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1

MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT  

E-Print Network (OSTI)

#12;MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT PHASE I: AUDIT OF CURRENT PRACTICE The Mushroom Waste Management Project (MWMP) was initiated by Environment Canada, the BC Ministry of solid and liquid wastes generated at mushroom producing facilities. Environmental guidelines

2

E17: The Thought and Process on Coal Side BFG Flux Display Eorr ...  

Science Conference Proceedings (OSTI)

Presentation Title, E17: The Thought and Process on Coal Side BFG Flux .... D18: Pure and Doped Ceria Nanoparticles for Green Natural Gas Combustion.

3

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

E-Print Network (OSTI)

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534) and identity of liquid waste Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534

Russell, Lynn

4

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

E-Print Network (OSTI)

2/2009 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 (9:1) OR Biohazard symbol (if untreated) and identity of liquid waste Biohazard symbol Address

Firtel, Richard A.

5

SRS - Programs - Liquid Waste Disposition  

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

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

6

Method for treating liquid wastes  

DOE Patents (OSTI)

The method of treating liquid waste in a media is accomplished by exposing the media to phosphinimines and sequestering .sup.99 Tc from the media by the phosphinimine (PN) functionalities. The system for treating the liquid waste in the media includes extraction of .sup.99 TcO.sub.4.sup.- from aqueous solutions into organic solvents or mixed organic/polar media, extraction of .sup.99 Tc from solutions on a solid matrix by using a container containing PN functionalities on solid matrices including an inlet and outlet for allowing flow of media through an immobilized phosphinimine ligand system contained within the container. Also, insoluble suspensions of phosphinimine functionalities on solid matrices in liquid solutions or present on supported liquid membranes (SLM) can be used to sequester .sup.99 Tc from those liquids.

Katti, Kattesh V. (Columbia, MO); Volkert, Wynn A. (Columbia, MO); Singh, Prahlad (Columbia, MO); Ketring, Alan R. (Columbia, MO)

1995-01-01T23:59:59.000Z

7

Method for treating liquid wastes  

DOE Patents (OSTI)

The method of treating liquid waste in a media is accomplished by exposing the media to phosphinimines and sequestering {sup 99}Tc from the media by the phosphinimine (PN) functionalities. The system for treating the liquid waste in the media includes extraction of {sup 99}TcO{sub 4}{sup {minus}} from aqueous solutions into organic solvents or mixed organic/polar media, extraction of {sup 99}Tc from solutions on a solid matrix by using a container containing PN functionalities on solid matrices including an inlet and outlet for allowing flow of media through an immobilized phosphinimine ligand system contained within the container. Also, insoluble suspensions of phosphinimine functionalities on solid matrices in liquid solutions or present on supported liquid membranes (SLM) can be used to sequester {sup 99}Tc from those liquids. 6 figs.

Katti, K.V.; Volkert, W.A.; Singh, P.; Ketring, A.R.

1995-12-26T23:59:59.000Z

8

Waste Logic™ Liquid Waste Manager (WL-LWM) Software, Version 2.0  

Science Conference Proceedings (OSTI)

In response to continuing industry efforts to reduce operating expenditures, EPRI developed the Waste Logic&trade: Liquid Waste Manager code to analyze costs associated with liquid waste processing and the disposition of its resultant solid waste. EPRI's Waste Logic: Liquid Waste Manager software for windows-based PC computers provides a detailed economic and performance view of liquid waste processing activities. The software will help nuclear utilities evaluate the costs associated with liquid radwaste...

2002-06-05T23:59:59.000Z

9

SRS Liquid Waste Program Partnering Agreement  

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

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

10

Method for solidifying liquid radioactive wastes  

DOE Patents (OSTI)

The quantity of nitrous oxides produced during the solidification of liquid radioactive wastes containing nitrates and nitrites can be substantially reduced by the addition to the wastes of a stoichiometric amount of urea which, upon heating, destroys the nitrates and nitrites, liberating nontoxic N.sub.2, CO.sub.2 and NH.sub.3.

Berreth, Julius R. (Idaho Falls, ID)

1976-01-01T23:59:59.000Z

11

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy–Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

Tripp, Julia Lynn; Archibald, Kip Ernest; Argyle, Mark Don; Demmer, Ricky Lynn; Miller, Rose Anna; Lauerhass, Lance

1999-03-01T23:59:59.000Z

12

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy ? Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

C. B. Millet; J. L. Tripp; K. E. Archibald; L. Lauerhauss; M. D. Argyle; R. L. Demmer

1999-02-01T23:59:59.000Z

13

Liquid low level waste management expert system  

SciTech Connect

An expert system has been developed as part of a new initiative for the Oak Ridge National Laboratory (ORNL) systems analysis program. This expert system will aid in prioritizing radioactive waste streams for treatment and disposal by evaluating the severity and treatability of the problem, as well as the final waste form. The objectives of the expert system development included: (1) collecting information on process treatment technologies for liquid low-level waste (LLLW) that can be incorporated in the knowledge base of the expert system, and (2) producing a prototype that suggests processes and disposal technologies for the ORNL LLLW system. 4 refs., 9 figs.

Ferrada, J.J.; Abraham, T.J. (Oak Ridge National Lab., TN (United States)); Jackson, J.R. (Southwest Baptist Univ., Bolivar, MO (USA))

1991-01-01T23:59:59.000Z

14

Conversion of cellulosic wastes to liquid fuels  

DOE Green Energy (OSTI)

The current status and future plans for a project to convert waste cellulosic (biomass) materials to quality liquid hydrocarbon fuels is described. The basic approach is indirect liquefaction, i.e., thermal gasification followed by catalytic liquefaction. The indirect approach results in separation of the oxygen in the biomass feedstock, i.e., oxygenated compounds do not appear in the liquid hydrocarbon fuel product. The process is capable of accepting a wide variety of feedstocks. Potential products include medium quality gas, normal propanol, diesel fuel and/or high octane gasoline. A fluidized bed pyrolysis system is used for gasification. The pyrolyzer can be fluidized with recycle pyrolysis gas, steam or recycle liquefaction system off gas or some combination thereof. Tars are removed in a wet scrubber. Unseparated pyrolysis gases are utilized as feed to a modified Fischer-Tropsch reactor. The liquid condensate from the reactor consists of a normal propanol-water phase and a paraffinic hydrocarbon phase. The reactor can be operated to optimize for either product. The following tasks were specified in the statement of work for the contract period: (1) feedstock studies; (2) gasification system optimization; (3) waste stream characterization; and (4) liquid fuels synthesis. In addition, several equipment improvements were implemented.

Kuester, J.L.

1980-09-01T23:59:59.000Z

15

Future radioactive liquid waste streams study  

SciTech Connect

This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

Rey, A.S.

1993-11-01T23:59:59.000Z

16

Recovery of Mercury From Contaminated Liquid Wastes  

SciTech Connect

The Base Contract program emphasized the manufacture and testing of superior sorbents for mercury removal, testing of the sorption process at a DOE site, and determination of the regeneration conditions in the laboratory. During this project, ADA Technologies, Inc. demonstrated the following key elements of a successful regenerable mercury sorption process: (1) sorbents that have a high capacity for dissolved, ionic mercury; (2) removal of ionic mercury at greater than 99% efficiency; and (3) thermal regeneration of the spent sorbent. ADA's process is based on the highly efficient and selective sorption of mercury by noble metals. Contaminated liquid flows through two packed columns that contain microporous sorbent particles on which a noble metal has been finely dispersed. A third column is held in reserve. When the sorbent is loaded with mercury to the point of breakthrough at the outlet of the second column, the first column is taken off-line and the flow of contaminated liquid is switched to the second and third columns. The spent column is regenerated by heating. A small flow of purge gas carries the desorbed mercury to a capture unit where the liquid mercury is recovered. Laboratory-scale tests with mercuric chloride solutions demonstrated the sorbents' ability to remove mercury from contaminated wastewater. Isotherms on surrogate wastes from DOE's Y-12 Plant in Oak Ridge, Tennessee showed greater than 99.9% mercury removal. Laboratory- and pilot-scale tests on actual Y-12 Plant wastes were also successful. Mercury concentrations were reduced to less than 1 ppt from a starting concentration of 1,000 ppt. The treatment objective was 50 ppt. The sorption unit showed 10 ppt discharge after six months. Laboratory-scale tests demonstrated the feasibility of sorbent regeneration. Results show that sorption behavior is not affected after four cycles.

1998-06-12T23:59:59.000Z

17

High-Level Liquid Waste Tank Integrity Workshop - 2008  

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

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

18

Newly Generated Liquid Waste Processing Alternatives Study, Volume 1  

SciTech Connect

This report identifies and evaluates three options for treating newly generated liquid waste at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory. The three options are: (a) treat the waste using processing facilities designed for treating sodium-bearing waste, (b) treat the waste using subcontractor-supplied mobile systems, or (c) treat the waste using a special facility designed and constructed for that purpose. In studying these options, engineers concluded that the best approach is to store the newly generated liquid waste until a sodium-bearing waste treatment facility is available and then to co-process the stored inventory of the newly generated waste with the sodium-bearing waste. After the sodium-bearing waste facility completes its mission, two paths are available. The newly generated liquid waste could be treated using the subcontractor-supplied system or the sodium-bearing waste facility or a portion of it. The final decision depends on the design of the sodium-bearing waste treatment facility, which will be completed in coming years.

Landman, William Henry; Bates, Steven Odum; Bonnema, Bruce Edward; Palmer, Stanley Leland; Podgorney, Anna Kristine; Walsh, Stephanie

2002-09-01T23:59:59.000Z

19

System for recovering methane gas from liquid waste  

SciTech Connect

A system for and method of recovering methane gas from liquid waste which is stored within a pit is disclosed herein. The methane gas is produced by causing the liquid waste to undergo anaerobic fermentation. Therefore, it is necessary to close the pit in an air tight fashion. This is carried out using a cover sheet which is fixedly disposed over the pit in an air tight but readily disengagable fashion. The liquid waste within this air tight pit is preferably agitated intermittently during its storage therein whereby to increase the amount of methane gas produced.

Grabis, D.W.

1983-07-19T23:59:59.000Z

20

Detection of free liquid in containers of solidified radioactive waste  

DOE Patents (OSTI)

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

Greenhalgh, Wilbur O. (Richland, WA)

1985-01-01T23:59:59.000Z

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

Radioactive Liquid Waste Treatment Facility: Environmental Information Document  

Science Conference Proceedings (OSTI)

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

1993-11-01T23:59:59.000Z

22

HNPF LIQUID WASTE DISPOSAL COST STUDY  

SciTech Connect

The HNPF cost analysis for waste disposal was made on the basis of 10,000 gallons of laundry waste and 9,000 gallons of other plant waste per year. The costs are compared for storage at HNPF site for 10 yr, packaging and shipment to AEC barial ground, packaging and shipment for sea disposal, and disposal by licensed vendor. A graphical comparison is given for the yearly costs of disposal by licensed vendor and the evaporator system as a function of waste volume. Recommendations are included for the handling of the wastes expected from HNPF operations. (B.O.G.)

Piccot, A.R.

1959-11-01T23:59:59.000Z

23

ICPP radioactive liquid and calcine waste technologies evaluation. Interim report  

SciTech Connect

The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

1994-06-01T23:59:59.000Z

24

Liquid and Gaseous Waste Operations Department Annual Operating Report, CY 1993  

SciTech Connect

This report summarizes the activities of the waste management operations section of the liquid and gaseous waste operations department at ORNL for 1993. The process waste, liquid low-level waste, gaseous waste systems activities are reported, as well as the low-level waste solidification project. Upgrade activities is the various waste processing and treatment systems are summarized. A maintenance activity overview is provided, and program management, training, and other miscellaneous activities are covered.

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

1994-02-01T23:59:59.000Z

25

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

26

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

27

Process for immobilizing radioactive boric acid liquid wastes  

DOE Patents (OSTI)

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

Greenhalgh, W.O.

1984-05-10T23:59:59.000Z

28

Process for immobilizing radioactive boric acid liquid wastes  

DOE Patents (OSTI)

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

Greenhalgh, Wilbur O. (Richland, WA)

1986-01-01T23:59:59.000Z

29

Iraq liquid radioactive waste tanks maintenance and monitoring program plan.  

SciTech Connect

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

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

2011-10-01T23:59:59.000Z

30

Pilot studies to achieve waste minimization and enhance radioactive liquid waste treatment at the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility  

SciTech Connect

The Radioactive and Industrial Wastewater Science Group manages and operates the Radioactive Liquid Waste Treatment Facility (RLWTF) at the Los Alamos National Laboratory (LANL). The RLWTF treats low-level radioactive liquid waste generated by research and analytical facilities at approximately 35 technical areas throughout the 43-square-mile site. The RLWTF treats an average of 5.8 million gallons (21.8-million liters) of liquid waste annually. Clarifloculation and filtration is the primary treatment technology used by the RLWTF. This technology has been used since the RLWTF became operable in 1963. Last year the RLWTF achieved an average of 99.7% removal of gross alpha activity in the waste stream. The treatment process requires the addition of chemicals for the flocculation and subsequent precipitation of radionuclides. The resultant sludge generated during this process is solidified in drums and stored or disposed of at LANL.

Freer, J.; Freer, E.; Bond, A. [and others

1996-07-01T23:59:59.000Z

31

Low-level liquid waste treatment system start-up  

Science Conference Proceedings (OSTI)

Following removal of Cs-137 by ion exchange in the Supernatant Treatment System immediately upstream, the radioactive liquid waste is volume-reduced by evaporation. Trace amounts of Cs-137 in the resulting distillate are removed by ion exchange, then the distillate is discharged to the existing plant water treatment system. The concentrated product, 37 to 41 percent solids (by weight), is encapsulated in cement, producing a stable low-level waste form. This report provides a summary of work performed to test the Liquid Waste Treatment System following construction turnover and prior to radioactive operation. All mechanical and electrical components, piping, valves, pumps, tanks, controls, and instrumentation required to operate the system were tested; first with water, then with simulated waste. Subsystems (individual tanks, pumps, and control loops) were tested individually, then as a complete system. Finally, the system began a controlled start-up phase, which included the first four months of radioactive operation. Components were tested for operability then for performance data to verify the system`s ability to produce an acceptable waste form at design feed rates.

Baker, M.N.; Gessner, R.F.

1989-07-01T23:59:59.000Z

32

Liquid and Gaseous Waste Operations Department annual operating report CY 1996  

SciTech Connect

This annual report summarizes operating activities dealing with the process waste system, the liquid low-level waste system, and the gaseous waste system. It also describes upgrade activities dealing with the process and liquid low-level waste systems, the cathodic protection system, a stack ventilation system, and configuration control. Maintenance activities are described dealing with nonradiological wastewater treatment plant, process waste treatment plant and collection system, liquid low-level waste system, and gaseous waste system. Miscellaneous activities include training, audits/reviews/tours, and environmental restoration support.

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

1997-03-01T23:59:59.000Z

33

EVALUATION OF ULTIMATE DISPOSAL METHOD FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART I. INTERIM LIQUID STORAGE  

SciTech Connect

As the first part of a study to evaluate the economics of the various steps leading to and including the permanent disposal of high-activity liquid and solid radioactive waste, costs of interim liquid storage of acid and alkaline Purex and Thorex wastes were estimated for storage times of 0.5 to 30 years. A 6- ton/day plant was assumed, processing 1500 tons/year of uranium converter fuel at a burnup of 10,000 Mwd/ton and 270 tons/year of thorium converter fuel at a burnup of 20,000 Mwd/ton. Tanks of Savannah River design were assumed, with stainless steel construction for acid wastes and mild steel construction for neutralized wastes. The operating cycle of each tank was assumed to consist of equal filling and emptying periods plus a full (or dead) period. With interim storage time defined as filling time plus full time, tank costs were minimum when full time was 40 to 70% of the interim storage time, using present worth considerations. For waste storage times of 0.5 to 30 years, costs ranged from 2.2 x 10/sup -3/ to 9.5 x 10/sup -3/ mill/kwh/sub e/ for acid wastes and from 1.7 x 10/sup -3/ to 5.1 x 10/sup -3/ mill/kwh/sub e/ for neutralized wastes. (auth)

Bradshaw, R.L.; Perona, J.J.; Roberts, J.T.; Blomeke, J.O.

1961-08-22T23:59:59.000Z

34

RECOVERY OF MERCURY FROM CONTAMINATED LIQUID WASTES  

SciTech Connect

Mercury was widely used in U.S. Department of Energy (DOE) weapons facilities, resulting in a broad range of mercury-contaminated wastes and wastewaters. Some of the mercury contamination has escaped to the local environment, particularly at the Y-12 Plant in Oak Ridge, Tennessee, where approximately 330 metric tons of mercury were discharged to the environment between 1953 and 1963 (TN & Associates, 1998). Effective removal of mercury contamination from water is a complex and difficult problem. In particular, mercury treatment of natural waters is difficult because of the low regulatory standards. For example, the Environmental Protection Agency has established a national ambient water quality standard of 12 parts-per-trillion (ppt), whereas the standard is 1.8 ppt in the Great Lakes Region. In addition, mercury in the environment is typically present in several different forms, but sorption processes are rarely effective with more than one or two of these forms. To meet the low regulatory discharge limits, an effective sorption process must be able to address all forms of mercury present in the water. One approach is to apply different sorbents in series depending on the mercury speciation and the regulatory discharge limits. ADA Technologies, Inc. has developed four new sorbents to address the variety of mercury species present in industrial discharges and natural waters. Three of these sorbents have been field tested on contaminated creek water at the Y-12 Plant. Two of these sorbents have been successfully demonstrated very high removal efficiencies for soluble mercury species, reducing mercury concentrations at the outlet of a pilot-scale system to less than 12 ppt for as long as six months. The other sorbent tested at the Y-12 Plant targeted colloidal mercury not removed by standard sorption or filtration processes. At the Y-12 Plant, colloidal mercury appears to be associated with iron, so a sorbent that removes mercury-iron complexes in the presence of a magnetic field was evaluated. Field results indicated good removal of this mercury fraction from the Y-12 waters. In addition, this sorbent is easily regenerated by simply removing the magnetic field and flushing the columns with water. The fourth sorbent is still undergoing laboratory development, but results to date indicate exceptionally high mercury sorption capacity. The sorbent is capable of removing all forms of mercury typically present in natural and industrial waters, including Hg{sup 2+}, elemental mercury, methyl mercury, and colloidal mercury. The process possesses very fast kinetics, which allows for higher flow rates and smaller treatment units. These sorbent technologies, used in tandem or individually depending on the treatment needs, can provide DOE sites with a cost-effective method for reducing mercury concentrations to very low levels mandated by the regulatory community. In addition, the technologies do not generate significant amounts of secondary wastes for disposal. Furthermore, the need for improved water treatment technologies is not unique to the DOE. The new, stringent requirements on mercury concentrations impact other government agencies as well as the private sector. Some of the private-sector industries needing improved methods for removing mercury from water include mining, chloralkali production, chemical processing, and medical waste treatment. The next logical step is to deploy one or more of these sorbents at a contaminated DOE site or at a commercial facility needing improved mercury treatment technologies. A full-scale deployment is planned in fiscal year 2000.

Robin M. Stewart

1999-09-29T23:59:59.000Z

35

Liquid Waste Processing Facilities (LWPF) Reliability and Availability and Maintainability (RAM) Analysis  

SciTech Connect

A reliability, availability, and maintainability (RAM) analysis was prepared for the liquid effluents support being provided to the River Protection Project Waste Treatment Plant (WTP). The availability of liquid effluents services to the WTP was determined. Recommendations are provided on improvements and upgrades to increase the availability of the Liquid Waste Processing Facilities treatment and disposal systems.

LOWE, S.S.

2001-02-20T23:59:59.000Z

36

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect

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

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

1989-01-01T23:59:59.000Z

37

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

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

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

38

EA-1115: Liquid Waste Treatment at the Nevada Test Site, Nye County, Nevada  

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

This EA evaluates the environmental impacts of the proposal to treat low-level radioactive liquid and low-level mixed liquid and semi-solid wastes generated at the U.S. Department of Energy Nevada...

39

Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim* and Nina MahootcheianAsl  

E-Print Network (OSTI)

Waste-Lithium-Liquid (WLL) Flow Battery for Stationary Energy Storage Applications Youngsik Kim in a Waste-Lithium-Liquid (WLL) flow battery that can be used in a stationary energy storage application. Li

Zhou, Yaoqi

40

Review of Potential Candidate Stabilization Technologies for Liquid and Solid Secondary Waste Streams  

SciTech Connect

Pacific Northwest National Laboratory has initiated a waste form testing program to support the long-term durability evaluation of a waste form for secondary wastes generated from the treatment and immobilization of Hanford radioactive tank wastes. The purpose of the work discussed in this report is to identify candidate stabilization technologies and getters that have the potential to successfully treat the secondary waste stream liquid effluent, mainly from off-gas scrubbers and spent solids, produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Down-selection to the most promising stabilization processes/waste forms is needed to support the design of a solidification treatment unit (STU) to be added to the Effluent Treatment Facility (ETF). To support key decision processes, an initial screening of the secondary liquid waste forms must be completed by February 2010.

Pierce, Eric M.; Mattigod, Shas V.; Westsik, Joseph H.; Serne, R. Jeffrey; Icenhower, Jonathan P.; Scheele, Randall D.; Um, Wooyong; Qafoku, Nikolla

2010-01-30T23:59:59.000Z

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

Recovery of valuable materials from waste liquid crystal display panel  

Science Conference Proceedings (OSTI)

Associated with the rapid development of the information and electronic industry, liquid crystal displays (LCDs) have been increasingly sold as displays. However, during the discarding at their end-of-life stage, significant environmental hazards, impacts on health and a loss of resources may occur, if the scraps are not managed in an appropriate way. In order to improve the efficiency of the recovery of valuable materials from waste LCDs panel in an environmentally sound manner, this study presents a combined recycling technology process on the basis of manual dismantling and chemical treatment of LCDs. Three key processes of this technology have been studied, including the separation of LCD polarizing film by thermal shock method the removal of liquid crystals between the glass substrates by the ultrasonic cleaning, and the recovery of indium metal from glass by dissolution. The results show that valuable materials (e.g. indium) and harmful substances (e.g. liquid crystals) could be efficiently recovered or separated through above-mentioned combined technology. The optimal conditions are: (1) the peak temperature of thermal shock to separate polarizing film, ranges from 230 to 240 deg. C, where pyrolysis could be avoided; (2) the ultrasonic-assisted cleaning was most efficient at a frequency of 40 KHz (P = 40 W) and the exposure of the substrate to industrial detergents for 10 min; and (3) indium separation from glass in a mix of concentrated hydrochloric acid at 38% and nitric acid at 69% (HCl:HNO{sub 3}:H{sub 2}O = 45:5:50, volume ratio). The indium separation process was conducted with an exposure time of 30 min at a constant temperature of 60 deg. C.

Li Jinhui [Department of Environmental Science and Engineering, Tsinghua University (China); Sino-Italia Environmental Energy Building, Room 804, Haidian District, Beijing 100084 (China)], E-mail: jinhui@tsinghua.edu.cn; Gao Song; Duan Huabo; Liu Lili [Department of Environmental Science and Engineering, Tsinghua University (China)

2009-07-15T23:59:59.000Z

42

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

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

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

43

ICPP radioactive liquid and calcine waste technologies evaluation final report and recommendation  

SciTech Connect

Using a formalized Systems Engineering approach, the Latched Idaho Technologies Company developed and evaluated numerous alternatives for treating, immobilizing, and disposing of radioactive liquid and calcine wastes at the Idaho Chemical Processing Plant. Based on technical analysis data as of March, 1995, it is recommended that the Department of Energy consider a phased processing approach -- utilizing Radionuclide Partitioning for radioactive liquid and calcine waste treatment, FUETAP Grout for low-activity waste immobilization, and Glass (Vitrification) for high-activity waste immobilization -- as the preferred treatment and immobilization alternative.

1995-04-01T23:59:59.000Z

44

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

Science Conference Proceedings (OSTI)

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

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

45

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

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

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

46

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

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

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

47

Liquid low-level waste generation projections for ORNL in 1993  

SciTech Connect

Liquid low-level waste (LLLW) is generated by various programs and projects throughout Oak Ridge National Laboratory (ORNL). These wastes are collected in underground collection tanks, bottles, and trucks; they are then neutralized with sodium hydroxide and treated for volume reduction at the ORNL evaporator facility. This report presents historical and projected data concerning the volume and characterization of LLLW, prior to and after evaporation. Storage space for projected waste generation is also discussed.

DePaoli, S.M.

1994-04-01T23:59:59.000Z

48

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

SciTech Connect

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

Biggs, J.

1995-12-31T23:59:59.000Z

49

Oak Ridge National Lebroatory Liquid&Gaseous Waste Treatment System Strategic Plan  

SciTech Connect

Excellence in Laboratory operations is one of the three key goals of the Oak Ridge National Laboratory (ORNL) Agenda. That goal will be met through comprehensive upgrades of facilities and operational approaches over the next few years. Many of ORNL's physical facilities, including the liquid and gaseous waste collection and treatment systems, are quite old, and are reaching the end of their safe operating life. The condition of research facilities and supporting infrastructure, including the waste handling facilities, is a key environmental, safety and health (ES&H) concern. The existing infrastructure will add considerably to the overhead costs of research due to increased maintenance and operating costs as these facilities continue to age. The Liquid Gaseous Waste Treatment System (LGWTS) Reengineering Project is a UT-Battelle, LLC (UT-B) Operations Improvement Program (OIP) project that was undertaken to develop a plan for upgrading the ORNL liquid and gaseous waste systems to support ORNL's research mission.

Van Hoesen, S.D.

2003-09-09T23:59:59.000Z

50

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

51

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

52

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

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

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

53

Recovery of Tritium from Pharmaceutical Mixed Waste Liquids  

Science Conference Proceedings (OSTI)

Decontamination and Waste / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

W. T. Shmayda; R. D. Gallagher

54

Liquid and Gaseous Waste Operations Project Annual Operating Report CY 1999  

SciTech Connect

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

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

2000-03-01T23:59:59.000Z

55

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

SciTech Connect

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

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

2003-10-01T23:59:59.000Z

56

Isolation of Metals from Liquid Wastes: Reactive in Turbulent Thermal Reactors  

SciTech Connect

A Generic Technology for treatment of DOE Metal-Bearing Liquid Waste The DOE metal-bearing liquid waste inventory is large and diverse, both with respect to the metals (heavy metals, transuranics, radionuclides) themselves, and the nature of the other species (annions, organics, etc.) present. Separation and concentration of metals is of interest from the standpoint of reducing the volume of waste that will require special treatment or isolation, as well as, potentially, from the standpoint of returning some materials to commerce by recycling. The variety of metal-bearing liquid waste in the DOE complex is so great that it is unlikely that any one process (or class of processes) will be suitable for all material. However, processes capable of dealing with a wide variety of wastes will have major advantages in terms of process development, capital, and operating costs, as well as in environmental and safety permitting. Moreover, to the extent that a process operates well with a variety of metal-bearing liquid feedwastes, its performance is likely to be relatively robust with respect to the inevitable composition variations in each waste feed. One such class of processes involves high-temperature treatment of atomized liquid waste to promote reactive capture of volatile metallic species on collectible particulate substrates injected downstream of a flame zone. Compared to low-temperature processes that remove metals from the original liquid phase by extraction, precipitation, ion exchange, etc., some of the attractive features of high-temperature reactive scavenging are: The organic constituents of some metal-bearing liquid wastes (in particular, some low-level mixed wastes) must be treated thermally in order to meet the requirements of the Resource Conservation and Recovery Act (RCRA) and Toxic Substances Control Act (TSCA), and the laws of various states. No species need be added to an already complex liquid system. This is especially important in light of the fact that DOE has already experienced problems with organic complexants added to precipitate radionuclides. For example, the Defense Nuclear Facilities Safety Board has expressed, in a formal Recommendation to the Secretary of Energy, its concern about the evolution of benzene vapor in concentrations greater then the lower flammability limit from tanks to which sodium tetraphenylborate has been added to precipitate 137Cs in the ''In-Tank Precipitation'' (ITP) process at the Savannah River Site. Other species added to the waste in the ITP process are sodium titanate (to adsorb 90Sr and Pu), and oxalic acid. Avoiding addition of organics to radioactive waste has the additional advantage that is likely to significantly reduce the rate of radiolytic and radiolytically-induced hydrogen generation (c.f. Meisel et al., [1993]), in which it is shown that removal of organics reduces the rate of hydrogen generation in simulated waste from Hanford tank 241-SY-101 by over 70%. Organic species already present are destroyed with very high efficiency. This attribute is especially attractive with respect to high-level tank waste at the Hanford Site, in which large amounts of citrate, glyoxylate, EDTA (ethylenediaminetetraacetic acid), and HEDTA [N-(2- hydroxyethyl)-ethylenediaminetriacetic acid] were added to precipitate radionuclides. These organic species are important in the thermal and radiolytic generation of methane, hydrogen, and nitrous oxide, flammable mixtures of which are episodically vented from 25 tanks on Hanford's Flammable Gas Watch List [Hopkins, 1994]. The same basic approach can be used to treat a broad range of liquid wastes, in each case concentrating the metals (regardless of liquid-phase oxidation state or association with chelators or absorbents) using a collectible sorbent, and destroying any organic species present. In common with the Army's approach (see section 2.2) to the thermal destruction of a 10 range of chemical warfare agents (GB, VX, and two blister agents), this may drastically simplify process and plant design and

Wendt, Jost O.L.

2001-09-30T23:59:59.000Z

57

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

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

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

58

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

SciTech Connect

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

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

1996-05-01T23:59:59.000Z

59

Novel Solvent for the Simultaneous recovery of Radioactive Nuclides from Liquid Radioactive Wastes  

DOE Patents (OSTI)

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

Romanovskiy, Valeriy Nicholiavich; Smirnov, Lgor V.; Babain, Vasiliy A.; Todd, Terry A.; Brewer, Ken N.

1999-10-07T23:59:59.000Z

60

Solvent extraction in the treatment of acidic high-level liquid waste : where do we stand?  

SciTech Connect

During the last 15 years, a number of solvent extraction/recovery processes have been developed for the removal of the transuranic elements, {sup 90}Sr and {sup 137}Cs from acidic high-level liquid waste. These processes are based on the use of a variety of both acidic and neutral extractants. This chapter will present an overview and analysis of the various extractants and flowsheets developed to treat acidic high-level liquid waste streams. The advantages and disadvantages of each extractant along with comparisons of the individual systems are discussed.

Horwitz, E. P.; Schulz, W. W.

1998-06-18T23:59:59.000Z

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

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

DOE Green Energy (OSTI)

This report investigated the potential of using municipal solid waste (MSW) to make synthesis gas (syngas) suitable for production of liquid fuels. Issues examined include: • MSW physical and chemical properties affecting its suitability as a gasifier feedstock and for liquid fuels synthesis • expected process scale required for favorable economics • the availability of MSW in quantities sufficient to meet process scale requirements • the state-of-the-art of MSW gasification technology.

Valkenburg, Corinne; Walton, Christie W.; Thompson, Becky L.; Gerber, Mark A.; Jones, Susanne B.; Stevens, Don J.

2008-12-01T23:59:59.000Z

62

Use of Chemical Pretreatment to Enhance Liquid Waste of Processing  

Science Conference Proceedings (OSTI)

This report details unique chemical pretreatment and processing techniques presently used by utilities in their nuclear plant liquid radwaste treatment programs. It presents specific utility experience from a number of plants employing these processing alternatives.

