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1

The feasibility of deep well injection for brine disposal  

E-Print Network (OSTI)

A generalized methodology for evaluating the technical feasibility of projects involving the disposal of waste brine by injection into deep saline aquifers is developed, primarily from the hydrology and petroleum engineering literature. Data collection, groundwater modeling, and fluid compatibility are discussed in detail. Injection system design, economics, and regulatory considerations are more related to economic than technical feasibility, and are discussed only as they relate to technical feasibility. The methodology is utilized to make a preliminary evaluation of a proposed brine injection project in the Dove Creek area of King and Stonewall Counties, North Central Texas. Four known deep aquifers are modeled, using the SWIFT/486 software, to determine their ability to receive two cfs of brine for a project life of one hundred years. Two aquifers, the Strawn and EUenburger Formations, are predicted to be acceptable for disposal. Each aquifer would require only one disposal well which is favorable for the economics of the project. Additional data, particularly hydraulic conductivity and net aquifer thickness data, are required to make a more definitive technical feasibility determination for this project.

Spongberg, Martin Edward

1994-01-01T23:59:59.000Z

2

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

3

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

4

West Hackberry Brine Disposal Project pre-discharge characterization. Final report  

SciTech Connect

The physical, chemical and biological attributes are described for: (1) a coastal marine environment centered about a Department of Energy Strategic Petroleum Reserve (SPR) brine disposal site 11.4 km off the southwest coast of Louisiana; and (2) the lower Calcasieu and Sabine estuarine systems that provide leach waters for the SPR project. A three month sampling effort, February through April 1981, and previous investigations from the study area are integrated to establish baseline information for evaluation of impacts from brine disposal in the nearshore marine waters and from freshwater withdrawal from the coastal marsh of the Chenier Plain. January data are included for some tasks that sampled while testing and mobilizing their instruments prior to the February field effort. The study addresses the areas of physical oceanography, estuarine hydrology and hydrography, water and sediment quality, benthos, nekton, phytoplankton, zooplankton, and data management.

DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C. (eds.) [eds.

1982-01-01T23:59:59.000Z

5

Portable brine evaporator unit, process, and system  

DOE Patents (OSTI)

The present invention discloses a comprehensive, efficient, and cost effective portable evaporator unit, method, and system for the treatment of brine. The evaporator unit, method, and system require a pretreatment process that removes heavy metals, crude oil, and other contaminates in preparation for the evaporator unit. The pretreatment and the evaporator unit, method, and system process metals and brine at the site where they are generated (the well site). Thus, saving significant money to producers who can avoid present and future increases in transportation costs.

Hart, Paul John (Indiana, PA); Miller, Bruce G. (State College, PA); Wincek, Ronald T. (State College, PA); Decker, Glenn E. (Bellefonte, PA); Johnson, David K. (Port Matilda, PA)

2009-04-07T23:59:59.000Z

6

The implications of UIC and NPDES regulations on selection of disposal options for spent geothermal brine  

Science Conference Proceedings (OSTI)

This document reviews and evaluates the various options for the disposal of geothermal wastewater with respect to the promulgated regulations for the protection of surface and groundwaters. The Clean Water Act of 1977 and the Safe Drinking Water Act Amendments are especially important when designing disposal systems for geothermal fluids. The former promulgates regulations concerning the discharge of wastewater into surface waters, while the latter is concerned with the protection of ground water aquifers through the establishment of underground injection control (UIC) programs. There is a specific category for geothermal fluid discharge if injection is to be used as a method of disposal. Prior to February 1982, the UIC regulations required geothermal power plant to use Class III wells and direct use plants to use Class V wells. More stringent regulatory requirements, including construction specification and monitoring, are imposed on the Class III wells. On February 3, 1982, the classification of geothermal injection wells was changed from a Class III to Class V on the basis that geothermal wells do not inject for the extraction of minerals or energy, but rather they are used to inject brines, from which heat has been extracted, into formations from which they were originally taken. This reclassification implies that a substantial cost reduction will be realized for geothermal fluid injection primarily because well monitoring is no longer mandatory. The Clean Water Act of 1977 provides the legal basis for regulating the discharge of liquid effluent into the nation's surface waters, through a permitting system called the National Pollution Discharge Elimination System (NPDES) Discharge quantities, rates, concentrations and temperatures are regulated by the NPDES permits. These permits systems are based upon effluent guidelines developed by EPA on an industry by industry basis. For geothermal energy industry, effluent guidelines have not been formulated and are not currently scheduled. There, are however, water quality standards that control the quantity and quality of wastewaters discharged into surface waters. These standards are established by the states in concert with EPA, and frequently result in NPDES conditions more restrictive than those based on effluent guidelines.

None

1982-07-01T23:59:59.000Z

7

Transportation, Aging and Disposal Canister System Performance...  

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

Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1...

8

Brine and gas recovery from geopressured systems. I. Parametric calculations  

DOE Green Energy (OSTI)

A series of parametric calculations was run with the S-CUBED geopressured-geothermal simulator MUSHRM to assess the effects of important formation, fluid and well parameters on brine and gas recovery from geopressured reservoir systems. The specific parameters considered are formation permeability, pore-fluid salinity, temperature and gas content, well radius and location with respect to reservoir boundaries, desired flow rate, and possible shale recharge. It was found that the total brine and gas recovered (as a fraction of the resource in situ) were most sensitive to formation permeability, pore-fluid gas content, and shale recharge.

Garg, S.K.; Riney, T.D.

1984-02-01T23:59:59.000Z

9

Improving the injectability of high-salinity brines for disposal or waterflooding operations  

DOE Green Energy (OSTI)

This work is part of a study conducted by Lawrence Livermore National Laboratory (LLNL) to improve the performance of brine injection wells at Gulf Coast Strategic Petroleum Reserve Sites. Our involvement established that granular media filtration, when used with proper chemical pretreatments, provides an effective and economical method for removing particulates from hypersaline brines. This treatment allows for the injection of 200,000 B/D with significantly increased well half-lives of 30 years.

Raber, E.; Thompson, R.E.; Smith, F.H.

1981-07-25T23:59:59.000Z

10

Disposable telemetry cable deployment system  

DOE Patents (OSTI)

A disposable telemetry cable deployment system for facilitating information retrieval while drilling a well includes a cable spool adapted for insertion into a drill string and an unarmored fiber optic cable spooled onto the spool cable and having a downhole end and a stinger end. Connected to the cable spool is a rigid stinger which extends through a kelly of the drilling apparatus. A data transmission device for transmitting data to a data acquisition system is disposed either within or on the upper end of the rigid stinger.

Holcomb, David Joseph (Sandia Park, NM)

2000-01-01T23:59:59.000Z

11

WETTING BEHAVIOR OF SELECTED CRUDE OIL/BRINE/ROCK SYSTEMS  

Science Conference Proceedings (OSTI)

The effect of aging and displacement temperatures, and brine and oil composition on wettability and the recovery of crude oil by spontaneous imbibition and waterflooding has been investigated. This study is based on displacement tests in Berea Sandstone using three distinctly different crude oils and three reservoir brines. Brine concentration was varied by changing the concentration of total dissolved solids of the synthetic brine in proportion to give brine of twice, one tenth, and one hundredth of the reservoir brine concentration. Aging and displacement temperatures were varied independently. For all crude oils, water-wetness and oil recovery increased with increase in displacement temperature. Tests on the effect of brine concentration showed that salinity of the connate and invading brines can have a major influence on wettability and oil recovery at reservoir temperature. Oil recovery increased over that for the reservoir brine with dilution of both the initial (connate) and invading brine or dilution of either. Removal of light components from the crude oil resulted in increased water-wetness. Addition of alkanes to the crude oil reduced the water-wetness, and increased oil recovery. Relationships between waterflood recovery and wettability are summarized.

G.Q. Tang; N.R. Morrow

1997-04-01T23:59:59.000Z

12

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR ...  

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR FUEL ASSEMBLIES United States Patent Application

13

Generic Disposal System Modeling, Fiscal Year 2011 Progress Report |  

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

Disposal System Modeling, Fiscal Year 2011 Progress Report Disposal System Modeling, Fiscal Year 2011 Progress Report Generic Disposal System Modeling, Fiscal Year 2011 Progress Report The UFD Campaign is developing generic disposal system models (GDSM) of different disposal environments and waste form options. Currently, the GDSM team is investigating four main disposal environment options: mined repositories in three geologic media (salt, clay, and granite) and the deep borehole concept in crystalline rock (DOE 2010d). Further developed the individual generic disposal system (GDS) models for salt, granite, clay, and deep borehole disposal environments. GenericDisposalSystModelFY11.pdf More Documents & Publications Integration of EBS Models with Generic Disposal System Models TSPA Model Development and Sensitivity Analysis of Processes Affecting

14

Transportation, Aging and Disposal Canister System Performance Specification: Revision 1  

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

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system.

15

Energy optimization in ice hockey halls I. The system COP as a multivariable function, brine and design choices  

E-Print Network (OSTI)

This work is the first in a series of articles addressing the energy optimization in ice hockey halls. Here we adopt an analytical method, called functional optimization, to find which design and operating conditions maximize the Coefficient Of Performance of the entire cooling system (brine pumps and cooling tower), which we call ${\\rm COP}_{sys}$. This is addressed as a function of several variables, like electric consumption and brine physical properties. By maximizing such function, the best configuration and brine choices for the system can thus be determined accurately and rigorously. We investigate the importance of pipe diameter, depth and brine type (ethylene glycol and ammonia) for average-sized ice rinks. An optimal brine density is found, and we compute the weight of the electric consumption of the brine pumps on ${\\rm COP}_{sys}$. Our formulas are validated with heat flow measurement data obtained at an ice hockey hall in Finland. They are also confronted with technical and cost-related constraints, and implemented by simulations with the program COMSOL Multiphysics. The multivariable approach here discussed is general, and can be applied to the rigorous preliminary study of diverse situations in building physics and in many other areas of interest.

Andrea Ferrantelli; Paul Melóis; Miska Räikkönen; Martti Viljanen

2012-11-02T23:59:59.000Z

16

DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

E. F. Loros

2000-06-30T23:59:59.000Z

17

Defense High Level Waste Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents.

N. E. Pettit

2001-07-13T23:59:59.000Z

18

Disposal Systems Evaluations and Tool Development - Engineered...  

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

... 156 Table 5-5 Fuel cycle, disposal environment, and aging time for 24 base case combinations. ......

19

Report on design, construction, and testing of CO/sub 2/ breakout system for geothermal brines  

DOE Green Energy (OSTI)

A skid mounted test facility has been built for determining conditions at which CO/sub 2/ flashes from geothermal brines. The system has been checked and operated at one geothermal plant. It performed as designed. The equipment is designed to operate at temperatures and pressures typical of wells near Heber, California. (Nominally 180/sup 0/C and 300 to 500 psig). It has heat exchangers which can cool the brine to less than 70/sup 0/C. (The cooling water is recirculated after being cooled by a forced air heat exchanger). Breakout pressures can be determined for any temperature between 70/sup 0/C and wellhead temperature. An adjustable orifice provides final control on pressure required to initiate flashing. The orifice is at the bottom of a sight glass. A light beam shines through the sight glass and focuses on a photoelectric cell. The presence of bubbles scatters light and decreases the output of the cell. Results using the cell were more reproducible than those using the naked eye. Results from one test show a smooth curve over the temperature range 75/sup 0/C to 165/sup 0/C. Agreement between the experimental values and calculated ones is discussed.

Robertus, R.J.; Shannon, D.W.; Sullivan, R.G.

1984-03-01T23:59:59.000Z

20

Defense High Level Waste Disposal Container System Description  

Science Conference Proceedings (OSTI)

The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Evaluation of materials for systems using cooled, treated geothermal or high-saline brines  

DOE Green Energy (OSTI)

Lack of adequate quantities of clean surface water for use in wet (evaporative) cooling systems indicates the use of high-salinity waste waters, or cooled geothermal brines, for makeup purposes. High-chloride, aerated water represents an extremely corrosive environment. In order to determine metals suitable for use in such an environment, metal coupons were exposed to aerated, treated geothermal brine salted to a chloride concentration of 10,000 and 50,000 ppM (mg/L) for periods of up to 30 days. The exposed coupons were evaluated to determine the general, pitting, and crevice corrosion characteristics of the metals. The metals exhibiting corrosion resistance at 50,000 ppM chloride were then evaluated at 100,000 and 200,000 ppM chloride. Since these were screening tests to select materials for components to be used in a cooling system, with primary emphasis on condenser tubing, several materials were exposed for 4 to 10 months in pilot cooling tower test units with heat transfer for further corrosion evaluation. The results of the screening tests indicate that ferritic stainless steels (29-4-2 and SEA-CURE) exhibit excellent corrosion resistance at all levels of chloride concentration. Copper-nickel alloys (70/30 and Monel 400) exhibited excellent corrosion resistance in the high-saline water. The 70/30 copper-nickel alloy, which showed excellent resistance to general corrosion, exhibited mild pitting in the 30-day tests. This pitting was not apparent, however, after 6 months of exposure in the pilot cooling tower tests. The nickel-base alloys exhibited excellent corrosion resistance, but their high cost prevents their use unless no other material is found feasible. Other materials tested, although unsuitable for condenser tubing material, would be suitable as tube sheet material.

Suciu, D.F.; Wikoff, P.M.

1982-09-01T23:59:59.000Z

22

Disposal Systems Evaluations and Tool Development - Engineered...  

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

disposable, plastic transfer pipettes. Sample vials were then filled with 40 mL of 2% nitric acid solutions (TraceSelect grade) in order to facilitate U(VI) desorption from...

23

Modeling of an adiabatic packed bed brine-air contactor for use in a solar energy driven food processing system  

Science Conference Proceedings (OSTI)

A mathematical model was developed for a packed bed brine-air contacting system which has applications in a solar energy driven food processing system. The model considers mass transfer resistances of both phases, but neglects the heat transfer resistance of the liquid phase. It takes into account the large heat effects associated with water absorption into and desorption from the brine. A computational method was also developed to calculate the minimum air flow rate which would prevent a pinch. A packed bed brine-air contactor was built, and experiments were conducted for a range of brine and air conditions. Good agreement between the computed and experimental results warrants use of the model to design and optimize the packed bed water stripping process. A periodic-flow packed bed heat regenerator was built to recover heat from the exit air of the contactor so as to improve the energy efficiency of the system. It was possible to preheat the inlet air to a temperature close to that of the exit air. The inlet air, however, during its passage through the regenerator picked up the condensate deposited from the exit air. This led to a decrease in the driving potential to mass transfer in the contactor. Optimization studies show that using a combined solar driven boiler and air assisted packed bed water stripper would be more economical than using a solar driven boiler alone or using flat plate solar collectors to drive the water stripper.

Biswal, R.N.

1983-01-01T23:59:59.000Z

24

Energy optimization in ice hockey halls I. The system COP as a multivariable function, brine and design choices  

E-Print Network (OSTI)

This work is the first of a series of articles addressing the energy optimization in ice hockey halls. Here we outline an analytic method to predict in which design and operating conditions the COP of the entire cooling system (refrigerator and cooling tower) ${\\rm COP}_{sys}$ is maximum. ${\\rm COP}_{sys}$ is investigated as a function of several variables, like electric consumption and brine physical properties. With this method, the best configuration and brine choices for the system can therefore be determined in advance. We estimate the optimal design of an average-sized ice rink, including pipe diameter, depth and brine type (ethylene glycol and ammonia). We also single out an optimal brine density and show the impact of the electric consumption of the pump on ${\\rm COP}_{sys}$. Our theoretical predictions are validated with heat flow measurement data obtained at an ice hockey hall in Finland. They are also confronted with technical and cost-related constraints, and implemented by simulations with the pr...

