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

375

Waste disposal package  

DOE Patents [OSTI]

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

376

Electrochemical and photochemical treatment of aqueous waste streams  

SciTech Connect (OSTI)

Carbon aerogel electrodes have been used to remove NH{sub 4}ClO{sub 4} and heavy metals from aqueous waste streams. Photochemical oixdation with H{sub 2}O{sub 2} has been used to destroy organic contamination and is proposed as a means of avoiding the fouling of carbon aerogel electrodes.

Farmer, J.C.; Pekala, R.W.; Wang, F.T.; Fix, D.V.; Volpe, A.M.; Dietrich, D.D.; Siegel, W.H.; Carley, J.F.

1996-03-01T23:59:59.000Z

377

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAOs). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWBs will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Box PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix configurations and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

Carlsbad Field Office

2001-01-31T23:59:59.000Z

378

Improving Bulk Microphysics Parameterizations in Simulations of Aerosol Effects  

SciTech Connect (OSTI)

To improve the microphysical parameterizations for simulations of the aerosol indirect effect (AIE) in regional and global climate models, a double-moment bulk microphysical scheme presently implemented in the Weather Research and Forecasting (WRF) model is modified and the results are compared against atmospheric observations and simulations produced by a spectral bin microphysical scheme (SBM). Rather than using prescribed aerosols as in the original bulk scheme (Bulk-OR), a prognostic doublemoment aerosol representation is introduced to predict both the aerosol number concentration and mass mixing ratio (Bulk-2M). The impacts of the parameterizations of diffusional growth and autoconversion and the selection of the embryonic raindrop radius on the performance of the bulk microphysical scheme are also evaluated. Sensitivity modeling experiments are performed for two distinct cloud regimes, maritime warm stratocumulus clouds (SC) over southeast Pacific Ocean from the VOCALS project and continental deep convective clouds (DCC) in the southeast of China from the Department of Energy/ARM Mobile Facility (DOE/AMF) - China field campaign. The results from Bulk-2M exhibit a much better agreement in the cloud number concentration and effective droplet radius in both the SC and DCC cases with those from SBM and field measurements than those from Bulk-OR. In the SC case particularly, Bulk-2M reproduces the observed drizzle precipitation, which is largely inhibited in Bulk-OR. Bulk-2M predicts enhanced precipitation and invigorated convection with increased aerosol loading in the DCC case, consistent with the SBM simulation, while Bulk-OR predicts the opposite behaviors. Sensitivity experiments using four different types of autoconversion schemes reveal that the autoconversion parameterization is crucial in determining the raindrop number, mass concentration, and drizzle formation for warm 2 stratocumulus clouds. An embryonic raindrop size of 40 ?m is determined as a more realistic setting in the autoconversion parameterization. The saturation adjustment employed in calculating condensation/evaporation in the bulk scheme is identified as the main factor responsible for the large discrepancies in predicting cloud water in the SC case, suggesting that an explicit calculation of diffusion growth with predicted supersaturation is necessary for further improvements of the bulk microphysics scheme. Lastly, a larger rain evaporation rate below cloud is found in the bulk scheme in comparison to the SBM simulation, which could contribute to a lower surface precipitation in the bulk scheme.

Wang, Yuan; Fan, Jiwen; Zhang, Renyi; Leung, Lai-Yung R.; Franklin, Charmaine N.

2013-06-05T23:59:59.000Z

379

Material Profile Influences in Bulk-Heterojunctions  

SciTech Connect (OSTI)

he morphology in mixed bulk-heterojunction films are compared using three different quantitative measurement techniques. We compare the vertical composition changes using high-angle annular dark-field scanning transmission electron microscopy with electron tomography and neutron and x-ray reflectometry. The three measurement techniques yield qualita-tively comparable vertical concentration measurements. The presence of a metal cathode during thermal annealing is observed to alter the fullerene concentration throughout the thickness of the film for all measurements. However, the abso-lute vertical concentration of fullerene is quantitatively different for the three measurements. The origin of the quantitative measurement differences is discussed. The authors thank Luna Innovations, Inc. for donating the endohedral fullerenes used in this study and Plextronics for the P3HT. They are gratefully thank the National Science Foundation Energy for Sustainability Program, Award No. 0933435. This work benefited from the use of the Lujan Neutron Scattering Center at Los Alamos Neutron Science Center funded by the DOE Office of Basic Energy Sciences and Los Alamos National Laboratory under DOE Contract DE-AC52-06NA25396. This research was also supported in part by Laboratory Directed Research & Development program at PNNL. The Pacific Northwest National Laboratory is operated by Battelle for the US Department of Energy under contract DE-AC05-76RL01830.

Roehling, John D.; Rochester, Christopher W.; Ro, Hyun W.; Wang, Peng; Majewski, Jaroslaw; Batenburg, Kees J.; Arslan, Ilke; Delongchamp, Dean M.; Moule, Adam J.

2014-10-01T23:59:59.000Z

380

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network [OSTI]

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

Note: This page contains sample records for the topic "bulk waste removal" 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

Massive Hanford Test Reactor Removed - Plutonium Recycle Test...  

Office of Environmental Management (EM)

Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed from Hanford's 300 Area Massive Hanford Test Reactor Removed - Plutonium Recycle Test Reactor removed...

382

Multipollutant Removal with WOWClean System  

E-Print Network [OSTI]

such as petcoke, coal, wood, diesel and natural gas. In addition to significant removal of CO2, test results demonstrate the capability to reduce 99.5% SOx (from levels as high as 2200 ppm), 90% reduction of NOx, and > 90% heavy metals. The paper will include...

Romero, M.