1999-04-23T23:59:59.000Z

63

Update of the management strategy for Oak Ridge National Laboratory Liquid Low-Level Waste  

Science Conference Proceedings (OSTI)

The strategy for management of the Oak Ridge National Laboratory`s (ORNL) radioactively contaminated liquid waste was reviewed in 1991. The latest information available through the end of 1990 on waste characterization, regulations, US Department of Energy (DOE) budget guidance, and research and development programs was evaluated to determine how the strategy should be revised. Few changes are needed to update the strategy to reflect new waste characterization, research, and regulatory information. However, recent budget guidance from DOE indicates that minimum funding will not be sufficient to accomplish original objectives to upgrade the liquid low-level waste (LLLW) system to comply with the Federal Facilities Agreement, provide long-term LLLW treatment capability, and minimize environmental, safety, and health risks. Options are presented that might allow the ORNL LLLW system to continue operations temporarily, but they would significantly reduce its capabilities to handle emergency situations, provide treatment for new waste streams, and accommodate waste from the Environmental Restoration Program and from decontamination and decommissioning of surplus facilities. These options are also likely to increase worker radiation exposure, risk of environmental insult, and generation of solid waste for on-site and off-site disposal/storage beyond existing facility capacities. The strategy will be fully developed after receipt of additional guidance. The proposed budget limitations are too severe to allow ORNL to meet regulatory requirements or continue operations long term.

Robinson, S.M.; Abraham, T.J.; DePaoli, S.M.; Walker, A.B.

1995-04-01T23:59:59.000Z

64

Metal decontamination for waste minimization using liquid metal refining technology  

Science Conference Proceedings (OSTI)

The current Department of Energy Mixed Waste Treatment Project flowsheet indicates that no conventional technology, other than surface decontamination, exists for metal processing. Current Department of Energy guidelines require retrievable storage of all metallic wastes containing transuranic elements above a certain concentration. This project is in support of the National Mixed Low Level Waste Treatment Program. Because of the high cost of disposal, it is important to develop an effective decontamination and volume reduction method for low-level contaminated metals. It is important to be able to decontaminate complex shapes where surfaces are hidden or inaccessible to surface decontamination processes and destruction of organic contamination. These goals can be achieved by adapting commercial metal refining processes to handle radioactive and organic contaminated metal. The radioactive components are concentrated in the slag, which is subsequently vitrified; hazardous organics are destroyed by the intense heat of the bath. The metal, after having been melted and purified, could be recycled for use within the DOE complex. In this project, we evaluated current state-of-the-art technologies for metal refining, with special reference to the removal of radioactive contaminants and the destruction of hazardous organics. This evaluation was based on literature reports, industrial experience, plant visits, thermodynamic calculations, and engineering aspects of the various processes. The key issues addressed included radioactive partitioning between the metal and slag phases, minimization of secondary wastes, operability of the process subject to widely varying feed chemistry, and the ability to seal the candidate process to prevent the release of hazardous species.

Joyce, E.L. Jr.; Lally, B. [Los Alamos National Lab., NM (United States); Ozturk, B.; Fruehan, R.J. [Carnegie-Mellon Univ., Pittsburgh, PA (United States). Dept. of Materials Science and Engineering

1993-09-01T23:59:59.000Z

65

Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility  

Science Conference Proceedings (OSTI)

In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

Alexander, D.J.; Johnson, V.G.

1993-09-01T23:59:59.000Z

66

Audit of the radioactive liquid waste treatment facility operations at the Los Alamos National Laboratory  

SciTech Connect

Los Alamos National Laboratory (Los Alamos) generates radioactive and liquid wastes that must be treated before being discharged to the environment. Presently, the liquid wastes are treated in the Radioactive Liquid Waste Treatment Facility (Treatment Facility), which is over 30 years old and in need of repair or replacement. However, there are various ways to satisfy the treatment need. The objective of the audit was to determine whether Los Alamos cost effectively managed its Treatment Facility operations. The audit determined that Los Alamos` treatment costs were significantly higher when compared to similar costs incurred by the private sector. This situation occurred because Los Alamos did not perform a complete analysis of privatization or prepare a {open_quotes}make-or-buy{close_quotes} plan for its treatment operations, although a {open_quotes}make-or-buy{close_quotes} plan requirement was incorporated into the contract in 1996. As a result, Los Alamos may be spending $2.15 million more than necessary each year and could needlessly spend $10.75 million over the next five years to treat its radioactive liquid waste. In addition, Los Alamos has proposed to spend $13 million for a new treatment facility that may not be needed if privatization proves to be a cost effective alternative. We recommended that the Manager, Albuquerque Operations Office (Albuquerque), (1) require Los Alamos to prepare a {open_quotes}make-or-buy{close_quotes} plan for its radioactive liquid waste treatment operations, (2) review the plan for approval, and (3) direct Los Alamos to select the most cost effective method of operations while also considering other factors such as mission support, reliability, and long-term program needs. Albuquerque concurred with the recommendations.

1997-11-19T23:59:59.000Z

67

Ionic Liquids for Utilization of Waste Heat from Distributed Power Generation Systems  

Science Conference Proceedings (OSTI)

The objective of this research project was the development of ionic liquids to capture and utilize waste heat from distributed power generation systems. Ionic Liquids (ILs) are organic salts that are liquid at room temperature and they have the potential to make fundamental and far-reaching changes in the way we use energy. In particular, the focus of this project was fundamental research on the potential use of IL/CO2 mixtures in absorption-refrigeration systems. Such systems can provide cooling by utilizing waste heat from various sources, including distributed power generation. The basic objectives of the research were to design and synthesize ILs appropriate for the task, to measure and model thermophysical properties and phase behavior of ILs and IL/CO2 mixtures, and to model the performance of IL/CO2 absorption-refrigeration systems.

Joan F. Brennecke; Mihir Sen; Edward J. Maginn; Samuel Paolucci; Mark A. Stadtherr; Peter T. Disser; Mike Zdyb

2009-01-11T23:59:59.000Z

68

Ultrafiltration treatment for liquid laundry wastes from nuclear power stations  

SciTech Connect

The authors conduct a comprehensive analysis of the waste constituents--radioactive and organic--of the laundry water resulting from the on-site laundering and decontamination of clothing worn in nuclear power plants. The primary isotope contaminants consist of niobium and zirconium 95, manganese 54, cobalt 60, iron 59, and cesium 134 and 137. A variety of filter and adsorbent materials used in an ultrafiltration process are comparatively tested for their effectiveness in removing not only these isotopes but also the organic contaminants in the process of recycling the water. Those materials consist of copper hexacyanoferrate, polyacrylophosphonic acid, and several metal-polymer complexes.

Kichik, V.A.; Maslova, M.N.; Svittsov, A.A.; Kuleshov, N.F.

1988-03-01T23:59:59.000Z

69

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

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

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

70

Oak Ridge National Lebroatory Liquid&Gaseous Waste Treatment System Strategic Plan  

SciTech Connect

Excellence in Laboratory operations is one of the three key goals of the Oak Ridge National Laboratory (ORNL) Agenda. That goal will be met through comprehensive upgrades of facilities and operational approaches over the next few years. Many of ORNL's physical facilities, including the liquid and gaseous waste collection and treatment systems, are quite old, and are reaching the end of their safe operating life. The condition of research facilities and supporting infrastructure, including the waste handling facilities, is a key environmental, safety and health (ES&H) concern. The existing infrastructure will add considerably to the overhead costs of research due to increased maintenance and operating costs as these facilities continue to age. The Liquid Gaseous Waste Treatment System (LGWTS) Reengineering Project is a UT-Battelle, LLC (UT-B) Operations Improvement Program (OIP) project that was undertaken to develop a plan for upgrading the ORNL liquid and gaseous waste systems to support ORNL's research mission.

Van Hoesen, S.D.

2003-09-09T23:59:59.000Z

71

Process for Removing Radioactive Wastes from Liquid Streams  

SciTech Connect

The process is under development at Mound Laboratory to remove radioactive waste (principally plutonium-238) from process water prior to discharge of the water to the Miami river. The contaminated water, as normally received, is at a pH between 6 and 90. Under these conditions, plutonium in all its oxidation states is hydrolyzed; however, the level of the radioactive solids varies from about 50ppm down to about 50 ppb and the plutonium remains in a colloidal or subcolloidal condition. The permissible concentration for discharge to the river is about 50 parts per trillion. Pilot plant test show that 95-99% of the radioactive material is removed by adsorption on diatomaceous earth. The remainder is removed by passage through a bed of either dibasic or tribasic calcium phosphate. Ground phosphate rock is equally effective in removing the radioactive material if the flow rate is controlled to permit sufficient contact time. Parameters for optimizing the process are now under study. Future plans include application of the process to wastes from reactor fuels reprocessing.

Kirby, H. W.; Blane, D. E.; Smolin, R. I.

1972-10-01T23:59:59.000Z

72

Techniques and Facilities for Handling and Packaging Tritiated Liquid Wastes for Burial  

SciTech Connect

Methods and facilities have been developed for the collection, storage, measurement, assay, solidification, and packaging of tritiated liquid wastes (concentrations up to 5 Ci/ml) for disposal by land burial. Tritium losses to the environment from these operations are less than 1 ppm. All operations are performed in an inert gas-purged glovebox system vented to an effluent removal system which permits nearly complete removal of tritium from the exhaust gases prior to their dischardge to the environment. Waste oil and water from tritium processing areas are vacuum-transferred to glovebox storage tanks through double-walled lines. Accommodations are also available for emptying portable liquid waste containers and for removing tritiated water from molecular sieve beds with heat and vacuum. The tritium concentration of the collected liquids is measured by an in-line calorimeter. A low-volume metering pump is used to transfer liquids from holding tanks to heavy walled polyethylene drums filled with an absorbent or cement for solidification. Final packaging of the sealed polyethylene drums is in either an asphalt-filled combination 30- and 55- gallon metal drum package or a 30-gallon welded stainless steel container.

Rhinehammer, T. B.; Mershad, E. A.

1974-06-01T23:59:59.000Z

73

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

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

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

74

Drop Dynamics and Speciation in Isolation of Metals from Liquid Wastes by Reactive Scavenging  

SciTech Connect

Computational and experimental studies of the motion and dynamics of liquid drops in gas flows were conducted with relevance to reactive scavenging of metals from atomized liquid waste. Navier-Stoke's computations of deformable drops revealed a range of conditions from which prolate drops are expected, and showed how frajectiones of deformable drops undergoing deceleration can be computed. Experimental work focused on development of emission fluorescence, and scattering diagnostics. The instrument developed was used to image drop shapes, soot, and nonaxisymmetric departures from steady flow in a 22kw combustor

Arne J. Pearlstein; Alexander Scheeline

2002-08-30T23:59:59.000Z

75

Current Practices: Solid Waste Management from Zero Liquid Discharge (ZLD) Wastewater Treatment  

Science Conference Proceedings (OSTI)

A study was conducted to identify current practices used by power plants to manage their solid waste residuals from zero liquid discharge (ZLD) operations treating flue gas desulfurization (FGD) wastewater. Because there are such few FGD ZLD systems in operation not only in the United States but also worldwide, the study scope was expanded to include non-FGD ZLD operations, as well. Only two of the seven facilities interviewed in this study operate ZLDs on FGD water; therefore, much of the current ...

2012-12-31T23:59:59.000Z

76

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

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

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

77

Digestion of frozen/thawed food waste in the hybrid anaerobic solid-liquid system  

SciTech Connect

The hybrid anaerobic solid-liquid (HASL) system, which is a modified two-phase anaerobic digester, is to be used in an industrial scale operation to minimize disposal of food waste at incineration plants in Singapore. The aim of the present research was to evaluate freezing/thawing of food waste as a pre-treatment for its anaerobic digestion in the HASL system. The hydrolytic and fermentation processes in the acidogenic reactor were enhanced when food waste was frozen for 24 h at -20 deg. C and then thawed for 12 h at 25 deg. C (experiment) in comparison with fresh food waste (control). The highest dissolved COD concentrations in the leachate from the acidogenic reactors were 16.9 g/l on day 3 in the control and 18.9 g/l on day 1 in the experiment. The highest VFA concentrations in the leachate from the acidogenic reactors were 11.7 g/l on day 3 in the control and 17.0 g/l on day 1 in the experiment. The same volume of methane was produced during 12 days in the control and 7 days in the experiment. It gave the opportunity to diminish operational time of batch process by 42%. The effect of freezing/thawing of food waste as pre-treatment for its anaerobic digestion in the HASL system was comparable with that of thermal pre-treatment of food waste at 150 deg. C for 1 h. However, estimation of energy required either to heat the suspended food waste to 150 deg. C or to freeze the same quantity of food waste to -20 deg. C showed that freezing pre-treatment consumes about 3 times less energy than thermal pre-treatment.

Stabnikova, O. [School of Civil and Environmental Engineering, Nanyang Technological University, 50 Nanyang Avenue, Singapore 639798 (Singapore)], E-mail: costab@ntu.edu.sg; Liu, X.Y.; Wang, J.Y. [School of Civil and Environmental Engineering, Nanyang Technological University, 50 Nanyang Avenue, Singapore 639798 (Singapore)

2008-07-01T23:59:59.000Z

78

EVALUATION AND SELECTION OF 99TC GETTERS FOR SEQUESTRATION OF LIQUID SECONDARY WASTE RESULTING FROM VITRIFICATION OF RADIOACTIVE WASTE FROM HANFORD  

Science Conference Proceedings (OSTI)

Getters are most commonly inorganic materials that selectively adsorb radionuclide and metallic contaminants. Typically, these materials have been deployed in two different modes to immobilize and retard contaminant release from monolithic waste forms. One mode is to first use getters to selectively scavenge the radionuclide of interest from a liquid waste stream, and then incorporate the radionuclide-loaded getters in cementitious or other monolithic waste forms. The other mode consists of mixing getters and liquid waste together during formulation of monolithic waste forms. Desirable characteristics for a getter material include, (1) specific adsorption of radionuclide of interest and very high selectivity toward radionuclides of concern in concentrations that would be several orders of magnitude less than the concentrations of competing anions and cations, (2) adsorption capacity that should be sufficient for the mass and volume of the material that will be deployed to be within practicable limits, (3) long-term adsorption and retention of radionuclide, (4) sufficient physical and chemical stability that its radionuclide retention performance will not degrade significantly during the designed life span of the waste form, (5) chemical stability under the range of Eh, pH, and solution conditions that exist in the waste form environment, and (6) should not adversely affect chemical and physical integrity of waste forms. We conducted a literature review to identify getters that are suitable for effectively sequestering 99Tc in monolithic waste forms that are being evaluated for stabilizing secondary liquid waste streams resulting from treatment and vitrification of radioactive tank wastes at Hanford. As a result of this review, we identified a set of getters that warrant further evaluation for this specific application.

Mattigod, Shas V.; Westsik, Joseph H.

2011-03-31T23:59:59.000Z

79

Selection of liquid-level monitoring method for the Oak Ridge National Laboratory inactive liquid low-level waste tanks, remedial investigation/feasibility study  

SciTech Connect

Several of the inactive liquid low-level waste (LLLW) tanks at Oak Ridge National Laboratory contain residual wastes in liquid or solid (sludge) form or both. A plan of action has been developed to ensure that potential environmental impacts from the waste remaining in the inactive LLLW tank systems are minimized. This document describes the evaluation and selection of a methodology for monitoring the level of the liquid in inactive LLLW tanks. Criteria are established for comparison of existing level monitoring and leak testing methods; a preferred method is selected and a decision methodology for monitoring the level of the liquid in the tanks is presented for implementation. The methodology selected can be used to continuously monitor the tanks pending disposition of the wastes for treatment and disposal. Tanks that are empty, are scheduled to be emptied in the near future, or have liquid contents that are very low risk to the environment were not considered to be candidates for installing level monitoring. Tanks requiring new monitoring equipment were provided with conductivity probes; tanks with existing level monitoring instrumentation were not modified. The resulting data will be analyzed to determine inactive LLLW tank liquid level trends as a function of time.

Not Available

1994-11-01T23:59:59.000Z

80

Liquid and Gaseous Waste Operations Department annual operating report, CY 1992  

SciTech Connect

A total of 6.05 x 10{sup 7} gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10{sup 6} gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system`s discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system`s discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10{sup 3} gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10{sup 4} gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10{sup 3} ft{sup 3}) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10{sup 2} ft{sup 3} of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10{sup 8} gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10{sup 7} gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10{sup 3} ft{sup 3}) of solid sludge generated by the precipitation/clarification process were removed from the filter press room.

Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

1993-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes bfg" from the National Library of EnergyBeta (NLEBeta).
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81

Environmental assessment for liquid waste treatment at the Nevada Test Site, Nye County, Nevada  

Science Conference Proceedings (OSTI)

This environmental assessment (EA) examines the potential impacts to the environment from treatment of low-level radioactive liquid and low-level mixed liquid and semi-solid wastes generated at the Nevada Test Site (NTS). The potential impacts of the proposed action and alternative actions are discussed herein in accordance with the National Environmental Policy Act (NEPA) of 1969, as amended in Title 42 U.S.C. (4321), and the US Department of Energy (DOE) policies and procedures set forth in Title 10 Code of Federal Regulations (CFR) Part 1021 and DOE Order 451.1, ``NEPA Compliance Program.`` The potential environmental impacts of the proposed action, construction and operation of a centralized liquid waste treatment facility, were addressed in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada. However, DOE is reevaluating the need for a centralized facility and is considering other alternative treatment options. This EA retains a centralized treatment facility as the proposed action but also considers other feasible alternatives.

NONE

1997-01-01T23:59:59.000Z

82

Environmental sampling program for a solar evaporation pond for liquid radioactive wastes  

Science Conference Proceedings (OSTI)

Los Alamos Scientific Laboratory (LASL) is evaluating solar evaporation as a method for disposal of liquid radioactive wastes. This report describes a sampling program designed to monitor possible escape of radioactivity to the environment from a solar evaporation pond prototype constructed at LASL. Background radioactivity levels at the pond site were determined from soil and vegetation analyses before construction. When the pond is operative, the sampling program will qualitatively and quantitatively detect the transport of radioactivity to the soil, air, and vegetation in the vicinity. Possible correlation of meteorological data with sampling results is being investigated and measures to control export of radioactivity by biological vectors are being assessed.

Romero, R.; Gunderson, T.C.; Talley, A.D.

1980-04-01T23:59:59.000Z

83

Process for converting sodium nitrate-containing, caustic liquid radioactive wastes to solid insoluble products  

DOE Patents (OSTI)

A method for converting sodium nitrate-containing, caustic, radioactive wastes to a solid, relatively insoluble, thermally stable form is provided and comprises the steps of reacting powdered aluminum silicate clay, e.g., kaolin, bentonite, dickite, halloysite, pyrophyllite, etc., with the sodium nitrate-containing radioactive wastes which have a caustic concentration of about 3 to 7 M at a temperature of 30.degree. C to 100.degree. C to thereby entrap the dissolved radioactive salts in the aluminosilicate matrix. In one embodiment the sodium nitrate-containing, caustic, radioactive liquid waste, such as neutralized Purex-type waste, or salts or oxide produced by evaporation or calcination of these liquid wastes (e.g., anhydrous salt cake) is converted at a temperature within the range of 30.degree. C to 100.degree. C to the solid mineral form-cancrinite having an approximate chemical formula 2(NaAlSiO.sub.4) .sup.. xSalt.sup.. y H.sub.2 O with x = 0.52 and y = 0.68 when the entrapped salt is NaNO.sub.3. In another embodiment the sodium nitrate-containing, caustic, radioactive liquid is reacted with the powdered aluminum silicate clay at a temperature within the range of 30.degree. C to 100.degree. C, the resulting reaction product is air dried eitheras loose powder or molded shapes (e.g., bricks) and then fired at a temperature of at least 600.degree. C to form the solid mineral form-nepheline which has the approximate chemical formula of NaAlSiO.sub.4. The leach rate of the entrapped radioactive salts with distilled water is reduced essentially to that of the aluminosilicate lattice which is very low, e.g., in the range of 10.sup.-.sup.2 to 10.sup.-.sup.4 g/cm.sup.2 -- day for cancrinite and 10.sup.-.sup.3 to 10.sup.-.sup.5 g/cm.sup.2 -- day for nepheline.

Barney, Gary S. (Richland, WA); Brownell, Lloyd E. (Richland, WA)

1977-01-01T23:59:59.000Z

84

New methods for determination of interstitial liquid levels in Hanford waste tanks  

Science Conference Proceedings (OSTI)

The key to the leak detection program for many tanks at Hanford is the method used to evaluate the apparent interstitial liquid interface (ILL) within the pore space of the solid waste medium (either crystalline or sludge). Three new approaches were introduced in the summer of 1993 (count rate, derivative, and sigmoid), all of which significantly improved the accuracy and repeatability of interstitial liquid level values from neutron survey data. This paper summarizes the three new methods and details a case study in which, as a direct result of this improved analysis, a tank that had been declared an ``assumed leaker`` was reclassified as ``sound`` for the first time in Hanford`s 50 year history.

Barnes, D.A.; Raymond, R.E. [Westinghouse Hanford Co., Richland, WA (United States); Whitney, P.D. [Pacific Northwest Lab., Richland, WA (United States)

1995-01-01T23:59:59.000Z

85

Detection of free liquid in drums of radioactive waste. [Patent application  

DOE Patents (OSTI)

A nondestructive thermal imaging method for detecting the presence of a liquid such as water within a sealed container is described. The process includes application of a low amplitude heat pulse to an exterior surface area of the container, terminating the heat input and quickly mapping the resulting surface temperatures. The various mapped temperature values can be compared with those known to be normal for the container material and substances in contact. The mapped temperature values show up in different shades of light or darkness that denote different physical substances. The different substances can be determined by direct observation or by comparison with known standards. The method is particularly applicable to the detection of liquids above solidified radioactive wastes stored in sealed containers.

Not Available

1979-10-16T23:59:59.000Z

86

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

Science Conference Proceedings (OSTI)

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

Not Available

1993-06-01T23:59:59.000Z

87

Double liquid membrane system for the removal of actinides and lanthanides from acidic nuclear wastes  

SciTech Connect

Supported liquid membranes (SLM), consisting of an organic solution of n-octyl-(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) and tributyl-phosphate (TBP) in decalin are able to perform selective separation and concentration of actinide and lanthanide ions from aqueous nitrate feed solutions and synthetic nuclear wastes. In the membrane process a possible strip solution is a mixture of formic acid and hydroxylammonium formate (HAF). The effectiveness of this strip solution is reduced and eventually nullified by the simultaneous transfer through the SLM of nitric acid which accumulates in the strip solution. A possible way to overcome this drawback is to make use of a second SLM consisting of a primary amine which is able to extract only HNO/sub 3/ from the strip solution. In this work the results obtained by experimentally studying the membrane system: synthetic nuclear waste/CMPO-TBP membrane/HCOOH-HAF strip solution/primary amine membrane/NaOH solution, are reported. They show that the use of a second liquid membrane is effective in controlling the HNO/sub 3/ concentration in the strip solution, thus allowing the actinide and lanthanide ions removal from the feed solution to proceed to completion. 15 refs., 10 figs., 1 tab.

Chiarizia, R.; Danesi, P.R.

1985-01-01T23:59:59.000Z

88

Characterization and monitoring of 300 Area Facility liquid waste streams: Status report  

SciTech Connect

This report summarizes the results of characterizing and monitoring the following sources during a portion of this year: liquid waste streams from Buildings 331, 320, and 3720; treated and untreated Columbia River water; and water at the confluence of the waste streams (that is, end-of-pipe). Characterization and monitoring data were evaluated for samples collected between March 22 and June 21, 1994, and subsequently analyzed for hazardous chemicals, radioactivity, and general parameters. Except for bis(2-ethylhexyl)phthalate, concentrations of chemicals detected and parameters measured at end-of-pipe were below the US Environmental Protection Agency existing and proposed drinking water standards. The source of the chemicals, except bis(2-ethylhexyl)phthalate, is not currently known. The bis(2-ethylhexyl)phthalate is probably an artifact of the plastic tubing used in the early stages of the sampling program. This practice was stopped. Concentrations and clearance times for contaminants at end-of-pipe depended strongly on source concentration at the facility release point, waste stream flow rates, dispersion, and the mechanical action of sumps. When present, the action of sumps had the greatest impact on contaminant clearance times. In the absence of sump activity, dispersion and flow rate were the controlling factors.

Manke, K.L. [ed.; Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Ikenberry, A.S.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.

1994-09-01T23:59:59.000Z

89

Development of the SREX process for the treatment of ICPP liquid wastes  

SciTech Connect

The removal of {sup 90}Sr from actual and simulated wastes at the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering and Environmental Laboratory (INEEL) has been demonstrated with the SREX process. This solvent extraction process employs the extractant 4{prime},4{prime}(5{prime}) di-(t-butylcyclohexano)-18-crown-6 in 1-octanol or a mixture of tributyl phosphate and a hydrocarbon diluent called Isopar L{reg_sign}. Process flowsheets have been designed for testing in countercurrent experiments with centrifugal contractors. The flowsheets have been designed using batch contract solvent extraction methods. The extraction of Sr as well as other interfering ions has been studied. The effect of various parameters including nitric acid dependence, extractant concentration dependence, hydronium ion concentration, and interferent concentrations upon the extraction efficiency of the process has been evaluated. The radiolysis of the SREX solvent has also been investigated as a function of absorbed gamma radiation. The extraction efficiency of the solvent has been shown to be only slightly dependent upon absorbed dose in the range 0--1,000 kGy. The decontamination of actual sodium-bearing waste and dissolved calcine solutions has been accomplished in batch contact flowsheets. Decontamination factors as high as 10E3 have been obtained with sequential batch contacts. Flowsheets have been developed to accomplish decontamination of the liquid wastes with respect to {sup 90}Sr as well as the removal of Pb and Hg. Pb may be partitioned from the Sr fraction in a separate stripping procedure using ammonium citrate. This work has led to the formulation of countercurrent flowsheets which have been tested in centrifugal contractors with actual waste and reported in the document INEEL/EXT-97-00832.

Wood, D.J.; Law, J.D.; Garn, T.G.; Tillotson, R.D.; Tullock, P.A.; Todd, T.A.

1997-12-01T23:59:59.000Z

90

Development of the SREX Process for the Treatment of ICPP Liquid Wastes  

SciTech Connect

The removal of Sr-90 from actual and simulated wastes at the Idaho Chemical Processing Plant (ICPP) at the Idaho National Engineering and Environmental Laboratory (INEEL) has been demonstrated with the SREX process. This solvent extraction process employs the extractant 4',4' (5') de-(t-butylcyclohexano)-18-crown-6 in 1-octanol or a mixture of tributyl phosphate and a hydrocarbon diluent called Isopar L. This development work is based upon earlier work performed by Horwitz, et al. at Argonne National Laboratory. Process flowsheets have been designed for testing in countercurrent experiments with centrifugal contactors. The flowsheets have been designed using batch contact solvent extraction methods. The extraction of Sr as well as other interfering ions has been studied. The effect of various parameters including nitric acid dependence, extractant concentration dependence, Hydronium ion concentration, and interferent concentrations upon the extraction efficiency of the process has been evaluated. The radiolysis of the SREX solvent has also been investigated as a function of absorbed gamma radiation. The extraction efficiency of the solvent has been shown to be only slightly dependent upon absorbed dose in the range 0-1000 kGy. The decontamination of actual sodium-bearing waste and dissolved calcine solutions has been accomplished in batch contact flowsheets. Decontamination factors as high as 10E3 have been obtained with sequential batch contacts. Flowsheets have been developed to accomplish decontamination of the liquid wastes with respect to Sr-90, as well as the removal of Pb and Hg. Pb may be partitioned from the Sr fraction in a separate stripping procedure using ammonium citrate. This work has led to the formulation of countercurrent flowsheets which have been tested in centrifugal contactors with actual waste and reported in the document INEEL/EXT-97-00832.

D. J. Wood; Garn, T. G.; J. D. Law; P. A. Tullock; R. D. Tillotson; T. A. Todd

1997-10-01T23:59:59.000Z

91

Application of thermogravimetric analysis to study the thermal degradation of solid and liquid organic wastes  

Science Conference Proceedings (OSTI)

In this work, the thermolysis of composite binary mixtures of refinery or coal-processing waste with waste biomass and D-grade (long-flame) coal was analyzed in order to increase the efficiency of the cothermolysis of chemically different organic wastes mainly because of the synergism of the thermolysis of mixture components and, correspondingly, the selectivity of formation of high-quality by-products (solid, gaseous, or liquid). A new approach to the analysis of thermogravimetric data was proposed and developed as applied to complex binary mixtures of carbon-containing materials. This approach was based on (1) the preliminary separation of the thermal degradation of individual carbon-containing mixture components into individual structural constituents and (2) the monitoring of the conversion of each particular structure fragment as a constituent of the mixtures in the course of the cothermolysis of the mixtures of starting components. Based on the approach developed, data on the main synergism effects in the course of cothermolysis in the binary test systems were obtained: the temperature regions of the appearance of these effects were distinguished, the main conclusions were made with respect to particular structure fragments in complex organic wastes responsible for the interaction of components in composite systems, and the directions (positive or negative) of changes in the yields of solid by-products and the degrees of effects (difference between the yields of cothermolysis by-products in each particular region of the appearance of synergistic effects in the systems) were determined. Additionally, the influence of alkali metal carbonate additives on synergistic effects in the interaction between binary system components under the process conditions of cothermolysis was analyzed.