Ferrantelli, Andrea; Räikkönen, Miska; Viljanen, Martti

2012-01-01T23:59:59.000Z

25

Disposal Systems Evaluations and Tool Development - Engineered Barrier  

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

Disposal Systems Evaluations and Tool Development - Engineered Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation The engineered barrier system (EBS) plays a key role in the long-term isolation of nuclear waste in geological repository environments. This report focuses on the progress made in the evaluation of EBS design concepts, assessment of clay phase stability at repository-relevant conditions, thermodynamic database development for cement and clay phases, and THMC coupled phenomena along with the development of tools and methods to examine these processes. This report also documents the advancements of the Disposal System Evaluation Framework (DSEF) for the development of

26

Integration of EBS Models with Generic Disposal System Models | Department  

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

Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the Used Fuel Disposition campaign. This report addresses: predictive model capability for used nuclear fuel degradation based on electrochemical and thermodynamic principles, radiolysis model to evaluate the U(VI)-H2O-CO2 system, steps towards the evaluation of uranium alteration products, discussion of instant release fraction (IRF) of radionuclides from the nuclear fuel, and

27

Integration of EBS Models with Generic Disposal System Models | Department  

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

Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models Integration of EBS Models with Generic Disposal System Models This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the Used Fuel Disposition campaign. This report addresses: predictive model capability for used nuclear fuel degradation based on electrochemical and thermodynamic principles, radiolysis model to evaluate the U(VI)-H2O-CO2 system, steps towards the evaluation of uranium alteration products, discussion of instant release fraction (IRF) of radionuclides from the nuclear fuel, and

28

Naval Spent Nuclear Fuel disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

N. E. Pettit

2001-07-13T23:59:59.000Z

29

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

30

Preliminary Transportation, Aging and Disposal Canister System Performance Specification  

SciTech Connect

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2. The TAD canister, in conjunction with specialized overpacks will accomplish a number of functions in the management and disposal of spent nuclear fuel. Some of these functions will be accomplished at purchaser sites where commercial spent nuclear fuel (CSNF) is stored, and some will be performed within the Office of Civilian Radioactive Waste Management (OCRWM) transportation and disposal system. This document contains only those requirements unique to applications within Department of Energy's (DOE's) system. DOE recognizes that TAD canisters may have to perform similar functions at purchaser sites. Requirements to meet reactor functions, such as on-site dry storage, handling, and loading for transportation, are expected to be similar to commercially available canister-based systems. This document is intended to be referenced in the license application for the Monitored Geologic Repository (MGR). As such, the requirements cited herein are needed for TAD system use in OCRWM's disposal system. This document contains specifications for the TAD canister, transportation overpack and aging overpack. The remaining components and equipment that are unique to the OCRWM system or for similar purchaser applications will be supplied by others.

C.A Kouts

2006-11-22T23:59:59.000Z

31

System for disposing of radioactive water  

DOE Patents (OSTI)

A system for reducing radioactivity released to the biosphere in the course of producing natural gas from a reservoir stimulated by the detonation of nuclear explosives therein. Tritiated water produced with the gas is separated out and returned to a nuclear chimney through a string of tubing positioned within the well casing. The tubing string is positioned within the well casing in a manner which enhances separation of the water out of the gas and minimizes entrainment of water into the gas flowing out of the chimney.

Gotchy, Reginald L. (Bethesda, MD)

1976-01-13T23:59:59.000Z

32

Improved Water Flooding through Injection Brine Modification  

Science Conference Proceedings (OSTI)

Crude oil/brine/rock interactions can lead to large variations in the displacement efficiency of waterflooding, by far the most widely applied method of improved oil recovery. Laboratory waterflood tests show that injection of dilute brine can increase oil recovery. Numerous fields in the Powder River basin have been waterflooded using low salinity brine (about 500 ppm) from the Madison limestone or Fox Hills sandstone. Although many uncertainties arise in the interpretation and comparison of field production data, injection of low salinity brine appears to give higher recovery compared to brine of moderate salinity (about 7,000 ppm). Laboratory studies of the effect of brine composition on oil recovery cover a wide range of rock types and crude oils. Oil recovery increases using low salinity brine as the injection water ranged from a low of no notable increase to as much as 37.0% depending on the system being studied. Recovery increases using low salinity brine after establishing residual oil saturation (tertiary mode) ranged from no significant increase to 6.0%. Tests with two sets of reservoir cores and crude oil indicated slight improvement in recovery for low salinity brine. Crude oil type and rock type (particularly the presence and distribution of kaolinite) both play a dominant role in the effect that brine composition has on waterflood oil recovery.

Robertson, Eric Partridge; Thomas, Charles Phillip; Morrow, Norman; (U of Wyoming)

2003-01-01T23:59:59.000Z

33

Unconventional gas sources. Volume IV. Geopressured brines  

DOE Green Energy (OSTI)

The following topics are covered: study objectives, regional geology and prospect evaluation, reservoir engineering, drilling and well costs, production and water disposal facilities, pressure maintenance, geothermal and hydraulic energy assessment, operating expense, economic evaluation, environmental considerations, legal considerations, and risks analysis. The study addresses only sandstone brine reservoirs in the Texas and Louisiana Gulf Coast onshore areas. (MHR)

Not Available

1980-01-01T23:59:59.000Z

34

Lattice-Boltzmann modeling of micromodel experiments representing a CO2-brine system  

Science Conference Proceedings (OSTI)

Successful sequestration of CO{sub 2} into deep saline aquifers presents an enormous challenge that requires fundamental understanding of reactive-multi phase flow and transport across many temporal and spatial scales. Of critical importance is accurately predicting the efficiency of CO{sub 2} trapping mechanisms. At the pore scale (e.g., microns to millimeters) the interfacial area between CO{sub 2} and brine, as well as CO{sub 2} and the solid phase, directly influences the amount of CO{sub 2} trapped due to capillary forces, dissolution and mineral precipitation. In this work, we model immiscible displacement micromodel experiments using the lattice-Boltzmann (LB) method. We focus on quantifying interfacial area as a function of capillary numbers and viscosity ratios typically encountered in CO{sub 2} sequestration operations. We show that the LB model adequately predicts the steady-state experimental flow patterns and interfacial area measurements. Based on the steady-state agreement, we use the LB model to investigate interfacial dynamics (e.g., fluid-fluid interfacial velocity and the rate of production of fluid-fluid interfacial area). In addition, we quantify the amount of interfacial area and the interfacial dynamics associated with the capillary trapped nonwetting phase. This is expected to be important for predicting the amount of nonwetting phase subsequently trapped due to dissolution and mineral precipitation.

Porter, Mark L [Los Alamos National Laboratory; Kang, Qinjun [Los Alamos National Laboratory; Tarimala, Sowmitri [Los Alamos National Laboratory; Abdel - Fattah, Amr I [Los Alamos National Laboratory; Backhaus, Scott [Los Alamos National Laboratory; Carey, James W [Los Alamos National Laboratory

2010-12-21T23:59:59.000Z

35

Thermodynamic data management system for nuclear waste disposal performance assessment  

Science Conference Proceedings (OSTI)

Thermodynamic property values for use in assessing the performance of a nuclear waste repository are described. More emphasis is on a computerized data base management system which facilitates use of the thermodynamic data in sensitivity analysis and other studies which critically assess the performance of disposal sites. Examples are given of critical evaluation procedures; comparison of apparent equilibrium constants calculated from the data base, with other work; and of correlations useful in estimating missing values of both free energy and enthalpy of formation for aqueous species. 49 refs., 11 figs., 6 tabs.

Phillips, S.L.; Hale, F.V.; Siegel, M.D.

1988-04-01T23:59:59.000Z

36

Advanced biochemical processes for geothermal brines FY 1998 annual operating plan  

DOE Green Energy (OSTI)

As part of the overall Geothermal Energy Research which is aimed at the development of economical geothermal resources production systems, the aim of the Advanced Biochemical Processes for Geothermal Brines (ABPGB) effort is the development of economic and environmentally acceptable methods for disposal of geothermal wastes and conversion of by-products to useful forms. Methods are being developed for dissolution, separation and immobilization of geothermal wastes suitable for disposal, usable in inert construction materials, suitable for reinjection into the reservoir formation, or used for recovery of valuable metals.

NONE

1997-10-01T23:59:59.000Z

37

A Systems Study on How to Dispose of Fleets of Small Satellites  

E-Print Network (OSTI)

A Systems Study on How to Dispose of Fleets of Small Satellites Jason M. Andringa and Daniel E Systems Laboratory2 #12;Jason Andringa MIT Space Systems Laboratory3 A Systems Study on How to Dispose in Aeronautics and Astronautics Abstract A systems study was conducted to determine the most mass

38

Brine flow in heated geologic salt.  

Science Conference Proceedings (OSTI)

This report is a summary of the physical processes, primary governing equations, solution approaches, and historic testing related to brine migration in geologic salt. Although most information presented in this report is not new, we synthesize a large amount of material scattered across dozens of laboratory reports, journal papers, conference proceedings, and textbooks. We present a mathematical description of the governing brine flow mechanisms in geologic salt. We outline the general coupled thermal, multi-phase hydrologic, and mechanical processes. We derive these processes' governing equations, which can be used to predict brine flow. These equations are valid under a wide variety of conditions applicable to radioactive waste disposal in rooms and boreholes excavated into geologic salt.

Kuhlman, Kristopher L.; Malama, Bwalya

2013-03-01T23:59:59.000Z

39

Automated Monitoring System for Waste Disposal Sites and Groundwater  

Science Conference Proceedings (OSTI)

A proposal submitted to the U.S. Department of Energy (DOE), Office of Science and Technology, Accelerated Site Technology Deployment (ASTD) program to deploy an automated monitoring system for waste disposal sites and groundwater, herein referred to as the ''Automated Monitoring System,'' was funded in fiscal year (FY) 2002. This two-year project included three parts: (1) deployment of cellular telephone modems on existing dataloggers, (2) development of a data management system, and (3) development of Internet accessibility. The proposed concept was initially (in FY 2002) to deploy cellular telephone modems on existing dataloggers and partially develop the data management system at the Nevada Test Site (NTS). This initial effort included both Bechtel Nevada (BN) and the Desert Research Institute (DRI). The following year (FY 2003), cellular modems were to be similarly deployed at Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL), and the early data management system developed at the NTS was to be brought to those locations for site-specific development and use. Also in FY 2003, additional site-specific development of the complete system was to be conducted at the NTS. To complete the project, certain data, depending on site-specific conditions or restrictions involving distribution of data, were to made available through the Internet via the DRI/Western Region Climate Center (WRCC) WEABASE platform. If the complete project had been implemented, the system schematic would have looked like the figure on the following page.

S. E. Rawlinson

2003-03-01T23:59:59.000Z

40

Modeling acid-gas generation from boiling chloride brines  

Science Conference Proceedings (OSTI)

This study investigates the generation of HCl and other acid gases from boiling calcium chloride dominated waters at atmospheric pressure, primarily using numerical modeling. The main focus of this investigation relates to the long-term geologic disposal of nuclear waste at Yucca Mountain, Nevada, where pore waters around waste-emplacement tunnels are expected to undergo boiling and evaporative concentration as a result of the heat released by spent nuclear fuel. Processes that are modeled include boiling of highly concentrated solutions, gas transport, and gas condensation accompanied by the dissociation of acid gases, causing low-pH condensate. Simple calculations are first carried out to evaluate condensate pH as a function of HCl gas fugacity and condensed water fraction for a vapor equilibrated with saturated calcium chloride brine at 50-150 C and 1 bar. The distillation of a calcium-chloride-dominated brine is then simulated with a reactive transport model using a brine composition representative of partially evaporated calcium-rich pore waters at Yucca Mountain. Results show a significant increase in boiling temperature from evaporative concentration, as well as low pH in condensates, particularly for dynamic systems where partial condensation takes place, which result in enrichment of HCl in condensates. These results are in qualitative agreement with experimental data from other studies. The combination of reactive transport with multicomponent brine chemistry to study evaporation, boiling, and the potential for acid gas generation at the proposed Yucca Mountain repository is seen as an improvement relative to previously applied simpler batch evaporation models. This approach allows the evaluation of thermal, hydrological, and chemical (THC) processes in a coupled manner, and modeling of settings much more relevant to actual field conditions than the distillation experiment considered. The actual and modeled distillation experiments do not represent expected conditions in an emplacement drift, but nevertheless illustrate the potential for acid-gas generation at moderate temperatures (<150 C).

Zhang, Guoxiang; Spycher, Nicolas; Sonnenthal, Eric; Steefel, Carl

2009-11-16T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Volatility of HCl and the thermodynamics of brines during brine dryout  

DOE Green Energy (OSTI)

Laboratory measurements of liquid-vapor partitioning (volatility) of chlorides from brines to steam can be used to indicate the potential for corrosion problems in geothermal systems. Measurements of volatilities of solutes in chloride brines have established a possible mechanism for the production of high-chloride steam from slightly acidic high temperature brines. Questions concerning the fate of NaCl in the steam production process have been addressed through extensive measurements of its volatility from brines ranging in concentration from dilute solutions to halite saturation. Recent measurements of chloride partitioning to steam over brines in contact with Geysers rock samples are consistent with our concept of the process for production of high-chloride steam.

Simonson, J.M.; Palmer, D.A.

1997-04-01T23:59:59.000Z

42

Generic Disposal System Modeling--Fiscal Year 2011 Progress Report  

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

12/2011 12/2011 Rev. 2 FCRD- T10-201 0-00005 FCRD Technical Integration Office (TIO) DOCUMENT NUMBER REQUEST TRANSMITTAL SHEET 1. Document Information Document Title/Description: Generic Disposal System Modeling--Fiscal Year 2011 Revision: 0 Progress Re~ort Assigned Document Number: FCRD-USED-2011-000184 Effective Start Date: 08/1112011 Document Author/Creator: D. Clayton, G. Freeze, T. Hadgu, E. Hardin, J. Lee, OR .~: J. Prouty, R. Rogers, W.M. Nutt, J. Berkholzer, H.H. Liu, L. Zheng, S. Chu Document Owner: Palmer Vaughn Date Range: Originating Organization: Sandia National Laboratories From: To: Milestone OM1 ~M2 OM3 ~M4 o Not a Milestone Milestone Number:: M21UF034101 and M41UF035102 Work Package WBS Number: FTSN11 UF0341 and FTSN11 UF0351; 1.02.08.03 Controlled Unclassified Infonnation (CUI) Type ~ None OOUO OAT o Other FCRD SYSTEM: Year: o FUEL Fuels 2011 OINTL International

43

Disposal Systems Evaluations and Tool Development - Engineered Barrier System Evaluation (Work Package LL1015080425)  

SciTech Connect

The Disposal Systems Evaluation Framework (DSEF) will use a logical process for developing one or more disposal system concepts (also referred to as repository system in this report) for any given waste form and geologic setting combination. In the Features, Events, and Processes (FEPs) group of work packages, there are seven categories of waste forms and eight categories of geologic setting being studied. The DSEF will also establish a Used Fuel Disposition Campaign (UFDC) knowledge management system to organize high-level information, data, and assumptions, thereby facilitating consistency in high-level system simulation and economic analyses. This system likely will be housed with the INL-based documentation system. Attention is given to lessons oearned from the systems used at the Waste Isolation Pilot Plant (WIPP) and the Yucca Mountain Project (YMP). Where reference material from other programs (e.g., international) is used or cited, the knowledge-management system imports the reference material directly or refer to it in bibliography form. Alternative data sets (e.g., from other programs) will also be utilized to evaluate their influence on DSEF analyses for given waste form and disposal-system combinations. The knowledge-management system can also be used to maintain the results of DSEF realizations, enabling the comparison and ranking of various waste-form/disposal-system-environment/disposal-system-design options. Finally, the UFDC knowledge-management system will be able to provide a compendium of 'templates' that can be utilized, in a labor-efficient fashion, to build parallel DSEF analyses (e.g., 'one offs'). The DSEF will not be a stand-alone, push-the-button and wait for the results, item of software. it will use osftware (probably EXCEL, initially), to guide the team members through a logical process of evaluating combinations of waste-form, disposal-syste-environment, and disposal-system design. In later stages, it will utilize software developed in the field of knowledge engineering and knowledge-management systems (Umeki et al. 2009). At certain points in the logical process, the DSEF software will point the evaluate to other software tools to do analyses needed to move the process forward. In the development of the DSEF, they will be mindful to make it no more complex than necessary to evaluate the system being considered. The DSEF will organize and document the work such that multiple realizations for different combinations can be compared and contrasted.

Blink, J A; Buscheck, T A; Halsey, W G; Wolery, T

2010-03-19T23:59:59.000Z

44

Comparison of elementary geothermal-brine power-production processes  

SciTech Connect

From applied technology geothermal committee meeting; Idaho Falls, Idaho, USA (7 Aug 1973). A comparison of three simple geothermal power- production systems shows that the flashed steam and the compound systems are favored for use with high-temperature brines. The binary system becomes economically competitive only when used on low-temperature brines (enthalpies less than 350 Btu/lb). Geothermal power appears to be economically attractive even when low-temperature brines are used. (auth)

Green, M.A.; Laird, A.D.K.