2010-01-01T23:59:59.000Z

383

Nanostructured High Temperature Bulk Thermoelectric Energy Conversion for Efficient Waste Heat Recovery  

Broader source: Energy.gov [DOE]

Proposed two-stage TEG system with half-heusler as the first stage, and Bi2Te3 as the low temperature stage expected to show a 5% fuel efficiency improvement in vehicle platform under US06 drive cycle

384

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion for Efficient Automotive Waste Heat Recovery  

Broader source: Energy.gov [DOE]

2012 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

385

Nanostructured High-Temperature Bulk Thermoelectric Energy Conversion for Efficient Automotive Waste Heat Recovery  

Broader source: Energy.gov [DOE]

2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

386

LANL completes excavation of 1940s waste disposal site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

LANL completes excavation LANL completes excavation LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 22, 2011 Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation. Contact Colleen Curran Communicatons Office (505) 664-0344 Email LOS ALAMOS, New Mexico, September 22, 2011-Los Alamos National Laboratory has completed excavation of its oldest waste disposal site, Material Disposal Area B (MDA-B). The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. MDA-B was used from 1944-48 as a waste disposal site for Manhattan Project and Cold War-era research and

387

Leptonic contribution to the bulk viscosity of nuclear matter  

SciTech Connect (OSTI)

For {beta}-equilibrated nuclear matter we estimate the contribution to the bulk viscosity from purely leptonic processes, namely the conversion of electrons to and from muons. For oscillation frequencies in the kilohertz range, we find that this process provides the dominant contribution to the bulk viscosity when the temperature is well below the critical temperature for superconductivity or superfluidity of the nuclear matter.

Alford, Mark G.; Good, Gerald [Physics Department, Washington University, St. Louis, Missouri 63130 (United States)

2010-11-15T23:59:59.000Z

388

BULK TITANIUM MICROFLUIDIC NETWORKS FOR PROTEIN SELF-ASSEMBLY STUDIES  

E-Print Network [OSTI]

BULK TITANIUM MICROFLUIDIC NETWORKS FOR PROTEIN SELF-ASSEMBLY STUDIES E.R. Parker1 , L.S. Hirst2 developed micromachining technique to fabricate microfluidic networks in thin titanium foils. These devices relevant conditions. Keywords: bulk titanium, cytoskeleton proteins, microfluidics, surface modification 1

MacDonald, Noel C.

389

MORPHOLOGY DEPENDENT SHORT CIRCUIT CURRENT IN BULK HETEROJUNCTION SOLAR CELL  

E-Print Network [OSTI]

a relatively inexpensive option for the future solar cell technology, provided its efficiency increases beyondMORPHOLOGY DEPENDENT SHORT CIRCUIT CURRENT IN BULK HETEROJUNCTION SOLAR CELL Biswajit Ray, Pradeep, West Lafayette, Indiana, USA ABSTRACT Polymer based bulk heterostructure (BH) solar cell offers

Alam, Muhammad A.

390

Bulk Hydrogen Storage - Strategic Directions for Hydrogen Delivery Workshop  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Hydrogen Hydrogen Storage Strategic Directions for Hydrogen Delivery Workshop May 7-8, 2003 Crystal City, Virginia Breakout Session - Bulk Hydrogen Storage Main Themes/Caveats Bulk Storage = Anything not on the vehicle 10's of Tons -- End use point 50-100 Tons - Terminals/City Gates 1000's Tons - Between Production Facility and Terminal/City Gate Bulk storage requirements less restrictive and different from on-board storage Uncertainty about evolution of infrastructure requires multiple pathways to be considered Bulk storage is an economic solution to address supply/demand imbalance Breakout Session - Bulk Hydrogen Storage Targets/Objectives Hard to quantify - scenario & end-use dependent Storage Materials (solid state) and container require different targets

391

Carbon nanotubes grown on bulk materials and methods for fabrication  

DOE Patents [OSTI]

Disclosed are structures formed as bulk support media having carbon nanotubes formed therewith. The bulk support media may comprise fibers or particles and the fibers or particles may be formed from such materials as quartz, carbon, or activated carbon. Metal catalyst species are formed adjacent the surfaces of the bulk support material, and carbon nanotubes are grown adjacent the surfaces of the metal catalyst species. Methods employ metal salt solutions that may comprise iron salts such as iron chloride, aluminum salts such as aluminum chloride, or nickel salts such as nickel chloride. Carbon nanotubes may be separated from the carbon-based bulk support media and the metal catalyst species by using concentrated acids to oxidize the carbon-based bulk support media and the metal catalyst species.

Menchhofer, Paul A. (Clinton, TN); Montgomery, Frederick C. (Oak Ridge, TN); Baker, Frederick S. (Oak Ridge, TN)

2011-11-08T23:59:59.000Z

392

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form (Iron-Enriched Basalt (IEB) glass/ceramic). The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

393

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

394

Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005  

SciTech Connect (OSTI)

The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

McDowell, Kip; Forrester, Tim [Oak Ridge National Laboratory, PO Box 2008 MS-6322, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, PO Box 2008 MS-6322, Oak Ridge, TN 37831 (United States); Saunders, Mark [Fairfield Services Group, PO Box 31468, KNOxville, TN 37930 (United States)] [Fairfield Services Group, PO Box 31468, KNOxville, TN 37930 (United States)

2013-07-01T23:59:59.000Z

395

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT  

SciTech Connect (OSTI)

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

J. D. Bigbee

2000-06-21T23:59:59.000Z

396

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents &...

397

Waste Isolation Pilot Plant Transportation Security | Department...  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security Waste Isolation Pilot Plant Transportation Security More Documents &...

398

Silicon bulk micromachined hybrid dimensional artifact.  

SciTech Connect (OSTI)

A mesoscale dimensional artifact based on silicon bulk micromachining fabrication has been developed and manufactured with the intention of evaluating the artifact both on a high precision coordinate measuring machine (CMM) and video-probe based measuring systems. This hybrid artifact has features that can be located by both a touch probe and a video probe system with a k=2 uncertainty of 0.4 {micro}m, more than twice as good as a glass reference artifact. We also present evidence that this uncertainty could be lowered to as little as 50 nm (k=2). While video-probe based systems are commonly used to inspect mesoscale mechanical components, a video-probe system's certified accuracy is generally much worse than its repeatability. To solve this problem, an artifact has been developed which can be calibrated using a commercially available high-accuracy tactile system and then be used to calibrate typical production vision-based measurement systems. This allows for error mapping to a higher degree of accuracy than is possible with a glass reference artifact. Details of the designed features and manufacturing process of the hybrid dimensional artifact are given and a comparison of the designed features to the measured features of the manufactured artifact is presented and discussed. Measurement results from vision and touch probe systems are compared and evaluated to determine the capability of the manufactured artifact to serve as a calibration tool for video-probe systems. An uncertainty analysis for calibration of the artifact using a CMM is presented.