E.S. Lygina; A.F. Dmitruk; S.B. Lyubchik; V.F. Tret'yakov [Tugan-Baranovsky State University of Economy and Trade, Donetsk (Ukraine)

2009-07-01T23:59:59.000Z

92

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

SciTech Connect

Various forms of general and localized corrosion represent principal threats to the integrity of DOE liquid waste storage tanks. These tanks, which are of a single wall or double wall design, depending upon their age, are fabricated from welded carbon steel and contain a complex waste-form comprised of NaOH and NaNO{sub 3}, along with trace amounts of phosphate, sulfate, carbonate, and chloride. Because waste leakage can have a profound environmental impact, considerable interest exists in predicting the accumulation of corrosion damage, so as to more effectively schedule maintenance and repair. The different tasks that are being carried out under the current program are as follows: (1) Theoretical and experimental assessment of general corrosion of iron/steel in borate buffer solutions by using electrochemical impedance spectroscopy (EIS), ellipsometry and XPS techniques; (2) Development of a damage function analysis (DFA) which would help in predicting the accumulation of damage due to pitting corrosion in an environment prototypical of DOE liquid waste systems; (3) Experimental measurement of crack growth rate, acoustic emission signals and coupling currents for fracture in carbon and low alloy steels as functions of mechanical (stress intensity), chemical (conductivity), electrochemical (corrosion potential, ECP), and microstructural (grain size, precipitate size, etc) variables in a systematic manner, with particular attention being focused on the structure of the noise in the current and its correlation with the acoustic emissions; (4) Development of fracture mechanisms for carbon and low alloy steels that are consistent with the crack growth rate, coupling current data and acoustic emissions; (5) Inserting advanced crack growth rate models for SCC into existing deterministic codes for predicting the evolution of corrosion damage in DOE liquid waste storage tanks; (6) Computer simulation of the anodic and cathodic activity on the surface of the steel samples in order to exactly predict the corrosion mechanisms; (7) Wavelet analysis of EC noise data from steel samples undergoing corrosion in an environment similar to that of the high level waste storage containers, to extract data pertaining to general, pitting and stress corrosion processes, from the overall data. The Point Defect Model (PDM) is directly applied as the theoretical assessment method for describing the passive film formed on iron/steels. The PDM is used to describe general corrosion in the passive region of iron. In addition, previous work suggests that pit formation is due to the coalescence of cation vacancies at the metal/film interface which would make it possible to use the PDM parameters to predict the onset of pitting. This previous work suggests that once the critical vacancy density is reached, the film ruptures to form a pit. Based upon the kinetic parameters derived for the general corrosion case, two parameters relating to the cation vacancy formation and annihilation can be calculated. These two parameters can then be applied to predict the transition from general to pitting corrosion for iron/mild steels. If cation vacancy coalescence is shown to lead to pitting, it can have a profound effect on the direction of future studies involving the onset of pitting corrosion. The work has yielded a number of important findings, including an unequivocal demonstration of the role of chloride ion in passivity breakdown on nickel in terms of cation vacancy generation within the passive film, the first detection and characterization of individual micro fracture events in stress corrosion cracking, and the determination of kinetic parameters for the generation and annihilation of point defects in the passive film on iron. The existence of coupling between the internal crack environment and the external cathodic environment, as predicted by the coupled environment fracture model (CEFM), has also been indisputably established for the AISI 4340/NaOH system. It is evident from the studies that analysis of coupling current noise is a very sensitive tool f

Digby D. Macdonald; Brian M. Marx; Sejin Ahn; Julio de Ruiz; Balaji Soundararaja; Morgan Smith; and Wendy Coulson

2008-01-15T23:59:59.000Z

93

Preliminary analysis of the ORNL Liquid Low-Level Waste system  

Science Conference Proceedings (OSTI)

The objective of this report is to summarize the status of the Liquid Low-Level Waste (LLLW) Systems Analysis project. The focus of this project has been to collect and tabulate data concerning the LLLW system, analyze the current LLLW system operation, and develop the information necessary for the development of long-term treatment options for the LLLW generated at ORNL. The data used in this report were collected through a survey of Oak Ridge National Laboratory (ORNL) literature, various letter reports, and a survey of all current LLLW generators. These data are also being compiled in a user friendly database for ORNL-wide distribution. The database will allow the quick retrieval of all information collected on the ORNL LLLW system and will greatly benefit any LLLW analysis effort. This report summarizes the results for the analyses performed to date on the LLLW system.

Abraham, T.J.; DePaoli, S.M.; Robinson, S.M.; Walker, A.B.

1994-08-01T23:59:59.000Z

94

Understanding Cement Waste Forms  

Science Conference Proceedings (OSTI)

Oct 29, 2009 ... Ongoing nuclear operations, decontamination and decommissioning, salt waste disposal, and closure of liquid waste tanks result in ...

95

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

Office of Legacy Management (LM)

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

96

Characterization and monitoring of 300 Area facility liquid waste streams: 1994 Annual report  

Science Conference Proceedings (OSTI)

This report summarizes the results of characterizing and monitoring the following sources during calendar year 1994: liquid waste streams from Buildings 306, 320, 324, 326, 331, and 3720 in the 300 Area of Hanford Site and managed by the Pacific Northwest Laboratory; treated and untreated Columbia River water (influent); and water at the confluence of the waste streams (that is, end-of-pipe). Data were collected from March to December before the sampling system installation was completed. Data from this initial part of the program are considered tentative. Samples collected were analyzed for chemicals, radioactivity, and general parameters. In general, the concentrations of chemical and radiological constituents and parameters in building wastewaters which were sampled and analyzed during CY 1994 were similar to historical data. Exceptions were the occasional observances of high concentrations of chloride, nitrate, and sodium that are believed to be associated with excursions that were occurring when the samples were collected. Occasional observances of high concentrations of a few solvents also appeared to be associated with infrequent building r eases. During calendar year 1994, nitrate, aluminum, copper, lead, zinc, bis(2-ethylhexyl) phthalate, and gross beta exceeded US Environmental Protection Agency maximum contaminant levels.

Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Julya, J.L.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.; Vogel, H.R.

1995-04-01T23:59:59.000Z

97

Surveillance and maintenance plan for the inactive liquid low-level waste tanks at Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

ORNL has a total of 54 inactive liquid low-level waste (ILLLW) tanks. In the past, these tanks were used to contain radioactive liquid wastes from various research programs, decontamination operations, and reactor operations. The tanks have since been removed from service for various reasons; the majority were retired because of their age, some due to integrity compromises, and others because they did not meet the current standards set by the Federal Facilities Agreement (FFA). Many of the tanks contain residual radioactive liquids and/or sludges. Plans are to remediate all tanks; however, until remediation of each tank, this Surveillance and Maintenance (S&M) Plan will be used to monitor the safety and inventory containment of these tanks.

Not Available

1994-11-01T23:59:59.000Z

98

PLUTONIUM FINISHING PLANT (PFP) 241-Z LIQUID WASTE TREATMENT FACILITY DEACTIVATION AND DEMOLITION  

Science Conference Proceedings (OSTI)

Fluor Hanford, Inc. (FH) is proud to submit the Plutonium Finishing Plant (PFP) 241-Z liquid Waste Treatment Facility Deactivation and Demolition (D&D) Project for consideration by the Project Management Institute as Project of the Year for 2008. The decommissioning of the 241-Z Facility presented numerous challenges, many of which were unique with in the Department of Energy (DOE) Complex. The majority of the project budget and schedule was allocated for cleaning out five below-grade tank vaults. These highly contaminated, confined spaces also presented significant industrial safety hazards that presented some of the most hazardous work environments on the Hanford Site. The 241-Z D&D Project encompassed diverse tasks: cleaning out and stabilizing five below-grade tank vaults (also called cells), manually size-reducing and removing over three tons of process piping from the vaults, permanently isolating service utilities, removing a large contaminated chemical supply tank, stabilizing and removing plutonium-contaminated ventilation ducts, demolishing three structures to grade, and installing an environmental barrier on the demolition site . All of this work was performed safely, on schedule, and under budget. During the deactivation phase of the project between November 2005 and February 2007, workers entered the highly contaminated confined-space tank vaults 428 times. Each entry (or 'dive') involved an average of three workers, thus equaling approximately 1,300 individual confined -space entries. Over the course of the entire deactivation and demolition period, there were no recordable injuries and only one minor reportable skin contamination. The 241-Z D&D Project was decommissioned under the provisions of the 'Hanford Federal Facility Agreement and Consent Order' (the Tri-Party Agreement or TPA), the 'Resource Conservation and Recovery Act of 1976' (RCRA), and the 'Comprehensive Environmental Response, Compensation, and Liability Act of 1980' (CERCLA). The project completed TPA Milestone M-083-032 to 'Complete those activities required by the 241-Z Treatment and Storage Unit's RCRA Closure Plan' four years and seven months ahead of this legally enforceable milestone. In addition, the project completed TPA Milestone M-083-042 to 'Complete transition and dismantlement of the 241-2 Waste Treatment Facility' four years and four months ahead of schedule. The project used an innovative approach in developing the project-specific RCRA closure plan to assure clear integration between the 241-Z RCRA closure activities and ongoing and future CERCLA actions at PFP. This approach provided a regulatory mechanism within the RCRA closure plan to place segments of the closure that were not practical to address at this time into future actions under CERCLA. Lessons learned from th is approach can be applied to other closure projects within the DOE Complex to control scope creep and mitigate risk. A paper on this topic, entitled 'Integration of the 241-Z Building D and D Under CERCLA with RCRA Closure at the PFP', was presented at the 2007 Waste Management Conference in Tucson, Arizona. In addition, techniques developed by the 241-Z D&D Project to control airborne contamination, clean the interior of the waste tanks, don and doff protective equipment, size-reduce plutonium-contaminated process piping, and mitigate thermal stress for the workers can be applied to other cleanup activities. The project-management team developed a strategy utilizing early characterization, targeted cleanup, and close coordination with PFP Criticality Engineering to significantly streamline the waste- handling costs associated with the project . The project schedule was structured to support an early transition to a criticality 'incredible' status for the 241-Z Facility. The cleanup work was sequenced and coordinated with project-specific criticality analysis to allow the fissile material waste being generated to be managed in a bulk fashion, instead of individual waste packages. This approach negated the need for real-time assay of individ

JOHNSTON GA

2008-01-15T23:59:59.000Z

99

HWMA/RCRA Closure Plan for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System (VES-SFE-106)  

Science Conference Proceedings (OSTI)

This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the Radioactive Solid and Liquid Waste Storage Tank System located in the adjacent to the Sludge Tank Control House (CPP-648), Idaho Nuclear Technology and Engineering Center, Idaho National Laboratory, was developed to meet the interim status closure requirements for a tank system. The system to be closed includes a tank and associated ancillary equipment that were determined to have managed hazardous waste. The CPP-648 Radioactive Solid and Liquid Waste Storage Tank System will be "cleaned closed" in accordance with the requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act as implemented by the Idaho Administrative Procedures Act and 40 Code of Federal Regulations 265. This closure plan presents the closure performance standards and methods of acheiving those standards for the CPP-648 Radioactive Solid and Liquid Waste Storage Tank System.

S. K. Evans

2006-08-15T23:59:59.000Z

100

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

DOE Green Energy (OSTI)

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

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

2011-01-12T23:59:59.000Z

Note: This page contains sample records for the topic "liquid wastes bfg" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


101

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

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

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

102

Information; and Other Matters- Amount of Uranium in Liquid Waste Effluents, Treated Domestic Sanitary Wastewater Sampling, and Liquid Effluent Collection and  

E-Print Network (OSTI)

for the AES exemption request related to commencement of construction (Ref. 2). On October 15, 2009, AES submitted the response to the NRC RAIs related to commencement of construction (Ref. 3). Subsequently, the NRC requested additional information regarding the AES response. Enclosure 1.1 provides the AES response to the additional information regarding preconstrucion activities requested by the NRC. Enclosure 2.1 provides the markup pages of the EREF ER. On August 10, 2009, the NRC transmitted to AES RAIs regarding the EREF Environmental Report (ER) (Ref. 4). On September 9, 2009, AES submitted the response to the NRC ER RAIs (Ref. 5). Subsequently, the NRC requested additional information regarding other matters including the amount of uranium in liquid waste effluents, treated domestic sanitary wastewater sampling, and Liquid Effluent Collection and Treatment System evaporator sediment sampling. Enclosure 1.2 provides the AES response regarding the amount of uranium in liquid waste effluent. There are no markup pages to the EREF ER for this response. Enclosure 1.3 provides the AES response regarding treated domestic sanitary wastewater sampling. Enclosure 2.2 provides the markup pages of the EREF ER. Enclosure 1.4 provides the AES

Eagle Rock; Enrichment Facility

2009-01-01T23:59:59.000Z

103

Analysis of Advanced Liquid Waste Minimization Techniques at a PWR: Advanced Media, Pleated Filters, and Ecomomic Evaluation Tools  

Science Conference Proceedings (OSTI)

Utilities may employ a number of options for processing radioactive liquids or improving processing system O&M. This report summarizes low level waste minimization studies for the Diablo Canyon Power Plant. These studies involved the performance of selective ion media, optimization of the chemical volume control system (CVCS) demineralizers, performance assessment of the application of advanced minimum precoat elements for processing condensate demineralizer system rinse water, and evaluation of the econ...

1998-06-30T23:59:59.000Z

104

EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART II. CONVERSION TO SOLID BY POT CALCINATION  

SciTech Connect

The costs of pot calcination of Purex and Thorex wastes were calculated. The wastes were assumed produced by a plant processing 1500 ton/year of U converter fuel at a burnup of 10,000 Mwd/ton and 270 ton/year of Th converter fuel at 20,000 Mwd/ton. Costs were calculated for processing Purex waste in acidic and reacidified forms and for processing Thorex wastes in acidic and reacidified forms and with constituents added for producing an acidic Thorex glass. Calcination vessel designs were right circular cylinders similar to those used in engineering development studies. Costs were calculated for processing in 6-, 12-, and 24-in.-dia vessels with a fixed length of 10 ft. Vessel costs used, based on estimates from private industry, were calculated for wastes decayed 120 days and 1, 3, 10, and 30 years after reactor discharge prior to calcination. Aging had negligible effect on costs, except as it permitted larger diameter vessels to be used, because vessel and operating costs were much larger than capital costs in all cases. The lowest cost was 0.87 x 10/sup -2/ mill/kwh/sub e/ for processing acidic Purex and Thorex wastes in 24-in.-dia vessels, and the highest was 5.0 x 10/sup -2/ mill/kwh/sub e/ for processing reacidified Purex and Thorex wastes in 6-in.-dia vessels. About 7 years of interim liquid storage would be required before acidic Purex wastes could be processed in 24-in.-dia vessels. (auth)

Perona, J.J.; Bradshaw, R.L.; Roberts, J.T.; Blomeke, J.O.

1961-10-16T23:59:59.000Z

105

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

Science Conference Proceedings (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

106

APPLICATION OF A THIN FILM EVAPORATOR SYSTEM FOR MANAGEMENT OF LIQUID HIGH-LEVEL WASTES AT HANFORD  

Science Conference Proceedings (OSTI)

A modular, transportable evaporator system, using thin film evaporative technology, is planned for deployment at the Hanford radioactive waste storage tank complex. This technology, herein referred to as a wiped film evaporator (WFE), will be located at grade level above an underground storage tank to receive pumped liquids, concentrate the liquid stream from 1.1 specific gravity to approximately 1.4 and then return the concentrated solution back into the tank. Water is removed by evaporation at an internal heated drum surface exposed to high vacuum. The condensed water stream will be shipped to the site effluent treatment facility for final disposal. This operation provides significant risk mitigation to failure of the aging 242-A Evaporator facility; the only operating evaporative system at Hanford maximizing waste storage. This technology is being implemented through a development and deployment project by the tank farm operating contractor, Washington River Protection Solutions (WRPS), for the Office of River Protection/Department of Energy (ORP/DOE), through Columbia Energy & Environmental Services, Inc. (Columbia Energy). The project will finalize technology maturity and install a system at one of the double-shell tank farms. This paper discusses results of pre-project pilot-scale testing by Columbia Energy and ongoing technology maturation development scope through fiscal year 2012, including planned additional pilot-scale and full-scale simulant testing and operation with actual radioactive tank waste.

TEDESCHI AR; WILSON RA

2010-01-14T23:59:59.000Z

107

MEASUREMENTS TAKEN IN SUPPORT OF QUALIFICATION OF PROCESSING SAVANNAH RIVER SITE LOW-LEVEL LIQUID WASTE INTO SALTSTONE  

Science Conference Proceedings (OSTI)

The Saltstone Facility at the Savannah River Site (SRS) immobilizes low-level liquid waste into Saltstone to be disposed of in the Z-Area Saltstone Disposal Facility, Class Three Landfill. In order to meet the permit conditions and regulatory limits set by the South Carolina Department of Health and Environmental Control (SCDHEC), the Resource Conservation and Recovery Act (RCRA) and the Environmental Protection Agency (EPA), both the low-level salt solution and Saltstone samples are analyzed quarterly. Waste acceptance criteria (WAC) are designed to confirm the salt solution sample from the Tank Farm meets specific radioactive and chemical limits. The toxic characteristic leaching procedure (TCLP) is used to confirm that the treatment has immobilized the hazardous constituents of the salt solution. This paper discusses the methods used to characterize the salt solution and final Saltstone samples from 2007-2009.

Reigel, M.; Bibler, N.; Diprete, C.; Cozzi, A.; Staub, A.; Ray, J.

2010-01-27T23:59:59.000Z

108

Waste  

Science Conference Proceedings (OSTI)

Nowadays, Brazilian´s Light Emitting Diode - Liquid Crystal Display (LED-LCD) End-of-Life (EoL) disposal is traditionally landfills and incineration.

109

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

SciTech Connect

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

Defferding, L.J.

1980-06-01T23:59:59.000Z

110

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

DOE Green Energy (OSTI)

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

Defferding, L.J.

1980-06-01T23:59:59.000Z

111

Compact Liquid Waste Evaporator for Cleanup on Hanfords Hot Cells [FULL PAPER  

SciTech Connect

Removal of radionuclide and hazardous contaminants from hot cells in Hanford's 324 Building will produce an aqueous waste stream requiring volume reduction and packaging. This paper describes a compact and remotely-operated evaporator system that was designed for use in the 324 Building's B-Cell (a shielded hot cell) to volume-reduce the waste waters that are generated from pressure washing of hot cell ceiling, wall, and floor surfaces. The evaporator incorporates an electric-heated reboiler to provide evaporation and drying to allow disposal of waste material. Design features of the evaporator system were strongly influenced by the need for remote handling and remote maintenance. Purified water vapor from the evaporation process will be released directly to the hot cell ventilation air.

HOBART, R.L.

2003-11-14T23:59:59.000Z

112

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

DOE Green Energy (OSTI)

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

Sherwood, D.J.

1994-03-01T23:59:59.000Z

113

CORROSION CONTROL MEASURES FOR LIQUID RADIOACTIVE WASTE STORAGE TANKS AT THE SAVANNAH RIVER SITE  

SciTech Connect

The Savannah River Site has stored radioactive wastes in large, underground, carbon steel tanks for approximately 60 years. An assessment of potential degradation mechanisms determined that the tanks may be vulnerable to nitrate- induced pitting corrosion and stress corrosion cracking. Controls on the solution chemistry and temperature of the wastes are in place to mitigate these mechanisms. These controls are based upon a series of experiments performed using simulated solutions on materials used for construction of the tanks. The technical bases and evolution of these controls is presented in this paper.

Wiersma, B.; Subramanian, K.

2012-11-27T23:59:59.000Z

114

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

Science Conference Proceedings (OSTI)

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

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

2008-04-15T23:59:59.000Z

115

Radioactive waste systems and radioactive effluents  

SciTech Connect

Radioactive waste systems for handling gaseous, liquid, and solid wastes generated at light and pressurized water reactors are described. (TFD)

Row, T.H.

1973-01-01T23:59:59.000Z

116

An Istrument for Measuring the TRU Concentration in High-Level Liquid Waste  

Science Conference Proceedings (OSTI)

An online monitor has been designed, built, and tested, which is capable of measuring the residual transuranic concentrations in processed high-level wastes with a detection limit of 370 Bq/ml (10 nCi/ml) in less than six hours. The monitor measures the neutrons produced by the transuranics, primarily via (?,n) reactions, in the presence of gamma-ray fields up to 1 Sv/h (100 R/h). The optimum design was determined by Monte Carlo modeling and then tempered with practical engineering and cost considerations. Correct operation of the monitor was demonstrated in a hot cell utilizing an actual sample of high-level waste. Results of that demonstration are given, and suggestions for improvements in the next generation system are discussed.

Brodzinski, Ronald L.; Craig, R. A.; Fink, Samuel D.; Hensley, Walter K.; Holt, Noah O.; Knopf, Michael A.; Lepel, Elwood A.; Mullen, O Dennis; Salaymeh, Saleem R.; Samuel, Todd J.; Smart, John E.; Tinker, Michael R.; Walker, Darrell D.

2005-02-01T23:59:59.000Z

117

Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors  

Science Conference Proceedings (OSTI)

The Overall project demonstrated that toxic metals (cesium Cs and strontium Sr) in aqueous and organic wastes can be isolated from the environment through reaction with kaolinite based sorbent substrates in high temperature reactor environments. In addition, a state-of-the art laser diagnostic tool to measure droplet characteristic in practical 'dirty' laboratory environments was developed, and was featured on the cover of a recent edition of the scientific journal ''applied Spectroscopy''. Furthermore, great strides have been made in developing a theoretical model that has the potential to allow prediction of the position and life history of every particle of waste in a high temperature, turbulent flow field, a very challenging problem involving as it does, the fundamentals of two phase turbulence and of particle drag physics.

Jost O.L. Wendt; Alan R. Kerstein; Alexander Scheeline; Arne Pearlstein; William Linak

2003-08-06T23:59:59.000Z

118

Nuclear waste solidification  

DOE Patents (OSTI)

High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition.

Bjorklund, William J. (Richland, WA)

1977-01-01T23:59:59.000Z

119

FULL SCALE TESTING TECHNOLOGY MATURATION OF A THIN FILM EVAPORATOR FOR HIGH-LEVEL LIQUID WASTE MANAGEMENT AT HANFORD - 12125  

SciTech Connect

Simulant testing of a full-scale thin-film evaporator system was conducted in 2011 for technology development at the Hanford tank farms. Test results met objectives of water removal rate, effluent quality, and operational evaluation. Dilute tank waste simulant, representing a typical double-shell tank supernatant liquid layer, was concentrated from a 1.1 specific gravity to approximately 1.5 using a 4.6 m{sup 2} (50 ft{sup 2}) heated transfer area Rototherm{reg_sign} evaporator from Artisan Industries. The condensed evaporator vapor stream was collected and sampled validating efficient separation of the water. An overall decontamination factor of 1.2E+06 was achieved demonstrating excellent retention of key radioactive species within the concentrated liquid stream. The evaporator system was supported by a modular steam supply, chiller, and control computer systems which would be typically implemented at the tank farms. Operation of these support systems demonstrated successful integration while identifying areas for efficiency improvement. Overall testing effort increased the maturation of this technology to support final deployment design and continued project implementation.

TEDESCHI AR; CORBETT JE; WILSON RA; LARKIN J

2012-01-26T23:59:59.000Z

120

Off-gas characteristics of defense waste vitrification using liquid-fed Joule-heated ceramic melters  

DOE Green Energy (OSTI)

Off-gas and effluent characterization studies have been established as part of a PNL Liquid-Fed Ceramic Melter development program supporting the Savannah River Laboratory Defense Waste Processing Facility (SRL-DWPF). The objectives of these studies were to characterize the gaseous and airborne emission properties of liquid-fed joule-heated melters as a function of melter operational parameters and feed composition. All areas of off-gas interest and concern including effluent characterization, emission control, flow rate behavior and corrosion effects have been studied using alkaline and formic-acid based feed compositions. In addition, the behavioral patterns of gaseous emissions, the characteristics of melter-generated aerosols and the nature and magnitude of melter effluent losses have been established under a variety of feeding conditions with and without the use of auxiliary plenum heaters. The results of these studies have shown that particulate emissions are responsible for most radiologically important melter effluent losses. Melter-generated gases have been found to be potentially flammable as well as corrosive. Hydrogen and carbon monoxide present the greatest flammability hazard of the combustibles produced. Melter emissions of acidic volatile compounds of sulfur and the halogens have been responsible for extensive corrosion observed in melter plenums and in associated off-gas lines and processing equipment. The use of auxiliary plenum heating has had little effect upon melter off-gas characteristics other than reducing the concentrations of combustibles.

Goles, R.W.; Sevigny, G.J.

1983-09-01T23:59:59.000Z

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

Evaluation of ultrafiltration membranes for treating low-level radioactive contaminated liquid waste  

SciTech Connect

A series of experiments were performed on Waste Disposal Facility (WD) influent using Romicon hollow fiber ultrafiltration modules with molecular weight cutoffs ranging from 2000 to 80,000. The rejection of conductivity was low in most cases. The rejection of radioactivity ranged from 90 to 98%, depending on the membrane type and on the feed concentration. Typical product activity ranged from 7 to 100 dis/min/ml of alpha radiation. Experiments were also performed on alpha-contaminated laundry wastewater. Results ranged from 98 to >99.8%, depending on the membrane type. This yielded a product concentration of less than 0.1 dis/min/ml of alpha radiation. Tests on PP-Building decontamination water yielded rejections of 85 to 88% alpha radiation depending on the membrane type. These experiments show that the ability to remove radioactivity by membrane is a function of the contents of the waste stream because the radioactivity in the wastewater is in various forms: ionic, polymeric, colloidal, and absorbed onto suspended solids. Although removal of suspended or colloidal material is very high, removal of ionic material is not as effective. Alpha-contaminated laundry wastewater proved to be the easiest to decontaminate, whereas the low-level PP-Building decontamination water proved to be the most difficult to decontaminate. Decontamination of the WD influent, a combined waste stream, varied considerably from day to day because of its constantly changing makeup. The WD influent was also treated with various substances, such as polyelectrolytes, complexing agents, and coagulants, to determine if these additives would aid in the removal of radioactive material from the various wastewaters by complexing the ionic species. At the present time, none of the additives evaluated has had much effect; but experiments are continuing.

Koenst, J.W.; Roberts, R.C.

1978-03-31T23:59:59.000Z

122

Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors  

Science Conference Proceedings (OSTI)

Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification.

William Linak

2004-12-16T23:59:59.000Z

123

Out-Of-Drum Grout Mixer Testing With Simulated Liquid Effluents Originating From Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is considering several optional processes for disposal of liquid sodium-bearing waste. During fiscal year 2003, alternatives were evaluated for grout formulation development and associated mixing for the Sodium-Bearing Waste cesium ion exchange process. The neutralization agents calcium or sodium hydroxide and the solidification agents Portland cement, with or without blast furnace slag were evaluated. A desired uniform formulation was pursued to develop a grout waste form without any bleed liquid and solidify within a reasonable period of about twenty-eight days. This testing evaluates the out-of-drum alternative of mixing the effluent with solidification agents prior to being poured into drums versus the in-drum alternative of mixing them all together after being poured into the drums. Experimental results indicate that sodium-bearing waste can be immobilized in grout using the Autocon continuous mixer within the range of 66 to 72 weight percent. Furthermore, a loading of 30 weight percent NWCF scrubber simulant also produced an acceptable grout waste form.

B. A. Scholes; A. K. Herbst; S. V. Raman; S. H. Hinckley

2003-09-01T23:59:59.000Z

124

An Instrument for Measuring the TRU Concentration in High-Level Liquid Waste  

Science Conference Proceedings (OSTI)

An online monitor has been designed, built, and tested that is capable of measuring the residual transuranic concentrations in processed high-level wastes with a detection limit of 370 Bq/ml (10 nCi/ml) in less than six hours. The monitor measures the ({alpha},n) neutrons in the presence of gamma-ray fields up to 1 Sv/h (100 R/h). The optimum design was determined by Monte Carlo modeling and then tempered with practical engineering and cost considerations. A multiplicity counter is used in data acquisition to reject the large fraction of coincident and highly variable cosmic-ray-engendered background events and results in a S/N ratio {approx}1.

Brodzinski, Ronald L.; Craig, R A.; Fink, Samuel D.; Hensley, Walter K.; Holt, Noah OA; Knopf, Michael A.; Lepel, Elwood A.; Mullen, O Dennis; Salaymeh, Saleem R.; Samuel, Todd J.; Smart, John E.; Tinker, Mike R.; Walker, D

2005-02-01T23:59:59.000Z

125

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

Science Conference Proceedings (OSTI)

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

Bryant, Jeffrey Whealdon; Nenni, Joseph A; Timothy S. Yoder

2003-04-01T23:59:59.000Z

126

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

SciTech Connect

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

Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

2003-04-22T23:59:59.000Z

127

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 scintillation vials must be collected separately. 5. Any "mixed waste" must be cleared with the RSO and labeled

128

Solidification of Simulated Liquid Effluents Originating From Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center, FY-03 Report  

SciTech Connect

In this report, the mechanism and methods of fixation of acidic waste effluents in grout form are explored. From the variations in the pH as a function of total solids addition to acidic waste effluent solutions, the stages of gellation, liquefaction, slurry formation and grout development are quantitatively revealed. Experimental results indicate the completion of these reaction steps to be significant for elimination of bleed liquid and for setting of the grout to a dimensionally stable and hardened solid within a reasonable period of about twenty eight days that is often observed in the cement and concrete industry. The reactions also suggest increases in the waste loading in the direction of decreasing acid molarity. Consequently, 1.0 molar SBW-180 waste is contained in higher quantity than the 2.8 molar SBW-189, given the same grout formulation for both effluents. The variations in the formulations involving components of slag, cement, waste and neutralizing agent are represented in the form of a ternary formulation map. The map in turn graphically reveals the relations among the various formulations and grout properties, and is useful in predicting the potential directions of waste loading in grouts with suitable properties such as slurry viscosity, Vicat hardness, and mechanical strength. A uniform formulation for the fixation of both SBW-180 and SBW-189 has emerged from the development of the formulation map. The boundaries for the processing regime on this map are 100 wt% cement to 50 wt% cement / 50 wt% slag, with waste loadings ranging from 55 wt% to 68 wt%. Within these compositional bounds all the three waste streams SBW-180, SBW-189 and Scrub solution are amenable to solidification. A large cost advantage is envisaged to stem from savings in labor, processing time, and processing methodology by adopting a uniform formulation concept for fixation of compositionally diverse waste streams. The experimental efforts contained in this report constitute the first attempt at developing a uniform methodology.

S. V. Raman; A. K. Herbst; B. A. Scholes; S. H. Hinckley; R. D. Colby

2003-09-01T23:59:59.000Z

129

Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste. Quarterly report, October, November, December 1976  

SciTech Connect

The objective of this program is to develop and demonstrate separation methods for removing radionuclides from liquid process waste streams. As part of this program, Mound Laboratory will develop lower cost alternatives for use i n1980 fuel reprocessing and waste solidification plants, evaluate the processes within the nuclear fuel cycle which contribute to low-level and intermediate-level waste, and determine the feasibility of ultrafiltration, reverse osmosis, inorganic adsorbents and other separation concepts as additions to process design to reduce the generation of this type of waste. In the initial phase of this program, membrane equipment will be obtained from a commercial membrane manufacturer. After the pilot plant is installed, it will be checked out on cold feed in order to obtain initial flux and rejection data for comparison to data obtained later in the program. After completion of the cold tests, the membrane pilot plant will be run on a combined contaminated feed emanating from showers, laboratory drains, janitorial sinks and decontamination in processing areas, as well as a laundry waste stream containing alpha-contaminated wastes. This combined waste stream contains only alpha contamination (uranium and plutonium). However, as part of this program, gamma activity will be added to the waste stream. These wastes will be representative of those streams found at fuel reprocessing plants, as well as various ERDA processing facilities such as Mound, LASL, Hanford, and Rocky Flats. For the second part of the program, laboratory tests will be run on various adsorbents to evaluate their capacities for removing radionuclides. As part of this program, a technique for screening adsorbents developed at Mound Laboratory will be utilized.

1976-12-31T23:59:59.000Z

130

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

E-Print Network (OSTI)

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

Hunt, Andrew Robert

2007-01-01T23:59:59.000Z

131

Implementation Plan for Liquid Low-Level Radioactive Waste tank systems at Oak Ridge National Laboratory under the Federal Facility Agreement, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

This document summarizes the progress that has been made to date in implementing the plans and schedules for meeting the Federal Facility Agreement (FFA) commitments for the Liquid Low-Level Waste (LLLW) System at Oak Ridge National Laboratory (ORNL). These commitments were initially submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste Tank Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Information presented in this document provides a comprehensive summary to facilitate understanding of the FFA compliance program for LLLW tank systems and to present plans and schedules associated with remediation, through the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process, of LLLW tank systems that have been removed from service. ORNL has a comprehensive program underway to upgrade the LLLW system as necessary to meet the FFA requirements. The tank systems that are removed from service are being investigated and remediated through the CERCLA process. Waste and risk characterizations have been submitted. Additional data will be prepared and submitted to EPA/TDEC as tanks are taken out of service and as required by the remedial investigation/feasibility study (RI/FS) process. The plans and schedules for implementing the FFA compliance program that were submitted in ES/ER-17&Dl, Federal Facility Agreement Plans and Schedules for Liquid Low-Level Radioactive Waste tanks Systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee, are updated in this document. Chapter 1 provides general background information and philosophies that lead to the plans and schedules that appear in Chaps. 2 through 5.