1973-08-01T23:59:59.000Z

45

BIOCHEMICAL PROCESSES FOR GEOTHERMAL BRINE TREATMENT  

DOE Green Energy (OSTI)

As part of the DOE Geothermal Energy Program, BNL's Advanced Biochemical Processes for Geothermal Brines (ABPGB) project is aimed at the development of cost-efficient and environmentally acceptable technologies for the disposal of geothermal wastes. Extensive chemical studies of high and low salinity brines and precipitates have indicated that in addition to trace quantities of regulated substances, e.g., toxic metals such as arsenic and mercury, there are significant concentrations of valuable metals, including gold, silver and platinum. Further chemical and physical studies of the silica product have also shown that the produced silica is a valuable material with commercial potential. A combined biochemical and chemical technology is being developed which (1) solubilizes, separates, and removes environmentally regulated constituents in geothermal precipitates and brines (2) generates an amorphous silica product which may be used as feedstock for the production of revenue generating materials, (3) recover economically valuable trace metals and salts. Geothermal power resources which utilize low salinity brines and use the Stretford process for hydrogen sulfide abatement generate a contaminated sulfur cake. Combined technology converts such sulfur to a commercial grade sulfur, suitable for agricultural use. The R and D activities at BNL are conducted jointly with industrial parties in an effort focused on field applications.

PREMUZIC,E.T.; LIN,M.S.; BOHENEK,M.; JOSHI-TOPE,G.; ZHOU,W.; SHELENKOVA,L.; WILKE,R.

1998-09-20T23:59:59.000Z

46

Biochemical processes for geothermal brine treatment  

DOE Green Energy (OSTI)

As part of the DOE Geothermal Energy Program, BNL`s Advanced Biochemical Processes for Geothermal Brines (ABPGB) project is aimed at the development of cost-efficient and environmentally acceptable technologies for the disposal of geothermal wastes. Extensive chemical studies of high and low salinity brines and precipitates have indicated that in addition to trace quantities of regulated substances, e.g., toxic metals such as arsenic and mercury, there are significant concentrations of valuable metals, including gold, silver and platinum. Further chemical and physical studies of the silica product have also shown that the produced silica is a valuable material with commercial potential. A combined biochemical and chemical technology is being developed which (1) solubilizes, separates, and removes environmentally regulated constituents in geothermal precipitates and brines, (2) generates an amorphous silica product which may be used as feedstock for the production of revenue generating materials, (3) recover economically valuable trace metals and salts. Geothermal power resources which utilize low salinity brines and use the Stretford process for hydrogen sulfide abatement generate a contaminated sulfur cake. Combined technology converts such sulfur to a commercial grade sulfur, suitable for agricultural use. The R and D activities at BNL are conducted jointly with industrial parties in an effort focused on field applications.

Premuzic, E.T.; Lin, M.S.; Bohenek, M.; Joshi-Tope, G.; Zhou, W.; Shelenkova, L.; Wilke, R.

1998-08-01T23:59:59.000Z

47

Disposal systems evaluations and tool development : Engineered Barrier System (EBS) evaluation.  

SciTech Connect

Key components of the nuclear fuel cycle are short-term storage and long-term disposal of nuclear waste. The latter encompasses the immobilization of used nuclear fuel (UNF) and radioactive waste streams generated by various phases of the nuclear fuel cycle, and the safe and permanent disposition of these waste forms in geological repository environments. The engineered barrier system (EBS) plays a very important role in the long-term isolation of nuclear waste in geological repository environments. EBS concepts and their interactions with the natural barrier are inherently important to the long-term performance assessment of the safety case where nuclear waste disposition needs to be evaluated for time periods of up to one million years. Making the safety case needed in the decision-making process for the recommendation and the eventual embracement of a disposal system concept requires a multi-faceted integration of knowledge and evidence-gathering to demonstrate the required confidence level in a deep geological disposal site and to evaluate long-term repository performance. The focus of this report is the following: (1) Evaluation of EBS in long-term disposal systems in deep geologic environments with emphasis on the multi-barrier concept; (2) Evaluation of key parameters in the characterization of EBS performance; (3) Identification of key knowledge gaps and uncertainties; and (4) Evaluation of tools and modeling approaches for EBS processes and performance. The above topics will be evaluated through the analysis of the following: (1) Overview of EBS concepts for various NW disposal systems; (2) Natural and man-made analogs, room chemistry, hydrochemistry of deep subsurface environments, and EBS material stability in near-field environments; (3) Reactive Transport and Coupled Thermal-Hydrological-Mechanical-Chemical (THMC) processes in EBS; and (4) Thermal analysis toolkit, metallic barrier degradation mode survey, and development of a Disposal Systems Evaluation Framework (DSEF). This report will focus on the multi-barrier concept of EBS and variants of this type which in essence is the most adopted concept by various repository programs. Empasis is given mainly to the evaluation of EBS materials and processes through the analysis of published studies in the scientific literature of past and existing repository research programs. Tool evaluations are also emphasized, particularly on THCM processes and chemical equilibria. Although being an increasingly important aspect of NW disposition, short-term or interim storage of NW will be briefly discussed but not to the extent of the EBS issues relevant to disposal systems in deep geologic environments. Interim storage will be discussed in the report Evaluation of Storage Concepts FY10 Final Report (Weiner et al. 2010).

Rutqvist, Jonny (LBNL); Liu, Hui-Hai (LBNL); Steefel, Carl I. (LBNL); Serrano de Caro, M. A. (LLNL); Caporuscio, Florie Andre (LANL); Birkholzer, Jens T. (LBNL); Blink, James A. (LLNL); Sutton, Mark A. (LLNL); Xu, Hongwu (LANL); Buscheck, Thomas A. (LLNL); Levy, Schon S. (LANL); Tsang, Chin-Fu (LBNL); Sonnenthal, Eric (LBNL); Halsey, William G. (LLNL); Jove-Colon, Carlos F.; Wolery, Thomas J. (LLNL)

2011-01-01T23:59:59.000Z

48

Modelling the upgrade of an urban waste disposal system  

Science Conference Proceedings (OSTI)

The waste intermodal station of Clyde, in the city of Sydney, Australia, is in the heart of a complex network of terminals connected by road and rail to transport urban waste from its first collection to its final disposal. The amount of waste the network ... Keywords: Discrete-event simulation, Intermodal transfer, Satellite stations, Urban solid waste, Waste collection

G. Guariso; F. Michetti; F. Porta; S. Moore

2009-11-01T23:59:59.000Z

49

Sustainable Carbon Sequestration: Increasing CO2-Storage Efficiency through a CO2-Brine Displacement Approach  

E-Print Network (OSTI)

CO2 sequestration is one of the proposed methods for reducing anthropogenic CO2 emissions to the atmosphere and therefore mitigating global climate change. Few studies on storing CO2 in an aquifer have been conducted on a regional scale. This study offers a conceptual approach to increasing the storage efficiency of CO2 injection in saline formations and investigates what an actual CO2 storage project might entail using field data for the Woodbine aquifer in East Texas. The study considers three aquifer management strategies for injecting CO2 emissions from nearby coal-fired power plants into the Woodbine aquifer. The aquifer management strategies studied are bulk CO2 injection, and two CO2-brine displacement strategies. A conceptual model performed with homogeneous and average reservoir properties reveals that bulk injection of CO2 pressurizes the aquifer, has a storage efficiency of 0.46% and can only last for 20 years without risk of fracturing the CO2 injection wells. The CO2-brine displacement strategy can continue injecting CO2 for as many as 240 years until CO2 begins to break through in the production wells. This offers 12 times greater CO2 storage efficiency than the bulk injection strategy. A full field simulation with a geological model based on existing aquifer data validates the storage capacity claims made by the conceptual model. A key feature in the geological model is the Mexia-Talco fault system that serves as a likely boundary between the saline aquifer region suitable for CO2 storage and an updip fresh water region. Simulation results show that CO2 does not leak into the fresh water region of the iv aquifer after 1000 years of monitoring if the faults have zero transmissibility, but a negligible volume of brine eventually gets through the mostly sealing fault system as pressure across the faults slowly equilibrates during the monitoring period. However, for fault transmissibilities of 0.1 and 1, both brine and CO2 leak into the fresh water aquifer in increasing amounts for both bulk injection and CO2-brine displacement strategies. In addition, brine production wells draw some fresh water into the saline aquifer if the Mexia-Talco fault system is not sealing. A CO2 storage project in the Woodbine aquifer would impact as many as 15 counties with high-pressure CO2 pipelines stretching as long as 875 km from the CO2 source to the injection site. The required percentage of power plant energy capacity was 7.43% for bulk injection, 7.9% for the external brine disposal case, and 10.2% for the internal saturated brine injection case. The estimated total cost was $0.00132–$0.00146/kWh for the bulk injection, $0.00191–$0.00211/kWh for the external brine disposal case, and $0.0019–$0.00209/kWh for the internal saturated brine injection case.

Akinnikawe, Oyewande

2012-08-01T23:59:59.000Z

50

Methane extraction from geopressured-geothermal brine at wellhead conditions  

DOE Green Energy (OSTI)

Disposal of geopressured-geothermal brine effluents by injection is expected to be costly, even into shallow aquifers. If injection into the production reservoir becomes necessary to maintain productivity and to minimize subsidence, the injection pumping costs can become overwhelming. An option aimed at reducing injection pump operating costs is to maintain a higher than normal pressure at the production wellhead to reduce the injection pumping load. The crucial element, however, is that a significant portion of CH/sub 4/ remains in solution and must be recovered in order for the pressure maintenance option to be cost effective. A laboratory and field test capability has been established, and several methods for extracting dissolved CH/sub 4/ at high temperature and pressure are being evaluated. Solvent extraction and use of hydraulic motors or turbines coupled to CH/sub 4/ recovery systems are the leading candidate methods.

Quong, R.; Owen, L.B.; Locke, F.E.; Otto, C.H.; Netherton, R.; Lorensen, L.E.

1980-05-29T23:59:59.000Z

51

Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation  

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

Disposal Systems Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation (FCRD-USED-2011-000132) Prepared for U.S. Department of Energy Used Fuel Disposition Campaign Carlos F. Jové Colón (SNL) Florie A. Caporuscio, Schön S. Levy (LANL) Mark Sutton, James A. Blink, Harris R. Greenberg, Massimiliano Fratoni, William G. Halsey, Thomas J. Wolery (LLNL) Jonny Rutqvist, Carl I. Steefel, Juan Galindez, Jens Birkholzer, Hui-Hai Liu, (LBNL) June 15 th , 2011 SAND2011-4335 P Prepared by: Sandia National Laboratories Albuquerque, New Mexico 87185 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of

52

Tank waste remediation system retrieval and disposal mission waste feed delivery plan  

Science Conference Proceedings (OSTI)

This document is a plan presenting the objectives, organization, and management and technical approaches for the Waste Feed Delivery (WFD) Program. This WFD Plan focuses on the Tank Waste Remediation System (TWRS) Project`s Waste Retrieval and Disposal Mission.

Potter, R.D.

1998-01-08T23:59:59.000Z

53

Treatment methods for geothermal brines  

DOE Green Energy (OSTI)

A survey is made of commercially available methods currently in use as well as those which might be used to prevent scaling and corrosion in geothermal brines. More emphasis is placed on scaling. Treatments are classified as inhibitors, alterants and coagulants; they are applied to control scaling and corrosion in fresh and waste geothermal brines. Recommendations for research in brine treatment are described.

Phillips, S.L.; Mathur, A.K.; Garrison, W.

1979-04-01T23:59:59.000Z

54

Processing of high salinity brines for subsurface injection  

DOE Green Energy (OSTI)

Different chemical pretreatments and filtration methods were evaluated as a possible means of clarifying and improving the injectivity of hypersaline brines. Six different downflow media combinations were evaluated over three geopressurized sites, using test data from 4 inch diameter filters. Also, tests were conducted with one hollow fiber ultrafilter unit and two types of disposable cartridge filters. The test procedures are mentioned briefly. (MHR)

Thompson, R.E.; Raber, E.

1979-08-06T23:59:59.000Z

55

Wetting behavior of selected crude oil/brine/rock systems. Topical report, March 1, 1995--March 31, 1996  

SciTech Connect

Previous studies of crude oil/brine/rock (COBR) and related ensembles showed that wettability and its effect on oil recovery depend on numerous complex interactions. In the present work, the wettability of COBR ensembles prepared using Prudhoe Bay crude oil, a synthetic formation brine, and Berea Sandstone was varied by systematic change in initial water saturation and length of aging time at reservoir temperature (88 C). All displacement tests were run at ambient temperature. Various degrees of water wetness were achieved and quantified by a modified Amott wettability index to water, the relative pseudo work of imbibition, and a newly defined apparent advancing dynamic contact angle. Pairs of spontaneous imbibition (oil recovery by spontaneous imbibition of water) and waterflood (oil recovery vs. pore volumes of water injected) curves were measured for each of the induced wetting states. Several trends were observed. Imbibition rate, and hence water wetness, decreased with increase in aging time and with decrease in initial water saturation. Breakthrough recoveries and final oil recovery by waterflooding increased with decrease in water wetness. Correlations between water wetness and oil recovery by waterflooding and spontaneous imbibition are presented.

Zhou, X.; Morrow, N.R.; Ma, S.

1996-12-31T23:59:59.000Z

56

Improving the performance of brine wells at Gulf Coast strategic petroleum reserve sites  

DOE Green Energy (OSTI)

At the request of the Department of Energy, field techniques were developed to evaluate and improve the injection of brine into wells at Strategic Petroleum Reserve (SPR) sites. These wells are necessary for the disposal of saturated brine removed from salt domes where oil is being stored. The wells, which were accepting brine at 50 percent or less of their initial design rates, were impaired by saturated brine containing particulates that deposited on the sand face and in the geologic formation next to the wellbore. Corrosion of the brine-disposal pipelines and injection wells contributed to the impairment by adding significant amounts of particulates in the form of corrosion products. When tests were implemented at the SPR sites, it was found that the poor quality of injected brines was the primary cause of impaired injection; that granular-media filtration, when used with chemical pretreatment, is an effective method for removing particulates from hypersaline brine; that satisfactory injection-well performance can be attained with prefiltered brines; and that corrosion rates can be substantially reduced by oxygen-scavenging.

Owen, L.B.; Quong, R. (eds.)

1979-11-05T23:59:59.000Z

57

Tank waste remediation system retrieval and disposal mission initial updated baseline summary  

Science Conference Proceedings (OSTI)

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor`s Readiness-to-Proceed in support of the Phase 1B mission.

Swita, W.R.

1998-01-05T23:59:59.000Z

58

Perspectives on integrating the US radioactive waste disposal system  

SciTech Connect

The waste management systems being developed and deployed by the DOE Office of Civilian Radioactive Waste Management (OCRWM) is large, complex, decentralized, and long term. As a result, a systems integration approach has been implemented by OCRWM. The fundamentals of systems integration and its application are examined in the context of the OCRWM program. This application is commendable, and some additional systems integration features are suggested to enhance its benefits. 6 refs., 1 fig.

Culler, F.L. (Electric Power Research Inst., Palo Alto, CA (USA)); Croff, A.G. (Oak Ridge National Lab., TN (USA))

1990-01-01T23:59:59.000Z

59

Explosive destruction system for disposal of chemical munitions  

DOE Patents (OSTI)

An explosive destruction system and method for safely destroying explosively configured chemical munitions. The system comprises a sealable, gas-tight explosive containment vessel, a fragment suppression system positioned in said vessel, and shaped charge means for accessing the interior of the munition when the munition is placed within the vessel and fragment suppression system. Also provided is a means for treatment and neutralization of the munition's chemical fills, and means for heating and agitating the contents of the vessel. The system is portable, rapidly deployable and provides the capability of explosively destroying and detoxifying chemical munitions within a gas-tight enclosure so that there is no venting of toxic or hazardous chemicals during detonation.

Tschritter, Kenneth L. (Livermore, CA); Haroldsen, Brent L. (Manteca, CA); Shepodd, Timothy J. (Livermore, CA); Stofleth, Jerome H. (Albuquerque, NM); DiBerardo, Raymond A. (Baltimore, MD)

2005-04-19T23:59:59.000Z

60

Explosive destruction system for disposal of chemical munitions  

SciTech Connect

An explosive destruction system and method for safely destroying explosively configured chemical munitions. The system comprises a sealable, gas-tight explosive containment vessel, a fragment suppression system positioned in said vessel, and shaped charge means for accessing the interior of the munition when the munition is placed within the vessel and fragment suppression system. Also provided is a means for treatment and neutralization of the munition's chemical fills, and means for heating and agitating the contents of the vessel. The system is portable, rapidly deployable and provides the capability of explosively destroying and detoxifying chemical munitions within a gas-tight enclosure so that there is no venting of toxic or hazardous chemicals during detonation.