Claudet, Andre A.; Tran, Hy D.; Bauer, Todd Marks; Shilling, Katherine Meghan; Oliver, Andrew David

2010-03-01T23:59:59.000Z

399

Staged mold for encapsulating hazardous wastes  

DOE Patents [OSTI]

A staged mold for stabilizing hazardous wastes for final disposal by molding an agglomerate of the hazardous wastes and encapsulating the agglomerate. Three stages are employed in the process. In the first stage, a first mold body is positioned on a first mold base, a mixture of the hazardous wastes and a thermosetting plastic is loaded into the mold, the mixture is mechanically compressed, heat is applied to cure the mixture to form a rigid agglomerate, and the first mold body is removed leaving the agglomerate sitting on the first mold base. In the second stage, a clamshell second mold body is positioned around the agglomerate and the first mold base, a powdered thermoplastic resin is poured on top of the agglomerate and in the gap between the sides of the agglomerate and the second mold body, the thermoplastic is compressed, heat is applied to melt the thermoplastic, and the plastic is cooled jacketing the agglomerate on the top and sides. In the third stage, the mold with the jacketed agglomerate is inverted, the first mold base is removed exposing the former bottom of the agglomerate, powdered thermoplastic is poured over the former bottom, the first mold base is replaced to compress the thermoplastic, heat is applied to melt the new thermoplastic and the top part of the jacket on the sides, the plastic is cooled jacketing the bottom and fusing with the jacketing on the sides to complete the seamless encapsulation of the agglomerate.

Unger, Samuel L. (Los Angeles, CA); Telles, Rodney W. (Alhambra, CA); Lubowitz, Hyman R. (Rolling Hills Estates, CA)

1990-01-01T23:59:59.000Z

400

Tank Waste and Waste Processing | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

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

Note: This page contains sample records for the topic "bulk waste removal" 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
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401

Surfactant-enhanced extraction of hazardous wastes from soils. First report  

SciTech Connect (OSTI)

Through combined efforts, researchers at Clark Atlanta University and Savannah River Site propose to develop improved soil washing techniques for decontaminating soils containing organic, inorganic and radioactive wastes. This project encompasses several tasks including (1) identification of organic, inorganic and radioactive pollutants in selected soils, (2) separation of soils into various fractions and the determination of wastes in each fraction, (3) soil decontamination by washing with surfactants and evaluation of the effectiveness of various types of surfactants in removing contaminants from soils, (4) determination of soil remediation and the effects of the surfactant concentration and wash solution-to-soil ratio on the desorption and removal of organic wastes from soils, (5) assessment of soil particle size distribution on waste efficiency, (6) evaluating the effects of temperature, mixing rates, and extraction times on waste solubilization and extraction, and (7) determination of the influence of surface charge properties and the pHs of the souls slurries on the decontamination efficiency.

Abotsi, G.; Davies, I.; Saha, G.

1996-10-01T23:59:59.000Z

402

Bioelectrochemical Integration of Waste Heat Recovery, Waste...  

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

electrolytic cell, designed to integrate waste heat recovery (i.e a microbial heat recovery cell or MHRC), can operate as a fuel cell and convert effluent streams into...

403

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect (OSTI)

This report addresses the issues of conducting debris treatment in the New Waste Calcine Facility (NWCF) decontamination area and the methods currently being used to decontaminate material at the NWCF.

K. E. Archibald

1999-08-01T23:59:59.000Z

404

Solid Waste Management Plan. Revision 4  

SciTech Connect (OSTI)

The waste types discussed in this Solid Waste Management Plan are Municipal Solid Waste, Hazardous Waste, Low-Level Mixed Waste, Low-Level Radioactive Waste, and Transuranic Waste. The plan describes for each type of solid waste, the existing waste management facilities, the issues, and the assumptions used to develop the current management plan.

NONE

1995-04-26T23:59:59.000Z

405

Waste Confidence Discussion | Department of Energy  

Office of Environmental Management (EM)

Waste Confidence Discussion Waste Confidence Discussion Long-Term Waste Confidence Update. Waste Confidence Discussion More Documents & Publications Status Update: Extended Storage...

406

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

407

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting...

408

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

409

Energy from Waste UK Joint Statement on Energy from Waste  

E-Print Network [OSTI]

Energy from Waste UK Joint Statement on Energy from Waste Read more overleaf Introduction Energy from waste provides us with an opportunity for a waste solution and a local source of energy rolled,itcan onlyaddressaportionofthewastestream andisnotsufficientonitsown. Energy obtained from the combustion of residual waste (Energy from

410

LOW ACTIVITY WASTE FEED SOLIDS CARACTERIZATION AND FILTERABILITY TESTS  

SciTech Connect (OSTI)

The primary treatment of the tank waste at the DOE Hanford site will be done in the Waste Treatment and Immobilization Plant (WTP) that is currently under construction. The baseline plan for the WTP Pretreatment facility is to treat the waste, splitting it into High Level Waste (HLW) feed and Low Activity Waste (LAW) feed. Both waste streams are then separately vitrified as glass and sealed in canisters. The LAW glass will be disposed onsite in the Integrated Disposal Facility (IDF). There are currently no plans to treat the waste to remove technetium in the WTP Pretreatment facility, so its disposition path is the LAW glass. Options are being explored to immobilize the LAW portion of the tank waste, i.e., the LAW feed from the WTP Pretreatment facility. Removal of {sup 99}Tc from the LAW Feed, followed by off-site disposal of the {sup 99}Tc, would eliminate a key risk contributor for the IDF Performance Assessment (PA) for supplemental waste forms, and has potential to reduce treatment and disposal costs. Washington River Protection Solutions (WRPS) is developing some conceptual flow sheets for LAW treatment and disposal that could benefit from technetium removal. One of these flowsheets will specifically examine removing {sup 99}Tc from the LAW feed stream to supplemental immobilization. The conceptual flow sheet of the {sup 99}Tc removal process includes a filter to remove insoluble solids prior to processing the stream in an ion exchange column, but the characteristics and behavior of the liquid and solid phases has not previously been investigated. This report contains results of testing of a simulant that represents the projected composition of the feed to the Supplemental LAW process. This feed composition is not identical to the aqueous tank waste fed to the Waste Treatment Plant because it has been processed through WTP Pretreatment facility and therefore contains internal changes and recycle streams that will be generated within the WTP process. Although a Supplemental LAW feed simulant has previously been prepared, this feed composition differs from that simulant because those tests examined only the fully soluble aqueous solution at room temperature, not the composition formed after evaporation, including the insoluble solids that precipitate after it cools. The conceptual flow sheet for Supplemental LAW immobilization has an option for removal of {sup 99}Tc from the feed stream, if needed. Elutable ion exchange has been selected for that process. If implemented, the stream would need filtration to remove the insoluble solids prior to processing in an ion exchange column. The characteristics, chemical speciation, physical properties, and filterability of the solids are important to judge the feasibility of the concept, and to estimate the size and cost of a facility. The insoluble solids formed during these tests were primarily natrophosphate, natroxalate, and a sodium aluminosilicate compound. At the elevated temperature and 8 M [Na+], appreciable insoluble solids (1.39 wt%) were present. Cooling to room temperature and dilution of the slurry from 8 M to 5 M [Na+] resulted in a slurry containing 0.8 wt% insoluble solids. The solids (natrophosphate, natroxalate, sodium aluminum silicate, and a hydrated sodium phosphate) were relatively stable and settled quickly. Filtration rates were in the range of those observed with iron-based simulated Hanford tank sludge simulants, e.g., 6 M [Na+] Hanford tank 241-AN-102, even though their chemical speciation is considerably different. Chemical cleaning of the crossflow filter was readily accomplished with acid. As this simulant formulation was based on an average composition of a wide range of feeds using an integrated computer model, this exact composition may never be observed. But the test conditions were selected to enable comparison to the model to enable improving its chemical prediction capability.