Not Available

1994-09-01T23:59:59.000Z

132

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

SciTech Connect

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

Bryant, J.W.; Nenni, J.A.; Yoder, T.S.

2003-04-22T23:59:59.000Z

133

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

SciTech Connect

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

Bryant, Jeffrey W.

2010-08-12T23:59:59.000Z

134

Thermodynamic estimation of minor element distribution between immiscible liquids in Fe-Cu-based metal phase generated in melting treatment of municipal solid wastes  

SciTech Connect

Graphical abstract: Display Omitted Highlights: Black-Right-Pointing-Pointer Two liquids separation of metal occurs in the melting of municipal solid waste. Black-Right-Pointing-Pointer The distribution of PGMs etc. between two liquid metal phases is studied. Black-Right-Pointing-Pointer Quite simple thermodynamic model is applied to predict the distribution ratio. Black-Right-Pointing-Pointer Au and Ag originated from WEEE are found to be concentrated into Cu-rich phase. - Abstract: Waste electrical and electronic equipment (WEEE) has become an important target in managing material cycles from the viewpoint of not only waste management and control of environmental pollution but also resource conservation. This study investigated the distribution tendency of trace elements in municipal solid waste (MSW) or incinerator ash, including valuable non-ferrous metals (Ni, Co, Cr, Mn, Mo, Ti, V, W, Zr), precious group metals (PGMs) originated from WEEE (Ag, Au, Pd, Pt), and others (Al, B, Pb, Si), between Fe-rich and Cu-rich metal phases by means of simple thermodynamic calculations. Most of the typical alloying elements for steel (Co, Cr, Mo, Nb, Ni, Si, Ti, V, and W) and Rh were preferentially distributed into the Fe-rich phase. PGMs, such as Au, Ag, and Pd, were enriched in the Cu-rich phase, whereas Pt was almost equally distributed into both phases. Since the primary metallurgical processing of Cu is followed by an electrolysis for refining, and since PGMs in crude copper have been industrially recovered from the resulting anode slime, our results indicated that Ag, Au, and Pd could be effectively recovered from MSW if the Cu-rich phase could be selectively collected.

Lu, X. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nakajima, K.; Sakanakura, H. [Research Center for Material Cycles and Waste Management, National Institute for Environmental Studies (NIES), 16-2 Onogawa, Tsukuba 305-8506 (Japan); Matsubae, K. [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan); Bai, H. [School of Metallurgical and Ecological Engineering, The University of Science and Technology Beijing, 30 Xueyuan Road, Haidian District, Beijing 100083 (China); Nagasaka, T., E-mail: t-nagasaka@m.tohoku.ac.jp [Graduate School of Engineering, Tohoku University, 6-6-11 Aza-Aoba, Aramaki, Sendai 980-8579 (Japan)

2012-06-15T23:59:59.000Z

135

In Situ Grouting of Liquid Waste Disposal Trenches and Experimental Reactor Fuel Disposal Wells at Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

In the early to mid-1960's, liquid low-level wastes (LLLW) generated at Oak Ridge National Laboratory were disposed of in specially-constructed, gravel-filled trenches within the Melton Valley watershed at the lab. The initial selected remedy for Trenches 5 and 7 was in situ vitrification; however, an amendment to the record of decision changed the remedy to in situ grouting of the trenches. The work was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout. At the HRE fuel wells, a 1-m ring of soil surrounding the fuel wells was grouted with acrylamide. The results of the hydraulic conductivity tests ranged from 4.74 x 10{sup -6} to 3.60 x 10{sup -7} cm/sec, values that were well below the 1 x 10{sup -5} cm/sec design criterion. In summary: The ISG Project was conducted to decrease hydraulic conductivity and thereby decrease water flow and contaminate migration from the area of the trenches. The initial remedy for Trenches 5 and 7 in the Melton Valley ROD was for in situ vitrification of the trench matrix. The remedy was changed to in situ grouting of the trenches and HRE fuel wells through an amendment to the ROD after moisture was found in the trenches. The grouting of the trenches was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout to further reduce water infiltration. Soil backfill above each of the seven HRE fuel wells was removed to a depth of approximately 1 m by augering, and the soils were replaced with a cement plug to prevent water infiltration from migrating down the original borehole. Soil surrounding the fuel wells was then grouted with acrylamide to ensure water infiltration through the HRE fuel wells is prevented. A summary of the quantities used is shown. After completion of grouting, in-situ hydraulic conductivities of the grouted materials were measured to verify attainment of the design objective. The areas were then covered with multi-layer caps as part of the MV hydrologic isolation project. (authors)

Johnson, Ch.; Cange, J.; Lambert, R. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Trujillo, E. [BWXT Pantex, LLC, Amarillo, TX (United States); Julius, J. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States)

2008-07-01T23:59:59.000Z

136

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

Science Conference Proceedings (OSTI)

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

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

2009-06-01T23:59:59.000Z

137

PILOT-SCALE TEST RESULTS OF A THIN FILM EVAPORATOR SYSTEM FOR MANAGEMENT OF LIQUID HIGH-LEVEL WASTES AT THE HANFORD SITE WASHINGTON USA -11364  

Science Conference Proceedings (OSTI)

A modular, transportable evaporator system, using thin film evaporative technology, is planned for deployment at the Hanford radioactive waste storage tank complex. This technology, herein referred to as a wiped film evaporator (WFE), will be located at grade level above an underground storage tank to receive pumped liquids, concentrate the liquid stream from 1.1 specific gravity to approximately 1.4 and then return the concentrated solution back into the tank. Water is removed by evaporation at an internal heated drum surface exposed to high vacuum. The condensed water stream will be shipped to the site effluent treatment facility for final disposal. This operation provides significant risk mitigation to failure of the aging 242-A Evaporator facility; the only operating evaporative system at Hanford maximizing waste storage. This technology is being implemented through a development and deployment project by the tank farm operating contractor, Washington River Protection Solutions (WRPS), for the Office of River Protection/Department of Energy (ORPIDOE), through Columbia Energy and Environmental Services, Inc. (Columbia Energy). The project will finalize technology maturity and install a system at one of the double-shell tank farms. This paper summarizes results of a pilot-scale test program conducted during calendar year 2010 as part of the ongoing technology maturation development scope for the WFE.

CORBETT JE; TEDESCH AR; WILSON RA; BECK TH; LARKIN J

2011-02-14T23:59:59.000Z

138

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

E-Print Network (OSTI)

loss in class I waste injection wells, in: Apps J.A. andR.F. , An overview of injection well history in the Unitedmeasures for Class I injection wells, in Apps J.A. and Tsang

Tsang, C.-F.

2009-01-01T23:59:59.000Z

139

Decommissioning and safety issues of liquid-mercury waste generated from high power spallation sources with particle accelerators  

E-Print Network (OSTI)

Large spallation sources are intended to be constructed in Europe (EURISOL nuclear physics facility and ESS-European Spallation Source). These facilities accumulate more than 20 metric tons of irradiated mercury in the target, which has to be treated as highly radioactive and chemo-toxic waste. Because solids are the only appropriate (immobile) form for this radiotoxic and toxic type of waste solidification is required for irradiated mercury. Our irradiation experimental studies on mercury waste revealed that mercury sulfide is a reasonable solid for disposal and shows larger stability in assumed accidents with water ingress in a repository compared to amalgams. For preparation of mercury sulfide a wet process is more suitable than a dry one. It is easier to perform under hot cell conditions and allows complete Hg-conversion. Embedding HgS in a cementitious matrix increases its stability.

Chiriki, S; Odoj, R; Moormann, R; Hinssen, H. K; Bukaemskiy, A

2009-01-01T23:59:59.000Z

140

The largest radioactive waste glassification  

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

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

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

Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) underground storage tanks (Uses) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. A total of 55 FFA Category D inactive LLLW tanks are discussed in this manual. Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration (ER) Program, all have been sampled for preliminary characterization, except for 5 tanks that were found to be empty plus I that was found not to exist. The remaining 16 tanks are in the Waste Management (WM) Program. Twelve were sampled for preliminary characterization, and four were found empty. Each sampled tank was scored on a scale of I to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was assigned a weighing factor based on perceived importance. The criterion score multiplied by the weighting factor equaled the tank`s total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation. Of the 54 tanks sampled in the risk characterization, 23 tanks scored 16 or higher, 11 scored between 10 and 15, 5 scored between 4 and 9, and 15 scored 3 or less.

Not Available

1993-09-01T23:59:59.000Z

142

Risk characterization data manual for Category D inactive liquid low-level waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

This manual reports the results of a risk characterization of Category D inactive liquid low-level radioactive waste (LLLW) underground storage tanks (USTs) at the Oak Ridge National Laboratory (ORNL). The risk characterization is required by the Federal Facility Agreement between the Department of Energy-Oak Ridge Operations Office, the Environmental Protection Agency-Region IV, and the Tennessee Department of Environment and Conservation. The intent of the risk characterization is to determine relative priorities for assessment and remediation. A total of 55 FFA Category D inactive LLLW tanks are discussed in this manual. Of the 39 tanks at ORNL that have been accepted into the Environmental Restoration (ER) Pregrain, all have been sampled for preliminary characterization, except for 5 tanks that were found to be empty plus 1 that was found not to exist. The remaining 16 tanks are in the Waste Management (WM) Program. Twelve were sampled for preliminary characterization, and four were found empty. Each sampled tank was scored on a scale of I to 5 on the basis of three criteria: (1) leak characteristics, (2) location, and (3) toxicological characteristics of residual sludges and liquids. Each criterion was assigned a weighing factor based on perceived importance. The criterion score multiplied by the weighting factor equaled the tank`s total score for that criterion. The three weighted criterion scores for each tank were then summed for a total score for that tank. When the scores for all tanks had been weighted and summed, the tanks were ranked in descending order on the basis of their total scores. The highest possible score for a tank is 30. The descending rank order represents the recommended priorities for evaluation: the higher the score, the higher the priority for evaluation. Of the 54 tanks sampled in the risk characterization, 23 tanks scored 16 or higher, 11 scored between 10 and 15, 5 scored between 4 and 9, and 15 scored 3 or less.

Not Available

1993-07-01T23:59:59.000Z

143

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

DOE Green Energy (OSTI)

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

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

2009-05-01T23:59:59.000Z

144

Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste  

DOE Patents (OSTI)

Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extracted from the aqueous phase using a phosphine oxide in a hydrocarbon diluent, and reextracted from the resulting organic phase into an aqueous phase by using a suitable strip reagent.

Zaitsev, Boris N. (St. Petersburg, RU); Esimantovskiy, Vyacheslav M. (St. Petersburg, RU); Lazarev, Leonard N. (St. Petersburg, RU); Dzekun, Evgeniy G. (Ozersk, RU); Romanovskiy, Valeriy N. (St. Petersburg, RU); Todd, Terry A. (Aberdeen, ID); Brewer, Ken N. (Arco, ID); Herbst, Ronald S. (Idaho Falls, ID); Law, Jack D. (Pocatello, ID)

2001-01-01T23:59:59.000Z

145

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

146

Development of a pilot safety information document (PSID) for the replacement of radioactive liquid waste treatment facility at Los Alamos National Laboratory  

E-Print Network (OSTI)

Based on recent decisions made by Los Alamos National Laboratory concerning the development of site-wide National Environmental Policy Act documents, an effort was undertaken to develop a Pilot Safety Information Document (PSID) for the replacement Radioactive Liquid Waste Treatment Facility. The PSID documents risk analysis for the proposed facility and some of the alternatives, accident analysis, radioactive and hazardous material doses to off-site individuals, and the cumulative safety risk from adjacent facilities. In addition, this study also compared two methods for calculating the consequences of a radioactive spill. The methods compared were the Superfund model and the release fraction model. It was determined that the release fraction model gives a more realistic estimate of the doses incurred as the result of an accident, and that the Superfund model should be used for estimating the dose before and during the remediation effort. The cumulative safety risk was determined by calculating the exceedance probability if the individual dose from four geographically related facilities. The risk for cancer fatalities was determined to be within the DOE's Nuclear Safety Policy Goals.

Selvage, Ronald Derek

1995-01-01T23:59:59.000Z

147

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

Science Conference Proceedings (OSTI)

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

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

2012-08-29T23:59:59.000Z

148

Savannah River Site Waste Disposition Project  

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

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

149

DuraLith Alkali-Aluminosilicate Geopolymer Waste Form Testing for Hanford Secondary Waste  

SciTech Connect

The primary objective of the work reported here was to develop additional information regarding the DuraLith alkali aluminosilicate geopolymer as a waste form for liquid secondary waste to support selection of a final waste form for the Hanford Tank Waste Treatment and Immobilization Plant secondary liquid wastes to be disposed in the Integrated Disposal Facility on the Hanford Site. Testing focused on optimizing waste loading, improving waste form performance, and evaluating the robustness of the waste form with respect to waste variability.

Gong, W. L.; Lutz, Werner; Pegg, Ian L.

2011-07-21T23:59:59.000Z

150

Radioactive Liquid Processing Guidelines  

Science Conference Proceedings (OSTI)

This report presents guidance for utility liquid radwaste processing program managers. The document is a summation of utility and vendor processing experience, and is intended for use as a tool to enhance liquid radwaste processing programs. Utilization of this information will result in optimized system performance, and a reduction in waste volumes and program costs.

2005-11-22T23:59:59.000Z

151

Liquid heat capacity lasers  

DOE Patents (OSTI)

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

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

2007-05-01T23:59:59.000Z

152

SRS - Programs - Waste Solidification  

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

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

153

Radioactive waste disposal package  

DOE Patents (OSTI)

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

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

154

Federal Facility Agreement plans and schedules for liquid low-level radioactive waste tank systems at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

The Superfund Amendments and Reauthorization Act of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requires a Federal Facility 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 Department of Energy Oak Ridge Field Office (DOE-OR), the US Environmental Protection Agency (EPA)-Region IV, and the Tennessee Department of Environment and Conservation (TDEC). The effective date of the FFA was January 1, 1992. Section 9 and Appendix F of the agreement impose design and operating requirements on the Oak Ridge National Laboratory (ORNL) liquid low-level radioactive waste (LLLW) tank systems and identify several plans, schedules, and assessments that must be submitted to EPA/TDEC for review or approval. The initial issue of this document in March 1992 transmitted to EPA/TDEC those plans and schedules that were required within 60 to 90 days of the FFA effective date. The current revision of this document updates the plans, schedules, and strategy for achieving compliance with the FFA, and it summarizes the progress that has been made over the past year. Chapter 1 describes the history and operation of the ORNL LLLW System, the objectives of the FFA, the organization that has been established to bring the system into compliance, and the plans for achieving compliance. Chapters 2 through 7 of this report contain the updated plans and schedules for meeting FFA requirements. This document will continue to be periodically reassessed and refined to reflect newly developed information and progress.

Not Available

1993-06-01T23:59:59.000Z

155

Cost of meeting geothermal liquid effluent disposal regulations  

DOE Green Energy (OSTI)

Background information is presented on the characteristics of liquid wastes and the available disposal options. Regulations that may directly or indirectly influence liquid waste disposal are reviewed. An assessment of the available wastewater-treatment systems is provided. A case study of expected liquid-waste-treatment and disposal costs is summarized. (MHR)

Wells, K.D.; Currie, J.W.; Price, B.A.; Rogers, E.A.

1981-06-01T23:59:59.000Z

156

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

157

Salt Waste Processing Facility Fact Sheet  

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

Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms.

158

Secondary Waste Forms and Technetium Management  

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

November 18, 2010 What are Secondary Wastes? Process condensates and scrubber andor off-gas treatment liquids from the pretreatment and ILAW melter facilities at the Hanford WTP....

159

Removal of radioisotopes from waste solutions  

DOE Patents (OSTI)

The invention comprises removing radioisotopes from waste liquids or solutions by passing these through filters and through a column containing a suitable salt of phosphoric acid. (Official Gazette)

Kirby, H.W.

1973-10-01T23:59:59.000Z

160

Waste Management | Department of Energy  

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

Management Management Waste Management Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Read more Tank Waste and Waste Processing The Department has approximately 88 million gallons of liquid waste stored in underground tanks and approximately 4,000 cubic meters of solid waste derived from the liquids stored in bins. The current DOE estimated cost for retrieval, treatment and disposal of this waste exceeds $50 billion to be spent over several decades.

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

Test plan for glass melter system technologies for vitrification of high-sodium content low-level radioactive liquid waste, Project No. RDD-43288  

Science Conference Proceedings (OSTI)

This document provides a test plan for the conduct of combustion fired cyclone vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System, Low-Level Waste Vitrification Program. The vendor providing this test plan and conducting the work detailed within it is the Babcock & Wilcox Company Alliance Research Center in Alliance, Ohio. This vendor is one of seven selected for glass melter testing.

Higley, B.A.

1995-03-15T23:59:59.000Z

162

Salt Waste Processing Facility Fact Sheet | Department of Energy  

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

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications EIS-0082-S2: Amended Record of Decision Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report EIS-0082-S2: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)

163

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes  

SciTech Connect

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D`Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D`Amico, N. [ed.

1994-10-20T23:59:59.000Z

164

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

165

Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form  

SciTech Connect

The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.

Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.

2011-09-12T23:59:59.000Z

166

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

Science Conference Proceedings (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

167

Dewatering equipment recommendations for the solids/liquid separation project at Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

The final closure of Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory will include the plugging and abandonment of many existing wells and boreholes and the installation of diversion trenches for groundwater control. These activities will generate soil that must be dewatered before it can be disposed of. Three different types of dewatering equipment{emdash}rotary vacuum drum filters, automatic discharge pressure filters, and centrifuges{emdash}have been evaluated to assess their suitability for the WAG 6 project. Because of its lower cost and minimal prescreening requirements, it is recommended that a centrifuge be used to dewater the WAG 6 soils.

Taylor, P.A.

1992-05-01T23:59:59.000Z

168

Dewatering equipment recommendations for the solids/liquid separation project at Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

SciTech Connect

The final closure of Waste Area Grouping (WAG) 6 at Oak Ridge National Laboratory will include the plugging and abandonment of many existing wells and boreholes and the installation of diversion trenches for groundwater control. These activities will generate soil that must be dewatered before it can be disposed of. Three different types of dewatering equipment{emdash}rotary vacuum drum filters, automatic discharge pressure filters, and centrifuges{emdash}have been evaluated to assess their suitability for the WAG 6 project. Because of its lower cost and minimal prescreening requirements, it is recommended that a centrifuge be used to dewater the WAG 6 soils.

Taylor, P.A.

1992-05-01T23:59:59.000Z

169

Secondary Waste Forms and Technetium Management  

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

Secondary Waste Forms and Secondary Waste Forms and Technetium Management Joseph H. Westsik, Jr. Pacific Northwest National Laboratory EM HLW Corporate Board Meeting November 18, 2010 What are Secondary Wastes? Process condensates and scrubber and/or off-gas treatment liquids from the pretreatment and ILAW melter facilities at the Hanford WTP. Sent from WTP to the Effluent Treatment Facility (ETF) for treatment and disposal Treated liquid effluents under the ETF State Wastewater Discharge Permit Solidified liquid effluents under the Dangerous Waste Permit for disposal at the Integrated Disposal Facility (IDF) Solidification Treatment Unit to be added to ETF to provide capacity for WTP secondary liquid wastes 2 Evaporator Condensate Solution Evaporator Pretreatment Melter SBS/ WESP Secondary

170

ORNL radioactive waste operations  

SciTech Connect

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01T23:59:59.000Z

171

Liquid-Liquid Extraction Processes  

E-Print Network (OSTI)

Liquid-liquid extraction is the separation of one or more components of a liquid solution by contact with a second immiscible liquid called the solvent. If the components in the original liquid solution distribute themselves differently between the two liquid phases, separation will result. This is the principle upon which separation by liquid-liquid extraction is based, and there are a number of important applications of this concept in industrial processes. This paper will review the basic concepts and applications as well as present future directions for the liquid-liquid extraction process.

Fair, J. R.; Humphrey, J. L.

1983-01-01T23:59:59.000Z

172

ZERO WASTE.  

E-Print Network (OSTI)

??The aim of the thesis was to develop a clear vision on better waste management system. The thesis introduced the sustainable waste management along with… (more)

Upadhyaya, Luv

2013-01-01T23:59:59.000Z

173

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 2. Alternatives for waste treatment  

DOE Green Energy (OSTI)

Volume II of the five-volume report is devoted to the description of alternatives for waste treatment. The discussion is presented under the following section titles: fuel reprocessing modifications; high-level liquid waste solidification; treatment and immobilization of chop-leach fuel bundle residues; treatment of noncombustible solid wastes; treatment of combustible wastes; treatment of non-high-level liquid wastes; recovery of transuranics from non-high-level wastes; immobilization of miscellaneous non-high-level wastes; volatile radioisotope recovery and off-gas treatment; immobilization of volatile radioisotopes; retired facilities (decontamination and decommissioning); and, modification and use of selected fuel reprocessing wastes. (JGB)

Not Available

1976-05-01T23:59:59.000Z

174

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

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

Ramsey, William Gene

2013-08-15T23:59:59.000Z

175

Radiation Chemistry of Ionic Liquids  

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

Liquids Liquids James F. Wishart, Alison M. Funston, and Tomasz Szreder in "Molten Salts XIV" Mantz, R. A., et al., Eds.; The Electrochemical Society, Pennington, NJ, (2006) pp. 802-813. [Information about the volume (look just above this link)] Abstract: Ionic liquids have potentially important applications in nuclear fuel and waste processing, energy production, improving the efficiency and safety of industrial chemical processes, and pollution prevention. Successful use of ionic liquids in radiation-filled environments will require an understanding of ionic liquid radiation chemistry. For example, characterizing the primary steps of ionic liquid radiolysis will reveal radiolytic degradation pathways and suggest ways to prevent them or mitigate their effects on the properties of the material

176

Estimating Waste Inventory and Waste Tank Characterization |...  

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

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

177

SELF SINTERING OF RADIOACTIVE WASTES  

DOE Patents (OSTI)

A method is described for disposal of radioactive liquid waste materials. The wastes are mixed with clays and fluxes to form a ceramic slip and disposed in a thermally insulated container in a layer. The temperature of the layer rises due to conversion of the energy of radioactivity to heat boillng off the liquid to fomn a dry mass. The dry mass is then covered with thermal insulation, and the mass is self-sintered into a leach-resistant ceramic cake by further conversion of the energy of radioactivity to heat.

McVay, T.N.; Johnson, J.R.; Struxness, E.G.; Morgan, K.Z.

1959-12-29T23:59:59.000Z

178

Waste Generated from LMR-AMTEC Reactor Concept  

SciTech Connect

The candidate Liquid Metal Reactor-Alkali Metal Thermal -to- Electric Converter (LMR-AMTEC) is considered to be the first reactor that would use pure liquid potassium as a secondary coolant, in which potassium vapor aids in the conversion of thermal energy to electric energy. As with all energy production, the thermal generation of electricity produces wastes. These wastes must be managed in ways which safeguard human health and minimize their impact on the environment. Nuclear power is the only energy industry, which takes full responsibility for all its wastes. Based on the candidate design of the LMR-AMTEC components and the coolant types, different wastes will be generated from LMR. These wastes must be classified and characterized according to the U.S. Code of Federal Regulation, CFR. This paper defines the waste generation and waste characterization from LMR-AMTEC and reviews the applicable U.S. regulations that govern waste transportation, treatment, storage and final disposition. The wastes generated from LMR-AMTEC are characterized as: (1) mixed waste which is generated from liquid sodium contaminated by fission products and activated corrosion products; (2) hazardous waste which is generated from liquid potassium contaminated by corrosion products; (3) spent nuclear fuel; and (4) low-level radioactive waste which is generated from the packing materials (e.g. activated carbon in cold trap and purification units). The regulations and management of these wastes are summarized in this paper.

Hasan, Ahmed; Mohamed, Yasser, T.; Mohammaden, Tarek, F.

2003-02-25T23:59:59.000Z

179

Waste management system alternatives for treatment of wastes from spent fuel reprocessing  

SciTech Connect

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

1986-09-01T23:59:59.000Z

180

Excellence in radioactive waste volume reduction  

SciTech Connect

The Brunswick plant is a two-unit boiling water reactor located at the mouth of the Cape Fear River near Wilmington, North Carolina. The plant has a once-through cooling system with highly brackish water. The operations subunit is responsible for liquid radwaste processing. The radiation control subunit is responsible for dry active waste processing and the transportation of all radioactive wast off-site. For the Brunswick plant, the development of an effective radioactive waste volume reduction program was a process involving a tremendous amount of grass-roots worker participation. With radioactive waste responsibilities divided between two separate groups, this process took place on a somewhat different schedule for liquid process waste and dry active waste. However, this development process did not begin until dedicated personnel were assigned to manage radwaste independently of other plant duties.

Henderson, J.

1987-01-01T23:59:59.000Z

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

Fuel gas production by microwave plasma in liquid  

Science Conference Proceedings (OSTI)

We propose to apply plasma in liquid to replace gas-phase plasma because we expect much higher reaction rates for the chemical deposition of plasma in liquid than for chemical vapor deposition. A reactor for producing microwave plasma in a liquid could produce plasma in hydrocarbon liquids and waste oils. Generated gases consist of up to 81% hydrogen by volume. We confirmed that fuel gases such as methane and ethylene can be produced by microwave plasma in liquid.

Nomura, Shinfuku; Toyota, Hiromichi; Tawara, Michinaga; Yamashita, Hiroshi; Matsumoto, Kenya [Graduate School of Science and Engineering, Ehime University, 3 Bunkyo-cho, Matsuyama, Ehime 790-8577 (Japan); Shikoku Industry and Technology Promotion Center, 2-5 Marunouchi, Takamatsu, Kagawa 760-0033 (Japan)

2006-06-05T23:59:59.000Z

182

Evaluation of waste disposal by shale fracturing  

SciTech Connect

The shale fracturing process is evaluated as a means for permanent disposal of radioactive intermediate level liquid waste generated at the Oak Ridge National Laboratory. The estimated capital operating and development costs of a proposed disposal facility are compared with equivalent estimated costs for alternative methods of waste fixation.

Weeren, H.O.

1976-02-01T23:59:59.000Z

183

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

184

Hazardous Waste  

Science Conference Proceedings (OSTI)

Table 6   General refractory disposal options...D landfill (b) Characterized hazardous waste by TCLP

185

Management of offshore wastes in the United States.  

SciTech Connect

During the process of finding and producing oil and gas in the offshore environment operators generate a variety of liquid and solid wastes. Some of these wastes are directly related to exploration and production activities (e.g., drilling wastes, produced water, treatment workover, and completion fluids) while other types of wastes are associated with human occupation of the offshore platforms (e.g., sanitary and domestic wastes, trash). Still other types of wastes can be considered generic industrial wastes (e.g., scrap metal and wood, wastes paints and chemicals, sand blasting residues). Finally, the offshore platforms themselves can be considered waste materials when their useful life span has been reached. Generally, offshore wastes are managed in one of three ways--onsite discharge, injection, or transportation to shore. This paper describes the regulatory requirements imposed by the government and the approaches used by offshore operators to manage and dispose of wastes in the US.

Veil, J. A.

1998-10-22T23:59:59.000Z

186

Physical and chemical characteristics of candidate wastes for tailored ceramics  

Science Conference Proceedings (OSTI)

Tailored Ceramics offer a potential alternative to glass as an immobilization form for nuclear waste disposal. The form is applicable to the wide variety of existing wastes and may be tailored to suit the diverse environments being considered as disposal sites. Consideration of any waste product form, however, require extensive knowledge of the waste to be incorporated. A varity of waste types are under consideration for incorporation into a Tailored Ceramic form. This report integrates and summarizes chemical and physical characteristics of the candidate wastes. Included here are data on Savannah River Purex Process waste; Hanford bismuth phosphate, uranium recovery, redox, Purex, evaporator and residual liquid wastes; Idaho Falls calcine; Nuclear Fuel Services Purex and Thorex wastes and miscellaneous waste including estimated waste stream compositions produced by possible future commercial fuel reprocessing.

Mitchell, M.E.

1980-12-15T23:59:59.000Z

187

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

188

Waste form product characteristics  

SciTech Connect

The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

Taylor, L.L.; Shikashio, R.

1995-01-01T23:59:59.000Z

189

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2  

SciTech Connect

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

Jacobsen, P.H.

1997-09-23T23:59:59.000Z

190

Infrared Thermography in High Level Waste  

Science Conference Proceedings (OSTI)

The Savannah River Site is a Department of Energy, government-owned, company-operated industrial complex built in the 1950s to produce materials used in nuclear weapons. Five reactors were built to support the production of nuclear weapons material. Irradiated materials were moved from the reactors to one of the two chemical separation plants. In these facilities, known as ''canyons,'' the irradiated fuel and target assemblies were chemically processed to separate useful products from waste. Unfortunately, the by-product waste of nuclear material production was a highly radioactive liquid that had to be stored and maintained. In 1993 a strategy was developed to implement predictive maintenance technologies in the Liquid Waste Disposition Project Division responsible for processing the liquid waste. Responsibilities include the processing and treatment of 51 underground tanks designed to hold 750,000 to1,300,000 gallons of liquid waste and operation of a facility that vitrifies highly radioactive liquid waste into glass logs. Electrical and mechanical equipment monitored at these facilities is very similar to that found in non-nuclear industrial plants. Annual inspections are performed on electrical components, roof systems, and mechanical equipment. Troubleshooting and post installation and post-maintenance infrared inspections are performed as needed. In conclusion, regardless of the industry, the use of infrared thermography has proven to be an efficient and effective method of inspection to help improve plant safety and reliability through early detection of equipment problems.

GLEATON, DAVIDT.

2004-08-24T23:59:59.000Z

191

Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes  

SciTech Connect

The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP.

Perona, J.J.; Brown, C.H.

1993-03-01T23:59:59.000Z

192

Hazardous Waste Program (Alabama)  

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

This rule states criteria for identifying the characteristics of hazardous waste and for listing hazardous waste, lists of hazardous wastes, standards for the management of hazardous waste and...

193

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

2000-10-31T23:59:59.000Z

194

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

2000-11-01T23:59:59.000Z

195

Integrated beta and gamma radiation dose calculations for the ferrocyanide waste tanks  

SciTech Connect

This report contains the total integrated beta and gamma radiation doses in all the ferrocyanide waste tanks. It also contains estimated gamma radiation dose rates for all single-shell waste tanks containing a liquid observation well.

Parra, S.A.

1994-11-30T23:59:59.000Z

196

Proceedings: 1996 EPRI International Low Level Waste Conference  

Science Conference Proceedings (OSTI)

Due to the changing business environment, U.S. utilities are evaluating methods to improve operations while minimizing costs. EPRI's fifth annual International Low Level Waste (LLW) Conference featured 65 papers on a variety of topics. More than a third of the papers emphasized liquid-wet waste processing enhancements, new or improved technologies, and LLW program cost reduction. Other subjects included dry active waste processing cost reduction, the new DOT/NRC transport regulations, mixed waste, vitrif...

1996-12-06T23:59:59.000Z

197

Liquid waste certification plan 340 waste handling facility  

Science Conference Proceedings (OSTI)

This document addresses the discharges from the 340 Facility to the 300 Area Process Sewer and Retention Process Sewer.

HALGREN, D.L.