Tschritter, Kenneth L. (Livermore, CA); Haroldsen, Brent L. (Manteca, CA); Shepodd, Timothy J. (Livermore, CA); Stofleth, Jerome H. (Albuquerque, NM); DiBerardo, Raymond A. (Baltimore, MD)

2005-04-19T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description  

SciTech Connect

This document is prepared in order to support the US Department of Energy`s evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors.

McLaughlin, T.J.

1998-01-06T23:59:59.000Z

62

By-product disposal from MSW incinerator flue gas cleaning systems  

Science Conference Proceedings (OSTI)

Waste incineration has been found to be an effective method of achieving significant volume reduction of Municipal Solid Waste (MSW) while at the same time allowing for energy recovery in the form of steam or electricity. Concern over potential air pollution from incinerators in the form of acid gases, heavy metals and dioxins has led to the application of Spray Dryer Absorption (SDA) flue gas cleaning systems to control these emissions. SDA has demonstrated high efficiencies in converting these air pollutants into a dry by-product for disposal. This has, in turn, led to concerns over potential secondary pollution from the disposal of these by-products. This paper presents a description of the SDA process and reviews disposal options for the SDA product. Product characteristics are given and results of leaching studies are presented. Comparisons between EPA's and TEP and TCLP procedures are presented. Results of dioxin measurements from the by-product are given.

Donnelly, J.R. (Joy Manufacturing Co., Los Angeles, CA (US)); Jons, E. (A/S Niro Atomizer, Copenhagen (DK))

1987-01-01T23:59:59.000Z

63

Discussions on Disposal Forms of Auxiliary Heat Source in Surface Water Heat Pump System  

E-Print Network (OSTI)

This paper presents two common forms of auxiliary heat source in surface water heat pump system and puts forward the idea that the disposal forms affect operation cost. It deduces operation cost per hour of the two forms. With a project calculation, it illuminates that the post-located auxiliary heat source cheaper and superior to the fore-located one.

Qian, J.; Sun, D.; Li, X.; Li, G.

2006-01-01T23:59:59.000Z

64

Dissolved Gas Analysis (DGA) by EPRI Disposable Oil Sampling System (EDOSS)  

Science Conference Proceedings (OSTI)

The utility industry has increasingly applied dissolved gas analysis (DGA) to assess the condition of fluid-filled equipment. Modifications to the EPRI Pressurized Oil Sampling System (EPOSS), a novel DGA method developed in 1983, have rendered the system more cost-effective without compromising its accuracy and precision. Designated the EPRI Disposable Oil Sampling System, EDOSS safely operates with all types of fluid-filled equipment under most weather conditions.

1998-10-12T23:59:59.000Z

65

Assessment of subsurface salt water disposal experience on the Texas and Louisiana Gulf Coast for applications to disposal of salt water from geopressured geothermal wells  

SciTech Connect

A representative cross section of the literature on the disposal of geothermal brine was perused and some of the general information and concepts is summarized. The following sections are included: disposal statistics--Texas Railroad Commission; disposal statistics--Louisiana Office of Conservation; policies for administering salt water disposal operations; salt water disposal experience of Gulf Coast operators; and Federal Strategic Petroleum Reserve Program's brine disposal operations. The literature cited is listed in the appended list of references. Additional literature is listed in the bibliography. (MHR)

Knutson, C.K.; Boardman, C.R.

1978-08-04T23:59:59.000Z

66

Assessment of subsurface salt water disposal experience on the Texas and Louisiana Gulf Coast for applications to disposal of salt water from geopressured geothermal wells  

DOE Green Energy (OSTI)

A representative cross section of the literature on the disposal of geothermal brine was perused and some of the general information and concepts is summarized. The following sections are included: disposal statistics--Texas Railroad Commission; disposal statistics--Louisiana Office of Conservation; policies for administering salt water disposal operations; salt water disposal experience of Gulf Coast operators; and Federal Strategic Petroleum Reserve Program's brine disposal operations. The literature cited is listed in the appended list of references. Additional literature is listed in the bibliography. (MHR)

Knutson, C.K.; Boardman, C.R.

1978-08-04T23:59:59.000Z

67

Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses  

SciTech Connect

This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

1994-08-01T23:59:59.000Z

68

Disposable rabbit  

DOE Patents (OSTI)

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, Leroy C. (Idaho Falls, ID); Trammell, David R. (Rigby, ID)

1986-01-01T23:59:59.000Z

69

Disposal rabbit  

DOE Patents (OSTI)

A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

Lewis, L.C.; Trammell, D.R.

1983-10-12T23:59:59.000Z

70

Weeks Island brine diffuser site study: baseline conditions and environmental assessment technical report  

SciTech Connect

This technical report presents the results of a study conducted at two alternative brine diffuser sites (A and B) proposed for the Weeks Island salt dome, together with an analysis of the potential physical, chemical, and biological effects of brine disposal for this area of the Gulf of Mexico. Brine would result from either the leaching of salt domes to form or enlarge oil storage caverns, or the subsequent use of these caverns for crude oil storage in the Strategic Petroleum Reserve (SPR) program. Brine leached from the Weeks Island salt dome would be transported through a pipeline which would extend from the salt dome either 27 nautical miles (32 statute miles) for Site A, or 41 nautical miles (47 statute miles) for Site B, into Gulf waters. The brine would be discharged at these sites through an offshore diffuser at a sustained peak rate of 39 ft/sup 3//sec. The disposal of large quantities of brine in the Gulf could have a significant impact on the biology and water quality of the area. Physical and chemical measurements of the marine environment at Sites A and B were taken between September 1977 and July 1978 to correlate the existing environmental conditions with the estimated physical extent of tthe brine discharge as predicted by the MIT model (US Dept. of Commerce, 1977a). Measurements of wind, tide, waves, currents, and stratification (water column structure) were also obtained since the diffusion and dispersion of the brine plume are a function of the local circulation regime. These data were used to calculate both near- and far-field concentrations of brine, and may also be used in the design criteria for diffuser port configuration and verification of the plume model. Biological samples were taken to characterize the sites and to predict potential areas of impact with regard to the discharge. This sampling focused on benthic organisms and demersal fish. (DMC)

None

1980-12-12T23:59:59.000Z

71

Navy explosive ordnance disposal project: Optical ordnance system development. Final report  

SciTech Connect

An optical ordnance firing system consisting of a portable hand held solid state rod laser and an optically ignited detonator has been developed for use in explosive ordnance disposal (EOD) activities. Solid state rod laser systems designed to have an output of 150 mJ in a 500 microsecond pulse have been produced and evaluated. A laser ignited detonator containing no primary explosives has been designed and fabricated. The detonator has the same functional output as an electrically fired blasting cap. The optical ordnance firing system has demonstrated the ability to reliably detonate Comp C-4 through 1000 meters of optical fiber.

Merson, J.A.; Salas, F.J.; Helsel, F.M.

1996-03-01T23:59:59.000Z

72

Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) System Configuration Management Plan  

Science Conference Proceedings (OSTI)

The Treated Effluent Disposal Facility Operator Training Station (TEDF OTS) is a computer based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS). It consists of PC compatible computers and a Programmable Logic Controller (PLC) designed to emulate the responses of various plant components connected to or under the control of the CCS. The system trains operators by simulating the normal operation but also has the ability to force failures of different equipment allowing the operator to react and observe the events. The paper describes organization, responsibilities, system configuration management activities, software, and action plans for fully utilizing the simulation program.

Carter, R.L. Jr.

1994-06-01T23:59:59.000Z

73

Advanced biochemical processes for geothermal brines current developments  

DOE Green Energy (OSTI)

A research program at Brookhaven National Laboratory (BNL) which deals with the development and application of processes for the treatment of geothermal brines and sludges has led to the identification and design of cost-efficient and environmentally friendly treatment methodology. Initially the primary goal of the processing was to convert geothermal wastes into disposable materials whose chemical composition would satisfy environmental regulations. An expansion of the R&D effort allowed to identify a combination of biochemical and chemical processes which became a basis for the development of a technology for the treatment of geothermal brines and sludges. The new technology satisfies environmental regulatory requirements and concurrently converts the geothermal brines and sludges into commercially promising products. Because the chemical composition of geothermal wastes depends on the type of the resource and therefore differs, the emerging technology has to be also flexible so that it can be readily modified to suit the needs of a particular type of resource. Recent conceptional designs for the processing of hypersaline and low salinity brines and sludges will be discussed.

Premuzic, E.T.; Lin, M.S.; Bohenek, M.

1997-03-10T23:59:59.000Z

74

Advanced biochemical processes for geothermal brines: Current developments  

DOE Green Energy (OSTI)

A research program at Brookhaven National Laboratory (BNL) which deals with the development and application of processes for the treatment of geothermal brines and sludges has led to the identification and design of cost-efficient and environmentally friendly treatment methodology. Initially the primary goal of the processing was to convert geothermal wastes into disposable materials whose chemical composition would satisfy environmental regulations. An expansion of the r and D effort identified a combination of biochemical and chemical processes which became the basis for the development of a technology for the treatment of geothermal brines and sludges. The new technology satisfies environmental regulatory requirements and concurrently converts the geothermal brines and sludges into commercially promising products. Because the chemical composition of geothermal wastes depends on the type of the resource, the emerging technology has to be flexible so that it can be readily modified to suit the needs of a particular type of resource. Recent conceptional designs for the processing of hypersaline and low salinity brines and sludges will be discussed.

Premuzic, E.T.; Lin, M.S.; Bohenek, M. [Brookhaven National Lab., Upton, NY (United States). Energy Science and Technology Div.; Bajsarowicz, V. [CET Environmental Services, Inc., Richmond, CA (United States); McCloud, M. [C.E. Holt/California Energy, Pasadena, CA (United States)

1997-07-07T23:59:59.000Z

75

Preliminary Systems Design Study assessment report. Volume 5, Land disposal compliance and hydrogen generation restricted concepts  

SciTech Connect

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques available for the remediation of hazardous and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept.

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1991-11-01T23:59:59.000Z

76

Gas evolution from geopressured brines  

DOE Green Energy (OSTI)

The process of gas evolution from geopressured brine is examined using as a basis the many past studies of gas evolution from liquids in porous media. A discussion of a number of speculations that have been made concerning gas evolution from geopressured brines is provided. According to one, rapid pressure reduction will cause methane gas to evolve as when one opens a champagne bottle. It has been further speculated that evolved methane gas would migrate up to form an easily producible cap. As a result of detailed analyses, it can be concluded that methane gas evolution from geopressured brines is far too small to ever form a connected gas saturation except very near to the producing well. Thus, no significant gas cap could ever form. Because of the very low solubility of methaned in brine, the process of methane gas evolution is not at all analogous to evolution of carbon dioxide from champagne. A number of other speculations and questions on gas evolution are analyzed, and procedures for completing wells and testing geopressured brine reservoirs are discussed, with the conclusion that presently used procedures will provide adequate data to enable a good evaluation of this resource.

Matthews, C.S.

1980-06-01T23:59:59.000Z

77

Tank waste remediation system retrieval and disposal mission initial updated baseline summary  

SciTech Connect

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors` operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors` facilities.

Swita, W.R.

1998-01-09T23:59:59.000Z

78

PERIODIC WASTE DISPOSAL SYSTEM MATERIAL BALANCE TEST. CORE I, SEED 2. Section 2. Test Results T-641317  

SciTech Connect

ABS>A test was made on the Radioactive Waste Disposal (RWD) system to determine the acceptability of procedures used in containing, processing, and disposing the wastes received from the plant during a steady-state operation. The RWD system was found to be adequate and to have 60,000 gallons available at all times in the Surge and Decay tanks for safety injection. (D.L.C.)

1961-03-17T23:59:59.000Z

79

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foaming Options · Compressed Air Foam Systems (CAFS) · Foam Blower · Foam Generator · Nozzle Systems #12;Disposal: Science and Theory Compressed ­ Industry owned response team #12;Disposal: Science and Theory Commercial CAFS for Poultry · Poultry

Benson, Eric R.

80

Use of depleted uranium metal as cask shielding in high-level waste storage, transport, and disposal systems  

SciTech Connect

The US DOE has amassed over 555,000 metric tons of depleted uranium from its uranium enrichment operations. Rather than dispose of this depleted uranium as waste, this study explores a beneficial use of depleted uranium as metal shielding in casks designed to contain canisters of vitrified high-level waste. Two high-level waste storage, transport, and disposal shielded cask systems are analyzed. The first system employs a shielded storage and disposal cask having a separate reusable transportation overpack. The second system employs a shielded combined storage, transport, and disposal cask. Conceptual cask designs that hold 1, 3, 4 and 7 high-level waste canisters are described for both systems. In all cases, cask design feasibility was established and analyses indicate that these casks meet applicable thermal, structural, shielding, and contact-handled requirements. Depleted uranium metal casting, fabrication, environmental, and radiation compatibility considerations are discussed and found to pose no serious implementation problems. About one-fourth of the depleted uranium inventory would be used to produce the casks required to store and dispose of the nearly 15,400 high-level waste canisters that would be produced. This study estimates the total-system cost for the preferred 7-canister storage and disposal configuration having a separate transportation overpack would be $6.3 billion. When credits are taken for depleted uranium disposal cost, a cost that would be avoided if depleted uranium were used as cask shielding material rather than disposed of as waste, total system net costs are between $3.8 billion and $5.5 billion.

Yoshimura, H.R.; Ludwigsen, J.S.; McAllaster, M.E. [and others

1996-09-01T23:59:59.000Z

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


81

Modeling acid-gas generation from boiling chloride brines  

E-Print Network (OSTI)

distillation of a calcium-chloride-dominant brine was simulateddistillation of a calcium-chloride-dominated brine is then simulated

Zhang, Guoxiang

2010-01-01T23:59:59.000Z

82

Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal  

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

performance cleanup closure performance cleanup closure M E Environmental Management Environmental Management Performance Assessment Community of Practice Technical Exchange July 13-14, 2009 Modeling the Performance of Engineered Systems for Closure and Near-Surface Disposal - Overview and Focused Discussions David S. Kosson CRESP and Vanderbilt University Tank Waste Corporate Board Meeting July 29, 2009 1 safety performance cleanup closure M E Environmental Management Environmental Management Agenda * Overview of DOE Performance Assessment Practices * Focused Discussions - Role of PA Process in Risk Communication and Decisions - Modeling Improvements - PA Assumption Validation - Uncertainty Evaluation - Evolving EPA Developments - Related IAEA Activities * Looking forward

83

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

84

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

85

Study on scale formation and suppression in heat-exchange systems for simulated geothermal brines. Final report, January 12, 1976-March 5, 1978  

DOE Green Energy (OSTI)

Control of scale formation in heat exchangers using simulated geothermal waters can be achieved by lowering the pH of the water to pH 6 or lower. This does not, however, appear to be an economic approach for highly buffered geothermal brines and would lead to severe corrosion problems. Two commercial scale control agents, Calgon CL-165 and Monsanto Dequest 2060, showed promise of effecting scaling in a minor way and should be tested further on actual geothermal waters. Other scale control methods tested were unsuccessful. These included seeding experiments, turbulence promotin and electostatic and electromagnetic devices reputated to modify scale formation. The experiments were performed with tube-in-shell heat exchangers using simulated geothermal waters prepared from a salt dome solution based brine. The scale formed was primarily silica with a small percent of calcium carbonate and traces of magnesium and iron. Physically it was a hydrous soft solid adhering only lightly to the heat exchange surface. This is not typical of geothermal water scales encountered in high temperature brine operations and the results of the scale control expeirments should be evaluated with that in mind.

Wilson, J.S.; King, J.E.; Bullard, G.R.

1978-01-01T23:59:59.000Z

86

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Brief History of Foam 2004 ­ Bud and foam 2009 ­ No advantage for gas #12;Disposal: Science and Theory What is foam? · What is fire fighting system. #12;Disposal: Science and Theory Foam Composition · Foam can include ­ Mixture of surfactants

Benson, Eric R.