McCabe, D.; Crawford, C.; Duignan, M.; Williams, M.; Burket, P.

2014-04-03T23:59:59.000Z

411

Waste Inspection Tomography (WIT)  

SciTech Connect (OSTI)

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

412

Removing Barriers to Interdisciplinary Research  

E-Print Network [OSTI]

A significant amount of high-impact contemporary scientific research occurs where biology, computer science, engineering and chemistry converge. Although programmes have been put in place to support such work, the complex dynamics of interdisciplinarity are still poorly understood. In this paper we interrogate the nature of interdisciplinary research and how we might measure its "success", identify potential barriers to its implementation, and suggest possible mechanisms for removing these impediments.

Naomi Jacobs; Martyn Amos

2010-12-19T23:59:59.000Z

413

Effect of bed medium moisture on {alpha}-pinene removal by biofilters  

SciTech Connect (OSTI)

In this study, laboratory scale continuous flow bioifilters were used to determine the effect of bed medium moisture on biofilter performance when treating off-gases containing {alpha}-pinene. Biofilters were packed using a proprietary wood waste bed medium and were operated at a flow rate of 700 ml of air per min, yielding an empty bed residence time of 2 minutes. For the bed medium moisture levels tested, a biofilter bed held at 100% moisture on a dry weight basis demonstrated the best overall {alpha}-pinene removal results. Volumetric productivity and percent removal were higher, while the time to reach maximum removal efficiency was decreased compared to biofilters operated at 40, 60 and 80% bed medium moisture. Results indicate that control of moisture in a biofilter is important for maximum removal of {alpha}-pinene.

Lee, B.D.; Apel, W.A.; Cook, L.L. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Nichols, K.M. [Weyerhaeuser, Federal Way, WA (United States)

1996-12-31T23:59:59.000Z

414

Waste Isolation Pilot Plant 2003 Site Environmental Report  

SciTech Connect (OSTI)

The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to convey that performance to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2003. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through the research and production of nuclear weapons and other activities related to the national defense of the United States. TRU waste is defined in the WIPP LWA as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years. Exceptions are noted as high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools, and sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. A TRU waste is eligible for disposal at WIPP if it has been generated in whole or in partby one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] 10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management, defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated storage rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. Salt under pressure is relatively plastic, and mine openings will be allowed to creep closed for final disposal, encapsulating and isolating the waste.

Washington Regulatory and Environmental Services

2005-09-03T23:59:59.000Z

415

Hanford Site Tank 241-C-108 Residual Waste Contaminant Release Models and Supporting Data  

SciTech Connect (OSTI)

This report presents the results of laboratory characterization, testing, and analysis for a composite sample (designated 20578) of residual waste collected from single-shell tank C-108 during the waste retrieval process after modified sluicing. These studies were completed to characterize concentration and form of contaminant of interest in the residual waste; assess the leachability of contaminants from the solids; and develop release models for contaminants of interest. Because modified sluicing did not achieve 99% removal of the waste, it is expected that additional retrieval processing will take place. As a result, the sample analyzed here is not expected to represent final retrieval sample.

Cantrell, Kirk J.; Krupka, Kenneth M.; Geiszler, Keith N.; Arey, Bruce W.; Schaef, Herbert T.

2010-06-18T23:59:59.000Z

416

Feasibility Study Using a Solar Evaporator to Reduce the Metalworking Fluid (MWF) Waste Stream  

SciTech Connect (OSTI)

A solar evaporator was designed, built, and operated to reduce the water-based metalworking fluid waste stream. The evaporator was setup in Waste Managements barrel lot inside one of the confinement areas. The unit processed three batches of waste fluid during the prototype testing. Initial tests removed 13% of the fluid waste stream. Subsequent modifications to the collector improved the rate to almost 20% per week. Evaluation of the risk during operation showed that even a small spill when associated with precipitation, and the unit placement within a confinement area, gave it the potential to contaminate more fluid that what it could save.

Lazarus, Lloyd

2008-12-03T23:59:59.000Z

417

RESORCINOL-FORMALDEHYDE ION EXCHANGE RESIN CHEMISTRY FOR HIGH LEVEL WASTE TREATMENT  

SciTech Connect (OSTI)

A principal goal at the Savannah River Site is to safely dispose of the large volume of liquid nuclear waste held in many storage tanks. In-tank ion exchange technology is being considered for cesium removal using a polymer resin made of resorcinol formaldehyde that has been engineered into microspheres. The waste under study is generally lower in potassium and organic components than Hanford waste; therefore, the resin performance was evaluated with actual dissolved salt waste. The ion exchange performance and resin chemistry results are discussed.

Nash, C.; Duignan, M.

2010-01-14T23:59:59.000Z

418

RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE  

SciTech Connect (OSTI)

The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

Peters, T.; Washington, A.; Fink, S.