1999-04-21T23:59:59.000Z

198

Screening for organic solvents in Hanford waste tanks using organic vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford Site high-level radioactive waste tanks has been identified as a safety issue because expanding gases could potentially affect tank dome integrity. Organic liquid waste has been found in some of the waste tanks, but most are thought to contain only trace amounts. Due to the inhomogeneity of the waste, direct sampling of the tank waste to locate organic liquids may not conclusively demonstrate that a given tank is free of risk. However, organic vapors present above the organic liquid waste can be detected with a high degree of confidence and can be used to identify problem tanks. This report presents the results of a screening test that has been applied to 82 passively ventilated high-level radioactive waste tanks at the Hanford Site to identify those that might contain a significant amount of organic liquid waste. It includes seven tanks not addressed in the previous version of this report, Screening for Organic Solvents in Hanford Waste Tanks Using Total Non-Methane Organic Compound Vapor Concentrations. The screening test is based on a simple model of the tank headspace that estimates the effective surface area of semivolatile organic liquid waste in a tank. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Thirteen tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Most of the tanks identified as containing potentially significant quantities of organic liquid waste are in the 241-BY and 241-C tank farms, which agrees qualitatively with the fact that these tank farms received the majority of the PUREX process organic wash waste and waste organic liquids.

Huckaby, J.L.; Sklarew, D.S.

1997-09-01T23:59:59.000Z

199

Role of carbon dioxide in gas expanded liquids for removal of photoresist and etch residue.  

E-Print Network (OSTI)

??Progress in the microelectronics industry is driven by smaller and faster transistors. As feature sizes in integrated circuits become smaller and liquid chemical waste becomes… (more)

Song, Ingu

2007-01-01T23:59:59.000Z

200

Method for solidification of radioactive and other hazardous waste  

SciTech Connect

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

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

Waste= Capital.  

E-Print Network (OSTI)

??The evolution of manufacturing practices over the last century has led to the creation of excess waste during the production process, depleting resources and overwhelming… (more)

Stidham, Steve P.

2011-01-01T23:59:59.000Z

202

reuse of waste from the cutting of marble for the production of ...  

Science Conference Proceedings (OSTI)

The study involved the use of: marble waste, fluorspar, lime, hot metal, sodalita. four mixtures were made and added to a liquid hot metal, with known chemical ...

203

Quality Assurance Program Plan (QAPP) Waste Management Project  

SciTech Connect

This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

VOLKMAN, D.D.

1999-10-27T23:59:59.000Z

204

Guidance Document Cryogenic Liquids  

E-Print Network (OSTI)

liquefies them. Cryogenic liquids are kept in the liquid state at very low temperatures. Cryogenic liquids are liquid nitrogen, liquid argon and liquid helium. The different cryogens become liquids under different. In addition, when they vaporize the liquids expand to enormous volumes. For example, liquid nitrogen

205

Frostbite Theater - Liquid Nitrogen Experiments - Liquid Nitrogen...  

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

Dry Ice vs. Liquid Nitrogen Previous Video (Dry Ice vs. Liquid Nitrogen) Frostbite Theater Main Index Next Video (Shattering Pennies) Shattering Pennies Liquid Nitrogen Cooled...

206

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL #12;#12;PNNL-SA-69994 Waste Disposal Workshops: Anthrax- Contaminated Waste AM Lesperance JF Upton SL

207

Microsoft PowerPoint - S05-05_Zapp_Liquid Air Interface.ppt  

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

Liquid-Air Interface Corrosion Studies at SRS Liquid-Air Interface Corrosion Studies at SRS EM Waste Processing Technical Exchange 2010 Philip E. Zapp Savannah River National Laboratory November 17, 2010 SRNL-STI-2010-00695 Print Close 2 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Introduction Pitting Corrosion in Carbon Steel Waste Tanks Pitting Induced by Dilute Waste Solutions Dilution for feed preparation for vitrification; waste removal Focus: Pitting Susceptibility at Liquid-Air Interface Service Experience Hydroxide Depletion Model Type III tanks under constr. Tank with ventilation & cooling equip. Print Close 3 Liquid-Air Interface Corrosion Studies at SRS SRNL-STI-2010-00695 Background Pitting in carbon steel at and above liquid-air interface in dilute wastes ([Nitrate] < 1 M)

208

Categorical Exclusion 4565, Waste Management Construction Support  

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

FornI FornI Project Title: Waste Management Construction Support (4565) Program or Program Office: Y -12 Site Office Location: Oak Ridge Tennessee Project Description: This work scope is an attempt to cover the general activities that construction would perform in support of Waste Management activities. Work includes construction work performed in support of Waste Management Sustainability and Stewardship projects and programs to include: load waste into containers; open, manipulate containers; empty containers; decommission out-of-service equipment (includes removal of liquids, hazardous, and universal wastes); apply fabric and gravel to ground; transport equipment; transport materials; transport waste; remove vegetation; place barriers; place erosion controls; operate wheeled and tracked equipment; general carpentry. Work will be performed on dirt, vegetated, graveled, or paved surfaces in

209

Plasma vitrification of waste materials  

DOE Patents (OSTI)

This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The extremely high temperatures and heat transfer rates makes it possible to convert the waste-glassformer mixture into a fully vitrified molten glass product in a matter of milliseconds. The molten product may then be collected in a crucible for casting into final wasteform geometry, quenching in water, or further holding time to improve homogeneity and eliminate bubbles. 4 figs.

McLaughlin, D.F.; Dighe, S.V.; Gass, W.R.

1997-06-10T23:59:59.000Z

210

Plasma vitrification of waste materials  

DOE Patents (OSTI)

This invention provides a process wherein hazardous or radioactive wastes in the form of liquids, slurries, or finely divided solids are mixed with finely divided glassformers (silica, alumina, soda, etc.) and injected directly into the plume of a non-transferred arc plasma torch. The extremely high temperatures and heat transfer rates makes it possible to convert the waste-glassformer mixture into a fully vitrified molten glass product in a matter of milliseconds. The molten product may then be collected in a crucible for casting into final wasteform geometry, quenching in water, or further holding time to improve homogeneity and eliminate bubbles.

McLaughlin, David F. (Oakmont, PA); Dighe, Shyam V. (North Huntingdon, PA); Gass, William R. (Plum Boro, PA)

1997-01-01T23:59:59.000Z

211

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH).sub.4 to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set.

Wagh, Arun S. (Joliet, IL); Singh, Dileep (Westmont, IL)

1997-01-01T23:59:59.000Z

212

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH){sub 4} to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set. 4 figs.

Wagh, A.S.; Singh, D.

1997-07-08T23:59:59.000Z

213

Liquid ventilation  

E-Print Network (OSTI)

For 350 million years, fish have breathed liquid through gills. Mammals evolved lungs to breathe air. Rarely, circumstances can occur when a mammal needs to `turn back the clock' to breathe through a special liquid medium. This is particularly true if surface tension at the air-liquid interface of the lung is increased, as in acute lung injury. In this condition, surface tension increases because the pulmonary surfactant system is damaged, causing alveolar collapse, atelectasis, increased right-to-left shunt and hypoxaemia. 69 The aims of treatment are: (i) to offset increased forces causing lung collapse by applying mechanical ventilation with PEEP; (ii) to decrease alveolar surface tension with exogenous surfactant; (iii) to eliminate the air-liquid interface by filling the lung with a fluid in

U. Kaisers; K. P. Kelly; T. Busch

2003-01-01T23:59:59.000Z

214

Waste Hoist  

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

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 capacity, it...

215

ICPP Waste Management Technology Development Program  

SciTech Connect

As a result of the decision to curtail reprocessing at the Idaho Chemical Processing Plant (ICPP), a Spent fuel and Waste Management Technology Development plan has been implemented to identify acceptable options for disposing of the (1) sodium-bearing liquid radioactive waste, (2) radioactive calcine, and (3) irradiated spent fuel stored at the Idaho National Engineering Laboratory (INEL). The plan was developed jointly by DOE and WINCO.

Hogg, G.W.; Olson, A.L.; Knecht, D.A. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Bonkoski, M.J. [USDOE, Washington, DC (United States)

1993-01-01T23:59:59.000Z

216

Recycling of CdTe photovoltaic waste  

DOE Patents (OSTI)

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate and electrolyzing the leachate to separate Cd from Te, wherein the Te is deposits onto a cathode while the Cd remains in solution.

Goozner, Robert E. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Drinkard, Jr., William F. (Charlotte, NC)

1999-01-01T23:59:59.000Z

217

Drilling Waste Management Fact Sheet: Slurry Injection of Drilling Wastes  

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

Slurry Injection Slurry Injection Fact Sheet - Slurry Injection of Drilling Wastes Underground Injection of Drilling Wastes Several different approaches are used for injecting drilling wastes into underground formations for permanent disposal. Salt caverns are described in a separate fact sheet. This fact sheet focuses on slurry injection technology, which involves grinding or processing solids into small particles, mixing them with water or some other liquid to make a slurry, and injecting the slurry into an underground formation at pressures high enough to fracture the rock. The process referred to here as slurry injection has been given other designations by different authors, including slurry fracture injection (this descriptive term is copyrighted by a company that provides slurry injection services), fracture slurry injection, drilled cuttings injection, cuttings reinjection, and grind and inject.

218

Tank Waste Corporate Board Meeting 11/06/08 | Department of Energy  

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

11/06/08 11/06/08 Tank Waste Corporate Board Meeting 11/06/08 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 6th, 2008. Note: (Please contact Steven Ross at steven.ross@em.doe.gov for a HLW Glass Waste Loadings version with animations on slide 6). Slurry Retrieval, Pipeline Transport & Plugging and Mixing Workshop The Way Ahead - West Valley Demonstration Project High-Level Liquid Waste Tank Integrity Workshop - 2008 Savannah River Tank Waste Residuals Hanford Tank Waste Residuals HLW Glass Waste Loadings High-Level Waste Corporate Board Performance Assessment Subcommittee More Documents & Publications Tank Waste Corporate Board Meeting 11/18/10 System Planning for Low-Activity Waste at Hanford Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility

219

Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at Idaho Nuclear Technology and Engineering Center  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

Herbst, Alan K.

2002-01-02T23:59:59.000Z

220

Testing and Disposal Strategy for Secondary Wastes from Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

Herbst, Alan Keith

2002-01-01T23:59:59.000Z

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

Advanced Electrochemical Waste Forms  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

222

Chapter 30 Waste Management: General Administrative Procedures (Kentucky) |  

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

Chapter 30 Waste Management: General Administrative Procedures Chapter 30 Waste Management: General Administrative Procedures (Kentucky) Chapter 30 Waste Management: General Administrative Procedures (Kentucky) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Retail Supplier Rural Electric Cooperative State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Solar Buying & Making Electricity Wind Program Info State Kentucky Program Type Environmental Regulations Provider Department for Environmental Protection The waste management administrative regulations apply to the disposal of solid waste and the management of all liquid, semisolid, solid, or gaseous

223

Characterization of industrial process waste heat and input heat streams  

SciTech Connect

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

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

1984-05-01T23:59:59.000Z

224

Nondestructive Evaluation of Low-Level Radioactive Waste Canisters for Free-Water Content  

Science Conference Proceedings (OSTI)

Federal regulations set limits on free-standing liquid in radioactive waste containers. This report identifies four nondestructive evaluation methods that may provide nuclear power plant operators with reliable and accurate determinations of the existence and amount of free-standing liquids in low-level radioactive waste (LLW) containers.

1991-06-17T23:59:59.000Z

225

Waste Logic™: FT 2.0: Waste Logic™: FastTrack Version 2.0 with Data Link  

Science Conference Proceedings (OSTI)

Tracking and trending liquid processing performance data is critical for utility low-level waste (LLW) managers to sufficiently recognize good performance of their liquid processing systems and identify areas for improvement. In response to this challenge, EPRI's LLW group developed FastTrack. EPRI's Waste Logic™: FastTrack Version 2.0 with Data Link software for Microsoft Windows-based PC computers is a custom database software application that provides storage, retrieval, analysis, graphing, repo...

2004-10-25T23:59:59.000Z

226

November 8, 1983: Defense Waste Processing Facility | Department of Energy  

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

November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983 The Department begins construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant in South Carolina. DWPF is designed to make high-level nuclear waste into a glass-like substance, which will then be shipped to a repository. DWPF will mix borosilicate glass with the waste, heat it to 2000 degrees F, and pour the mixture into stainless steel canisters. The mixture will cool into solid glass that can be permanently stored. DWPF will immobilize the more than 34 million gallons of liquid high-level waste that have accumulated from producing defense-related nuclear materials

227

Solid Waste Program (Alabama) | Department of Energy  

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

Program (Alabama) Program (Alabama) Solid Waste Program (Alabama) < Back Eligibility Commercial Construction Developer General Public/Consumer Industrial Residential Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Alabama Program Type Environmental Regulations This article states the authority of the department, regulations for the control of unauthorized dumping, disposal fees, violations and penalties. Solid waste refers to any garbage, rubbish, construction or demolition debris, ash, or sludge from a waste treatment facility, water supply plant, or air pollution control facility, and any other discarded materials, including solid, liquid, semisolid, or contained gaseous material resulting

228

Waste treatment at the La Hague and Marcoule sites  

SciTech Connect

In this report, an overview of waste treatment and solidification facilities located at the La Hague and Marcoule sites, which are owned and/or operated by Cogema, provided. The La Hague facilities described in this report include the following: The STE3 liquid effluent treatment facility (in operation); the AD2 solid waste processing facility (also in operation); and the UCD alpha waste treatment facility (under construction). The Marcoule facilities described in this report, both of which are in operation, include the following: The STEL-EVA liquid effluent treatment facilities for the entire site; and the alpha waste incinerator of the UPI plant. This report is organized into four sections: this introduction, low-level waste treatment at La Hague, low-level waste treatment at Marcoule, and new process development. including the solvent pyrolysis process currently in the development stage for Cogema`s plants.

1995-04-01T23:59:59.000Z

229

RADIOACTIVE WASTE DISPOSAL AT KNOLLS ATOMIC POWER LABORATORY  

SciTech Connect

One of Its Monograph Series The Industrial Atom.'' Disposal of radioactive wastes from KAPL is considered with respect to the three physical categories of waste--solid, liquid, and airborne---and the three environmental recipients ---ground, surface water, and atmosphere. Solid waste-handling includes monitoring radiation levels, segregation, collection, processing, packaging, storing if necessary, and shipping to a remote burial ground at the Oak Ridge National Laboratory. Liquid waste is collected by controlled drain systems, monitored for radioactivity content, and stored if necessary or released to the Mohawk River. Exhaust air is cleaned before released and con tinuously monitored. rhe environment is monitored to assure safe and proper disposal of wastes. The cost of operations and the depreciation of facilities incurred by KAPL for disposing of radioactive contaminated waste is less than 0.7% per year of the tofal cost of the Laboratory. (auth)

Manieri, D.A.; Truran, W.H.

1958-03-01T23:59:59.000Z

230

Waste management project fiscal year 1998 multi-year work plan WBS 1.2  

SciTech Connect

The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.

Slaybaugh, R.R.

1997-08-29T23:59:59.000Z

231

Savannah River Site sample and analysis plan for Clemson Technical Center waste  

Science Conference Proceedings (OSTI)

The purpose of this sampling and analysis plan is to determine the chemical, physical and radiological properties of the SRS radioactive Polychlorinated Biphenyl (PCB) liquid waste stream, to verify that it conforms to Waste Acceptance Criteria of the Department of Energy (DOE) East Tennessee Technology Park (ETTP) Toxic Substance Control Act (TSCA) Incineration Facility. Waste being sent to the ETTP TSCA Incinerator for treatment must be sufficiently characterized to ensure that the waste stream meets the waste acceptance criteria to ensure proper handling, classification, and processing of incoming waste to meet the Waste Storage and Treatment Facility`s Operating Permits. This sampling and analysis plan is limited to WSRC container(s) of homogeneous or multiphasic radioactive PCB contaminated liquids generated in association with a treatability study at Clemson Technical Center (CTC) and currently stored at the WSRC Solid Waste Division Mixed Waste Storage Facility (MWSF).

Hagstrom, T.

1998-04-01T23:59:59.000Z

232

Proceedings: 1995 EPRI International Low-Level Waste Conference  

Science Conference Proceedings (OSTI)

EPRI's fourth annual International Low-Level Waste (LLW) Conference featured 72 papers on a variety of topics. Some of the subjects included were interim storage experiences; liquid, wet, and DAW improved processing and technology; mixed waste; decontamination; and building public trust. In addition, a nuclear industry and EPRI LLW projects update was presented.

1995-12-05T23:59:59.000Z

233

Potential dispositioning flowsheets for ICPP SNF and wastes  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Laboratory (INEL), has reprocessed irradiated nuclear fuels for the US Department of Energy (DOE) since 1953. This activity resulted mainly in the recovery of uranium and the management of the resulting wastes. The acidic radioactive high-level liquid waste was routinely stored in stainless steel tanks and then calcined to form a dry granular solid. The calcine is stored in stainless steel bins that are housed in underground concrete vaults. In April 1992, the DOE discontinued the practice of reprocessing irradiated nuclear fuels. This decision has left a legacy of 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste), 3800 cubic meters of calcine waste, and 289 metric tons of heavy metal within unprocessed spent nuclear fuel (SNF) left in inventory at the ICPP. The nation`s radioactive waste policy has been established by the Nuclear Waste Policy Act (NWPA), which requires the final disposal of SNF and radioactive waste in accordance with US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) standards. In accordance with these regulations and other legal agreements between the State of Idaho and the DOE, the DOE must, among other requirements, (1) complete a final Environmental Impact Statement by April 30, 1995, (2) evaluate and test sodium-bearing waste pre-treatment technologies, (3) select the sodium-bearing and calcine waste pre-treatment technology, if necessary, by June 1, 1995, and (4) select a technology for converting calcined waste into an appropriate disposal form by June 1, 1995.

Olson, A.L. [ed.; Anderson, P.A.; Bendixsen, C.L. [and others

1995-11-01T23:59:59.000Z

234

Waste Minimization Contents  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Waste Minimization Contents ...

235

Waste minimization/pollution prevention study of high-priority waste streams  

Science Conference Proceedings (OSTI)

Although waste minimization has been practiced by the Metals and Ceramics (M&C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division`s pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M&C staff members empowered by the Division Director to study specific waste streams.

Ogle, R.B. [comp.

1994-03-01T23:59:59.000Z

236

Waste management practices used in the attempt to protect the environment  

Science Conference Proceedings (OSTI)

Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. The term usually relates to materials produced by human activity, and is generally undertaken to reduce their effect on health, the environment ... Keywords: effect on health, environment, gaseous or radioactive substances, liquid, solid, waste materials

Zorica Bacinschi; Cristiana Zizi Rizescu; Elena Valentina Stoian; Cezarina Necula

2010-07-01T23:59:59.000Z

237

Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center FY-2001 Status Report  

SciTech Connect

The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

Herbst, A.K.; Kirkham, R.J.; Losinski, S.J.

2002-09-26T23:59:59.000Z

238

Secondary Waste Considerations for Vitrification of Sodium-Bearing Waste at the Idaho Nuclear Techology and Engineering Center FY-2001 Status Report  

SciTech Connect

The Idaho Nuclear Technology and Engineering Center (INTEC) is considering vitrification to process liquid sodium-bearing waste. Preliminary studies were completed to evaluate the potential secondary wastes from the melter off-gas clean up systems. Projected secondary wastes comprise acidic and caustic scrubber solutions, HEPA filters, activated carbon, and ion exchange media. Possible treatment methods, waste forms, and disposal sites are evaluated from radiological and mercury contamination estimates.

Herbst, Alan Keith; Kirkham, Robert John; Losinski, Sylvester John

2001-09-01T23:59:59.000Z

239

Process and installation for simultaneously producing compost and biogas from organic waste  

Science Conference Proceedings (OSTI)

A process is described for the simultaneous treatment of solid or semi-solid organic waste and liquid organic waste with a view to the simultaneous production of compost and biogas, wherein the liquid organic waste is subjected to a liquid-solid separation. The liquid phase from this separation is subjected to anaerobic fermentation in at least one closed digester, the solid phase from the liquid-solid separation is mixed with the solid or semi-solid organic waste, and the resulting mixture is subjected to aerobic fermentation at the periphery of the digester and in contact therewith. Mud, clarified liquid and gas are respectively discharged from the digester whereas compost from the aerobic fermentation of the solid or semi-solid waste is recovered at the periphery of the digester wherein the digester is characterized by two superimposed compartments, an upper compartment at low pressure and a lower compartment at high pressure, the compartments communicating together through at least one lateral pipe and through a central siphon. A means is provided for lowering the pressure of the lower compartment when the liquid reaches a predetermined level therein. An installation is described for the simultaneous treatment of solid or semi-solid organic waste and liquid waste with a view to the simultaneous production of compost and biogas. This comprises: means for separating the liquid organic waste into a solid phase and a liquid phase; at least one closed digester; means for introducing the liquid phase into the digester; means for mixing the solid phase with the solid or semi-solid waste; means for bringing the resulting mixture to the periphery of the digester in contact therewith; and means for discharging respectively from the digester the gas which is formed therein by anaerobic fermentation and the sludges which are deposited therein.

Lebesgue, Y.; Zeana, A.

1986-12-30T23:59:59.000Z

240

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

1999-10-01T23:59:59.000Z

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

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

1999-09-30T23:59:59.000Z

242

Sorbent Testing for the Solidification of Unidentified Rocky Flats Laboratory Waste Stored at the Idaho National Laboratory  

Science Conference Proceedings (OSTI)

At the request of the U.S. Department of Energy (DOE), MSE Technology Applications, Inc. (MSE) evaluated various commercially available sorbents to solidify unidentified laboratory liquids from Rocky Flats that are stored at the Idaho National Laboratory (INL). The liquids are a collection of laboratory wastes that were generated from various experiments and routine analytical laboratory activities carried out at Rocky Flats. The liquids are in bottles discovered inside of buried waste drums being exhumed from the subsurface disposal area at the Radioactive Waste Management Complex (RWMC) by the contractor, CH2M Hill Washington International (CWI). Free liquids are unacceptable at the Waste Isolation Pilot Plant (WIPP), and some of these liquids cannot be returned to the retrieval pit. Stabilization of the liquids into a solid mass will allow these materials to be sent to an appropriate disposal location. The selected sorbent or sorbent combinations should produce a stabilized mass that is capable of withstanding conditions similar to those experienced during storage, shipping, and burial. The final wasteform should release less than 1% liquid by volume per the WIPP Waste Acceptance Criteria (WAC). The absence or presence of free liquid in the solidified waste-forms was detected when tested by SW-846, Method 9095B, Paint Filter Free Liquids, and the amount of liquid released from the wasteform was determined by SW-846, Method 9096, Liquid Release Test. Reactivity testing was also conducted on the solidified laboratory liquids. (authors)

Bickford, J. [MSE Technology Applications, Inc., Butte, MT (United States); Kimmitt, R. [CH2M WG Idaho, LLC, Idaho National Laboratory, CF-601, MF-637, MS4201, Scoville, ID (United States)

2007-07-01T23:59:59.000Z

243

Support for the delisting of decontaminated liquid chemical surety materials as listed hazardous waste from specific sources (state) MD02 in COMAR 10. 51. 02. 16-1. Technical report, December 1987-February 1988  

SciTech Connect

Maryland recently enacted regulations that listed decontaminated residues of certain chemical warfare agents as hazardous wastes. The State would consider delisting if the Army document the effects of its decontamination procedures. Army specialists at U.S. Army Chemical Research, Development and Engineering Center (CRDEC), Aberdeen Proving Ground, MD, have had exhaustive experience in this area since 1918 when chemical agents were first used in combat in World War I. Competence accrued during this 70-year legacy includes destruction of laboratory and training wastes, combat decontamination, and largescale demilitarization of unserviceable and obsolete agent-filled munitions. The facts and circumstances enumerated in this document indicate that current decontamination practices are safe, scientifically valid, and result in the total destruction of agents in questions.

Durst, H.D.; Sarver, E.W.; Yurow, H.W.; Beaudry, W.T.; D'Eramo, P.A.

1988-11-01T23:59:59.000Z

244

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 BREFs and their BATs Next Generation of Waste Fired Power Plants: Getting the most out of your trash Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From

Columbia University

245

Liquid electrode  

DOE Patents (OSTI)

A dropping electrolyte electrode for use in electrochemical analysis of non-polar sample solutions, such as benzene or cyclohexane. The liquid electrode, preferably an aqueous salt solution immiscible in the sample solution, is introduced into the solution in dropwise fashion from a capillary. The electrolyte is introduced at a known rate, thus, the droplets each have the same volume and surface area. The electrode is used in making standard electrochemical measurements in order to determine properties of non-polar sample solutions.

Ekechukwu, Amy A. (Augusta, GA)

1994-01-01T23:59:59.000Z

246

Hanford Waste Physical and Rheological Properties: Data and Gaps  

SciTech Connect

The Hanford Site in Washington State manages 177 underground storage tanks containing approximately 250,000 m3 of waste generated during past defense reprocessing and waste management operations. These tanks contain a mixture of sludge, saltcake and supernatant liquids. The insoluble sludge fraction of the waste consists of metal oxides and hydroxides and contains the bulk of many radionuclides such as the transuranic components and 90Sr. The saltcake, generated by extensive evaporation of aqueous solutions, consists primarily of dried sodium salts. The supernates consist of concentrated (5-15 M) aqueous solutions of sodium and potassium salts. The 177 storage tanks include 149 single-shell tanks (SSTs) and 28 double -hell tanks (DSTs). Ultimately the wastes need to be retrieved from the tanks for treatment and disposal. The SSTs contain minimal amounts of liquid wastes, and the Tank Operations Contractor is continuing a program of moving solid wastes from SSTs to interim storage in the DSTs. The Hanford DST system provides the staging location for waste feed delivery to the Department of Energy (DOE) Office of River Protection’s (ORP) Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP is being designed and constructed to pretreat and then vitrify a large portion of the wastes in Hanford’s 177 underground waste storage tanks.

Wells, Beric E.; Kurath, Dean E.; Mahoney, Lenna A.; Onishi, Yasuo; Huckaby, James L.; Cooley, Scott K.; Burns, Carolyn A.; Buck, Edgar C.; Tingey, Joel M.; Daniel, Richard C.; Anderson, K. K.

2011-08-01T23:59:59.000Z

247

EIS-0217: Savannah River Site Waste Management | Department of Energy  

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

17: Savannah River Site Waste Management 17: Savannah River Site Waste Management EIS-0217: Savannah River Site Waste Management Summary This EIS evaluates the potential environmental impacts and costs of storing, treating, and/or disposing of liquid high-level radioactive, low-level radioactive, hazardous, mixed (radioactive and hazardous), and transuranic wastes at SRS. Public Comment Opportunities None available at this time. Documents Available for Download June 28, 2001 EIS-0217: Amended Record of Decision Savannah River Site Waste Management, Savannah River Operations Office, Aiken, South Carolina May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management May 19, 1997 EIS-0217: Supplemental Record of Decision Savannah River Site Waste Management, Savannah River Operations Office,

248

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

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

NDAA Section NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Section 3116 is currently only applicable to Idaho National Laboratory (INL) and the Savannah River Site (SRS). The other two DOE sites with similar waste (residuals remaining after cleaning out tanks and equipment that held liquid high-level waste)

249

Oklahoma Hazardous Waste Management Act (Oklahoma) | Department of Energy  

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

Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) Oklahoma Hazardous Waste Management Act (Oklahoma) < Back Eligibility Agricultural Construction Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Oklahoma Program Type Environmental Regulations Provider Oklahoma Department of Environmental Quality A hazardous waste facility permit from the Department of Environmental Quality is required to store, treat or dispose of hazardous waste materials, or to construct, own or operate any facility engaged in the operation of storing, treating or disposing of hazardous waste or storing recyclable materials. The Department shall not issue a permit for the treatment, disposal or temporary storage of any liquid hazardous waste in a

250

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect

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

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

2004-07-01T23:59:59.000Z

251

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

252

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

253

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

254

WASTE TREATMENT AND DISPOSAL PROBLEMS OF THE FUTURE NUCLEAR POWER INDUSTRY  

SciTech Connect

The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition, the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off-gases and on conversion of wastes to a more suitable form than liquid for storage. (J.R.D.)

Bruce, F.R.

1959-01-28T23:59:59.000Z

255

WRPS MEETING THE CHALLENGE OF TANK WASTE  

SciTech Connect

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

BRITTON JC

2012-02-21T23:59:59.000Z

256

Medical School Biomedical Waste  

E-Print Network (OSTI)

Medical School Biomedical Waste Labware, gloves, pipets, pipet tips Stock cultures, bacterial with or without needles, razor blades, scalpel blades) Key: Pathological waste BL1 & BL2 waste (low risk ­ LR) BL2 waste (moderate risk - MR)/BL3 waste Blood Blood Autoclave Needle box Metal Cart Must either bleach

Cooley, Lynn

257

Waste Sorting Activity Introduction  

E-Print Network (OSTI)

Waste Sorting Activity Introduction: This waste sorting game was originally designed to be one have completed the waste sorting activity quickly, no team was able to complete the waste sorting task who were unfamiliar with Dalhousie's waste management system. Goals: The primary goal of the activity

Beaumont, Christopher

258

University of Waste Procedures  

E-Print Network (OSTI)

University of Maryland Hazardous And Regulated Waste Procedures Manual Revised July 2001 #12;Review II. HAZARDOUS WASTE MANAGEMENT III. BIOLOGICAL, PATHOLOGICAL AND MEDICAL WASTE (BPMW) MANAGEMENT IV. LOW-LEVEL RADIOACTIVE WASTE (LLRW) MANAGEMENT V. EMERGENCY PROCEDURES VI. WASTE MINIMIZATION VII

Rubloff, Gary W.

259

Secondary Waste Form Development and Optimization—Cast Stone  

SciTech Connect

Washington River Protection Services is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF is a Resource Conservation and Recovery Act-permitted, multi-waste, treatment and storage unit and can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid wastes generated during operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The STU to ETF will provide the additional capacity needed for ETF to process the increased volume of secondary wastes expected to be produced by WTP.

Sundaram, S. K.; Parker, Kent E.; Valenta, Michelle M.; Pitman, Stan G.; Chun, Jaehun; Chung, Chul-Woo; Kimura, Marcia L.; Burns, Carolyn A.; Um, Wooyong; Westsik, Joseph H.

2011-07-14T23:59:59.000Z

260

Co-processing of agricultural and biomass waste with coal  

Science Conference Proceedings (OSTI)

A major thrust of our research program is the use of waste materials as co-liquefaction agents for the first-stage conversion of coal to liquid fuels. By fulfilling one or more of the roles of an expensive solvent in the direct coal liquefaction (DCL) process, the waste material is disposed off ex-landfill, and may improve the overall economics of DCL. Work in our group has concentrated on co-liquefaction with waste rubber tires, some results from which are presented elsewhere in these Preprints. In this paper, we report on preliminary results with agricultural and biomass-type waste as co-liquefaction agents.

Stiller, A.H.; Dadyburjor, D.B.; Wann, Ji-Perng [West Virginia Univ., Morgantown, WV (United States)] [and others

1995-12-31T23:59:59.000Z

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

Liquid electrode  

DOE Patents (OSTI)

A dropping electrolyte electrode is described for use in electrochemical analysis of non-polar sample solutions, such as benzene or cyclohexane. The liquid electrode, preferably an aqueous salt solution immiscible in the sample solution, is introduced into the solution in dropwise fashion from a capillary. The electrolyte is introduced at a known rate, thus, the droplets each have the same volume and surface area. The electrode is used in making standard electrochemical measurements in order to determine properties of non-polar sample solutions. 2 figures.