87

Chemistry of silica in Cerro Prieto brines  

DOE Green Energy (OSTI)

The precipitation of amorphous silica from synthetic geothermal brines which resemble the flashed brine at Cerro Prieto has been studied. It was found that part of the dissolved silica quickly polymerizes to form suspended colloidal silica. The colloidal silica flocculates and settles slowly at unmodified brine pH values near 7.35. Raising the pH of the brine to about 7.8 by adding base and stirring for a few minutes causes rapid and complete flocculation and settling. These results have been confirmed in the field using actual Cerro Prieto brine. Both in the laboratory and in the field quaternary amines were found to be effective with some brine compositions but not with others. Polyacrylamides do not work at all. These results suggest the following simple preinjection brine treatment process: age the brine for 10 to 20 minutes in a covered holding tank, add 20 to 30 ppM lime (CaO), stir for 5 minutes, and separate the flocculated silica from the brine using a conventional clarifier. The brine coming out of such a process will be almost completely free of suspended solids. The pilot plant tests needed to reduce this conceptual process to practice are discussed. The rate of deposition of silica scale from synthetic brines was separately studied. It was found that a modest decrease in pH could significantly reduce the scaling rate at a reasonable cost. The equilibrium chemistry of Cerro Prieto brine was studied theoretically. These calculations indicate that increasing the brine pH to remove silica might cause some precipitation of carbonate minerals, but also that this problem could easily be eliminated at a reasonable cost if it did arise.

Weres, O.; Tsao, L.; Iglesias, E.

1980-04-01T23:59:59.000Z

88

Chemistry of Silica in Cerro Prieto Brines  

DOE Green Energy (OSTI)

The precipitation of amorphous silica from synthetic geothermal, brines which resemble the flashed brine at Cerro Prieto has been studied. It was found that part of the dissolved silica quickly polymerizes to form suspended colloidal silica. The colloidal silica flocculates and settles slowly at unmodified brine pH values near 7.35. Raising the pH of the brine to about 7.8 by adding base and stirring for a few minutes causes rapid and complete flocculation and settling. these results have been confirmed in the field using actual Cerro Prieto brine. Both in the laboratory and in the field quaternary amines were found to be effective with some brine compositions but not with others. Polyacrylamides do not work at all. These results suggest the following simple preinjection brine treatment process: age the brine for 10-20 minutes in a covered holding tank, add 20-30 ppm lime (CaO), stir for 5 minutes, and separate the flocculated silica from the brine using a conventional clarifier. The brine coming out of such a process will be almost completely free of suspended solids. The pilot plant tests needed to reduce this conceptual process to practice are discussed. The rate of deposition of silica scale from synthetic brines was separately studied. It was found that a modest decrease in pH could significantly reduce the scaling rate at a reasonable cost. The equilibrium chemistry of Cerro Prieto brine was studied theoretically. These calculations indicate that increasing the brine pH to remove silica might cause some precipitation of carbonate minerals, but also that this problem could easily be eliminated at a reasonable cost if it did arise.

Weres, Oleh; Iglesias, Eduardo; Tsao, Leon

1980-04-01T23:59:59.000Z

89

Geothermal Power Production from Brine Co-Produced from Oil and Gas Wells  

Science Conference Proceedings (OSTI)

Millions of barrels of water (brine) per day are co-produced from oil and gas wells. Currently, the oil and gas industry views this as a waste stream that costs millions of dollars per year to manage, through either treatment or disposal/reinjection. A significant percentage of the co-produced brine, however, flows at sufficient rate and temperature to generate power using a binary power plant, and this is viewed by some as a potential value stream. The value lies in that the co-produced water is "free" ...

2012-04-30T23:59:59.000Z

90

Study of thermal-gradient-induced migration of brine inclusions in salt. Final report  

Science Conference Proceedings (OSTI)

Natural salt deposits, which are being considered for high-level waste disposal, contain a small volume fraction of water in the form of brine inclusions distributed throughout the salt. Radioactive decay heating of the nuclear wastes will impose a temperature gradient on the surrounding salt which mobilizes the brine inclusions. Inclusions filled completely with brine (the all-liquid inclusions) migrate up the temperature gradient and eventually accumulate brine near the buried waste forms. The brine may slowly corrode or degrade the waste forms, which is undesirable. Therefore it is important to consider the migration of brine inclusions in salt under imposed temperature gradients to properly evaluate the performance of a future salt repository for nuclear wastes. The migration velocities of the inclusions were found to be dependent on temperature, temperature gradient, and inclusion shape and size. The velocities were also dictated by the interfacial mass transfer resistance at brine/solid interface. This interfacial resistance depends on the dislocation density in the crystal, which in turn, depends on the axial compressive loading of the crystal. At low axial loads, the dependence between the velocity and temperature gradient is nonlinear. At high axial loads, the interfacial resistance is reduced and the migration velocity depends linearly on the temperature gradient. All-liquid inclusions filled with mixed brines were also studied. For gas-liquid inclusions, helium, air and argon were compared. Migration studies were also conducted on single crystallites of natural salt as well as in polycrystalline natural salt samples. The behavior of the inclusions at large-ange grain boundaries was observed.

Olander, D.R.

1984-08-01T23:59:59.000Z

91

Property:BrineConstituents | Open Energy Information  

Open Energy Info (EERE)

BrineConstituents BrineConstituents Jump to: navigation, search Property Name BrineConstituents Property Type String Description Describes major elements, compounds in geothermal brine This is a property of type Page. Subproperties This property has the following 1 subproperty: V Valles Caldera - Redondo Geothermal Area Pages using the property "BrineConstituents" Showing 2 pages using this property. N North Brawley Geothermal Area + Chlorine, sodium, potassium, and calcium. Silica concentrations are 527 mg/l and total dissolved solids measure 82,900 mg/l. + S Salt Wells Geothermal Area + Cl, Na, SO4, SiO2, HCO3, and minor Ca, K + Retrieved from "http://en.openei.org/w/index.php?title=Property:BrineConstituents&oldid=598832#SMWResults" Category: Properties

92

Development Operations Hypersaline Geothermal Brine Utilization Imperial  

Open Energy Info (EERE)

Hypersaline Geothermal Brine Utilization Imperial Hypersaline Geothermal Brine Utilization Imperial County, California Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Development Operations Hypersaline Geothermal Brine Utilization Imperial County, California Abstract N/A Authors Whitescarver and Olin D. Published U.S. Department of Energy, 1984 Report Number N/A DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Development Operations Hypersaline Geothermal Brine Utilization Imperial County, California Citation Whitescarver, Olin D.. 1984. Development Operations Hypersaline Geothermal Brine Utilization Imperial County, California. (!) : U.S. Department of Energy. Report No.: N/A. Retrieved from "http://en.openei.org/w/index.php?title=Development_Operations_Hypersaline_Geothermal_Brine_Utilization_Imperial_County,_California&oldid=682648

93

Studies of brine chemistry, precipitation of solids, and scale formation at the Salton Sea geothermal field  

DOE Green Energy (OSTI)

Factors affecting the precipitation of solids and deposition of scale from the hypersaline brines of the Salton Sea geothermal field - two potential problems in the proposed utilization of these brines for electric power generation - were investigated. The average physical and chemical composition of the fluid from Magmamax No. 1 well was noted and the effects of changes in well flowrate on the chemistry of the brine and the formation of solids were determined. The effects of pH on the process stream chemistry and on the composition and rates of formation of solids and scale that precipitated from this brine were studied. Reduction of the pH from 6 to 4-5 decreased the scaling rates and increased the proportions of bariun sulfate and calcium fluoride in the scales and precipitated solids. These studies were conducted using a small-scale four-stage brine flash system constructed at the site.

Harrar, J.E.; Otto, C.H. Jr.; Deutscher, S.B.; Ryon, R.W.; Tardiff, G.E.

1979-01-08T23:59:59.000Z

94

Development Operations Hypersaline Geothermal Brine Utilization...  

Open Energy Info (EERE)

Number NA DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for Development Operations Hypersaline Geothermal Brine Utilization Imperial...

95

Uncertainty and sensitivity analyses for gas and brine migration at the Waste Isolation Pilot Plant, May 1992  

SciTech Connect

Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis, stepwise regression analysis and examination of scatterplots are used in conjunction with the BRAGFLO model to examine two phase flow (i.e., gas and brine) at the Waste Isolation Pilot Plant (WIPP), which is being developed by the US Department of Energy as a disposal facility for transuranic waste. The analyses consider either a single waste panel or the entire repository in conjunction with the following cases: (1) fully consolidated shaft, (2) system of shaft seals with panel seals, and (3) single shaft seal without panel seals. The purpose of this analysis is to develop insights on factors that are potentially important in showing compliance with applicable regulations of the US Environmental Protection Agency (i.e., 40 CFR 191, Subpart B; 40 CFR 268). The primary topics investigated are (1) gas production due to corrosion of steel, (2) gas production due to microbial degradation of cellulosics, (3) gas migration into anhydrite marker beds in the Salado Formation, (4) gas migration through a system of shaft seals to overlying strata, and (5) gas migration through a single shaft seal to overlying strata. Important variables identified in the analyses include initial brine saturation of the waste, stoichiometric terms for corrosion of steel and microbial degradation of cellulosics, gas barrier pressure in the anhydrite marker beds, shaft seal permeability, and panel seal permeability.

Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Bean, J.E. [New Mexico Engineering Research Inst., Albuquerque, NM (United States); Butcher, B.M. [Sandia National Labs., Albuquerque, NM (United States); Garner, J.W.; Vaughn, P. [Applied Physics, Inc., Albuquerque, NM (United States); Schreiber, J.D. [Science Applications International Corp., Albuquerque, NM (United States); Swift, P.N. [Tech Reps, Inc., Albuquerque, NM (United States)

1993-08-01T23:59:59.000Z

96

An Evaluation of Long-Term Performance of Liner Systems for Low-Level Waste Disposal Facilities  

SciTech Connect

Traditional liner systems consisting of a geosynthetic membrane underlying a waste disposal facility coupled with a leachate collection system have been proposed as a means of containing releases of low-level radioactive waste within the confines of the disposal facility and thereby eliminating migration of radionuclides into the vadose zone and groundwater. However, this type of hydraulic containment liner system is only effective as long as the leachate collection system remains functional or an overlying cover limits the total infiltration to the volumetric pore space of the disposal system. If either the leachate collection system fails, or the overlying cover becomes less effective during the 1,000’s of years of facility lifetime, the liner may fill with water and release contaminated water in a preferential or focused manner. If the height of the liner extends above the waste, the waste will become submerged which could increase the release rate and concentration of the leachate. If the liner extends near land surface, there is the potential for contamination reaching land surface creating a direct exposure pathway. Alternative protective liner systems can be engineered that eliminate radionuclide releases to the vadose zone during operations and minimizing long term migration of radionuclides from the disposal facility into the vadose zone and aquifer. Non-traditional systems include waste containerization in steel or composite materials. This type of system would promote drainage of clean infiltrating water through the facility without contacting the waste. Other alternatives include geochemical barriers designed to transmit water while adsorbing radionuclides beneath the facility. Facility performance for a hypothetical disposal facility has been compared for the hydraulic and steel containerization liner alternatives. Results were compared in terms of meeting the DOE Order 435.1 low-level waste performance objective of 25 mrem/yr all-pathways dose during the 1) institutional control period (0-100 years), compliance period (0-1000 years) and post-compliance period (>1000 years). Evaluation of the all pathway dose included the dose from ingestion and irrigation of contaminated groundwater extracted from a well 100 meters downgradient, in addition to the dose received from direct contact of radionuclides deposited near the surface resulting from facility overflow. Depending on the disposal facility radionuclide inventory, facility design, cover performance, and the location and environment where the facility is situated, the dose from exposure via direct contact of near surface deposited radionuclides can be much greater than the dose received via transport to the groundwater and subsequent ingestion.

Arthur S. Rood; Annette L. Schafer; A. Jeffrey Sondrup

2011-03-01T23:59:59.000Z

97

Use of data obtained from core tests in the design and operation of spent brine injection wells in geopressured or geothermal systems  

DOE Green Energy (OSTI)

The effects of formation characteristics on injection well performance are reviewed. Use of data acquired from cores taken from injection horizons to predict injectivity is described. And methods for utilizing data from bench scale testing of brine and core samples to optimize injection well design are presented. Currently available methods and equipment provide data which enable the optimum design of injection wells through analysis of cores taken from injection zones. These methods also provide a means of identifying and correcting well injection problems. Methods described in this report are: bulk density measurement; porosity measurement; pore size distribution analysis; permeability measurement; formation grain size distribution analysis; core description (lithology) and composition; amount, type and distribution of clays and shales; connate water analysis; consolidatability of friable reservoir rocks; grain and pore characterization by scanning electron microscopy; grain and pore characterization by thin section analysis; permeability damage and enhancement tests; distribution of water-borne particles in porous media; and reservoir matrix acidizing effectiveness. The precise methods of obtaining this information are described, and their use in the engineering of injection wells is illustrated by examples, where applicable. (MHR)

Jorda, R.M.

1980-03-01T23:59:59.000Z

98

Some logistical considerations in designing a system of deep boreholes for disposal of high-level radioactive waste.  

Science Conference Proceedings (OSTI)

Deep boreholes could be a relatively inexpensive, safe, and rapidly deployable strategy for disposing Americas nuclear waste. To study this approach, Sandia invested in a three year LDRD project entitled %E2%80%9CRadionuclide Transport from Deep Boreholes.%E2%80%9D In the first two years, the borehole reference design and backfill analysis were completed and the supporting modeling of borehole temperature and fluid transport profiles were done. In the third year, some of the logistics of implementing a deep borehole waste disposal system were considered. This report describes what was learned in the third year of the study and draws some conclusions about the potential bottlenecks of system implementation.

Gray, Genetha Anne; Brady, Patrick Vane [Sandia National Laboratories, Albuquerque, NM; Arnold, Bill Walter [Sandia National Laboratories, Albuquerque, NM

2012-09-01T23:59:59.000Z

99

Some logistical considerations in designing a system of deep boreholes for disposal of high-level radioactive waste.  

SciTech Connect

Deep boreholes could be a relatively inexpensive, safe, and rapidly deployable strategy for disposing Americas nuclear waste. To study this approach, Sandia invested in a three year LDRD project entitled %E2%80%9CRadionuclide Transport from Deep Boreholes.%E2%80%9D In the first two years, the borehole reference design and backfill analysis were completed and the supporting modeling of borehole temperature and fluid transport profiles were done. In the third year, some of the logistics of implementing a deep borehole waste disposal system were considered. This report describes what was learned in the third year of the study and draws some conclusions about the potential bottlenecks of system implementation.

Gray, Genetha Anne; Brady, Patrick Vane [Sandia National Laboratories, Albuquerque, NM; Arnold, Bill Walter [Sandia National Laboratories, Albuquerque, NM

2012-09-01T23:59:59.000Z

100

Lessons learned from reactive transport modeling of a low-activity waste glass disposal system  

Science Conference Proceedings (OSTI)

A set of reactive chemical transport calculations were conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal ... Keywords: chemical transport, low-level waste, numerical model, unsaturated flow, vadose zone

Diana H. Bacon; B. Peter McGrail

2003-04-01T23:59:59.000Z

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


101

Power Production from Geothermal Brine with the Rotary Separator Turbine  

SciTech Connect

The rotary separator turbine is a new turbine device that operates with gas-liquid mixtures. This device achieves complete gas-liquid separation, generates power from the liquid and repressurizes the liquid. The use of the rotary separator turbine for geothermal power generation was investigated on this program. A pilot scale unit was designed and tested. Tests were conducted with a clean water/steam mixture and with geothermal brine/steam flows at East Mesa, California; Raft River, Idaho; and Roosevelt Hot Springs, Utah. The test results were used to calculate the performance advantage of a rotary separator turbine power system compared to a flash steam power system and a binary power system. The calculated performance advantages were then used to estimate market potential for wellhead and central station Biphase units. The measured performance in the laboratory and in the field agreed to within {+-} 10% of the predicted values. The design goal of 20 kWe was generated both in the laboratory and from brine. Separated steam quality was measured to be greater than 99.96% at all three geothermal resources and in the laboratory. Brine pressure leaving the test unit was greater than reinjection pressure requirements. Maximum brine outlet pressure of 90 psig was demonstrated. The measured performance values would result in a 34% increase in electric power production above a single stage flash steam system. Increasing the size from the pilot size unit (20kWe) to a wellhead unit (2000 kWe) gave a calculated performance advantage of 40%. Based on these favorable results, design, construction and testing of a full-size well-head unit was initiated.

Cerini, Donald J.; Hays, Lance G.