2012-01-09T23:59:59.000Z

419

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.

Most, W. A.; Kehrman, R.; Gist, C.; Biedscheid, J.; Devarakonda, J.; Whitworth, J.

2002-02-26T23:59:59.000Z

420

Zone Freezing Study for Pyrochemical Process Waste Minimization  

SciTech Connect (OSTI)

Pyroprocessing technology is a non-aqueous separation process for treatment of used nuclear fuel. At the heart of pyroprocessing lies the electrorefiner, which electrochemically dissolves uranium from the used fuel at the anode and deposits it onto a cathode. During this operation, sodium, transuranics, and fission product chlorides accumulate in the electrolyte salt (LiCl-KCl). These contaminates change the characteristics of the salt overtime and as a result, large volumes of contaminated salt are being removed, reprocessed and stored as radioactive waste. To reduce the storage volumes and improve recycling process for cost minimization, a salt purification method called zone freezing has been proposed at Korea Atomic Energy Research Institute (KAERI). Zone freezing is melt crystallization process similar to the vertical Bridgeman method. In this process, the eutectic salt is slowly cooled axially from top to bottom. As solidification occurs, the fission products are rejected from the solid interface and forced into the liquid phase. The resulting product is a grown crystal with the bulk of the fission products near the bottom of the salt ingot, where they can be easily be sectioned and removed. Despite successful feasibility report from KAERI on this process, there were many unexplored parameters to help understanding and improving its operational routines. Thus, this becomes the main motivation of this proposed study. The majority of this work has been focused on the CsCl-LiCl-KCl ternary salt. CeCl3-LiCl-KCl was also investigated to check whether or not this process is feasible for the trivalent speciessurrogate for rare-earths and transuranics. For the main part of the work, several parameters were varied, they are: (1) the retort advancement rate1.8, 3.2, and 5.0 mm/hr, (2) the crucible lid configurationslid versus no-lid, (3) the amount or size of mixture50 and 400 g, (4) the composition of CsCl in the salt1, 3, and 5 wt%, and (5) the temperature differences between the high and low furnace zones200 and 300 ?C. During each experiment, the temperatures at selected locations around the crucible were measured and recorded to provide temperature profiles. Following each experiment, samples were collected and elemental analysis was done to determine the composition of iii the salt. Several modelsnon-mixed, well-mixed, Favier, and hybridwere explored to describe the zone freezing process. For CsCl-LiCl-KCl system, experimental results indicate that through this process up to 90% of the used salt can be recycled, effectively reducing waste volume by a factor of ten. The optimal configuration was found to be a 5.0 mm/hr rate with a lid configuration and a ?T of 200C. The larger 400 g mixtures had recycle percentages similar to the 50 g mixtures; however, the throughput per time was greater for the 400 g case. As a result, the 400 g case is recommended. For the CeCl3-LiCl-KCl system, the result implies that it is possible to use this process to separate the rare-earth and transuranics chlorides. Different models were applied to only CsCl ternary system. The best fit model was the hybrid model as a result of a solute transport transition from non- mixed to well-mixed throughout the growing process.

Ammon Williams

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "bulk waste removal" 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

Aqueous Waste Treatment Plant at Aldermaston  

SciTech Connect (OSTI)

For over half a century the Pangbourne Pipeline formed part of AWE's liquid waste management system. Since 1952 the 11.5 mile pipeline carried pre-treated wastewater from the Aldermaston site for safe dispersal in the River Thames. Such discharges were in strict compliance with the exacting conditions demanded by all regulatory authorities, latterly, those of the Environment Agency. In March 2005 AWE plc closed the Pangbourne Pipeline and ceased discharges of treated active aqueous waste to the River Thames via this route. The ability to effectively eliminate active liquid discharges to the environment is thanks to an extensive programme of waste minimization on the Aldermaston site, together with the construction of a new Waste Treatment Plant (WTP). Waste minimization measures have reduced the effluent arisings by over 70% in less than four years. The new WTP has been built using best available technology (evaporation followed by reverse osmosis) to remove trace levels of radioactivity from wastewater to exceptionally stringent standards. Active operation has confirmed early pilot scale trials, with the plant meeting throughput and decontamination performance targets, and final discharges being at or below limits of detection. The performance of the plant allows the treated waste to be discharged safely as normal industrial effluent from the AWE site. Although the project has had a challenging schedule, the project was completed on programme, to budget and with an exemplary safety record (over 280,000 hours in construction with no lost time events) largely due to a pro-active partnering approach between AWE plc and RWE NUKEM and its sub-contractors. (authors)

Keene, D. [RWE NUKEM, Ltd, 424 Harwell, Didcot, Oxfordshire, OX 110GJ (United Kingdom); Fowler, J.; Frier, S. [AWE plc, Aldermaston, Berkshire RG7 4PR (United Kingdom)

2006-07-01T23:59:59.000Z

422

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark  

Broader source: Energy.gov (indexed) [DOE]

Landfill Reaches 15 Million Tons Disposed - Waste Disposal Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor July 9, 2013 - 12:00pm Addthis Media Contacts Cameron Hardy, DOE, (509) 376-5365 Cameron.Hardy@rl.doe.gov Mark McKenna, WCH, (509) 372-9032 media@wch-rcc.com RICHLAND, Wash. - The U.S. Department of Energy (DOE) and its contractors have disposed of 15 million tons of contaminated material at the Environmental Restoration Disposal Facility (ERDF) since the facility began operations in 1996. Removing contaminated material and providing for its safe disposal prevents contaminants from reaching the groundwater and the Columbia River. ERDF receives contaminated soil, demolition debris, and solid waste from

423

NETL: News Release - Converting Coal Wastes to Clean Energy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

November 28, 2000 November 28, 2000 Converting Coal Wastes to Clean Energy DOE to Scale Up 3 Projects That Upgrade Coal Fines, Wastes PITTSBURGH, PA - Three new technologies that can help the nation's coal industry turn waste into energy are now ready for scale up, the U.S. Department of Energy said today. MORE INFO Solid Fuels & Feedstocks Program Each of the three recover carbon-rich materials that in the past have been discarded during coal mining and cleaning operations. Using innovative approaches, the technologies remove unwanted water and other impurities and upgrade the waste materials into clean-burning fuels for power plants. The three were first selected for smaller-scale research in August 1998 as part of the Energy Department's Fossil Energy "solid fuels and feedstocks"

424

Submergible torch for treating waste solutions and method thereof  

DOE Patents [OSTI]

A submergible torch for removing nitrate and/or nitrite ions from a waste solution containing nitrate and/or nitrite ions comprises: a torch tip, a fuel delivery mechanism, a fuel flow control mechanism, a catalyst, and a combustion chamber. The submergible torch is ignited to form a flame within the combustion chamber of the submergible torch. The torch is submerged in a waste solution containing nitrate and/or nitrite ions in such a manner that the flame is in contact with the waste solution and the catalyst and is maintained submerged for a period of time sufficient to decompose the nitrate and/or nitrite ions present in the waste solution.