Ekechukwu, A.A.

1994-07-05T23:59:59.000Z

262

THEORETICAL AND EXPERIMENTAL EVALUATION OF WASTE TRANS -PORT IN SELECTED ROCKS: 1977 ANNUAL REPORT OF LBL CONTRACT NO. 45901AK. Waste Isolation Safety Assessment Program-Collection and Generation of Transport Data.  

E-Print Network (OSTI)

Liquid wastes containing greater than 100 VCi/ml of mixedLiquid waste containing less than 5 x 10~5 jjCi/ral of mixedwastes containing between 5 x 10""' and 100 yCi/ml of mixed

Apps, J.A.

2011-01-01T23:59:59.000Z

263

Thermal denitration and mineralization of waste constituents  

SciTech Connect

In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions.

Nenni, J.A.; Boardman, R.D.

1997-08-01T23:59:59.000Z

264

Radioactive tank waste remediation focus area  

SciTech Connect

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

1996-08-01T23:59:59.000Z

265

Applicability of slags as waste forms for hazardous waste  

SciTech Connect

Slags, which are a combination of glassy and ceramic phases, were produced by the Component Development and Integration Facility, using a combination of soil and metal feeds. The slags were tested for durability using accelerated test methods in both water vapor and liquid water for time periods up to 179 days. The results indicated that under both conditions there was little reaction of the slag, in terms of material released to solution, or the reaction of the slag to form secondary mineral phases. The durability of the slags tested exceeded that of current high-level nuclear glass formulations and are viable materials, for waste disposal.

Bates, J.K.; Buck, E.C.; Dietz, N.L.; Wronkiewicz, D.J.; Feng, X. [Argonne National Lab., IL (United States); Whitworth, C.; Filius, K.; Battleson, D. [MSE, Inc., Butte, MT (United States)

1994-07-01T23:59:59.000Z

266

Vitrified waste option study report  

SciTech Connect

A {open_quotes}Settlement Agreement{close_quotes} between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This report investigates vitrification treatment of all ICPP calcine, including the existing and future HLW calcine resulting from calcining liquid Sodium-Bearing Waste (SBW). Currently, the SBW is stored in the tank farm at the ICPP. Vitrification of these wastes is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the calcined waste and casting the vitrified mass into stainless steel canisters that will be ready to be moved out of the Idaho for disposal by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory (INEEL) until they are sent to a HLW national repository. The operating period for vitrification treatment will be from 2013 through 2032; all HLW will be treated and in storage by the end of 2032.

Lopez, D.A.; Kimmitt, R.R.

1998-02-01T23:59:59.000Z

267

Radioactive Waste Management (Minnesota)  

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

268

Waste Management Program  

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

Waste Management Facility ISO 14001 Registered A wide range of wastes are generated during the normal course of business at BNL. These waste streams are common to many businesses...

269

Secondary waste form testing : ceramicrete phosphate bonded ceramics.  

Science Conference Proceedings (OSTI)

The cleanup activities of the Hanford tank wastes require stabilization and solidification of the secondary waste streams generated from the processing of the tank wastes. The treatment of these tank wastes to produce glass waste forms will generate secondary wastes, including routine solid wastes and liquid process effluents. Liquid wastes may include process condensates and scrubber/off-gas treatment liquids from the thermal waste treatment. The current baseline for solidification of the secondary wastes is a cement-based waste form. However, alternative secondary waste forms are being considered. In this regard, Ceramicrete technology, developed at Argonne National Laboratory, is being explored as an option to solidify and stabilize the secondary wastes. The Ceramicrete process has been demonstrated on four secondary waste formulations: baseline, cluster 1, cluster 2, and mixed waste streams. Based on the recipes provided by Pacific Northwest National Laboratory, the four waste simulants were prepared in-house. Waste forms were fabricated with three filler materials: Class C fly ash, CaSiO{sub 3}, and Class C fly ash + slag. Optimum waste loadings were as high as 20 wt.% for the fly ash and CaSiO{sub 3}, and 15 wt.% for fly ash + slag filler. Waste forms for physical characterizations were fabricated with no additives, hazardous contaminants, and radionuclide surrogates. Physical property characterizations (density, compressive strength, and 90-day water immersion test) showed that the waste forms were stable and durable. Compressive strengths were >2,500 psi, and the strengths remained high after the 90-day water immersion test. Fly ash and CaSiO{sub 3} filler waste forms appeared to be superior to the waste forms with fly ash + slag as a filler. Waste form weight loss was {approx}5-14 wt.% over the 90-day immersion test. The majority of the weight loss occurred during the initial phase of the immersion test, indicative of washing off of residual unreacted binder components from the waste form surface. Waste forms for ANS 16.1 leach testing contained appropriate amounts of rhenium and iodine as radionuclide surrogates, along with the additives silver-loaded zeolite and tin chloride. The leachability index for Re was found to range from 7.9 to 9.0 for all the samples evaluated. Iodine was below detection limit (5 ppb) for all the leachate samples. Further, leaching of sodium was low, as indicated by the leachability index ranging from 7.6-10.4, indicative of chemical binding of the various chemical species. Target leachability indices for Re, I, and Na were 9, 11, and 6, respectively. Degradation was observed in some of the samples post 90-day ANS 16.1 tests. Toxicity characteristic leaching procedure (TCLP) results showed that all the hazardous contaminants were contained in the waste, and the hazardous metal concentrations were below the Universal Treatment Standard limits. Preliminary scale-up (2-gal waste forms) was conducted to demonstrate the scalability of the Ceramicrete process. Use of minimal amounts of boric acid as a set retarder was used to control the working time for the slurry. Flexibility in treating waste streams with wide ranging compositional make-ups and ease of process scale-up are attractive attributes of Ceramicrete technology.

Singh, D.; Ganga, R.; Gaviria, J.; Yusufoglu, Y. (Nuclear Engineering Division); ( ES)

2011-06-21T23:59:59.000Z

270

Biological upgrading of coal liquids. Final report  

SciTech Connect

A large number of bacterial enrichments have been developed for their ability to utilize nitrogen and sulfur in coal liquids and the model compound naphtha. These bacteria include the original aerobic bacteria isolated from natural sources which utilize heteroatom compounds in the presence of rich media, aerobic nitrogen-utilizing bacteria and denitrifying bacteria. The most promising isolates include Mix M, a mixture of aerobic bacteria; ER15, a pyridine-utilizing isolate; ERI6, an aniline-utilizing isolate and a sewage sludge isolate. Culture optimization experiments have led to these bacteria being able to remove up to 40 percent of the sulfur and nitrogen in naphtha and coal liquids in batch culture. Continuous culture experiments showed that the coal liquid is too toxic to the bacteria to be fed without dilution or extraction. Thus either semi-batch operation must be employed with continuous gas sparging into a batch of liquid, or acid extracted coal liquid must be employed in continuous reactor studies with continuous liquid flow. Isolate EN-1, a chemical waste isolate, removed 27 percent of the sulfur and 19 percent of the nitrogen in fed batch experiments. Isolate ERI5 removed 28 percent of the nitrogen in coal liquid in 10 days in fed batch culture. The sewage sludge isolate removed 22.5 percent of the sulfur and 6.5 percent of the nitrogen from extracted coal liquid in continuous culture, and Mix M removed 17.5 percent of the nitrogen from medium containing extracted coal liquid. An economic evaluation has been prepared for the removal of nitrogen heteroatom compounds from Wilsonville coal liquid using acid extraction followed by fermentation. Similar technology can be developed for sulfur removal. The evaluation indicates that the nitrogen heteroatom compounds can be removed for $0.09/lb of coal liquid treated.

NONE

1995-02-01T23:59:59.000Z

271

Waste Logic Decommissioning Waste Manager 2.0 Users Manual  

Science Conference Proceedings (OSTI)

The Decommissioning Waste Manager, part of EPRI's Waste Logic series of computer programs, analyzes decommissioning waste cost and volume reduction strategies with the intent of quantifying the existing waste management program for any given waste generator.

2001-10-29T23:59:59.000Z

272

Secondary Waste Form Down Selection Data Package – Ceramicrete  

SciTech Connect

As part of high-level waste pretreatment and immobilized low activity waste processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed in the Integrated Disposal Facility. Currently, four waste forms are being considered for stabilization and solidification of the liquid secondary wastes. These waste forms are Cast Stone, Ceramicrete, DuraLith, and Fluidized Bed Steam Reformer. The preferred alternative will be down selected from these four waste forms. Pacific Northwest National Laboratory is developing data packages to support the down selection process. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilization and solidification of the liquid secondary wastes. The information included will be based on information available in the open literature and from data obtained from testing currently underway. This data package is for the Ceramicrete waste form. Ceramicrete is a relatively new engineering material developed at Argonne National Laboratory to treat radioactive and hazardous waste streams (e.g., Wagh 2004; Wagh et al. 1999a, 2003; Singh et al. 2000). This cement-like waste form can be used to treat solids, liquids, and sludges by chemical immobilization, microencapsulation, and/or macroencapsulation. The Ceramicrete technology is based on chemical reaction between phosphate anions and metal cations to form a strong, dense, durable, low porosity matrix that immobilizes hazardous and radioactive contaminants as insoluble phosphates and microencapsulates insoluble radioactive components and other constituents that do not form phosphates. Ceramicrete is a type of phosphate-bonded ceramic, which are also known as chemically bonded phosphate ceramics. The Ceramicrete binder is formed through an acid-base reaction between calcined magnesium oxide (MgO; a base) and potassium hydrogen phosphate (KH{sub 2}PO{sub 4}; an acid) in aqueous solution. The reaction product sets at room temperature to form a highly crystalline material. During the reaction, the hazardous and radioactive contaminants also react with KH{sub 2}PO{sub 4} to form highly insoluble phosphates. In this data package, physical property and waste acceptance data for Ceramicrete waste forms fabricated with wastes having compositions that were similar to those expected for secondary waste effluents, as well as secondary waste effluent simulants from the Hanford Tank Waste Treatment and Immobilization Plant were reviewed. With the exception of one secondary waste form formulation (25FA+25 W+1B.A. fabricated with the mixed simulant did not meet the compressive strength requirement), all the Ceramicrete waste forms that were reviewed met or exceeded Integrated Disposal Facility waste acceptance criteria.

Cantrell, Kirk J.; Westsik, Joseph H.

2011-08-31T23:59:59.000Z

273

Chemical aspects of nuclear waste treatment  

SciTech Connect

The chemical aspects of the treatment of gaseous, liquid, and solid wastes are discussed in overview. The role of chemistry and the chemical reactions in waste treatment are emphasized. Waste treatment methods encompass the chemistry of radioactive elements from every group of the periodic table. In most streams, the radioactive elements are present in relatively low concentrations and are often associated with moderately large amounts of process reagents, or materials. In general, it is desirable that waste treatment methods are based on chemistry that is selective for the concentration of radionuclides and does not require the addition of reagents that contribute significantly to the volume of the treated waste. Solvent extraction, ion exchange, and sorbent chemistry play a major role in waste treatment because of the high selectivity provided for many radionuclides. This paper deals with the chemistry of the onsite treatment methods that is typically used at nuclear installations and is not concerned with the chemistry of the various alternative materials proposed for long-term storage of nuclear wastes. The chemical aspects are discussed from a generic point of view in which the chemistry of important radionuclides is emphasized.

Bond, W.D.

1980-01-01T23:59:59.000Z

274

Solid Waste (New Mexico)  

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

The New Mexico Environment Department's Solid Waste Bureau manages solid waste in the state. The Bureau implements and enforces the rules established by the Environmental Improvement Board.

275

Industrial Waste Generation  

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

9) Page 2 of 7 Industrial Waste Generation Work with Engineered Nanomaterials Power Consumption Historical Contamination (groundwater, soil) Hazardous Waste Generation Atmospheric...

276

Recycling Electronic Waste - Website  

Science Conference Proceedings (OSTI)

Jun 18, 2010 ... Joined: 2/13/2007. Below is a link to a website that has articles on recycling electronic waste. http://www.scientificamerican....ectronic-waste- ...

277

International Trade with Waste.  

E-Print Network (OSTI)

?? In this thesis, trade with waste between developed countries and the third world will be presented to analyze whether waste?trading can create a possible… (more)

Willén, Jenny

2008-01-01T23:59:59.000Z

278

Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith  

SciTech Connect

To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that all the waste forms had leachability indices better than the target LI > 9 for technetium; (2) Rhenium diffusivity: Cast Stone 2M specimens, when tested using EPA 1315 protocol, had leachability indices better than the target LI > 9 for technetium based on rhenium as a surrogate for technetium. All other waste forms tested by ANSI/ANS 16.1, ASTM C1308, and EPA 1315 test methods had leachability indices that were below the target LI > 9 for Tc based on rhenium release. These studies indicated that use of Re(VII) as a surrogate for 99Tc(VII) in low temperature secondary waste forms containing reductants will provide overestimated diffusivity values for 99Tc. Therefore, it is not appropriate to use Re as a surrogate 99Tc in future low temperature waste form studies. (3) Iodine diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that the three waste forms had leachability indices that were below the target LI > 11 for iodine. Therefore, it may be necessary to use a more effective sequestering material than silver zeolite used in two of the waste forms (Ceramicrete and DuraLith); (4) Sodium diffusivity: All the waste form specimens tested by the three leach methods (ANSI/ANS 16.1, ASTM C1308, and EPA 1315) exceeded the target LI value of 6; (5) All three leach methods (ANS 16.1, ASTM C1308 and EPA 1315) provided similar 99Tc diffusivity values for both short-time transient diffusivity effects as well as long-term ({approx}90 days) steady diffusivity from each of the three tested waste forms (Cast Stone 2M, Ceramicrete and DuraLith). Therefore, any one of the three methods can be used to determine the contaminant diffusivities from a selected waste form.

Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

2011-08-12T23:59:59.000Z

279

Waste analysis plan for central waste complex  

SciTech Connect

This waste analysis plan (WAP) has been prepared for the Central Waste Complex which is located in the 200 West Area of the Hanford Facility, Richland, Washington. This WAP documents the methods used to characterize, and obtain and analyze representative samples of waste managed at this unit.

Weston, N.L.

1996-09-20T23:59:59.000Z

280

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

Science Conference Proceedings (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

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

UK Energy Statistics: Renewables and Waste, Commodity Balances (2010) |  

Open Energy Info (EERE)

403 403 Varnish cache server Browse Upload data GDR 429 Throttled (bot load) Error 429 Throttled (bot load) Throttled (bot load) Guru Meditation: XID: 2142288403 Varnish cache server UK Energy Statistics: Renewables and Waste, Commodity Balances (2010) Dataset Summary Description Annual commodity balances (supply, consumption) for renewables and waste in the UK from 1998 to 2009. Published as part of the Digest of UK energy statistics (DUKES), by the UK Department of Energy & Climate Change (DECC). Waste includes: wood waste, farm waste, sewage gas, landfill gas, waste and tyres. Renewables includes: wood, plant-based biomass, geothermal and active solar heat, hydro, wind, wave and tidal, and liquid biofuels. These data were used to produce Tables 7.1 to 7.3 in the Digest of United Kingdom Energy Statistics 2010 (available: http://decc.gov.uk/assets/decc/Statistics/publications/dukes/348-dukes-2...).

282

Savannah River Site Contractor Achieves Tank Waste Milestone | Department  

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

Contractor Achieves Tank Waste Milestone Contractor Achieves Tank Waste Milestone Savannah River Site Contractor Achieves Tank Waste Milestone February 2, 2012 - 12:00pm Addthis Pictured here is a component of the Interim Salt Disposition Process — known as Modular Caustic Side Solvent Extraction Unit (MCU) — that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. Pictured here is a component of the Interim Salt Disposition Process - known as Modular Caustic Side Solvent Extraction Unit (MCU) - that helped Savannah River Remediation process more than 500,000 gallons of salt waste since October last year, a contract milestone. AIKEN, S.C. - The Savannah River Site's liquid waste contractor recently achieved a contract milestone by processing 500,000 gallons of

283

The Hanford site tank waste remediation system technical strategy  

SciTech Connect

The US Department of Energy`s Hanford Site, located in southeastern Washington State, has the most diverse and largest amount of radioactive tank the United States. High-level radioactive waste has been stored in large underground tanks since 1944. Approximately 230,000 m{sup 3} (61 Mgal) of caustic liquids, slurries, saltcakes, and sludges have accumulated in 177 tanks. In addition, significant amounts of {sup 90}S and {sup 137}Cs were removed from the tank waste, converted to salts, doubly encapsulated in metal containers, and stored in water basins. A Tank Waste Remediation System Program was established by the US DOE Energy in 1991 to safely manage and immobilize these wastes for permanent disposal of the high-level waste fraction in a geologic repository. The technical strategy to manage and dispose of these wastes has been revised and successfully negotiated with the regulatory agencies.

Wodrich, D.D.

1994-04-01T23:59:59.000Z

284

Glossary Term - Liquid Nitrogen  

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

Lepton Previous Term (Lepton) Glossary Main Index Next Term (Mercury) Mercury Liquid Nitrogen Liquid nitrogen boils in a frying pan on a desk. The liquid state of the element...

285

Liquid foams of graphene  

E-Print Network (OSTI)

Liquid foams are dispersions of bubbles in a liquid. Bubbles are stabilized by foaming agents that position at the interface between the gas and the liquid. Most foaming agents, such as the commonly used sodium dodecylsulfate, ...

Alcazar Jorba, Daniel

2012-01-01T23:59:59.000Z

286

Recycling of CdTe photovoltaic waste  

DOE Patents (OSTI)

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the metals in dilute nitric acid, leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate, adding a calcium containing base to the leachate to precipitate Cd and Te, separating the precipitated Cd and Te from the leachate, and recovering the calcium-containing base.

Goozner, Robert E. (Charlotte, NC); Long, Mark O. (Charlotte, NC); Drinkard, Jr., William F. (Charlotte, NC)

1999-04-27T23:59:59.000Z

287

Recycling of CdTe photovoltaic waste  

DOE Patents (OSTI)

A method for extracting and reclaiming metals from scrap CdTe photovoltaic cells and manufacturing waste by leaching the metals in dilute nitric acid, leaching the waste with a leaching solution comprising nitric acid and water, skimming any plastic material from the top of the leaching solution, separating the glass substrate from the liquid leachate, adding a calcium containing base to the leachate to precipitate Cd and Te, separating the precipitated Cd and Te from the leachate, and recovering the calcium-containing base. 3 figs.

Goozner, R.E.; Long, M.O.; Drinkard, W.F. Jr.

1999-04-27T23:59:59.000Z

288

Actinide removal from nitric acid waste streams  

SciTech Connect

Actinide separations research at the Rocky Flats Plant (RFP) has found ways to significantly improve plutonium secondary recovery and americium removal from nitric acid waste streams generated by plutonium purification operations. Capacity and breakthrough studies show anion exchange with Dowex 1x4 (50 to 100 mesh) to be superior for secondary recovery of plutonium. Extraction chromatography with TOPO(tri-n-octyl-phosphine oxide) on XAD-4 removes the final traces of plutonium, including hydrolytic polymer. Partial neutralization and solid supported liquid membrane transfer removes americium for sorption on discardable inorganic ion exchangers, potentially allowing for non-TRU waste disposal.

Muscatello, A.C.; Navratil, J.D.

1986-01-01T23:59:59.000Z

289

Engineering-Scale Demonstration of DuraLith and Ceramicrete Waste Forms  

Science Conference Proceedings (OSTI)

To support the selection of a waste form for the liquid secondary wastes from the Hanford Waste Immobilization and Treatment Plant, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing on four candidate waste forms. Two of the candidate waste forms have not been developed to scale as the more mature waste forms. This work describes engineering-scale demonstrations conducted on Ceramicrete and DuraLith candidate waste forms. Both candidate waste forms were successfully demonstrated at an engineering scale. A preliminary conceptual design could be prepared for full-scale production of the candidate waste forms. However, both waste forms are still too immature to support a detailed design. Formulations for each candidate waste form need to be developed so that the material has a longer working time after mixing the liquid and solid constituents together. Formulations optimized based on previous lab studies did not have sufficient working time to support large-scale testing. The engineering-scale testing was successfully completed using modified formulations. Further lab development and parametric studies are needed to optimize formulations with adequate working time and assess the effects of changes in raw materials and process parameters on the final product performance. Studies on effects of mixing intensity on the initial set time of the waste forms are also needed.

Josephson, Gary B.; Westsik, Joseph H.; Pires, Richard P.; Bickford, Jody; Foote, Martin W.

2011-09-23T23:59:59.000Z

290

Safety assessment of the liquid-fed ceramic melter process  

Science Conference Proceedings (OSTI)

As part of its development program for the solidification of high-level nuclear waste, Pacific Northwest Laboratory assessed the safety issues for a complete liquid-fed ceramic melter (LFCM) process. The LFCM process, an adaption of commercial glass-making technology, is being developed to convert high-level liquid waste from the nuclear fuel cycle into glass. This safety assessment uncovered no unresolved or significant safety problems with the LFCM process. Although in this assessment the LFCM process was not directly compared with other solidification processes, the safety hazards of the LFCM process are comparable to those of other processes. The high processing temperatures of the glass in the LFCM pose no additional significant safety concerns, and the dispersible inventory of dried waste (calcine) is small. This safety assessment was based on the nuclear power waste flowsheet, since power waste is more radioactive than defense waste at the time of solidification, and all accident conditions for the power waste would have greater radiological consequences than those for defense waste. An exhaustive list of possible off-standard conditions and equipment failures was compiled. These accidents were then classified according to severity of consequence and type of accident. Radionuclide releases to the stack were calculated for each group of accidents using conservative assumptions regarding the retention and decontamination features of the process and facility. Two recommendations that should be considered by process designers are given in the safety assessment.

Buelt, J.L.; Partain, W.L.

1980-08-01T23:59:59.000Z

291

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect

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

NONE

1994-12-31T23:59:59.000Z

292

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

Science Conference Proceedings (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

293

Breathing liquid oxygen  

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

question is interesting though because it would be desirable to breath liquid instead of gas under certain conditions. Special liquids are being designed to carry dissolved...

294

Liquid Nitrogen Ice Cream  

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

Liquid Nitrogen Ice Cream If you have access to liquid nitrogen and the proper safety equipment and training, try this in place of your normal cryogenics demonstration Download...

295

Radiological Issues for the Thin Liquid Walls of ARIES-IFE Study  

SciTech Connect

Heavy ion beam driven inertial fusion energy (IFE) power plants employ liquid wall materials to protect the structure against the energetic x-rays, ions, and debris emitted from the target following each shot. The objective of this assessment is to identify the radiological issues of the candidate liquid wall materials (Pb, LiPb, Sn, and Flibe) using the ARIES-IFE radiation chamber environment. The issues to be addressed include the radioactivity level and liquid waste minimization for waste management. Specifically, the liquids are evaluated with regard to the Class C limitation for waste disposal, a top-level requirement for all ARIES power plant designs. Two extreme cases were analyzed; the worst case is separation of the liquid wall material (highest radiation exposure) and the breeder (lowest radiation exposure), and the best case is the mixing of the two liquid streams. Both tangential and porous wall injection schemes were examined. Pb and LiPb are more radioactive than Sn and Flibe. For the liquid breeder system, the porous wall injection scheme with mixed liquid flows results in the lowest waste disposal rating and smallest waste stream achieved in our study.

El-Guebaly, L. [University of Wisconsin-Madison (United States); Wilson, P. [University of Wisconsin-Madison (United States); Henderson, D. [University of Wisconsin-Madison (United States); Waganer, L. [Boeing Company (United States); Raffray, R. [University of California-San Diego (United States)

2003-09-15T23:59:59.000Z

296

Supplement Analysis for Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) (6/23/04)  

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

Disposal of Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is waste that contains alpha particle-emitting radionuclides with atomic numbers greater than uranium (92) and half-lives greater than 20 years, in concentrations greater than 100 nanocuries per gram of waste. Some TRU wastes are mixed with polychlorinated biphenyls (PCBs) (referred to as PCB-commingled TRU waste). PCBs exist in DOE's TRU waste as mixtures of synthetic organic chemicals with physical properties ranging from oily liquids to waxy solids. Exposure to PCBs can result in adverse health effects. For example, PCBs in blood or in fatty tissue as a result of inhalation, ingestion, or dermal absorption may cause reproductive effects,

297

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

298

A full featured monitoring, control and data management system for liquid metal coolant loops  

Science Conference Proceedings (OSTI)

The heavy liquid metals (HLM) lead and lead-bismuth are considered as coolant and spallation material in accelerator driven systems (ADS) for nuclear waste transmutation. To investigate the viability of HLM cooled reactor systems the Karlsruhe Lead Laboratory ...

Cord H. Lefhalm; Viktor Krieger

2005-06-01T23:59:59.000Z

299

Data Package for Secondary Waste Form Down-Selection—Cast Stone  

SciTech Connect

Available literature on Cast Stone and Saltstone was reviewed with an emphasis on determining how Cast Stone and related grout waste forms performed in relationship to various criteria that will be used to decide whether a specific type of waste form meets acceptance criteria for disposal in the Integrated Disposal Facility (IDF) at Hanford. After the critical review of the Cast Stone/Saltstone literature, we conclude that Cast Stone is a good candidate waste form for further consideration. Cast stone meets the target IDF acceptance criteria for compressive strength, no free liquids, TCLP leachate are below the UTS permissible concentrations and leach rates for Na and Tc-99 are suiteably low. The cost of starting ingredients and equipment necessary to generate Cast Stone waste forms with secondary waste streams are low and the Cast Stone dry blend formulation can be tailored to accommodate variations in liquid waste stream compositions. The database for Cast Stone short-term performance is quite extensive compared to the other three candidate waste solidification processes. The solidification of liquid wastes in Cast Stone is a mature process in comparison to the other three candidates. Successful production of Cast Stone or Saltstone has been demonstrated from lab-scale monoliths with volumes of cm3 through m3 sized blocks to 210-liter sized drums all the way to the large pours into vaults at Savannah River. To date over 9 million gallons of low activity liquid waste has been solidified and disposed in concrete vaults at Savannah River.

Serne, R. Jeffrey; Westsik, Joseph H.

2011-09-05T23:59:59.000Z

300

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

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

High level waste facilities -- Continuing operation or orderly shutdown  

SciTech Connect

Two options for Environmental Impact Statement No action alternatives describe operation of the radioactive liquid waste facilities at the Idaho Chemical Processing Plant at the Idaho National Engineering and Environmental Laboratory. The first alternative describes continued operation of all facilities as planned and budgeted through 2020. Institutional control for 100 years would follow shutdown of operational facilities. Alternatively, the facilities would be shut down in an orderly fashion without completing planned activities. The facilities and associated operations are described. Remaining sodium bearing liquid waste will be converted to solid calcine in the New Waste Calcining Facility (NWCF) or will be left in the waste tanks. The calcine solids will be stored in the existing Calcine Solids Storage Facilities (CSSF). Regulatory and cost impacts are discussed.

Decker, L.A.

1998-04-01T23:59:59.000Z

302

Thirty-year solid waste generation forecast for facilities at SRS  

SciTech Connect

The information supplied by this 30-year solid waste forecast has been compiled as a source document to the Waste Management Environmental Impact Statement (WMEIS). The WMEIS will help to select a sitewide strategic approach to managing present and future Savannah River Site (SRS) waste generated from ongoing operations, environmental restoration (ER) activities, transition from nuclear production to other missions, and decontamination and decommissioning (D&D) programs. The EIS will support project-level decisions on the operation of specific treatment, storage, and disposal facilities within the near term (10 years or less). In addition, the EIS will provide a baseline for analysis of future waste management activities and a basis for the evaluation of the specific waste management alternatives. This 30-year solid waste forecast will be used as the initial basis for the EIS decision-making process. The Site generates and manages many types and categories of waste. With a few exceptions, waste types are divided into two broad groups-high-level waste and solid waste. High-level waste consists primarily of liquid radioactive waste, which is addressed in a separate forecast and is not discussed further in this document. The waste types discussed in this solid waste forecast are sanitary waste, hazardous waste, low-level mixed waste, low-level radioactive waste, and transuranic waste. As activities at SRS change from primarily production to primarily decontamination and decommissioning and environmental restoration, the volume of each waste s being managed will change significantly. This report acknowledges the changes in Site Missions when developing the 30-year solid waste forecast.

Not Available

1994-07-01T23:59:59.000Z

303

Frostbite Theater - Liquid Oxygen vs. Liquid Nitrogen - Liquid Oxygen and  

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

Cells vs. Liquid Nitrogen! Cells vs. Liquid Nitrogen! Previous Video (Cells vs. Liquid Nitrogen!) Frostbite Theater Main Index Next Video (Paramagnetism) Paramagnetism Liquid Oxygen and Fire! What happens when nitrogen and oxygen are exposed to fire? [ Show Transcript ] Announcer: Frostbite Theater presents... Cold Cuts! No baloney! Joanna and Steve: Just science! Joanna: Hi! I'm Joanna! Steve: And I'm Steve! Joanna: And this is a test tube of liquid nitrogen! Steve: And this is a test tube of liquid oxygen! Joanna: Let's see what happens when nitrogen and oxygen are exposed to fire. Steve: Fire?! Joanna: Yeah! Steve: Really?! Joanna: Why not! Steve: Okay! Joanna: As nitrogen boils, it changes into nitrogen gas. Because it's so cold, it's denser than the air in the room. The test tube fills up with

304

Actinide separations by supported liquid membranes  

SciTech Connect

The work has demonstrated that actinide removal from synthetic waste solutions using both flat-sheet and hollow-fiber SLM's is a feasible chemical process at the laboratory scale level. The process is characterized by the typical features of SLM's processes: very small quantities of extractant required; the potential for operations with high feed/strip volume ratios, resulting in a corresponding concentration factor of the actinides; and simplicity of operation. Major obstacles to the implementation of the SLM technology to the decontamination of liquid nuclear wastes are the probable low resistance of polypropylene supports to high radiation fields, which may prevent the application to high-level nuclear wastes; the unknown lifetime of the SLM; and the high Na content of the separated actinide solution.

Danesi, P.R.; Horwitz, E.P.; Rickert, P.; Chiarizia, R.

1984-01-01T23:59:59.000Z

305

New and Underutilized Technology: Liquid Desiccant Air Conditioner |  

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

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

306

Solid Waste Disposal, Hazardous Waste Management Act, Underground...  

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

Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Eligibility...

307

Business Plan : Residential Solid Waste Collection.  

E-Print Network (OSTI)

??Residential solid waste means all the solid wastes produced in household level, which includes bio-waste, metal, mixed wastes, organic and inorganic waste. The inability of… (more)

Mazengo, Dorice

2013-01-01T23:59:59.000Z

308

Preconceptual design study for solidifying high-level waste: Appendices A, B and C West Valley Demonstration Project  

SciTech Connect

This report presents a preconceptual design study for processing radioactive high-level liquid waste presently stored in underground tanks at Western New York Nuclear Service Center (WNYNSC) near West Valley, New York, and for incorporating the radionculides in that waste into a solid. The high-level liquid waste accumulated from the operation of a chemical reprocessing plant by the Nuclear Fuel Services, Inc. from 1966 to 1972. The high-level liquid waste consists of approximately 560,000 gallons of alkaline waste from Purex process operations and 12,000 gallons of acidic (nitric acid) waste from one campaign of processing thoria fuels by a modified Thorex process (during this campaign thorium was left in the waste). The alkaline waste contains approximately 30 million curies and the acidic waste contains approximately 2.5 million curies. The reference process described in this report is concerned only with chemically processing the high-level liquid waste to remove radionuclides from the alkaline supernate and converting the radionuclide-containing nonsalt components in the waste into a borosilicate glass.