1980-12-01T23:59:59.000Z

102

Hydrocarbon content of geopressured brines. Final report  

DOE Green Energy (OSTI)

Design Well data (bottomhole pressure minus wellhead pressure, GWR, and hydrocarbon composition) is presented as a function of producing conditions. These are examined in conjunction with the following models to attempt to deduce the reservoir brine saturation level: (1) reservoir contains gas dispersed in the pores and the gas saturation is greater than critical; (2) reservoir brine is gas-saturated; (3) bubble point below hydrostatic pressure; and (4) bubble point between hydrostatic pressure and reservoir pressure. 24 figs., 10 tabs. (ACR)

Osif, T.L.

1985-08-01T23:59:59.000Z

103

Septage Disposal, Licensure (Montana)  

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

This statute describes licensing requirements for septage disposal, and addresses land disposal and processing facilities.

104

Brine flow up a borehole caused by pressure perturbation from CO2 storage: Static and dynamic evaluations  

SciTech Connect

Industrial-scale storage of CO{sub 2} in saline sedimentary basins will cause zones of elevated pressure, larger than the CO{sub 2} plume itself. If permeable conduits (e.g., leaking wells) exist between the injection reservoir and overlying shallow aquifers, brine could be pushed upwards along these conduits and mix with groundwater resources. This paper discusses the potential for such brine leakage to occur in temperature- and salinity-stratified systems. Using static mass-balance calculations as well as dynamic well flow simulations, we evaluate the minimum reservoir pressure that would generate continuous migration of brine up a leaking wellbore into a freshwater aquifer. Since the brine invading the well is denser than the initial fluid in the wellbore, continuous flow only occurs if the pressure perturbation in the reservoir is large enough to overcome the increased fluid column weight after full invasion of brine into the well. If the threshold pressure is exceeded, brine flow rates are dependent on various hydraulic (and other) properties, in particular the effective permeability of the wellbore and the magnitude of pressure increase. If brine flow occurs outside of the well casing, e.g., in a permeable fracture zone between the well cement and the formation, the fluid/solute transfer between the migrating fluid and the surrounding rock units can strongly retard brine flow. At the same time, the threshold pressure for continuous flow to occur decreases compared to a case with no fluid/solute transfer.

Birkholzer, J.T.; Nicot, J.-P.; Oldenburg, C.M.; Zhou, Q.; Kraemer, S.; Bandilla, K.W.

2011-05-01T23:59:59.000Z

105

Stability of plutonium(VI) in WIPP brine  

Science Conference Proceedings (OSTI)

The redox stability of plutonium (VI) in WIPP brine was investigated by monitoring the oxidation state as a function of time using a combination of absorption spectrometry, radiochemical counting and filtration. Studies were performed with Pu-239 and Pu-238 in four WIPP brines at concentrations between 10{sup {minus}3} and 10{sup {minus}8} M for durations as long as two years. Two synthetic brines, Brine A and ERDA-6, and two underground collected brines, DH-36 and G-Seep, were used. The stability of Pu(VI) depended on the brine composition and the speciation of the plutonium in that brine. When carbonate was present, a Pu(VI)-carbonate complex was observed that was stable. In the absence of carbonate, Pu(VI) hydrolytic species predominated which had a wide range of stability in the brines investigated. The results reported will help define the speciation of plutonium in WIPP brine and hence its potential for migration.

Reed, D.T.; Okajima, S.

1993-12-01T23:59:59.000Z

106

Recovery of energy from geothermal brine and other hot water sources  

DOE Patents (OSTI)

Process and system for recovery of energy from geothermal brines and other hot water sources, by direct contact heat exchange between the brine or hot water, and an immiscible working fluid, e.g. a hydrocarbon such as isobutane, in a heat exchange column, the brine or hot water therein flowing countercurrent to the flow of the working fluid. The column can be operated at subcritical, critical or above the critical pressure of the working fluid. Preferably, the column is provided with a plurality of sieve plates, and the heat exchange process and column, e.g. with respect to the design of such plates, number of plates employed, spacing between plates, area thereof, column diameter, and the like, are designed to achieve maximum throughput of brine or hot water and reduction in temperature differential at the respective stages or plates between the brine or hot water and the working fluid, and so minimize lost work and maximize efficiency, and minimize scale deposition from hot water containing fluid including salts, such as brine. Maximum throughput approximates minimum cost of electricity which can be produced by conversion of the recovered thermal energy to electrical energy.

Wahl, III, Edward F. (Claremont, CA); Boucher, Frederic B. (San Juan Capistrano, CA)

1981-01-01T23:59:59.000Z

107

Vitrification of high level nuclear waste inside ambient temperature disposal containers using inductive heating: The SMILE system  

Science Conference Proceedings (OSTI)

A new approach, termed SMILE (Small Module Inductively Loaded Energy), for the vitrification of high level nuclear wastes (HLW) is described. Present vitrification systems liquefy the HLW solids and associated frit material in large high temperature melters. The molten mix is then poured into small ({approximately}1 m{sup 3}) disposal canisters, where it solidifies and cools. SMILE eliminates the separate, large high temperature melter. Instead, the BLW solids and frit melt inside the final disposal containers, using inductive heating. The contents then solidify and cool in place. The SMILE modules and the inductive heating process are designed so that the outer stainless can of the module remains at near ambient temperature during the process cycle. Module dimensions are similar to those of present disposal containers. The can is thermally insulated from the high temperature inner container by a thin layer of refractory alumina firebricks. The inner container is a graphite crucible lined with a dense alumina refractory that holds the HLW and fiit materials. After the SMILE module is loaded with a slurry of HLW and frit solids, an external multi-turn coil is energized with 30-cycle AC current. The enclosing external coil is the primary of a power transformer, with the graphite crucible acting as a single turn ``secondary.`` The induced current in the ``secondary`` heats the graphite, which in turn heats the HLW and frit materials. The first stage of the heating process is carried out at an intermediate temperature to drive off remnant liquid water and water of hydration, which takes about 1 day. The small fill/vent tube to the module is then sealed off and the interior temperature raised to the vitrification range, i.e., {approximately}1200C. Liquefaction is complete after approximately 1 day. The inductive heating then ceases and the module slowly loses heat to the environment, allowing the molten material to solidify and cool down to ambient temperature.

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

1996-03-01T23:59:59.000Z

108

Brines formed by multi-salt deliquescence  

SciTech Connect

The FY05 Waste Package Environment testing program at Lawrence Livermore National Laboratory focused on determining the temperature, relative humidity, and solution compositions of brines formed due to the deliquescence of NaCl-KNO{sub 3}-NaNO{sub 3} and NaCl-KNO{sub 3}-NaNO{sub 3}-Ca(NO{sub 3}){sub 2} salt mixtures. Understanding the physical and chemical behavior of these brines is important because they define conditions under which brines may react with waste canister surfaces. Boiling point experiments show that NaCl-KNO{sub 3}-NaNO{sub 3} and NaCl-KNO{sub 3}-NaNO{sub 3}-Ca(NO{sub 3}){sub 2} salt mixtures form brines that transform to hydrous melts that do not truly 'dry out' until temperatures exceed 300 and 400 C, respectively. Thus a conducting solution is present for these salt assemblages over the thermal history of the repository. The corresponding brines form at lower relative humidity at higher temperatures. The NaCl-KNO{sub 3}-NaNO{sub 3} salt mixture has a mutual deliquescence relative humidity (MDRH) of 25.9% at 120 C and 10.8% at 180 C. Similarly, the KNO{sub 3}-NaNO{sub 3} salt mixture has MDRH of 26.4% at 120 C and 20.0% at 150 C. The KNO{sub 3}-NaNO{sub 3} salt mixture salts also absorb some water (but do not appear to deliquesce) at 180 C and thus may also contribute to the transfer of electrons at interface between dust and the waste package surface. There is no experimental evidence to suggest that these brines will degas and form less deliquescent salt assemblages. Ammonium present in atmospheric and tunnel dust (as the chloride, nitrate, or sulfate) will readily decompose in the initial heating phase of the repository, and will affect subsequent behavior of the remaining salt mixture only through the removal of a stoichiometric equivalent of one or more anions. Although K-Na-NO{sub 3}-Cl brines form at high temperature and low relative humidity, these brines are dominated by nitrate, which is known to inhibit corrosion at lower temperature. Nitrate to chloride ratios of the NaCl-KNO{sub 3}-NaNO{sub 3} salt mixture are about NO{sub 3}:Cl = 19:1. The role of nitrate on corrosion at higher temperatures is addressed in a companion report (Dixit et al., 2005).

Carroll, S; Rard, J; Alai, M; Staggs, K

2005-11-04T23:59:59.000Z

109

Silica scaling in simulated geothermal brines  

DOE Green Energy (OSTI)

A 6.3 1/sec (100 GPM) titanium corrosion test loop was modified to provide a dynamic facility for studying the formation of silica deposits, their properties and fates, as a function of brine composition, temperature, and flow conditions. Scale formation was studied in a segmented heat exchanger operating under realistic conditions; the segmented design permitted examination of scale formations in five temperature regimes. The program was terminated after minimal exploratory operation because of reduced sponsor perceptions of the need for concern with scaling problems. The runs which were completed dealt cursorily with brine concentration and pH effects. Results are presented.

Bohlmann, E.G.; Shor, A.J.; Berlinski, P.; Mesmer, R.E.

1981-04-01T23:59:59.000Z

110

A Phase-Partitioning Model for CO2–Brine Mixtures at Elevated Temperatures and Pressures: Application to CO2-Enhanced Geothermal Systems  

E-Print Network (OSTI)

D.W. : A hot dry rock geothermal energy concept utilizingtwenty-?fth workshop on geothermal reservoir engineering,the development of enhanced geothermal systems? In: Paper

Spycher, Nicolas; Pruess, Karsten

2010-01-01T23:59:59.000Z

111

Submergible barge retrievable storage and permanent disposal system for radioactive waste  

DOE Patents (OSTI)

A submergible barge and process for submerging and storing radioactive waste material along a seabed. A submergible barge receives individual packages of radwaste within segregated cells. The cells are formed integrally within the barge, preferably surrounded by reinforced concrete. The cells are individually sealed by a concrete decking and by concrete hatch covers. Seawater may be vented into the cells for cooling, through an integral vent arrangement. The vent ducts may be attached to pumps when the barge is bouyant. The ducts are also arranged to promote passive ventilation of the cells when the barge is submerged. Packages of the radwaste are loaded into individual cells within the barge. The cells are then sealed and the barge is towed to the designated disposal-storage site. There, the individual cells are flooded and the barge will begin descent controlled by a powered submarine control device to the seabed storage site. The submerged barge will rest on the seabed permanently or until recovered by a submarine control device.

Goldsberry, Fred L. (Spring, TX); Cawley, William E. (Richland, WA)

1981-01-01T23:59:59.000Z

112

Geothermal Chemical Modeling Project DOE Advanced Brine Chemistry Program  

DOE Green Energy (OSTI)

The brine-calcite-anhydrite-silica scale model program is ready to be used by the industry at a research level. Versions are already in use in studies of scaling in geothermal and oil production systems. A set of short course notes has been prepared to help perspective users. IBM and Macintosh versions of the model are available. The gas phase models have been incorporated in the general package for distribution. Both mainframe (SUN) and PC versions (MacIntosh and IBM) of the code have been distributed.

Moeller, N.; Weare, J.H.

1993-04-01T23:59:59.000Z

113

Salt effects on stable isotope partitioning and their geochemical implications for geothermal brines  

DOE Green Energy (OSTI)

It has long been recognized that dissolved salts in water can change oxygen and hydrogen isotope partitioning between water and other phases (i.e., vapor, minerals) due to the hydration of ions upon the dissolution of salts in water. However, their effects have not been well determined at elevated temperatures. We are currently conducting a series of hydrothermal experiments of the system brine-vapor or minerals to 350{degrees}C, in order to determine precisely the effects of dissolved salts abundant in brines on isotope partitioning at temperatures encountered in geothermal systems. The so-called ``isotope salt effect`` has important implications for the interpretation and modeling of isotopic data of brines and rocks obtained from geothermal fields. We will show how to use our new results of isotopic partitioning to help better evaluate energy resources of many geothermal fields.

Horita, J.; Cole, D.R.; Wesolowski, D.J.

1994-06-01T23:59:59.000Z

114

Expected brine movement at potential nuclear waste repository salt sites  

SciTech Connect

The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

McCauley, V.S.; Raines, G.E.

1987-08-01T23:59:59.000Z

115

The depth of the oil/brine interface and crude oil leaks in SPR caverns  

Science Conference Proceedings (OSTI)

Monitoring wellhead pressure evolution is the best method of detecting crude oil leaks in SPR caverns while oil/brine interface depth measurements provide additional insight. However, to fully utilize the information provided by these interface depth measurements, a thorough understanding of how the interface movement corresponds to cavern phenomena, such as salt creep, crude oil leakage, and temperature equilibration, as well as to wellhead pressure, is required. The time evolution of the oil/brine interface depth is a function of several opposing factors. Cavern closure due to salt creep and crude oil leakage, if present, move the interface upward. Brine removal and temperature equilibration of the oil/brine system move the interface downward. Therefore, the relative magnitudes of these factors determine the net direction of interface movement. Using a mass balance on the cavern fluids, coupled with a simplified salt creep model for closure in SPR caverns, the movement of the oil/brine interface has been predicted for varying cavern configurations, including both right-cylindrical and carrot-shaped caverns. Three different cavern depths and operating pressures have been investigated. In addition, the caverns were investigated at four different points in time, allowing for varying extents of temperature equilibration. Time dependent interface depth changes of a few inches to a few feet were found to be characteristic of the range of cases studied. 5 refs, 19 figs., 1 tab.

Heffelfinger, G.S.

1991-06-01T23:59:59.000Z

116

Tank waste remediation system retrieval and disposal mission readiness-to-proceed guidance and requirements to deliverables crosswalk  

Science Conference Proceedings (OSTI)

In September 1996, the US Department of Energy, Richland Operations Office (RL) initiated the first of a two-phase program to remediate waste storage in tanks at the Hanford Site in Washington State. Initiating the first phase, RL signed contracts with two private companies who agreed to receive and vitrify a portion of the tank waste in a demonstration and to return the vitrified product and by-products to the Project Management Hanford Contract (PHMC) team for disposition. The first phase of the overall remediation effort is a demonstration of treatment concepts, and the second phase includes treatment of the remaining tank wastes. The demonstration phase, Phase 1 of the project, is further subdivided into two parts, A and B. During Phase 1A, the vitrification contractors are to establish the technical, operational, regulatory, business, and financial elements required to provide treatment services on a fixed unit price basis. Phase 1A deliverables will be evaluated by RL to determine whether it is in the best interest of the government to have one or more vitrification contractors proceed with Phase 1B, in which 6% to 13% of the tank waste would be treated in the demonstration. In addition, before RL can authorize proceeding with Phase 1B, the PHMC team must demonstrate its readiness to retrieve and deliver the waste to the private contractor(s) and to receive and dispose of the products and by-products returned from the treatment. The PHMC team has organized their plans for providing these vitrification-support services into the Retrieval and Disposal Mission within the Tank Waste Remediation System (TWRS) Project. Three RL core teams were established to assist in evaluating the PHMC team`s readiness specifically in regard to three task areas: Waste feed delivery; Infrastructure and by-products delivery; and Immobilized products. The core teams each developed a set of criteria and plans to be used in evaluating the PHMC team`s readiness to proceed (RTP).

Hall, C.E.

1998-01-06T23:59:59.000Z

117

Flare system for safe disposal of LNG from a disabled tanker  

SciTech Connect

The feasibility of a flare system for the rapid and safe incineration of the cargo of a disabled LNG tanker is evaluated. The project developed design parameters and proof-of-principle investigations of a system for off-loading and flaring LNG from a disabled LNG tanker. The system described offers enough promise to warrant additional investigation, if cargo burning is desired as a way of reducing other possible hazards.

Not Available

1982-12-01T23:59:59.000Z

118

Hydrocarbons associated with brines from geopressured wells  

DOE Green Energy (OSTI)

The purpose of this research is to determine the concentration of the cryocondensates in fluids of the various USDOE Geopressured wells as a function of production volume, to correlate the production of these compounds with reservoir and well production characteristics, to precisely measure solubilities of cryocondensates components in water and sodium chloride solutions (brines) as a function of ionic strength and temperature and the component's distribution coefficients between these solutions and oil, to develop models of the reservoir which are consistent with the data obtained, to monitor the wells for the production of aliphatic oils and relate any such production with the data obtained, and to develop a harsh environment pH probe for use in well brines. Results are summarized.