Mattus, Alfred J. (Oak Ridge, TN)

1994-01-01T23:59:59.000Z

425

Submergible torch for treating waste solutions and method thereof  

DOE Patents [OSTI]

A submergible torch for removing nitrate and/or nitrite ions from a waste solution containing nitrate and/or nitrite ions comprises: a torch tip, a fuel delivery mechanism, a fuel flow control mechanism, a catalyst, and a combustion chamber. The submergible torch is ignited to form a flame within the combustion chamber of the submergible torch. The torch is submerged in a waste solution containing nitrate and/or nitrite ions in such a manner that the flame is in contact with the waste solution and the catalyst and is maintained submerged for a period of time sufficient to decompose the nitrate and/or nitrite ions present in the waste solution.

Mattus, Alfred J. (Oak Ridge, TN)

1995-01-01T23:59:59.000Z

426

Pioneering Nuclear Waste Disposal  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

18 18 19 T he WIPP's first waste receipt, 11 years later than originally planned, was a monumental step forward in the safe management of nuclear waste. Far from ending, however, the WIPP story has really just begun. For the next 35 years, the DOE will face many challenges as it manages a complex shipment schedule from transuranic waste sites across the United States and continues to ensure that the repository complies with all regulatory requirements. The DOE will work to maintain the highest level of safety in waste handling and trans- portation. Coordination with sites Disposal operations require coordination with sites that will ship transuranic waste to the WIPP and include periodic certification of waste characterization and handling practices at those facilities. During the WIPP's

427

SRS - Programs - Waste Solidification  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (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

428

High level nuclear waste  

SciTech Connect (OSTI)

The DOE Division of Waste Products through a lead office at Savannah River is developing a program to immobilize all US high-level nuclear waste for terminal disposal. DOE high-level wastes include those at the Hanford Plant, the Idaho Chemical Processing Plant, and the Savannah River Plant. Commercial high-level wastes, for which DOE is also developing immobilization technology, include those at the Nuclear Fuel Services Plant and any future commercial fuels reprocessing plants. The first immobilization plant is to be the Defense Waste Processing Facility at Savannah River, scheduled for 1983 project submission to Congress and 1989 operation. Waste forms are still being selected for this plant. Borosilicate glass is currently the reference form, but alternate candidates include concretes, calcines, other glasses, ceramics, and matrix forms.

Crandall, J L

1980-01-01T23:59:59.000Z

429

Underground waste barrier structure  

DOE Patents [OSTI]

Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

430

Bulk viscosity, chemical equilibration and flow at RHIC  

E-Print Network [OSTI]

We study the effects of bulk viscosity on p_T spectra and elliptic flow in heavy ion collisions at RHIC. We argue that direct effect of the bulk viscosity on the evolution of the velocity field is small, but corrections to the freezeout distributions can be significant. These effects are dominated by chemical non-equilibration in the hadronic phase. We show that a non-zero bulk viscosity in the range $\\zeta/s \\lsim 0.05$ improves the description of spectra and flow at RHIC.

Thomas Schaefer; Kevin Dusling

2012-10-15T23:59:59.000Z

431

Brane-Bulk energy exchange and agegraphic dark energy  

E-Print Network [OSTI]

We consider the agegraphic models of dark energy in a braneworld scenario with brane-bulk energy exchange. We assume that the adiabatic equation for the dark matter is satisfied while it is violated for the agegraphic dark energy due to the energy exchange between the brane and the bulk. Our study shows that with the brane-bulk interaction, the equation of state parameter of agegraphic dark energy on the brane, $w_D$, can have a transition from normal state where $w_D >-1 $ to the phantom regime where $w_D energy always satisfies $w^{\\mathrm{eff}}_D\\geq-1$.

Ahmad Sheykhi

2010-02-06T23:59:59.000Z

432

Synthesizing Optimal Waste Blends  

Science Journals Connector (OSTI)

Vitrification of tank wastes to form glass is a technique that will be used for the disposal of high-level waste at Hanford. ... Durability restrictions ensure that the resultant glass meets the quantitative criteria for disposal/long-term storage in a repository. ... If glasses are formulated to minimize the volume of glass that would be produced, then the cost of processing the waste and storing the resultant glass would be greatly reduced. ...

Venkatesh Narayan; Urmila M. Diwekar; Mark Hoza

1996-10-08T23:59:59.000Z

433

Process for treating alkaline wastes for vitrification  

DOE Patents [OSTI]

A process for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO.sub.2 to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO.sub.2, noble metal compounds, nitrates, formates and so forth. The process minimizes the amount of hydrogen generated during treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product.

Hsu, Chia-lin W. (Augusta, GA)

1995-01-01T23:59:59.000Z

434

Process for treating alkaline wastes for vitrification  

DOE Patents [OSTI]

A process is described for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO{sub 2} to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO{sub 2}, noble metal compounds, nitrates, formates and so forth. The process minimizes the amount of hydrogen generated during treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product. 4 figs.

Hsu, C.L.W.

1995-07-25T23:59:59.000Z

435

Nevada nuclear waste storage investigations: briefing book  

SciTech Connect (OSTI)

The Nevada Nuclear Waste Storage Investigations (NNWSI) are discussed briefly. The tuff in Yucca mountains being investigated as a possible repository host for radioactive wastes. The Spent Fuel Test-Climax began in the spring of 1980 in the northeastern Nevada Test Site about 1400 ft below the desert surface. The test has provided significant scientific and technical contributions in the following areas: heat impact on a large underground facility in a hard, brittle rock, impact of ventilation designs on repository heat removal, suitability and operational characteristics of instrumentation in a repository, impact of the mining procedures on underground openings and the surrounding rock, and heat and radiation effects on the physical, mechanical, and chemical properties of granite.