Hill, O.F. (comp.)

1981-04-01T23:59:59.000Z

309

Cementitious waste option scoping study report  

SciTech Connect

A Settlement Agreement between the Department of Energy (DOE) and the State of Idaho mandates that all high-level radioactive waste (HLW) now stored at the Idaho Chemical Processing Plant (ICPP) on the Idaho National Engineering and Environmental Laboratory (INEEL) will be treated so that it is ready to be moved out of Idaho for disposal by a target date of 2035. This study investigates the nonseparations Cementitious Waste Option (CWO) as a means to achieve this goal. Under this option all liquid sodium-bearing waste (SBW) and existing HLW calcine would be recalcined with sucrose, grouted, canisterized, and interim stored as a mixed-HLW for eventual preparation and shipment off-Site for disposal. The CWO waste would be transported to a Greater Confinement Disposal Facility (GCDF) located in the southwestern desert of the US on the Nevada Test Site (NTS). All transport preparation, shipment, and disposal facility activities are beyond the scope of this study. CWO waste processing, packaging, and interim storage would occur over a 5-year period between 2013 and 2017. Waste transport and disposal would occur during the same time period.

Lee, A.E.; Taylor, D.D.

1998-02-01T23:59:59.000Z

310

Progress Continues Toward Closure of Two Underground Waste Tanks at Savannah River Site  

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

AIKEN, S.C. – The EM program at the Savannah River Site (SRS) is filling two radioactive liquid waste tanks with a cement-like grout in an effort to operationally close them this fall.

311

BY tank farm waste inventory and transfer data ITS-2 operation during January To June 1972  

Science Conference Proceedings (OSTI)

Daily record inventory of pumping activities and liquid level changes including occasional operations comments for the BY Tank Farm. Waste inventory and transfer data for ITS-2 operation during January to June 1972.

Reich, F.R., Westinghouse Hanford

1996-08-02T23:59:59.000Z

312

Planning for the Management and Disposition of Newly Generated TRU Waste from REDC  

SciTech Connect

This paper describes the waste characteristics of newly generated transuranic waste from the Radiochemical Engineering and Development Center at the Oak Ridge National Laboratory and the basic certification structure that will be proposed by the University of Tennessee-Battelle and Bechtel Jacobs Company LLC to the Waste Isolation Pilot Plant for this waste stream. The characterization approach uses information derived from the active production operations as acceptable knowledge for the Radiochemical Engineering and Development Center transuranic waste. The characterization approach includes smear data taken from processing and waste staging hot cells, as well as analytical data on product and liquid waste streams going to liquid waste disposal. Bechtel Jacobs Company and University of Tennessee-Battelle are currently developing the elements of a Waste Isolation Pilot Plant-compliant program with a plan to be certified by the Waste Isolation Pilot Plant for shipment of newly generated transuranic waste in the next few years. The current activities include developing interface plans, program documents, and waste stream specific procedures.

Coffey, D. E.; Forrester, T. W.; Krause, T.

2002-02-26T23:59:59.000Z

313

Conversion of cellulosic and waste polymer material to gasoline  

DOE Green Energy (OSTI)

The present status and future plans for a project to convert cellulosic (biomass) and waste synthetic polymer materials to quality liquid fuels is presented. A thermal gasification approach is utilized followed by catalytic liquid fuels synthesis steps. Potential products include a medium quality substitute for natural gas or liquid fuel equivalents of diesel fuel, kerosene or high octane gasoline. The process appears very flexible with regard to ability to handle different sources of feedstock. Results to date indicate quality products can be produced. Product yields need to be improved with the main thrust centered on improvement of pyrolysis gas composition. This will be a major effort in the new contract period. Other items to be addressed are study of alternate economic feedstocks, waste stream characterization, and liquid fuels synthesis and tailoring with particular attention on the effects of alternate feedstocks. A description of a proposed 10 ton/day pilot plant is presented with flow sheet, material balance and cost estimates.

Kuester, J.L.

1979-03-28T23:59:59.000Z

314

Waste analysis plan for 222-S dangerous and mixed waste storage area  

Science Conference Proceedings (OSTI)

The 222-S Laboratory Complex, in the southeast corner of the 200 West Area, consists of the 222-S Laboratory, the 222-SA Standards Laboratory, and several ancillary facilities. Currently, 222-S Laboratory activities are in supporting efforts to characterize the waste stored in the 200 Areas single shell and double shell tanks. Besides this work, the laboratory also provides analytical services for waste-management processing plants, Tank Farms, B Plant, 242-A Evaporator Facility, Plutonium-Uranium Extraction Plant, Plutonium Finishing Plant, Uranium-Oxide Plant, Waste Encapsulation Storage Facility, environmental monitoring and surveillance programs, and activities involving essential materials and research and development. One part of the 222-SA Laboratory prepares nonradioactive standards for the 200 Area laboratories. The other section of the laboratory is used for cold (nonradioactive) process development work and standards preparation. The 219-S Waste Handling Facility has three storage tanks in which liquid acid waste from 222-S can be received, stored temporarily, and neutralized. From this facility, neutralized waste, containing radionuclides, is transferred to the Tank Farms. A 700-gallon sodium-hydroxide supply tank is also located in this facility. This plan provides the methods used to meet the acceptance criteria required by the 204-AR Waste Receiving Facility.

Warwick, G.J.

1994-08-30T23:59:59.000Z

315

Waste Management Quality Assurance Plan  

E-Print Network (OSTI)

Raya James Johnson Rad/Mixed Waste** Steve Bakhtiar – Leadhazardous, radioactive, and mixed waste at the Hazardoustraining. Radioactive and mixed waste generators must take

Waste Management Group

2006-01-01T23:59:59.000Z

316

Waste Minimization Plan Prepared by  

E-Print Network (OSTI)

Waste Minimization Plan Prepared by: Environmental Health and Safety Department Revised February 2012 #12;Waste Minimization Plan Table of Contents Policy Statement........................................................... 3 Centralized Waste Management Program

317

Hazardous Waste Act (New Mexico)  

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

"Hazardous waste" means any solid waste or combination of solid wastes that because of their quantity, concentration or physical, chemical or infectious characteristics may:  cause or significantly...

318

ICPP waste management technology development program  

SciTech Connect

A program has been implemented at the Idaho Chemical Processing Plant (ICPP) to identify technologies for disposing of sodium-bearing liquid radioactive waste, radioactive calcine, and irradiated spent fuel stored at the Idaho National Engineering Laboratory (INEL). The sodium bearing waste and calcine, have resulted from ICPP reprocessing operations conducted since 1953. The irradiated spent fuel consists of various fuel compositions and ranges from complete fuel elements to fuel pieces for which no reprocessing flowsheet had been identified. The program includes a very strong systems analysis program to assure complete consideration of all issues (technical, economic, safety, environmental, etc.) affecting final disposal of the waste and spent fuel. A major goal of the program is to assure the final implementation is environmentally acceptable, ensures public and worker safety, and is economically feasible.

Hogg, G.W.; Olson, A.L.; Knecht, D.A. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States); Bonkoski, M.J. [USDOE Idaho Field Office, Idaho Falls, ID (United States)

1993-06-01T23:59:59.000Z

319

Performance estimates for waste treatment pyroprocesses in ATW  

SciTech Connect

The author has identified several pyrometallurgical processes for the conceptual ATW waste treatment cycle. These processes include reductive extraction, electrowinning and electrorefining, which constitute some versatile treatment cycles for liquid-metal based and molten-salt based waste forms when they are properly integrated. This paper examines the implementation of these processes and the achievable separations for some typical species. The author also presents a simple analysis of the processing rates limited by mass diffusion through a thin hydrodynamic boundary layer. It is shown that these processes can be realized with compact and efficient devices to meet the ATW demand for the periodic feeding and cleaning of the waste.

Li, N.

1997-05-01T23:59:59.000Z

320

Development of Cementitious Waste Forms for Nuclear Waste ...  

Science Conference Proceedings (OSTI)

Symposium, Materials Solutions for the Nuclear Renaissance. Presentation Title, Development of Cementitious Waste Forms for Nuclear Waste Immobilization.

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

Industrial waste management information for 1990 and record-to-date  

SciTech Connect

This product provides detailed data and graphics on airborne and liquid effluent releases, fuel oil consumption, and water usage for the calendar year 1990. It summarizes industrial waste data records compiled since 1971 for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Industrial Waste Management Information System (IWMIS).

Litteer, D.L.; Peterson, C.N.; Sims, A.M.

1991-08-01T23:59:59.000Z

322

Glass Science tutorial lecture No. 5: Historical review of USDOE tank waste management  

Science Conference Proceedings (OSTI)

This is a two day course whose objective is to present an unbiased historical overview of the DOE tank waste activities. World events which impacted the US nuclear program (or vise versa) will be presented. Liquid, mostly tank waste, and sludge are the primary concerns of this course.

McDaniel, E.W.

1995-02-01T23:59:59.000Z

323

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

Science Conference Proceedings (OSTI)

This report provides a quantitative inventory and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. From December 1963 through May 2000, liquid radioactive wastes generated by spent nuclear fuel reprocessing were converted into a solid, granular form called calcine. This report also contains a description of the calcine storage bins.

M. D. Staiger M. C. Swenson

2007-06-01T23:59:59.000Z

324

Waste Heat Recovery from Industrial Process Heating Equipment -  

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

Waste Heat Recovery from Industrial Process Heating Equipment - Waste Heat Recovery from Industrial Process Heating Equipment - Cross-cutting Research and Development Priorities Speaker(s): Sachin Nimbalkar Date: January 17, 2013 - 11:00am Location: 90-2063 Seminar Host/Point of Contact: Aimee McKane Waste heat is generated from several industrial systems used in manufacturing. The waste heat sources are distributed throughout a plant. The largest source for most industries is exhaust / flue gases or heated air from heating systems. This includes the high temperature gases from burners in process heating, lower temperature gases from heat treat, dryers, and heaters, heat from heat exchangers, cooling liquids and gases etc. The previous studies and direct contact with the industry as well as equipment suppliers have shown that a large amount of waste heat is not

325

Waste treatment facility passes federal inspection, completes final  

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

23, 2012 23, 2012 Media Contact: Danielle Miller, 208-526-5709 Erik Simpson, 208-390-9464 Waste treatment facility passes federal inspection, completes final milestone, begins startup The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. An exterior view of the Integrated Waste Treatment Unit A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to resolve before the 53,000-square-foot Integrated Waste Treatment Unit

326

Salt Waste Contractor Reaches Contract Milestone | Department of Energy  

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

Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone April 29, 2013 - 12:00pm Addthis Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. AIKEN, S.C. - The liquid waste cleanup contractor for the EM program at the Savannah River Site (SRS) recently surpassed a 2013 contract milestone by processing more than 600,000 gallons of salt waste. Savannah River Remediation (SRR) salt disposition process facilities

327

Waste Treatment Facility Passes Federal Inspection, Completes Final  

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

Waste Treatment Facility Passes Federal Inspection, Completes Final Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup Waste Treatment Facility Passes Federal Inspection, Completes Final Milestone, Begins Startup April 23, 2012 - 12:00pm Addthis Media Contact Erik Simpson, 208-390-9464 Danielle Miller, 208-526-5709 The Idaho site today initiated the controlled, phased startup of a new waste treatment facility scheduled to begin treating 900,000 gallons of radioactive liquid waste stored in underground tanks at a former Cold War spent nuclear fuel reprocessing facility next month. A U.S. Department of Energy (DOE) operational readiness review team (made up of Subject Matter Experts across the country) in early April identified a dozen issues for the cleanup contractor CH2M-WG Idaho, LLC (CWI) to

328

State Waste Discharge Permit application: 400 Area Septic System  

Science Conference Proceedings (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations, the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affects groundwater or has the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 400 Area Septic System. The influent to the system is domestic waste water. Although the 400 Area Septic System is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. Therefore, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used.

Not Available

1994-06-01T23:59:59.000Z

329

How to deal with laboratory waste Radioactive waste  

E-Print Network (OSTI)

How to deal with laboratory waste Radioactive waste: Any laboratory waste, whether chemical or biological, containing radioactive material, should be disposed as radioactive waste. Radioactive waste should be removed from the laboratory to the departmental waste area, soon after finishing the experiment

Maoz, Shahar

330

Thermal Treatment of Solid Wastes Using the Electric Arc Furnace  

Science Conference Proceedings (OSTI)

A thermal waste treatment facility has been developed at the Albany Research Center (ARC) over the past seven years to process a wide range of heterogeneous mixed wastes, on a scale of 227 to 907 kg/h (500 to 2,000 lb/h). The current system includes a continuous feed system, a 3-phase AC, 0.8 MW graphite electrode arc furnace, and a dedicated air pollution control system (APCS) which includes a close-coupled thermal oxidizer, spray cooler, baghouse, and wet scrubber. The versatility of the complete system has been demonstrated during 5 continuous melting campaigns, ranging from 11 to 25 mt (12 to 28 st) of treated wastes per campaign, which were conducted on waste materials such as (a) municipal incinerator ash, (b) simulated low-level radioactive, high combustible-bearing mixed wastes, (c) simulated low-level radioactive liquid tank wastes, (d) heavy metal contaminated soils, and (e) organic-contaminated dredging spoils. In all cases, the glass or slag products readily passed the U.S. Environmental Protection Agency (EPA) Toxicity Characteristic Leachability Program (TCLP) test. Additional studies are currently under way on electric utility wastes, steel and aluminum industry wastes, as well as zinc smelter residues. Thermal treatment of these solid waste streams is intended to produce a metallic product along with nonhazardous glass or slag products.

O'Connor, W.K.; Turner, P.C.

1999-09-01T23:59:59.000Z

331

Transuranic (TRU) Waste  

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

Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A)...

332

Hanford Waste Vitrification Plant  

SciTech Connect

The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs.

Larson, D.E.; Allen, C.R. (Pacific Northwest Lab., Richland, WA (United States)); Kruger, O.L.; Weber, E.T. (Westinghouse Hanford Co., Richland, WA (United States))

1991-10-01T23:59:59.000Z

333

Transuranic Waste Screener  

The TRU waste screener (TRU-WS) is a multifunctional system for the rapid screening of transuranic material for criticality safety or screening for TRU content in open trays or waste containers.

334

Pioneering Nuclear Waste Disposal  

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

Department of Energy (DOE) is closing the circle on the generation, management, and disposal of transuranic waste. But the WIPP story is not just about radioactive waste. It is...

335

Immobilization of Nuclear Wastes  

Science Conference Proceedings (OSTI)

Oct 20, 2010 ... Glassy and Glass Composite Nuclear Wasteforms: Michael Ojovan1; Bill Lee2; ... wastes which should be solidified for safe storage and disposal. ... has been vitrifying the Department of Energy's High Level Waste (HLW) at ...

336

Pet Waste Management  

E-Print Network (OSTI)

About 1 million pounds of dog waste is deposited daily in North Texas alone. That's why proper disposal of pet waste can make a big difference in the environment. 5 photos, 2 pages

Mechell, Justin; Lesikar, Bruce J.

2008-08-28T23:59:59.000Z

337

Liquid level detector  

DOE Patents (OSTI)

A liquid level detector for low pressure boilers. A boiler tank, from which apor, such as steam, normally exits via a main vent, is provided with a vertical side tube connected to the tank at the desired low liquid level. When the liquid level falls to the level of the side tube vapor escapes therethrough causing heating of a temperature sensitive device located in the side tube, which, for example, may activate a liquid supply means for adding liquid to the boiler tank. High liquid level in the boiler tank blocks entry of vapor into the side tube, allowing the temperature sensitive device to cool, for example, to ambient temperature.

Grasso, Albert P. (Vernon, CT)

1986-01-01T23:59:59.000Z

338

Liquid level detector  

DOE Patents (OSTI)

A liquid level detector for low pressure boilers. A boiler tank, from which vapor, such as steam, normally exits via a main vent, is provided with a vertical side tube connected to the tank at the desired low liquid level. When the liquid level falls to the level of the side tube vapor escapes therethrough causing heating of a temperature sensitive device located in the side tube, which, for example, may activate a liquid supply means for adding liquid to the boiler tank. High liquid level in the boiler tank blocks entry of vapor into the side tube, allowing the temperature sensitive device to cool, for example, to ambient temperature.

Grasso, A.P.

1984-02-21T23:59:59.000Z

339

Polymer Solidification and Stabilization: Adaptable Processes for Atypical Wastes  

Science Conference Proceedings (OSTI)

Vinyl Ester Styrene (VES) and Advanced Polymer Solidification (APS{sup TM}) processes are used to solidify, stabilize, and immobilize radioactive, pyrophoric and hazardous wastes at US Department of Energy (DOE) and Department of Defense (DOD) sites, and commercial nuclear facilities. A wide range of projects have been accomplished, including in situ immobilization of ion exchange resin and carbon filter media in decommissioned submarines; underwater solidification of zirconium and hafnium machining swarf; solidification of uranium chips; impregnation of depth filters; immobilization of mercury, lead and other hazardous wastes (including paint chips and blasting media); and in situ solidification of submerged demineralizers. Discussion of the adaptability of the VES and APS{sup TM} processes is timely, given the decommissioning work at government sites, and efforts by commercial nuclear plants to reduce inventories of one-of-a-kind wastes. The VES and APS{sup TM} media and processes are highly adaptable to a wide range of waste forms, including liquids, slurries, bead and granular media; as well as metal fines, particles and larger pieces. With the ability to solidify/stabilize liquid wastes using high-speed mixing; wet sludges and solids by low-speed mixing; or bead and granular materials through in situ processing, these polymer will produce a stable, rock-hard product that has the ability to sequester many hazardous waste components and create Class B and C stabilized waste forms for disposal. Technical assessment and approval of these solidification processes and final waste forms have been greatly simplified by exhaustive waste form testing, as well as multiple NRC and CRCPD waste form approvals. (authors)

Jensen, C. [Diversified Technologies Services, Inc., Knoxville, TN (United States)

2007-07-01T23:59:59.000Z

340

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $311k in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R.; Wrights, R. S.

2002-02-25T23:59:59.000Z

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

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250-liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WlPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $3 1 lk in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R. (David R.); Wright, R. (Robert)

2002-01-01T23:59:59.000Z

342

Comparison of Waste Feed Delivery Small Scale Mixing Demonstration Simulant to Hanford Waste  

Science Conference Proceedings (OSTI)

'The Hanford double-shell tank (DST) system provides the staging location for waste feed delivery to the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Hall (2008) includes WTP acceptance criteria that describe physical and chemical characteristics of the waste that must be certified as acceptable before the waste is transferred from the DSTs to the WTP. One of the more challenging requirements relates to the sampling and characterization of the undissolved solids (UDS) in a waste feed DST. The objectives of Washington River Protection Solutions' (WRPS) Small Scale Mixing Demonstration (SSMD) project are to understand and demonstrate the DST sampling and batch transfer performance at multiple scales using slurry simulants comprised of UDS particles and liquid (Townson 2009). The SSMD project utilizes geometrically scaled DST feed tanks to generate mixing, sampling, and transfer test data. In Phase 2 of the testing, RPP-49740, the 5-part simulant defined in RPP-48358 was used as the waste slurry simulant. The Phase 2 test data are being used to estimate the expected performance of the prototypic systems in the full-scale DSTs. As such, understanding of the how the small-scale systems as well as the simulant relate to the full-scale DSTs and actual waste is required. The focus of this report is comparison of the size and density of the 5-part SSMD simulant to that of the Hanford waste. This is accomplished by computing metrics for particle mobilization, suspension, settling, transfer line intake, and pipeline transfer from the characterization of the 5-part SSMD simulant and characterizations of the Hanford waste. In addition, the effects of the suspending fluid characteristics on the test results are considered, and a computational fluid dynamics tool useful to quantify uncertainties from simulant selections is discussed.'

Wells, Beric E.; Gauglitz, Phillip A.; Rector, David R.

2011-08-15T23:59:59.000Z

343

Project_Descriptions_ITP_ARRA_Awards.xls  

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

Selections for Industrial Technologies Program Recovery Act Funding Selections for Industrial Technologies Program Recovery Act Funding Deployment of Combined Heat and Power (CHP) Systems, District Energy Systems, Waste Energy Recovery Systems, and Efficient Industrial Equipment Award Winners City and State Project Description Total DOE Funding Air Products and Chemicals, Inc. Middletown, OH Waste Energy Project at the AK Steel Corporation Middletown Works. The project will construct a combined cycle power generation plant at the Middletown, OH, works of AK Steel that will capture and process the blast furnace gas (BFG). The BFG, generated in ironmaking operations, is either flared or used to make steam needed for industrial processes . Currently, over 50% of the BFG is flared. This project will utilize

344

The wild wild waste: e-waste  

Science Conference Proceedings (OSTI)

E-Waste is a popular, informal name for discarded electronic products such as computers, VCRs, cameras, which have reached the end of their "useful life". Discarded electronic products contain a stew of toxic metals and chemicals such as lead, mercury, ... Keywords: donate, e-waste, ecology, efficiency, environment, green computing, hazardous material, re-use, recycle, reduce, thin-client, upgrade, virtualization

Scott E. Hanselman; Mahmoud Pegah

2007-10-01T23:59:59.000Z

345

Waste canister for storage of nuclear wastes  

DOE Patents (OSTI)

A waste canister for storage of nuclear wastes in the form of a solidified glass includes fins supported from the center with the tips of the fins spaced away from the wall to conduct heat away from the center without producing unacceptable hot spots in the canister wall.

Duffy, James B. (Fullerton, CA)

1977-01-01T23:59:59.000Z

346

Conditioning Matrices of Liquid Scintillation Cocktails Contaminated with Tritium  

Science Conference Proceedings (OSTI)

This paper describes a viable solidification technology to convert the liquid scintillation cocktail into a stable form which minimizes the probability to release tritium in the environment.This radioactive waste type is generated by the radio-chemical analysis lab of a CANDU nuclear power plant.

Dianu, Magdalena [Institute for Nuclear Research (Romania)

2005-07-15T23:59:59.000Z

347

Mixed Waste Treatment Study  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented nuclear utility industry experience in the on-site treatment of mixed waste. This report reviews all available exclusions/exceptions to EPA permitting requirements for environmentally responsible on-site management of mixed waste. Included is a description of emerging mixed waste treatment technologies along with a detailed evaluation of off-site treatment/disposal facilities.

1996-01-31T23:59:59.000Z

348

Recycle Plastic Waste Recommended Action  

E-Print Network (OSTI)

AR No. 5 Recycle Plastic Waste Recommended Action Separate scrap plastic bag waste from solid waste stream and recycle. This can be accomplished by either arranging for no-cost pick-up of loose waste or by selling baled waste material. Assessment Recommendation Summary Recommended Waste Cost Implementation

Tullos, Desiree

349

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in SingaporeStatus in Singapore  

E-Print Network (OSTI)

Waste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in Singapore #12;Singapore's Waste Management · In 2003, 6877 tonnes/day (2.51 M tonnes/year) of MSW collected plants · 8% (non-incinerable waste) and incineration ash goes to the offshore Semakau Landfill · To reach

Columbia University

350

PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED I. Test Results T-641317. Section 1. First issue, June 14, 1961  

SciTech Connect

Tests were performed to determine the adequacy of storage facilities and operating procedures of the Shippingport PWR waste disposal system during a reactor refueling operation. Problems associated with the liquid waste evaporator and the various storage tanks were outlined. The activities of the wastes expelled to the reactor effluent channel and the Ohio River were compared with the design activities. (T.F.H.)

1961-10-31T23:59:59.000Z

351

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation  

SciTech Connect

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives. (JGB)

1976-05-01T23:59:59.000Z

352

5. Natural Gas Liquids Statistics  

U.S. Energy Information Administration (EIA)

5. Natural Gas Liquids Statistics Natural Gas Liquids Proved Reserves U.S. natural gas liquids proved reserves decreased 7 percent to 7,459 million ...

353

Liquid Hydrogen Absorber for MICE  

E-Print Network (OSTI)

REFERENCES Figure 5: Liquid hydrogen absorber and test6: Cooling time of liquid hydrogen absorber. Eight CernoxLIQUID HYDROGEN ABSORBER FOR MICE S. Ishimoto, S. Suzuki, M.

Ishimoto, S.

2010-01-01T23:59:59.000Z

354

Reducing waste, Photoby stcvcchan  

E-Print Network (OSTI)

I ' I I t Reducing waste, Photoby stcvcchan AMs President Mike Lee (left to right), Point Grey M U recycling given high priority on campus By GAVIN WILSON UBC is taking stepsto reduce waste and encourageGellatly,Vice-President,Administration and Finance,to develop and recommend university policies on waste recycling. Another task force has submitted

Farrell, Anthony P.

355

Hazardous Waste Management Training  

E-Print Network (OSTI)

Hazardous Waste Management Training Persons (including faculty, staff and students) working be thoroughly familiar with waste handling and emergency procedures ap- plicable to their job responsibilities before handling hazardous waste. Departments are re- quired to keep records of training for as long

Dai, Pengcheng

356

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

357

Waste acceptance criteria for closure generated waste  

Science Conference Proceedings (OSTI)

The PORTS Facility has been operating since 1954. The PORTS Facility is used to enrich uranium for nuclear navy applications and commercial nuclear reactors. The PORTS process uses molecular diffusion techniques to separate the U-235 isotope from the U-238 isotope. The PORTS Facility consists of a complex cascade of compressors and converters through which gaseous uranium hexafluoride feed is processed. The feed contains approximately 0.7 percent U-235 by weight while products contain from 4 to 97 percent U-235 by weight, depending on the final application. In general, the majority of the closure wastes generated at PORTS consists of personal protective equipment (PPE), rags, soils, decontamination solutions, and construction related debris. These hazardous wastes will be predominately characterized on the basis of process knowledge. PORTS assumes its conservative waste characterizations that are based on process knowledge are correct unless and until further investigation and/or analysis proves the constituents are not present or are present at concentrations below characteristic regulatory thresholds. Waste Acceptance Criteria for wastes generated by the closure of active and inactive RCRA facilities at PORTS has been developed. The criteria presented in this document govern the activities that are performed during the closure and subsequent generation of waste and relocation from the closure locations to the storage unit. These criteria are intended to ensure the proper handling, classification, processing, and storage of wastes in order to prevent hazardous waste release that may pose a threat to human health or the environment. Any wastes currently stored at each of the facilities that are to be closed will be transferred to the X-326 or X-7725 Storage Units. The waste transfers will be accomplished in accordance with the Container Transfer Plan.

Not Available

1992-05-01T23:59:59.000Z

358

Method for removing and decolorizing aqueous waste effluents containing dissolved or dispersed organic matter  

DOE Patents (OSTI)

A method is provided for treating organic waste material dissolved or dispersed in an aqueous effluent, which comprises contacting the effluent with an inert particulate carbonaceous sorbent at an oxygen pressure up to 2000 psi, irradiating the resultant mixture with high energy radiation until a decolorized liquid is produced, and then separating the decolorized liquid.

Case, F.N.; Ketchen, E.E.

1975-10-14T23:59:59.000Z

359

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste  

E-Print Network (OSTI)

Waste Disposal Matrix Type of Chemical University-related Waste Personal Waste Batteries, used or unwanted including lithium, alkaline, lead ­ acid or lithium aluminum hydride Chemical Waste Check Disposal of Toxics website for disposal options or Take to Bookstore Biological Waste Biological Waste Residential

Zaferatos, Nicholas C.

360

Ultimate Disposal of Wastes by Pyrolysis and Incineration  

E-Print Network (OSTI)

fan into the stack to atmosphere. The system incorporates the latest available designs in combustion This paper describes a new disposal facility designed to reduce thermally, without causing pollution, liq authorized the design and construction of a facility to reduce liquid/fluid industrial wastes by pyrolysis

Columbia University

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

Prospects for pyrolysis technologies in managing municipal, industrial, and DOE cleanup wastes  

DOE Green Energy (OSTI)

Pyrolysis converts portions of municipal solid wastes, hazardous wastes, and special wastes such as tires, medical wastes, and even old landfills into solid carbon and a liquid or gaseous hydrocarbon stream. Pyrolysis heats a carbonaceous waste stream typically to 290--900 C in the absence of oxygen, and reduces the volume of waste by 90% and its weight by 75%. The solid carbon char has existing markets as an ingredient in many manufactured goods, and as an adsorbent or filter to sequester certain hazardous wastes. Pyrolytic gases may be burned as fuel by utilities, or liquefied for use as chemical feedstocks, or low-pollution motor vehicle fuels and fuel additives. This report analyzes the potential applications of pyrolysis in the Long Island region and evaluates for the four most promising pyrolytic systems their technological and commercial readiness, their applicability to regional waste management needs, and their conformity with DOE requirements for environmental restoration and waste management. This summary characterizes their engineering performance, environmental effects, costs, product applications, and markets. Because it can effectively treat those wastes that are inadequately addressed by current systems, pyrolysis can play an important complementing role in the region`s existing waste management strategy. Its role could be even more significant if the region moves away from existing commitments to incineration and MSW composting. Either way, Long Island could become the center for a pyrolysis-based recovery services industry serving global markets in municipal solid waste treatment and hazardous waste cleanup. 162 refs.

Reaven, S.J. [State Univ. of New York, Stony Brook, NY (United States)

1994-12-01T23:59:59.000Z

362

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

363

Municipal waste processing apparatus  

DOE Patents (OSTI)

This invention relates to apparatus for processing municipal waste, and more particularly to vibrating mesh screen conveyor systems for removing grit, glass, and other noncombustible materials from dry municipal waste. Municipal waste must be properly processed and disposed of so that it does not create health risks to the community. Generally, municipal waste, which may be collected in garbage trucks, dumpsters, or the like, is deposited in processing areas such as landfills. Land and environmental controls imposed on landfill operators by governmental bodies have increased in recent years, however, making landfill disposal of solid waste materials more expensive. 6 figs.

Mayberry, J.L.

1988-04-13T23:59:59.000Z

364

ASSEMBLAGES ON WASTE ROCK  

E-Print Network (OSTI)

Abstract: Natural regeneration on waste rock was investigated at the old Wangaloa coal mine, south-east Otago. A 450-m long waste rock stack had been created 40–50 years ago, and has had little anthropogenic intervention since. The stack is made up of a gradient of three main waste rock types, defined as ‘silt-rich’, ‘mixed’, and ‘quartz-rich’, which reflect different proportions of loess siltstone and quartz gravel conglomerate. Plant species assemblages were quantified in four 5-m 2 quadrats in each waste rock type. Invertebrates were heat extracted from substrate cores (7 cm diameter; depth 5 cm) collected from quadrats over an eight-week period in spring 2003. Ordination analysis showed statistically distinct plant and invertebrate assemblages had arisen on each waste rock type. Revegetation patterns were dominated by native, woody individuals on all waste rock types, particularly manuka (Leptospermum scoparium) and kanuka (Kunzea ericoides). Plant cover on ‘silt-rich ’ waste rock was four-fold that on ‘quartz-rich ’ waste rock. Total numbers of invertebrates were highest on ‘quartz-rich’ waste rock, but richness greatest on ‘silt-rich ’ waste rock. Collembola dominated the fauna but their numbers were proportionally greatest in poorly vegetated areas. Further work is required to explain the absence of plants and invertebrates from local areas of waste rock. ___________________________________________________________________________________________________________________________________

C. G. Rufaut; S. Hammit; D. Craw; S. G. Clearwater

2006-01-01T23:59:59.000Z

365

Mixed waste: Proceedings  

SciTech Connect

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31T23:59:59.000Z

366

Screening for organic solvents in Hanford waste tanks using total non- methane organic compound vapor concentrations  

SciTech Connect

The potential ignition of organic liquids stored in the Hanford high-level radioactive waste tanks is a safety issue because expanding gases could affect tank dome integrity. This report presents results of a screening test that was applied to 75 passively ventilated waste tanks at Hanford to determine those that might contain a significant amount of organic liquid waste. The screening test is based on a simple model of tank headspace, headspace organic vapor concentrations, and certain tank physical parameters. Analyses indicate that damage to the tank dome is credible only if the organic liquid burn rate is above a threshold value, and this can occur only if the surface area of organic liquid in a tank is above a corresponding threshold value of about one square meter. Twelve tanks were identified as potentially containing at least that amount of semivolatile organic liquid based on conservative estimates. Tank head space organic vapor concentrations and physical parameters required by the screening test have been compiled and are presented for each of the tanks studied. Estimates of the ventilation rates of the waste tanks were revised to reflect recent information obtained from hydrogen monitoring data. A simple analysis of the uncertainty in the test results suggests that the largest current uncertainty in the estimation of organic liquid surface area is that associated with knowledge of the tank ventilation rate. The uncertainty analysis is applied to determine 95% confidence limits for the estimated organic waste surface area in each tank.