Not Available

1991-01-15T23:59:59.000Z

119

Geothermal brines and sludges: a new resource  

DOE Green Energy (OSTI)

Development of cost efficient biochemical processes for the treatment of geothermal brines and sludges is the main thrust of a major R&D effort at Brookhaven National Laboratory (BNL). This effort has led to the design of an environmentally acceptable, technically and economically feasible new technology which converts geothermal wastes into products with significant commercial potential. These include valuable metals recovery with a metal extraction and recovery efficiency of better then 80% over short periods of time (5-25 hours). The new technology also yields valuable salts, such as potassium chloride and generates high quality pigment free silica. The basic technology is versatile and can, with slight modifications, be used in the treatment of hypersaline as well as low salinity brines and sludges. Concurrently traces of toxic metals, including radium are removed to levels which are within regulatory limits. The current status of the new biochemical technology will be discussed in this paper.

Premuzic, E.T.; Lin, M.S.; Lian, H.; Miltenberger, R.P.

1996-10-01T23:59:59.000Z

120

Approach to recover strategic metals from brines  

DOE Green Energy (OSTI)

The objective of the proposed research is to evaluate hypersaline brines from geothermal sources and salt domes as possible sources for some strategic metals. This research is suggested because several previous analyses of brine from geothermal wells in the Imperial Valley, California, and from Gulf Coast salt domes, indicate near commercial values for platinum as well as other metals (i.e., gold, silver). Extraction of the platinum should be technically feasible. A research program should include more complete systematic sampling and analysis for resource delineation, followed by bench-scale investigation of several potential extraction processes. This could be followed by engineering feasibility and design studies, for extraction of the metals either as a by-product of other operations or in a stand-alone process.

Raber, E.; Harrar, J.; Gregg, D.

1981-09-16T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

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

122

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal...  

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

Million Tons Disposed - Waste Disposal Mark Shows Success Cleaning Up River Corridor Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark Shows Success...

123

Origin, distribution, and movement of brine in the Permian Basin (U. S. A. ). A model for displacement of connate brine  

SciTech Connect

Na-Cl, halite Ca-Cl, and gypsum Ca-Cl brines with salinities from 45 to >300 g/L are identified and mapped in four hydrostratigraphic units in the Permian Basin area beneath western Texas and Oklahoma and eastern New Mexico, providing spatial and lithologic constraints on the interpretation of the origin and movement of brine. Na-Cl brine is derived from meteoric water as young as 5-10 Ma that dissolved anhydrite and halite, whereas Ca-Cl brine is interpreted to be ancient, modified-connate Permian brine that now is mixing with, and being displaced by, the Na-Cl brine. Displacement fronts appear as broad mixing zones with no significant salinity gradients. Evolution of Ca-Cl brine composition from ideal evaporated sea water is attributed to dolomitization and syndepositional recycling of halite and bittern salts by intermittent influx of fresh water and sea water. Halite Ca-Cl brine in the evaporite section in the northern part of the basin differs from gypsum Ca-Cl brine in the south-central part in salinity and Na/Cl ratio and reflects segregation between halite- and gypsum-precipitating lagoons during the Permian. Ca-Cl brine moved downward through the evaporite section into the underlying Lower Permian and Pennsylvanian marine section that is now the deep-basin brine aquifer, mixing there with pre-existing sea water. Buoyancy-driven convection of brine dominated local flow for most of basin history, with regional advection governed by topographically related forces dominant only for the past 5 to 10 Ma. 71 refs., 11 figs.

Bein, A.; Dutton, A.R. (Univ. of Texas, Austin (United States))

1993-06-01T23:59:59.000Z

124

EVALUATIONS OF RADIONUCLIDES OF URANIUM, THORIUM, AND RADIUM ASSOCIATED WITH PRODUCED FLUIDS, PRECIPITATES, AND SLUDGES FROM OIL, GAS, AND OILFIELD BRINE INJECTION WELLS IN MISSISSIPPI  

SciTech Connect

Naturally occurring radioactive materials (NORM) are known to be produced as a byproduct of hydrocarbon production in Mississippi. The presence of NORM has resulted in financial losses to the industry and continues to be a liability as the NORM-enriched scales and scale encrusted equipment is typically stored rather than disposed of. Although the NORM problem is well known, there is little publically available data characterizing the hazard. This investigation has produced base line data to fill this informational gap. A total of 329 NORM-related samples were collected with 275 of these samples consisting of brine samples. The samples were derived from 37 oil and gas reservoirs from all major producing areas of the state. The analyses of these data indicate that two isotopes of radium ({sup 226}Ra and {sup 228}Ra) are the ultimate source of the radiation. The radium contained in these co-produced brines is low and so the radiation hazard posed by the brines is also low. Existing regulations dictate the manner in which these salt-enriched brines may be disposed of and proper implementation of the rules will also protect the environment from the brine radiation hazard. Geostatistical analyses of the brine components suggest relationships between the concentrations of {sup 226}Ra and {sup 228}Ra, between the Cl concentration and {sup 226}Ra content, and relationships exist between total dissolved solids, BaSO{sub 4} saturation and concentration of the Cl ion. Principal component analysis points to geological controls on brine chemistry, but the nature of the geologic controls could not be determined. The NORM-enriched barite (BaSO{sub 4}) scales are significantly more radioactive than the brines. Leaching studies suggest that the barite scales, which were thought to be nearly insoluble in the natural environment, can be acted on by soil microorganisms and the enclosed radium can become bioavailable. This result suggests that the landspreading means of scale disposal should be reviewed. This investigation also suggests 23 specific components of best practice which are designed to provide a guide to safe handling of NORM in the hydrocarbon industry. The components of best practice include both worker safety and suggestions to maintain waste isolation from the environment.

Charles Swann; John Matthews; Rick Ericksen; Joel Kuszmaul

2004-03-01T23:59:59.000Z

125

Corrosivity of geothermal brines. Progress report for period ending June 1976  

DOE Green Energy (OSTI)

Studies carried out during FY 1976 on the corrosivity of ferrous materials in synthetic geothermal brines are described. Electrochemical measurements on the spontaneous corrosion potentials and corrosion rates, and on the kinetics of the anodic and cathodic corrosion reactions of iron and carbon steel were made in 4 M NaCl solution over the pH range from 1 to 11 at temperatures up to 100/sup 0/C in a conventional Pyrex electrochemical cell. A refreshed, stirred titanium autoclave system was designed, constructed, and tested, and will be used for making electrochemical measurements in synthetic brines up to at least 200/sup 0/C. The effect of pH on hydrolysis, precipitation, and electrochemical reactivity of ferrous and ferric ions in 4 M NaCl at 25/sup 0/C was studied, and implications for plant operation are discussed. The pitting potential of type 304 stainless steel in synthetic brine was measured as a function of temperature from 25 to 85/sup 0/C. Plans for research on electrochemical aspects of the corrosion of iron and carbon steel in synthetic geothermal brines during FY1977 are presented. 14 fig. (auth)

Posey, F.A.; Palko, A.A.

1976-12-01T23:59:59.000Z

126

slc_disposal.cdr  

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

Disposal Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site at Salt Lake City, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Salt Lake City, Utah, Disposal Site ENERGY Office of Legacy Management U.S. DEPARTMENT OF Site Description and History Regulatory Setting The Salt Lake Disposal Site is located approximately 81 miles west of Salt Lake City and 2.5 miles south of Interstate 80 on the eastern edge of the Great Salt Lake Desert. The disposal cell is adjacent to Energy Solutions, Inc., a commercial low-level radioactive materials disposal site. The surrounding area is sparsely populated, and the nearest residences are at least 15 miles from the site. Vegetation in the area is sparse and typical of semiarid low shrubland. The disposal cell encapsulates about

127

Origin and geochemical evolution of the Michigan basin brine  

Science Conference Proceedings (OSTI)

Chemical and isotopic data were collected on 126 oil field brine samples and were used to investigate the origin and geochemical evolution of water in 8 geologic formations in the Michigan basin. Two groups of brine are found in the basin, the Na-Ca-Cl brine in the upper Devonian formations, and Ca-Na-Cl brine from the lower Devonian and Silurian aged formations. Water in the upper Devonian Berea, Traverse, and Dundee formations originated from seawater concentrated into halite facies. This brine evolved by halite precipitation, dolomitization, aluminosilicate reactions, and the removal of SO{sub 4} by bacterial action or by CaSO{sub 4} precipitation. The stable isotopic composition (D, O) is thought to represent dilution of evapo-concentrated seawater by meteoric water. Water in the lower Devonian Richfield, Detroit River Group, and Niagara-Salina formations is very saline Ca-Na-Cl brine. Cl/Br suggest it originated from seawater concentrated through the halite and into the MgSO{sub 4} salt facies, with an origin linked to the Silurian and Devonian salt deposits. Dolomitization and halite precipitation increased the Ca/Na, aluminosilicate reactions removed K, and bacterial action or CaSO{sub 4} precipitation removed SO{sub 4} from this brine. Water chemistry in the Ordovician Trenton-Black River formations indicates dilution of evapo-concentrated seawater by fresh or seawater. Possible saline end-members include Ordovician seawater, present-day upper Devonian brine, or Ca-Cl brine from the deeper areas in the basin.

Wilson, T.P.

1989-01-01T23:59:59.000Z

128

Experimental testing of a direct contact heat exchanger for geothermal brine. Final report, July 1, 1978-February 1, 1979  

DOE Green Energy (OSTI)

A series of direct contact heat exchanger (DCHX) experiments were conducted at the East Mesa Geothermal Test Site during the period July 1, 1978 to February 1, 1979. The purpose of these tests was to provide additional data necessary to better understand the thermal and hydraulic characteristics of the DCHX binary cycle loop components that may be used to extract energy from geothermal brines. Isobutane and Isopentane were tested as secondary working fluids. The analytical and experimental efforts were directed at the problems of working fluid loss in the effluent brine, carryover of water vapor with the vaporized secondary fluid and the free CO/sub 2/ content of the feed brine. The tests aimed at evaluating the heat transfer performance of various type tubes installed in vertical shell-and-tube secondary fluid condensers. Data was collected while operating a low temperature isopentane cycle with brine preflashed to 210 to 212/sup 0/F; the objective being to gain insight to waste heat recovery applications such as the Arkansas Power and Light project. Possible alternatives for isobutane recovery from the spent brine were investigated. A system was designed and the economic aspects studied.

Urbanek, M.W.

1979-12-01T23:59:59.000Z

129

High-pressure solvent extraction of methane from geopressured brines: technical evaluation and cost analysis  

DOE Green Energy (OSTI)

Solvent extraction is proposed as a means of recovering dissolved methane from geopressured-geothermal brines at high pressures. The assessment shows that additional investment in a high pressure solvent extraction plant preceding direct injection disposal of brines into isolated aquifers can be profitable. The technical and economic issues are discussed, and compared with other injection methods such as complete depressurization for methane recovery followed by conventional mechanical pumping. The contributions of hydraulic (pressure) energy recovery and geothermal power production are also assessed. For deep injection into the producing formation, it is concluded that methane extraction processes are not applicable, insofar as maintenance of high surface pressures provides no clear-cut energy benefits. As a first step in the evaluation of solvent extraction, the solubility of a promising solvent candidate, n-hexadecane, was measured in 15 wt % NaCl solutions at temperatures up to 150/sup 0/C. The solubility of a potential low cost solvent, No. 2 Diesel fuel, was also measured.

Quong, R.; Otsuki, H.H.; Locke, F.E.

1981-07-01T23:59:59.000Z

130

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

131

ADVANCED NUCLEAR FUEL CYCLE EFFECTS ON THE TREATMENT OF UNCERTAINTY IN THE LONG-TERM ASSESSMENT OF GEOLOGIC DISPOSAL SYSTEMS - EBS INPUT  

Science Conference Proceedings (OSTI)

The Used Fuel Disposition (UFD) Campaign within the Department of Energy's Office of Nuclear Energy (DOE-NE) Fuel Cycle Technology (FCT) program has been tasked with investigating the disposal of the nation's spent nuclear fuel (SNF) and high-level nuclear waste (HLW) for a range of potential waste forms and geologic environments. The planning, construction, and operation of a nuclear disposal facility is a long-term process that involves engineered barriers that are tailored to both the geologic environment and the waste forms being emplaced. The UFD Campaign is considering a range of fuel cycles that in turn produce a range of waste forms. The UFD Campaign is also considering a range of geologic media. These ranges could be thought of as adding uncertainty to what the disposal facility design will ultimately be; however, it may be preferable to thinking about the ranges as adding flexibility to design of a disposal facility. For example, as the overall DOE-NE program and industrial actions result in the fuel cycles that will produce waste to be disposed, and the characteristics of those wastes become clear, the disposal program retains flexibility in both the choice of geologic environment and the specific repository design. Of course, other factors also play a major role, including local and State-level acceptance of the specific site that provides the geologic environment. In contrast, the Yucca Mountain Project (YMP) repository license application (LA) is based on waste forms from an open fuel cycle (PWR and BWR assemblies from an open fuel cycle). These waste forms were about 90% of the total waste, and they were the determining waste form in developing the engineered barrier system (EBS) design for the Yucca Mountain Repository design. About 10% of the repository capacity was reserved for waste from a full recycle fuel cycle in which some actinides were extracted for weapons use, and the remaining fission products and some minor actinides were encapsulated in borosilicate glass. Because the heat load of the glass was much less than the PWR and BWR assemblies, the glass waste form was able to be co-disposed with the open cycle waste, by interspersing glass waste packages among the spent fuel assembly waste packages. In addition, the Yucca Mountain repository was designed to include some research reactor spent fuel and naval reactor spent fuel, within the envelope that was set using the commercial reactor assemblies as the design basis waste form. This milestone report supports Sandia National Laboratory milestone M2FT-12SN0814052, and is intended to be a chapter in that milestone report. The independent technical review of this LLNL milestone was performed at LLNL and is documented in the electronic Information Management (IM) system at LLNL. The objective of this work is to investigate what aspects of quantifying, characterizing, and representing the uncertainty associated with the engineered barrier are affected by implementing different advanced nuclear fuel cycles (e.g., partitioning and transmutation scenarios) together with corresponding designs and thermal constraints.

Sutton, M; Blink, J A; Greenberg, H R; Sharma, M

2012-04-25T23:59:59.000Z

132

Fluid Dynamics of Carbon Dioxide Disposal into Saline Aquifers  

SciTech Connect

Injection of carbon dioxide (CO{sub 2}) into saline aquifers has been proposed as a means to reduce greenhouse gas emissions (geological carbon sequestration). Large-scale injection of CO{sub 2} will induce a variety of coupled physical and chemical processes, including multiphase fluid flow, fluid pressurization and changes in effective stress, solute transport, and chemical reactions between fluids and formation minerals. This work addresses some of these issues with special emphasis given to the physics of fluid flow in brine formations. An investigation of the thermophysical properties of pure carbon dioxide, water and aqueous solutions of CO{sub 2} and NaCl has been conducted. As a result, accurate representations and models for predicting the overall thermophysical behavior of the system CO{sub 2}-H{sub 2}O-NaCl are proposed and incorporated into the numerical simulator TOUGH2/ECO{sub 2}. The basic problem of CO{sub 2} injection into a radially symmetric brine aquifer is used to validate the results of TOUGH2/ECO2. The numerical simulator has been applied to more complex flow problem including the CO{sub 2} injection project at the Sleipner Vest Field in the Norwegian sector of the North Sea and the evaluation of fluid flow dynamics effects of CO{sub 2} injection into aquifers. Numerical simulation results show that the transport at Sleipner is dominated by buoyancy effects and that shale layers control vertical migration of CO{sub 2}. These results are in good qualitative agreement with time lapse surveys performed at the site. High-resolution numerical simulation experiments have been conducted to study the onset of instabilities (viscous fingering) during injection of CO{sub 2} into saline aquifers. The injection process can be classified as immiscible displacement of an aqueous phase by a less dense and less viscous gas phase. Under disposal conditions (supercritical CO{sub 2}) the viscosity of carbon dioxide can be less than the viscosity of the aqueous phase by a factor of 15. Because of the lower viscosity, the CO{sub 2} displacement front will have a tendency towards instability. Preliminary simulation results show good agreement between classical instability solutions and numerical predictions of finger growth and spacing obtained using different gas/liquid viscosity ratios, relative permeability and capillary pressure models. Further studies are recommended to validate these results over a broader range of conditions.