NONE

1983-03-01T23:59:59.000Z

436

Waste Confidence Discussion  

Broader source: Energy.gov (indexed) [DOE]

Long-Term Long-Term Waste Confidence Update Christine Pineda Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission National Transportation Stakeholders Forum May 2012 ♦ Knoxville, Tennessee Long-Term Update Draft Report, "Background and Preliminary Assumptions for an Environmental Impact Statement- Long-Term Waste Confidence Update" Elements of the Long-Term Update - Draft environmental impact statement - Draft Waste Confidence Decision - Proposed Waste Confidence Rule based on the EIS and Decision, if applicable 2 Overview of Draft Report Background and assumptions report is first step in process. Basic topics in the report are:

437

Norcal Waste Systems, Inc.  

SciTech Connect (OSTI)

Fact sheet describes the LNG long-haul heavy-duty trucks at Norcal Waste Systems Inc.'s Sanitary Fill Company.

Not Available

2002-12-01T23:59:59.000Z

438

Section 24: Waste Characterization  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Energy (DOE). 1995b. Transuranic Waste Baseline Inventory Report (Revision 2, December). DOECAO-95-1121. ERMS 531643. Carlsbad Area Office, Carlsbad, NM. PDF Author U.S....

439

Hanford Dangerous Waste Permit  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

training, security) * Closure plan Tank-Related Permit Units New * 149 single-shell tanks (SSTs) * 28 double-shell tanks (DSTs) Existing * 242-A Evaporator * Waste Treatment...

440

Waste Heat Recovery  

Office of Environmental Management (EM)

DRAFT - PRE-DECISIONAL - DRAFT 1 Waste Heat Recovery 1 Technology Assessment 2 Contents 3 1. Introduction to the TechnologySystem ......

Note: This page contains sample records for the topic "bulk waste removal" 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

Electronic Waste Transformation  

Science Journals Connector (OSTI)

Electronic Waste Transformation ... Instead, entrepreneurial individuals and small businesses recover valuable metals such as copper from obsolete equipment through activities such as burning. ...

CHERYL HOGUE

2012-04-01T23:59:59.000Z

442

Waste minimization assessment procedure  

SciTech Connect (OSTI)

Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative.

Kellythorne, L.L. (Centerior Energy, Cleveland, OH (United States))

1993-01-01T23:59:59.000Z

443

Vitrification of waste  

DOE Patents [OSTI]

A method is described for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300 C to 800 C to incinerate organic materials, then heated further to a temperature in the range of approximately 1100 C to 1400 C at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, G.G.

1999-04-06T23:59:59.000Z

444

Avoidable waste management costs  

SciTech Connect (OSTI)

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

445

Waste Isolation Pilot Plant  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

September 19, 2014 - No second release at WIPP September 12, 2014 - Waste hoist transformer replacement September 09, 2014 - Additional areas cleared in WIPP underground...

446

Vitrification of waste  

DOE Patents [OSTI]

A method for encapsulating and immobilizing waste for disposal. Waste, preferably, biologically, chemically and radioactively hazardous, and especially electronic wastes, such as circuit boards, are placed in a crucible and heated by microwaves to a temperature in the range of approximately 300.degree. C. to 800.degree. C. to incinerate organic materials, then heated further to a temperature in the range of approximately 1100.degree. C. to 1400.degree. C. at which temperature glass formers present in the waste will cause it to vitrify. Glass formers, such as borosilicate glass, quartz or fiberglass can be added at the start of the process to increase the silicate concentration sufficiently for vitrification.

Wicks, George G. (Aiken, SC)

1999-01-01T23:59:59.000Z

447

Report of the Bulk Working Group  

SciTech Connect (OSTI)

The world in general and the USA in particular are facing an oncoming energy shortage. One key mechanism to provide carbon-free energy is nuclear fission. At this point, 20% of the US electrical power grid is supplied by nuclear energy. (Interestingly, it is 50% in Illinois.) European nations such as Sweden (50% nuclear electricity) and France (80% nuclear electricity) are pushing ahead with permanent radioactive waste storage and processing. If nothing else, the USA needs to provide the scientific foundation for improving its nuclear-power generation facilities. One key issue and how the APS could affect it are discussed below. (This discussion of this issue is not meant to be a comprehension argument in support of a facility but merely an example of the sort of science that could be pursued. An exhaustive collection of arguments would take more time and effort.) The modification of various zones inside a nuclear fuel is an important issue. This includes microscopic re-crystallization, stress, fission gas production, He bubble formation and the intermixing, depletion and enrichment of various chemical, daughter and other isotopic species. For example, past studies of the ternary nuclear fuel UPuZr have demonstrated constituent redistribution when irradiated or with thermal treatment. The concentration variations shown above are of significant concern. Driven in part by the thermal gradient within the nuclear fuel, these variations can affect reactor performance and fuel burn-up levels. Similar gradients were observed in samples that were not irradiated but underwent thermal gradient treatments. From measurement such as these, kinetic parameters such as effective inter-diffusion coefficients were derived. The amount of such experimental data is very limited. Interaction of the fuel constituents with cladding and coolant are also important. At present, INL scientists pursue a number of measurements on-site at INL and off-site to address issues such as this. Here, we will propose two key examples of how a new facility at the APS could impact this technological issue.

Tobin, J G

2010-02-09T23:59:59.000Z

448

Libya HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Libya HEU Removal Libya HEU Removal Location Libya United States 27 34' 9.5448" N, 17 24' 8.4384" E See map: Google Maps Javascript is required to view this map....

449

Canada HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Canada HEU Removal Canada HEU Removal Location Canada United States 53 47' 24.972" N, 104 35' 23.4384" W See map: Google Maps Javascript is required to view this map....

450

Israel HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Israel HEU Removal Israel HEU Removal Location Israel United States 30 53' 18.2328" N, 34 52' 14.178" E See map: Google Maps Javascript is required to view this map....

451

Uzbekistan HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Uzbekistan HEU Removal Uzbekistan HEU Removal Location Uzbekistan United States 42 6' 56.196" N, 63 22' 8.9076" E See map: Google Maps Javascript is required to view this map...