Huckaby, J.L.; Glissmeyer, J.A.; Sklarew, D.S.

1997-02-01T23:59:59.000Z

367

Process development for remote-handled mixed-waste treatment  

SciTech Connect

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

368

Mixed Waste Integrated Program -- Problem-oriented technology development  

SciTech Connect

The Mixed Waste Integrated Program (MWIP) is responding to the need for DOE mixed waste treatment technologies that meet these dual regulatory requirements. MWIP is developing emerging and innovative treatment technologies to determine process feasibility. Technology demonstrations will be used to determine whether processes are superior to existing technologies in reducing risk, minimizing life-cycle cost, and improving process performance. Technology development is ongoing in technical areas required to process mixed waste: materials handling, chemical/physical treatment, waste destruction, off-gas treatment, final forms, and process monitoring/control. MWIP is currently developing a suite of technologies to process heterogeneous waste. One robust process is the fixed-hearth plasma-arc process that is being developed to treat a wide variety of contaminated materials with minimal characterization. Additional processes encompass steam reforming, including treatment of waste under the debris rule. Advanced off-gas systems are also being developed. Vitrification technologies are being demonstrated for the treatment of homogeneous wastes such as incinerator ash and sludge. An alternative to conventional evaporation for liquid removal--freeze crystallization--is being investigated. Since mercury is present in numerous waste streams, mercury removal technologies are being developed.

Hart, P.W.; Wolf, S.W. [Dept. of Energy, Germantown, MD (United States); Berry, J.B. [Oak Ridge National Lab., TN (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

369

An Overview of Waste Classification for Disposal Summary  

E-Print Network (OSTI)

Radioactive waste is a byproduct of nuclear weapons production, commercial nuclear power generation, and the naval reactor program. Waste byproducts also result from radioisotopes used for scientific, medical, and industrial purposes. The legislative definitions adopted for radioactive wastes, for the most part, refer to the processes that generated the wastes. Thus, waste disposal policies have tended to link the processes to uniquely tailored disposal solutions. Consequently, the origin of the waste, rather than its radiologic characteristics, often determines its fate. Plutonium and enriched uranium-235 were first produced by the Manhattan Project during World War II. These materials were later defined by the Atomic Energy Act of 1954 as special nuclear materials, along with other materials that the former Atomic Energy Commission (AEC) determined were capable of releasing energy through nuclear fission. Reprocessing of irradiated nuclear fuel to extract special nuclear material generated highly radioactive liquid and solid byproducts. The Nuclear Waste Policy Act of 1982 (NWPA) defined irradiated fuel as spent nuclear fuel, and the byproducts as high-level waste. Uranium ore processing

Anthony Andrews

2006-01-01T23:59:59.000Z

370

Options and cost for disposal of NORM waste.  

Science Conference Proceedings (OSTI)

Oil field waste containing naturally occurring radioactive material (NORM) is presently disposed of both on the lease site and at off-site commercial disposal facilities. The majority of NORM waste is disposed of through underground injection, most of which presently takes place at a commercial injection facility located in eastern Texas. Several companies offer the service of coming to an operator's site, grinding the NORM waste into a fine particle size, slurrying the waste, and injecting it into the operator's own disposal well. One company is developing a process whereby the radionuclides are dissolved out of the NORM wastes, leaving a nonhazardous oil field waste and a contaminated liquid stream that is injected into the operator's own injection well. Smaller quantities of NORM are disposed of through burial in landfills, encapsulation inside the casing of wells that are being plugged and abandoned, or land spreading. It is difficult to quantify the total cost for disposing of NORM waste. The cost components that must be considered, in addition to the cost of the operation, include analytical costs, transportation costs, container decontamination costs, permitting costs, and long-term liability costs. Current NORM waste disposal costs range from $15/bbl to $420/bbl.

Veil, J. A.

1998-10-22T23:59:59.000Z

371

Analysis of long-lived radionuclidic impurities in short-lived radiopharmaceutical waste using gamma spectrometry  

Science Conference Proceedings (OSTI)

Large hospitals and biomedical research centers utilize decay-in-storage programs to minimize the volume of their low level radioactive waste. However, some medically useful radionuclides often contain small amounts of long-lived radionuclidic impurities which may complicate simple waste management procedures. We have evaluated the extent of this problem in low level radioactive waste involving {sup 67}Cu and {sup 111}In over a 6-mo cycle of decay-in-storage by identifying the residual radionuclides in our dry waste using a multichannel analyzer. The multichannel analyzer was also used to quantify the radionuclide constituents of our liquid waste at the beginning of a decay-in-storage cycle. Radionuclides were identified by the presence of characteristic photopeaks of each isotope in the gamma spectrum and quantified by region of interest analysis. Gamma spectrometry can be used to aid waste segregation and final management decisions on low level radioactive waste. 10 refs., 1 fig., 2 tabs.

Salako, Q.; DeNardo, S.J. [Univ. of California, Sacramento, CA (United States)

1997-01-01T23:59:59.000Z

372

Tank Waste Corporate Board Meeting 03/05/09 | Department of Energy  

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

Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 Tank Waste Corporate Board Meeting 03/05/09 The following documents are associated with the Tank Waste Corporate Board Meeting held on March 5th, 2009. Overview of Integrated Waste Treatment Unit Desired PU Loading During Vitrification HLW System Integrated Project Team Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective Status of Art & Practice of Performance Assessment within the DOE Complex Experience from the Short Course on Introduction to Nuclear Chemistry and Fuel Cycle Separations and Future Educational Opportunities Role of Liquid Waste Pretreatment Technologies in Solving the DOE Clean-up Mission Performance Assessment Community of Practice Action Item Review and Status

373

Report: Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project at Hanford  

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

EMAB Tank Waste Subcommittee Summary Report 1 EMAB Tank Waste Subcommittee Summary Report 1 Report of Findings, Conclusions, and Recommendations Concerning the Waste Treatment and Immobilization Project (WTP) at Hanford Submitted by the Environmental Management Advisory Board Tank Waste Subcommittee September 15, 2010 Introduction In May 2010, the Department of Energy established the Environmental Management Tank Waste Subcommittee (EM-TWS). The EM-TWS was charged with conducting an independent technical review of liquid waste capital and operations projects related to the Office of Environmental Management (EM) tank waste cleanup programs at Hanford, Washington; the Savannah River Site in South Carolina; the Idaho National Laboratory; and the West Valley Demonstration Project in New York. The EM-TWS's review focused on the facilities being

374

Waste management plan for the Lower East Fork Poplar Creek Operable Unit, Oak Ridge, Tennessee  

SciTech Connect

The Lower East Fork Poplar Creek (LEFPC) Remedial Action project will remove mercury-contaminated soils from the floodplain of LEFPC, dispose of these soils at the Y-12 Plant Landfill V, and restore the affected floodplain. The waste management plan addresses management and disposition of all wastes generated during the LEFPC remedial action. Most of the solid wastes will be sanitary or construction/demolition wastes and will be disposed of at existing Y- 12 facilities. Some small amounts of hazardous waste are anticipated, along with possible low-level or mixed wastes (> 35 pCi/g). Liquid wastes will be generated which will be sanitary and capable of being disposed of at the Oak Ridge Sewage Treatment Plant, except sanitary sewage.

1996-04-01T23:59:59.000Z

375

Spent Fuel and Waste Management Technology Development Program. Annual progress report  

SciTech Connect

This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

Bryant, J.W.

1994-01-01T23:59:59.000Z

376

Summary of radioactive solid waste received in the 200 areas during calendar year 1996  

Science Conference Proceedings (OSTI)

Rust Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1996. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document.

Hladek, K.L.

1997-05-21T23:59:59.000Z

377

High level radioactive waste vitrification process equipment component testing  

Science Conference Proceedings (OSTI)

Remote operability and maintainability of vitrification equipment were assessed under shielded-cell conditions. The equipment tested will be applied to immobilize high-level and transuranic liquid waste slurries that resulted from plutonium production for defense weapons. Equipment tested included: a turntable for handling waste canisters under the melter; a removable discharge cone in the melter overflow section; a thermocouple jumper that extends into a shielded cell; remote instrument and electrical connectors; remote, mechanical, and heat transfer aspects of the melter glass overflow section; a reamer to clean out plugged nozzles in the melter top; a closed circuit camera to view the melter interior; and a device to retrieve samples of the glass product. A test was also conducted to evaluate liquid metals for use in a liquid metal sealing system.

Siemens, D.H.; Heath, W.O.; Larson, D.E.; Craig, S.N.; Berger, D.N.; Goles, R.W.

1985-04-01T23:59:59.000Z

378

Mediated electrochemical hazardous waste destruction  

SciTech Connect

There are few permitted processes for mixed waste (radioactive plus chemically hazardous) treatment. We are developing electrochemical processes that convert the toxic organic components of mixed waste to water, carbon dioxide, an innocuous anions such as chloride. Aggressive oxidizer ions such as Ag{sup 2+} or Ce{sup +4} are produced at an anode. These can attack the organic molecules directly. They can also attack water which yields hydroxyl free radicals that in turn attack the organic molecules. The condensed (i.e., solid and/or liquid) effluent streams contain the inorganic radionuclide forms. These may be treated with existing technology and prepared for final disposal. Kinetics and the extent of destruction of some toxic organics have been measured. Depending on how the process is operated, coulombic efficiency can be nearly 100%. In addition, hazardous organic materials are becoming very expensive to dispose of and when they are combined with transuranic radioactive elements no processes are presently permitted. Mediated electrochemical oxidation is an ambient-temperature aqueous-phase process that can be used to oxidize organic components of mixed wastes. Problems associated with incineration, such as high-temperature volatilization of radionuclides, are avoided. Historically, Ag (2) has been used as a mediator in this process. Fe(6) and Co(3) are attractive alternatives to Ag(2) since they form soluble chlorides during the destruction of chlorinated solvents. Furthermore, silver itself is a toxic heavy metal. Quantitative data has been obtained for the complete oxidation of ethylene glycol by Fe(6) and Co(3). Though ethylene glycol is a nonhalogenated organic, this data has enabled us to make direct comparisons of activities of Fe(6) and Co(3) with Ag(2). Very good quantitative data for the oxidation of ethylene glycol by Ag(2) had already been collected. 4 refs., 6 figs.

Hickman, R.G.; Farmer, J.C.; Wang, F.T.

1991-08-01T23:59:59.000Z

379

Tank Waste and Waste Processing | Department of Energy  

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

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

380

Waste treatment by selective mineral ion exchanger  

Science Conference Proceedings (OSTI)

STMI, subsidiary company of the AREVA Group with over 40 years in the D and D business, has been continuously innovating and developing new decontamination techniques, with the objectives of achieving more efficient decontaminations on a growing spectrum of media. In the field of liquid waste treatment, STMI manufactures uses and commercialises selective inorganic ion exchangers (RAN). These are hydrated synthetic inorganic compounds prepared from very pure raw materials. Different types of RANs (POLYAN, OXTAIN, Fe-Cu, Fe-CoK, Si-Fe-CoK) can be used to trap a large number of radioactive elements in contaminated effluents. Different implementations could be applied depending on technical conditions. STMI's offers consist in building global solution and preliminary design of installation either in dispersed form (batch) or in column (cartridge filtration). Those products are used all over the world not only in the nuclear business (Canada, US, Belgium, France...) but also in other fields. Indeed, it provides competitive solutions to many domains of application especially water pollution control, liquid waste treatment in the nuclear business by decreasing the activity level of waste. The following paper will focus on the theoretical principle of the mineral exchanger, its implementation and the feed back collected by STMI. (author)

Polito, Aurelie [Areva NC - BUA STMI, 1 route de la Noue - 91196 Gif sur Yvette, Cedex (France)

2007-07-01T23:59:59.000Z

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

New Waste Calcining Facility (NWCF) Waste Streams  

SciTech Connect

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

382

Waste Confidence Discussion | Department of Energy  

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

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

383

TSA waste stream and final waste form composition  

SciTech Connect

A final vitrified waste form composition, based upon the chemical compositions of the input waste streams, is recommended for the transuranic-contaminated waste stored at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The quantities of waste are large with a considerable uncertainty in the distribution of various waste materials. It is therefore impractical to mix the input waste streams into an ``average`` transuranic-contaminated waste. As a result, waste stream input to a melter could vary widely in composition, with the potential of affecting the composition and properties of the final waste form. This work examines the extent of the variation in the input waste streams, as well as the final waste form under conditions of adding different amounts of soil. Five prominent Rocky Flats Plant 740 waste streams are considered, as well as nonspecial metals and the ``average`` transuranic-contaminated waste streams. The metals waste stream is the most extreme variation and results indicate that if an average of approximately 60 wt% of the mixture is soil, the final waste form will be predominantly silica, alumina, alkaline earth oxides, and iron oxide. This composition will have consistent properties in the final waste form, including high leach resistance, irrespective of the variation in waste stream. For other waste streams, much less or no soil could be required to yield a leach resistant waste form but with varying properties.

Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1993-01-01T23:59:59.000Z

384

Integrated Waste Services Association National Solid Wastes Management Association  

E-Print Network (OSTI)

Can Help Meet Our Energy Needs October 5, 2006 - WASHINGTON, DC--A broad coalition of government-244-4700 Evan Von Leer, SWANA 240-494-2252 John Varrasi, ASME 212-591-8158 Don't Waste Waste! Waste-Based Energy and utilization of energy produced from waste, or waste-based energy (WBE). The United States Conference of Mayors

Columbia University

385

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

386

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:50 2.6 % LASB00411 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

387

8-Waste treatment and disposal A. Responsibility for waste management  

E-Print Network (OSTI)

8- Waste treatment and disposal A. Responsibility for waste management 1. Each worker is responsible for correctly bagging and labeling his/her own waste. 2. A BSL3 technician will be responsible for transporting and autoclaving the waste. Waste will be autoclaved once or twice per day, depending on use

388

WIPP Waste Information System Waste Container Data Report  

E-Print Network (OSTI)

WIPP Waste Information System Waste Container Data Report 06/06/2008 07:49 2.6 % LAS817174 % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360 Selection Criteria - Total Pages PRD02Instance 5 #12;Waste Isolation Pilot Plant Waste Container Data Report

389

Aerosol can waste disposal device  

DOE Patents (OSTI)

Disclosed is a device for removing gases and liquid from containers. The ice punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container.

O' Brien, Michael D. (Las Vegas, NV); Klapperick, Robert L. (Las Vegas, NV); Bell, Chris (Las Vegas, NV)

1993-01-01T23:59:59.000Z

390

Aerosol can waste disposal device  

DOE Patents (OSTI)

Disclosed is a device for removing gases and liquid from containers. The device punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container. 7 figures.

O' Brien, M.D.; Klapperick, R.L.; Bell, C.

1993-12-21T23:59:59.000Z

391

HIGH TEMPERATURE TREATMENT OF INTERMEDIATE-LEVEL RADIOACTIVE WASTES - SIA RADON EXPERIENCE  

SciTech Connect

This review describes high temperature methods of low- and intermediate-level radioactive waste (LILW) treatment currently used at SIA Radon. Solid and liquid organic and mixed organic and inorganic wastes are subjected to plasma heating in a shaft furnace with formation of stable leach resistant slag suitable for disposal in near-surface repositories. Liquid inorganic radioactive waste is vitrified in a cold crucible based plant with borosilicate glass productivity up to 75 kg/h. Radioactive silts from settlers are heat-treated at 500-700 0C in electric furnace forming cake following by cake crushing, charging into 200 L barrels and soaking with cement grout. Various thermochemical technologies for decontamination of metallic, asphalt, and concrete surfaces, treatment of organic wastes (spent ion-exchange resins, polymers, medical and biological wastes), batch vitrification of incinerator ashes, calcines, spent inorganic sorbents, contaminated soil, treatment of carbon containing 14C nuclide, reactor graphite, lubricants have been developed and implemented.

Sobolev, I.A.; Dmitriev, S.A.; Lifanov, F.A.; Kobelev, A.P.; Popkov, V.N.; Polkanov, M.A.; Savkin, A.E.; Varlakov, A.P.; Karlin, S.V.; Stefanovsky, S.V.; Karlina, O.K.; Semenov, K.N.

2003-02-27T23:59:59.000Z

392

SRS Waste Tanks 5 and 6 Are Operationally Closed | Department of Energy  

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

SRS Waste Tanks 5 and 6 Are Operationally Closed SRS Waste Tanks 5 and 6 Are Operationally Closed SRS Waste Tanks 5 and 6 Are Operationally Closed December 19, 2013 - 12:00pm Addthis The final amount of grout is poured into Tank 6, marking the operational closure of Tanks 5 and 6. The final amount of grout is poured into Tank 6, marking the operational closure of Tanks 5 and 6. Media Contacts Amy Caver, Amy.Caver@srs.gov, 803-952-7213 Rick Kelley, Rick.Kelley@srs.gov, 803-208-0198 AIKEN, S.C. - Savannah River Remediation (SRR), the liquid waste contractor at the U.S. Department of Energy (DOE) Savannah River Site, has removed from service two more Cold War-era liquid radioactive waste tanks, marking the third and fourth tanks operationally closed by SRR in the last 14 months. Grouting and closure of Tanks 5 and 6 were completed approximately two

393

Secondary Waste Form Screening Test Results—THOR® Fluidized Bed Steam Reforming Product in a Geopolymer Matrix  

SciTech Connect

Screening tests are being conducted to evaluate waste forms for immobilizing secondary liquid wastes from the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Plans are underway to add a stabilization treatment unit to the Effluent Treatment Facility to provide the needed capacity for treating these wastes from WTP. The current baseline is to use a Cast Stone cementitious waste form to solidify the wastes. Through a literature survey, DuraLith alkali-aluminosilicate geopolymer, fluidized-bed steam reformation (FBSR) granular product encapsulated in a geopolymer matrix, and a Ceramicrete phosphate-bonded ceramic were identified both as candidate waste forms and alternatives to the baseline. These waste forms have been shown to meet waste disposal acceptance criteria, including compressive strength and universal treatment standards for Resource Conservation and Recovery Act (RCRA) metals (as measured by the toxicity characteristic leaching procedure [TCLP]). Thus, these non-cementitious waste forms should also be acceptable for land disposal. Information is needed on all four waste forms with respect to their capability to minimize the release of technetium. Technetium is a radionuclide predicted to be in the secondary liquid wastes in small quantities, but the Integrated Disposal Facility (IDF) risk assessment analyses show that technetium, even at low mass, produces the largest contribution to the estimated IDF disposal impacts to groundwater.

Pires, Richard P.; Westsik, Joseph H.; Serne, R. Jeffrey; Mattigod, Shas V.; Golovich, Elizabeth C.; Valenta, Michelle M.; Parker, Kent E.

2011-07-14T23:59:59.000Z

394

Integrated Waste Treatment Facility Fact Sheet | Department of...  

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

Waste Management Tank Waste and Waste Processing Integrated Waste Treatment Facility Fact Sheet Integrated Waste Treatment Facility Fact Sheet Waste Management Nuclear...

395

NDAA Section 3116 Waste Determinations with Related Disposal...  

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

NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste...

396

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

397

Waste management plan for inactive LLLW tanks 3001-B, 3004-B, 3013, and T-30 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Environmental Restoration Program  

Science Conference Proceedings (OSTI)

This Project Waste Management Plan identifies the waste that is expected to be generated in connection with the removal and disposition of inactive liquid low-level radioactive waste tanks 3001-B, 3004-B, and T-30, and grouting of tank 3013 at the Oak Ridge National Laboratory and the isolation of these tanks` associated piping systems. The plan also identifies the organization, responsibilities, and administrative controls that will be followed to ensure proper handling of the waste.

NONE

1995-07-01T23:59:59.000Z

398

Pioneering Nuclear Waste Disposal  

NLE Websites -- All DOE Office Websites (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

399

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

400

Guidelines for mixed waste minimization  

SciTech Connect

Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization.

Owens, C.

1992-02-01T23:59:59.000Z

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


401

Enzymes and microorganisms in food industry waste processing and conversion to useful products: a review of the literature  

DOE Green Energy (OSTI)

Bioconversion of food processing wastes is receiving increased attention with the realization that waste components represent an available and utilizable resource for conversion to useful products. Liquid wastes are characterized as dilute streams containing sugars, starches, proteins, and fats. Solid wastes are generally cellulosic, but may contain other biopolymers. The greatest potential for economic bioconversion is represented by processes to convert cellulose to glucose, glucose to alcohol and protein, starch to invert sugar, and dilute waste streams to methane by anaerobic digestion. Microbial or enzymatic processes to accomplish these conversions are described.

Carroad, P.A.; Wilke, C.R.

1976-12-01T23:59:59.000Z

402

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

Science Conference Proceedings (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

403

Operational Waste Volume Projection  

SciTech Connect

Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June. 2000.

STRODE, J.N.

2000-08-28T23:59:59.000Z

404

Liquid abrasive pressure pot scoping tests report  

SciTech Connect

The primary initiatives of the LITCO Decontamination Development group at the Idaho Chemical Process Plant (ICPP) are the development of methods to eliminate the use of sodium bearing decontamination chemicals and minimization of the amount of secondary waste generated during decontamination activities. In July of 1994, a Commerce Business Daily (CBD) announcement was issued by the INEL to determine commercial interest in the development of an in-situ liquid abrasive grit blasting system. As a result of the CBD announcement, Klieber & Schulz issued an Expression of Interest letter which stated they would be interested in testing a prototype Liquid Abrasive Pressure Pot (LAPP). LITCO`s Decontamination group and Kleiber & Schulz entered into a Cooperative Research and Development Agreement (CRADA) in which the Decontamination Development group tested the prototype LAPP in a non-radioactive hot cell mockup. Test results are provided.

Archibald, K.E.

1996-01-01T23:59:59.000Z

405

The TEES process cleans waste and produces energy  

DOE Green Energy (OSTI)

A gasification system is under development that can be used with most types of wet organic wastes. The system operates at 350{degrees}C and 205 atm using a liquid water phase as the processing medium. Since a pressurized system is used, the wet waste can be fed as a solution or slurry to the reactor without drying. Through the development of catalysts, a useful processing system has been produced. The system has utility both for direct conversion of high-moisture biomass to fuel gas or as a wastewater cleanup system for wet organic wastes including unconverted biomass from bioconversion processes. By the use of this system >99% conversions of organic waste to medium-Btu fuel gas can be achieved.

Elliott, D.C.; Silva, L.J.

1995-02-01T23:59:59.000Z

406

State Waste Discharge Permit application: 200-W Powerhouse Ash Pit  

Science Conference Proceedings (OSTI)

As part of the Hanford Federal Facility Agreement and Consent Order negotiations; the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173-216 (or 173-218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. This document constitutes the State Waste Discharge Permit application for the 200-W Powerhouse Ash Pit. The 200-W Powerhouse Ash Waste Water discharges to the 200-W Powerhouse Ash Pit via dedicated pipelines. The 200-W Powerhouse Ash Waste Water is the only discharge to the 200-W Powerhouse Ash Pit. The 200-W Powerhouse is a steam generation facility consisting of a coal-handling and preparation section and boilers.

Atencio, B.P.

1994-06-01T23:59:59.000Z

407

Norcal Waste Systems, Inc.  

SciTech Connect

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

408

CLAB Transuranic Waste Spreadsheets  

Science Conference Proceedings (OSTI)

The Building 772-F Far-Field Transuranic (TRU) Waste Counting System is used to measure the radionuclide content of waste packages produced at the Central Laboratory Facilities (CLAB). Data from the instrument are entered into one of two Excel spreadsheets. The waste stream associated with the waste package determines which spreadsheet is actually used. The spreadsheets calculate the necessary information required for completion of the Transuranic Waste Characterization Form (OSR 29-90) and the Radioactive Solid Waste Burial Ground Record (OSR 7-375 or OSR 7-375A). In addition, the spreadsheets calculate the associated Low Level Waste (LLW) stream information that potentially could be useful if the waste container is ever downgraded from TRU to LLW. The spreadsheets also have the capability to sum activities from source material added to a waste container after assay. A validation data set for each spreadsheet along with the appropriate results are also presented in this report for spreadsheet verification prior to each use.

Leyba, J.D.

2000-08-11T23:59:59.000Z

409

Waste Confidence Discussion  

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

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:

410

Solid Waste Permits (Louisiana)  

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

The Louisiana Department of Environmental Quality administers the rules and regulations governing the storage, collection, processing, recovery, and reuse of solid waste protect the air,...

411

Nuclear Waste Management  

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

Waste Management's Yucca Mountain Project and the Office of Nuclear Energy's Advanced Fuel Cycle Initiative (AFCI) and Global Nuclear Energy Partnership (GNEP) programs. Efforts...

412

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

413

The Power of Waste.  

E-Print Network (OSTI)

?? Abstract It is estimated that up to 2 percent of the population in Third World countries survives on waste in one way or another.… (more)

Frykman, Carina

2006-01-01T23:59:59.000Z

414

Making waste public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social… (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

415

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

416

Make love not waste.  

E-Print Network (OSTI)

?? The purpose of this thesis was to investigate a waste management project and its public awareness components, in the Korca region, Albania. We wanted… (more)

Carlsson Engström, Christina

2008-01-01T23:59:59.000Z

417

Making Waste Public.  

E-Print Network (OSTI)

??This thesis questions the boundaries that define waste as a public or private dilemma, investigating these boundaries as productive sites for the imagination of social… (more)

Gambetta, Curt

2009-01-01T23:59:59.000Z

418

WEB RESOURCE: Radioactive Waste  

Science Conference Proceedings (OSTI)

May 8, 2007 ... This resource offers a a very broad explanation of how the Belgian Agency for Management of Radioactive Waste and Enriched Fissile Material ...

419

Integrated waste management.  

E-Print Network (OSTI)

??Integrated waste management is considered from a systems’ approach, with a particular emphasis on advancing sustainability. The focus of the thesis is to examine the… (more)

Seadon, Jeffrey Keith

2010-01-01T23:59:59.000Z

420

Waste Clean Up 5  

Science Conference Proceedings (OSTI)

... deployment and clean-up activities of robot arms into a nuclear contaminated pit at the opening of waste storage tank C-106 at Hanford, Washington ...

2011-08-30T23:59:59.000Z

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

Liquid level detector  

DOE Patents (OSTI)

A liquid level detector for conductive liquids for vertical installation in a tank, the detector having a probe positioned within a sheath and insulated therefrom by a seal so that the tip of the probe extends proximate to but not below the lower end of the sheath, the lower end terminating in a rim that is provided with notches, said lower end being tapered, the taper and notches preventing debris collection and bubble formation, said lower end when contacting liquid as it rises will form an airtight cavity defined by the liquid, the interior sheath wall, and the seal, the compression of air in the cavity preventing liquid from further entry into the sheath and contact with the seal. As a result, the liquid cannot deposit a film to form an electrical bridge across the seal.

Tshishiku, Eugene M. (Augusta, GA)

2011-08-09T23:59:59.000Z

422

Transuranic contaminated waste functional definition and implementation  

Science Conference Proceedings (OSTI)

The purpose of this report is to examine the problem(s) of TRU waste classification and to document the development of an easy-to-apply standard(s) to determine whether or not this waste package should be emplaced in a geologic repository for final disposition. Transuranic wastes are especially significant because they have long half-lives and some are rather radiotoxic. Transuranic radionuclides are primarily produced by single or multiple neutron capture by U-238 in fuel elements during the operation of a nuclear reactor. Reprocessing of spent fuel elements attempts to remove plutonium, but since the separation is not complete, the resulting high-activity liquids still contain some plutonium as well as other transuranics. Likewise, transuranic contamination of low-activity wastes also occurs when the transuranic materials are handled or processed, which is primarily at federal facilities involved in R and D and nuclear weapons production. Transuranics are persistent in the environment and, as a general rule, are strongly retained by soils. They are not easily transported through most food chains, although some reconcentration does take place in the aquatic food chain. They pose no special biological hazard to humans upon ingestion because they are weakly absorbed from the gastrointestional tract. A greater hazard results from inhalation since they behave like normal dust and fractionate accordingly.

Kniazewycz, B.G.

1980-03-01T23:59:59.000Z

423

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

424

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

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

2, 2009. Savannah River Remediation, LLC is a limited liability company consisting of URS Washington Division; Babcock & Wilcox Technical Services Group, Inc.; Bechtel National,...

425

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

SciTech Connect

This research was intended to provide the scientific foundation upon which the feasibility of liquid-liquid extraction chemistry for bulk reduction of the volume of high-activity tank waste can be evaluated. Primary focus has been on sodium hydroxide separation, with potential Hanford application. Value in sodium hydroxide separation can potentially be found in alternative flowsheets for treatment and disposal of low-activity salt waste. Additional value can be expected in recycle of sodium hydroxide for use in waste retrieval and sludge washing, whereupon additions of fresh sodium hydroxide to the waste can be avoided. Potential savings are large both because of the huge cost of vitrification of the low-activity waste stream and because volume reduction of high-activity wastes could obviate construction of costly new tanks. Toward these ends, the conceptual development begun in the original proposal was extended with the formulation of eight fundamental approaches that could be undertaken for extraction of sodium hydroxide.

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

2004-06-08T23:59:59.000Z

426

Waste Isolation Pilot Plant (WIPP) Waste Isolation Pilot Plant...  

National Nuclear Security Administration (NNSA)

dispose of transuranic radioactive waste, or TRU waste, left over from the production of nuclear weapons. After more than 20 years of scientific study, public input, and...

427

Gas scrubbing liquids  

DOE Patents (OSTI)

Fully chlorinated and/or fluorinated hydrocarbons are used as gas scrubbing liquids for preventing noxious gas emissions to the atmosphere.

Lackey, Walter J. (Oak Ridge, TN); Lowrie, Robert S. (Oak Ridge, TN); Sease, John D. (Knoxville, TN)

1981-01-01T23:59:59.000Z

428

Liquid level detection  

Science Conference Proceedings (OSTI)

This paper discusses a method. It is for detecting presence of a liquid level at a first predetermined point along the depth of a borehole.

Fryer, C.D.; Stie, K.E.; Wedel, M.W.; Stamper, K.R.

1990-11-27T23:59:59.000Z