452

France HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Four-Year Plan France HEU Removal France HEU Removal Location United States 45 44' 20.0544" N, 2 17' 6.5616" E See map: Google Maps Javascript is required to view this map...

453

Chile HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Four-Year Plan Chile HEU Removal Chile HEU Removal Location United States 25 28' 1.4916" S, 69 33' 55.548" W See map: Google Maps Javascript is required to view this map...

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Taiwan HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Taiwan HEU Removal Taiwan HEU Removal Location Taiwan United States 24 35' 37.4964" N, 120 53' 36.798" E See map: Google Maps Javascript is required to view this map....

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Romania HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Romania HEU Removal Romania HEU Removal Location Romania United States 45 47' 1.932" N, 24 41' 50.1576" E See map: Google Maps Javascript is required to view this map....

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Serbia HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Serbia HEU Removal Serbia HEU Removal Location Serbia United States 44 22' 45.7068" N, 20 26' 4.452" E See map: Google Maps Javascript is required to view this map....

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Poland HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Poland HEU Removal Poland HEU Removal Location Poland United States 53 23' 50.2872" N, 17 50' 30.4692" E See map: Google Maps Javascript is required to view this map....

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Vietnam HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plan Vietnam HEU Removal Vietnam HEU Removal Location Vietnam United States 13 12' 30.8628" N, 108 19' 30.702" E See map: Google Maps Javascript is required to view this map....

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Ukraine HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Apply for Our Jobs Our Jobs Working at NNSA Blog Home content Four-Year Plan Ukraine HEU Removal Ukraine HEU Removal Location Ukraine United States 50 12' 24.8688" N,...

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Japan HEU Removal | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home content Four-Year Plan Japan HEU Removal Japan HEU Removal Location Japan United States 37 36' 59.5872" N, 140...

Note: This page contains sample records for the topic "bulk waste removal" from the National Library of EnergyBeta (NLEBeta).
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Pyrolysis Autoclave Technology Demonstration Program for Treatment of DOE Solidified Organic Wastes  

SciTech Connect (OSTI)

In the summer of 2005, MSE Technologies Applications, Inc. (MSE) and THOR Treatment Technologies, LLC (TTT) conducted a demonstration test of the Thermal Organic Reduction (THOR{sup sm}) in-drum pyrolysis autoclave system under contract to the Department of Energy. The purpose of the test was to demonstrate that the THOR{sup sm} pyrolysis autoclave system could successfully treat solidified organic waste to remove organics from the waste drums. The target waste was created at Rocky Flats and currently resides at the Radioactive Waste Management Complex (RWMC) at the Idaho National Laboratory (INL). Removing the organics from these drums would allow them to be shipped to the Waste Isolation Pilot Plant for disposal. Two drums of simulated organic setup waste were successfully treated. The simulated waste was virtually identical to the expected waste except for the absence of radioactive components. The simulated waste included carbon tetrachloride, trichloroethylene, perchloroethylene, Texaco Regal oil, and other organics mixed with calcium silicate and Portland cement stabilization agents. The two-stage process consisted of the THOR{sup sm} electrically heated pyrolysis autoclave followed by the MSE off gas treatment system. The treatment resulted in a final waste composition that meets the requirements for WIPP transportation and disposal. There were no detectable volatile organic compounds in the treated solid residues. The destruction and removal efficiency (DRE) for total organics in the two drums ranged from >99.999% to >99.9999%. The operation of the process proved to be easily controllable using the pyrolysis autoclave heaters. Complete treatment of a fully loaded surrogate waste drum including heat-up and cooldown took place over a two-day period. This paper discusses the results of the successful pyrolysis autoclave demonstration testing. (authors)

Roesener, W.S.; Mason, J.B.; Ryan, K. [THOR Treatment Technologies, LLC, 7800 E Union Ave, Denver, CO 80237 (United States); Bryson, S. [MSE Technologies Applications, Inc., 200 Technology Way, Butte, MT 59702 (United States); Eldredge, H.B. [Eldredge Engineering, P.A., 1090 Blue Ridge Dr., Idaho Falls, ID 83402 (United States)

2006-07-01T23:59:59.000Z

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Quaternised biomass as anion exchanger for the removal of fluoride from water  

Science Journals Connector (OSTI)

Dried Chinese Reed, a fast growing plant, was used as a model biomass for the development of anion exchangers using a quaternisation agent, N-(3-chloro-2-hydroxypropyl) trimethylammonium chloride (CHMAC), for the removal of fluoride from water. Parameters investigated in the adsorption studies include F? concentration, agitation time, adsorbent dose and pH. Equilibrium adsorption data followed both Langmuir and Freundlich isotherms. Presence of chloride, nitrate and sulfate decreased the adsorption significantly. Quaternised Hanf sativa and coconut coir pith (solid waste from coconut coir fibre industry) were also tested for the removal of fluoride with and without cross linking.

C. Namasivayam; W.H. Hoell

2008-01-01T23:59:59.000Z

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Waste Loading Enhancements for Hanford Low-Activity Waste Glasses  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

WASTE LOADING ENHANCEMENTS FOR HANFORD LOW-ACTIVITY WASTE GLASSES Albert A. Kruger, Glass Scientist DOE-WTP Project Office Engineering Division US Department of Energy Richland,...

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Tank Waste Committee Page 1  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

of a PA is to examine the final waste disposition at Hanford, such as waste in the tanks at C-Farm. Vince said the quest is to model waste movement over 10,000 years,...

465

ARM - Campaign Instrument - ec-convair580-bulk  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

govInstrumentsec-convair580-bulk govInstrumentsec-convair580-bulk Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign Instrument : Environment Canada Convair 580 Bulk Parameters (EC-CONVAIR580-BULK) Instrument Categories Aerosols, Cloud Properties, Airborne Observations Campaigns Indirect and Semi-Direct Aerosol Campaign (ISDAC) [ Download Data ] North Slope Alaska, 2008.04.01 - 2008.04.30 Primary Measurements Taken The following measurements are those considered scientifically relevant. Refer to the datastream (netcdf) file headers for the list of all available measurements, including those recorded for diagnostic or quality assurance purposes. Ice water content Liquid water content Hydrometeor size Cloud particle number concentration Aerosol concentration

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