Garcia, Julio Enrique

2003-12-18T23:59:59.000Z

133

Study and testing of direct contact heat exchangers for geothermal brines. Final report, June 1975--July 1976  

DOE Green Energy (OSTI)

The object of the work reported herein was to assess the technical and economic feasibility of preheating and evaporating a secondary fluid via direct contact with hot geothermal brine. The work covered a period of 12 months and included the design, construction, and testing of a unit which heats and vaporizes 10 gpm of isobutane by direct contact with 325/sup 0/F brine. The analytical and experimental efforts explored design and economic characteristics, including anticipated problem areas such as working fluid loss in the brine, production of a stable dispersion of the working fluid in brine, fluids separation, axial mixing and carry-over of water vapor with the working fluid. Isobutane was selected as the working fluid for tests primarily because of the favorable amount of net work produced per pound of geothermal brine and the low amount and cost of working fluid lost in the heat exchange process. The Elgin Spray Tower concept was selected for the preheater and boiler. The test apparatus includes a separate boiler and a separate preheater, each 6'' diameter by 6' high. Brine enters the top of each vessel and leaves the bottom. Isobutane enters the bottom of the preheater through a distributor plate to produce 0.15 inch diameter drops. The experimental unit operated with no major problems and demonstrated its hydraulic and thermal capabilities. Volumetric heat transfer coefficients obtained ranged up to 4000 BTU/hr /sup 0/F ft/sup 3/. Boiling heat transfer coefficients of as high as 17,000 BTU/hr /sup 0/F ft/sup 3/ were obtained with a design value of 10,000 BTU/hr /sup 0/F ft/sup 3/. Amount of isobutane in a 21 percent NaCl solution leaving the preheater was less than 40 ppM. A conceptual design and cost estimate was prepared for a direct contact heat exchange system sized for a 50 MW power plant.

Suratt, W.B.; Hart, G.K.

1977-01-01T23:59:59.000Z

134

Material Disposal Areas  

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

Material Disposal Areas Material Disposal Areas Material Disposal Areas Material Disposal Areas, also known as MDAs, are sites where material was disposed of below the ground surface in excavated pits, trenches, or shafts. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Material Disposal Areas at LANL The following are descriptions and status updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf). MDA A MDA A is a Hazard Category 2 nuclear facility comprised of a 1.25-acre, fenced, and radiologically controlled area situated on the eastern end of Delta Prime Mesa. Delta Prime Mesa is bounded by Delta Prime Canyon to the north and Los Alamos Canyon to the south.

135

Disposal configuration options for future uses of greater confinement disposal at the Nevada Test Site  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. The DOE`s Nevada Field Office contracted with Sandia National Laboratories to investigate the possibility of disposing of some of this special-case waste at the Nevada Test Site (NTS). As part of this investigation, a review of a near-surface and subsurface disposal options that was performed to develop alternative disposal configurations for special-case waste disposal at the NTS. The criteria for the review included (1) configurations appropriate for disposal at the NTS; (2) configurations for disposal of waste at least 100 ft below the ground surface; (3) configurations for which equipment and technology currently exist; and (4) configurations that meet the special requirements imposed by the nature of special-case waste. Four options for subsurface disposal of special-case waste are proposed: mined consolidated rock, mined alluvium, deep pits or trenches, and deep boreholes. Six different methods for near-surface disposal are also presented: earth-covered tumuli, above-grade concrete structures, trenches, below-grade concrete structures, shallow boreholes, and hydrofracture. Greater confinement disposal (GCD) in boreholes at least 100 ft deep, similar to that currently practiced at the GCD facility at the Area 5 Radioactive Waste Management Site at the NTS, was retained as the option that met the criteria for the review. Four borehole disposal configurations are proposed with engineered barriers that range from the native alluvium to a combination of gravel and concrete. The configurations identified will be used for system analysis that will be performed to determine the disposal configurations and wastes that may be suitable candidates for disposal of special-case wastes at the NTS.

Price, L. [Science Applications International Corp., Albuquerque, NM (United States)

1994-09-01T23:59:59.000Z

136

Material Disposal Areas  

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

wastewater absorption beds that received effluent from the DP Site radioactive laundry facility from 1945 to 1963, two surface debris disposal sites, and a former septic...

137

NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria  

SciTech Connect

At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

None

1981-04-01T23:59:59.000Z

138

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Poultry Farm Daily Disposal Methods 0;Disposal: Science and Theory First Composter in Delaware · Delmarva was of the first daily composting · 120 in USA over next 10 years #12;Disposal: Science and Theory Composting Procedure · Mixture ­ 1 ½ to 2

Benson, Eric R.

139

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Table of Contents · Disposal options emergency mortality composting procedure · Use of composting during outbreaks #12;Disposal: Science and disinfection of farms and surveillance around affected flocks. " USDA APHIS VS EMD, 2007 #12;Disposal: Science

Benson, Eric R.

140

How to treat and recycle heavy clear brine fluids  

Science Conference Proceedings (OSTI)

Clear brine fluids, such as CaCl/sub 2/, are replacing muds in well completions and workovers. These ''solids-free'' fluids have caused increases in well productivity of as much as 850%. To use the fluids in higher density ranges, it is necessary to blend the CaCl/sub 2/ brines with the more expensive bromide fluids. This, in turn, has increased the importance of reclaiming weighted brines to make their use more cost effective. To reclaim clear fluids, the solids picked up during use are removed and the fluid is reused or reweighted. A common problem though is the post-precipitation of dissolved contaminants that may appear in the used brines after several days or weeks in storage. Precipitation also may occur if other heavy fluids are added to adjust density before reuse. Laboratory tests have identified the solids as primarily iron hydroxides and halides. (Halides are salts containing a halogen-flourine, chlorine, bromine, or iodine.) Additional experimentation has shown that pH adjustment at the well site or before transfer to storage facilities can provide a simple and effective way of controlling the precipitation of metal hydroxides and halides. This article discusses methods of pH control, measurement, and adjustment, which will allow for optimum use of clear brine fluids.

Pasztor, A.J.; Snover, J.S.

1983-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Assessment of the impacts of spent fuel disassembly alternatives on the Nuclear Waste Isolation System. [Preparing and packaging spent fuel assemblies for geologic disposal  

SciTech Connect

The objective of this report was to evaluate four possible alternative methods of preparing and packaging spent fuel assemblies for geologic disposal against the Reference Process of unmodified spent fuel. The four alternative processes were: (1) End fitting removal, (2) Fission gas venting and resealing, (3) Fuel bundle disassembly and close packing of fuel pins, and (4) Fuel shearing and immobilization. Systems analysis was used to develop a basis of comparison of the alternatives. Conceptual processes and facility layouts were devised for each of the alternatives, based on technology deemed feasible for the purpose. Assessments were made of 15 principal attributes from the technical, operational, safety/risk, and economic considerations related to each of the alternatives, including both the surface packaging and underground repository operations. Specific attributes of the alternative processes were evaluated by assigning a number for each that expressed its merit relative to the corresponding attribute of the Reference Process. Each alternative process was then ranked by summing the numbers for attributes in each of the four assessment areas and collectively. Fuel bundle disassembly and close packing of fuel pins was ranked the preferred method of disposal of spent fuel. 63 references, 46 figures, 46 tables.

Not Available

1984-07-01T23:59:59.000Z

142

Advanced biochemical processes for geothermal brines: Annual operating plan, FY 1995  

DOE Green Energy (OSTI)

An R and D program to identify methods for the utilization and/or low cost of environmentally acceptable disposal of toxic geothermal residues has been established at the Brookhaven National Laboratory (BNL). Laboratory work has shown that a biochemical process developed at BNL, would meet regulatory costs and environmental requirements. In this work, microorganisms which can convert insoluble species of toxic metals, including radionuclides, into soluble species, have been identified. These organisms serve as models in the development of a biochemical process in which toxic metals present in geothermal residual sludges are converted into water soluble species. The produced solution can be reinjected or processed further to concentrate and recover commercially valuable metals. After the biochemical detoxification of geothermal residual sludges, the end-products are non-toxic and meet regulatory requirements. The overall process is a technically and environmentally acceptable cost-efficient process. It is anticipated that the new biotechnology will reduce the cost of surface disposal of sludges derived from geothermal brines by 25% or better.

Premuzic, E.T.

1995-02-01T23:59:59.000Z

143

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

144

Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms  

SciTech Connect

This report provides a technical assessment of the Melt-Dilute and Direct Al-SNF forms in disposable canisters with respect to meeting the requirements for disposal in the Mined Geologic Disposal System (MGDS) and for interim dry storage in the Treatment and Storage Facility (TSF) at SRS.

Vinson, D.W.

1998-11-06T23:59:59.000Z

145

Effect of explicit representation of detailed stratigraphy on brine and gas flow at the Waste Isolation Pilot Plant  

Science Conference Proceedings (OSTI)

Stratigraphic units of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) disposal room horizon includes various layers of halite, polyhalitic halite, argillaceous halite, clay, and anhydrite. Current models, including those used in the WIPP Performance Assessment calculations, employ a ``composite stratigraphy`` approach in modeling. This study was initiated to evaluate the impact that an explicit representation of detailed stratigraphy around the repository may have on fluid flow compared to the simplified ``composite stratigraphy`` models currently employed. Sensitivity of model results to intrinsic permeability anisotropy, interbed fracturing, two-phase characteristic curves, and gas-generation rates were studied. The results of this study indicate that explicit representation of the stratigraphy maintains higher pressures and does not allow as much fluid to leave the disposal room as compared to the ``composite stratigraphy`` approach. However, the differences are relatively small. Gas migration distances are also different between the two approaches. However, for the two cases in which explicit layering results were considerably different than the composite model (anisotropic and vapor-limited), the gas-migration distances for both models were negligible. For the cases in which gas migration distances were considerable, van Genuchten/Parker and interbed fracture, the differences between the two models were fairly insignificant. Overall, this study suggests that explicit representation of the stratigraphy in the WIPP PA models is not required for the parameter variations modeled if ``global quantities`` (e.g., disposal room pressures, net brine and gas flux into and out of disposal rooms) are the only concern.

Christian-Frear, T.L.; Webb, S.W. [Sandia National Labs., Albuquerque, NM (United States). Geohydrology Dept.

1996-04-01T23:59:59.000Z

146

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

147

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

148

Actinide (III) solubility in WIPP Brine: data summary and recommendations  

Science Conference Proceedings (OSTI)

The solubility of actinides in the +3 oxidation state is an important input into the Waste Isolation Pilot Plant (WIPP) performance assessment (PA) models that calculate potential actinide release from the WIPP repository. In this context, the solubility of neodymium(III) was determined as a function of pH, carbonate concentration, and WIPP brine composition. Additionally, we conducted a literature review on the solubility of +3 actinides under WIPP-related conditions. Neodymium(III) was used as a redox-invariant analog for the +3 oxidation state of americium and plutonium, which is the oxidation state that accounts for over 90% of the potential release from the WIPP through the dissolved brine release (DBR) mechanism, based on current WIPP performance assessment assumptions. These solubility data extend past studies to brine compositions that are more WIPP-relevant and cover a broader range of experimental conditions than past studies.

Borkowski, Marian; Lucchini, Jean-Francois; Richmann, Michael K.; Reed, Donald T.

2009-09-01T23:59:59.000Z

149

Cementation process for minerals recovery from Salton Sea geothermal brines  

DOE Green Energy (OSTI)

The potential for minerals recovery from a 1000-MWe combined geothermal power and minerals recovery plant in the Salton Sea is examined. While the possible value of minerals recovered would substantially exceed the revenue from power production, information is insufficient to carry out a detailed economic analysis. The recovery of precious metals - silver, gold, and platinum - is the most important factor in determining the economics of a minerals recovery plant; however, the precious metals content of the brines is not certain. Such a power plant could recover 14 to 31% of the US demand for manganese and substantial amounts of zinc and lead. Previous work on minerals extraction from Salton Sea brines is also reviewed and a new process, based on a fluidized-bed cementation reaction with metallic iron, is proposed. This process would recover the precious metals, lead, and tin present in the brines.

Maimoni, A.

1982-01-26T23:59:59.000Z

150

Conditioning of geothermal brine effluents for injection: use of coagulants  

DOE Green Energy (OSTI)

The use of various chemical coagulants and flocculants with spent geothermal brine for enhancing the removal of colloidal solids prior to injection was studied. Brine at 80 to 85/sup 0/C was obtained from the injection line of the SDG and E/DOE Geothermal Loop Experimental Facility during a period of operation with Magmamax No. 1 Fluid. The solids consist primarily of an iron-rich amorphous silica and heavy metal sulfides, principally lead. Standard jar testing equipment was used to carry out the tests.

Quong, R.; Shoepflin, F.; Stout, N.D.

1978-02-01T23:59:59.000Z

151

Delicate disposal of PCBs  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) has published three handbooks to help utilities evaluate the alternatives for disposal of polychlorinated biphenyls (PCBs), which will continue to be a utility responsibility for some time. The identification of PCBs as a toxic substance in 1976 ended their use as a capacitor and transformer insulator, but 375 million pounds are distributed in equipment and their disposal must be carefully planned. The booklets outline Environmental Protection Agency (EPA) regulations, the disposal technology by incineration or landfill which is currently available, and guidelines for preventing spills and controlling risks. (DCK)

Lihach, N.; Golden, D.

1980-03-01T23:59:59.000Z

152

Pioneering Nuclear Waste Disposal  

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

request for further delays After the EPA certified that the WIPP met the standards for disposal of transuranic waste in May 1998, then-New Mexico Attorney General Tom Udall...

153

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...

154

Demonstration of a rotary separator for two-phase brine and steam flows. Final report  

DOE Green Energy (OSTI)

The application of a two-phase rotary separator for geothermal energy conversion was demonstrated. Laboratory tests were conducted with clean water and steam at Biphase Energy Systems, Inc., Santa Monica, California. Field tests were conducted at the Union Oil Co., Tow No. 1 wellsite near Brawley, California. The system tested consisted of the major components of a total flow rotary separator/turbine conversion system. A nozzle converted the brine wellhead enthalpy to two-phase flow kinetic by impinging the nozzle flow tangentially on the inside of the separator. The flow was therefore subjected to the high centrifugal force field in the separator. This caused the liquid phase to collect as a film on the separator drum with very little energy loss. The steam was allowed to flow radially inward to the central steam discharge. Potable water was obtained by condensing the steam exhaust. The brine collection system converted the liquid film kinetic energy to static pressure head. The system was operated for 116 hours in a high salinity environment (115,000 ppM TDS). The system operated properly with no adverse effects from solids precipitation or scale buildup. The rotary separator produced separate flows of pure liquid and steam of greater than 99.5% quality.

Cerini, D.J.

1978-01-01T23:59:59.000Z

155

Uranium (VI) solubility in carbonate-free ERDA-6 brine  

Science Conference Proceedings (OSTI)

When present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is the most prevalent actinide component by mass, with about 647 metric tons to be placed in the repository. Therefore, the chemistry of uranium, and especially its solubility in the WIPP conditions, needs to be well determined. Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pC{sub H+} values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brines and a lack of amphotericity. At the expected pC{sub H+} in the WIPP ({approx} 9.5), measured uranium solubility approached 10{sup -7} M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines.

Lucchini, Jean-francois [Los Alamos National Laboratory; Khaing, Hnin [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

156

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Use of Composting · Composting has ­ British Columbia 2009 #12;Disposal: Science and Theory · Initial farm linked to NY LBM · Two additional and pile procedure Delmarva 2004 #12;Disposal: Science and Theory Delmarva 2004 · Composting used

Benson, Eric R.

157

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foam Used in Actual Outbreak · Water #12;Disposal: Science and Theory Water Based Foam Culling Demo · First large scale comparison · Two:46 (m:s) #12;Disposal: Science and Theory WV H5N2 AIV 2007 · AIV positive turkeys ­ 25,000 turkey farm

Benson, Eric R.

158

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · El compostaje se ha usado como Virginia (2007) ­ British Columbia (2009) Uso del compostaje #12;Disposal: Science and Theory · Primera apilamiento Delmarva (2004) #12;Disposal: Science and Theory · El compostaje se usó para proteger una densa

Benson, Eric R.

159

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Compostaje de aves de corralRouchey et al., 2005) Investigación previa #12;Disposal: Science and Theory · Se ha evaluado y documentado el, bovino Investigación previa #12;Disposal: Science and Theory · Experimento nro. 1 Impacto de la espuma en

Benson, Eric R.

160

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Opciones para la eliminación · ¿Qué compostaje durante brotes de enfermedades Lista de contenido #12;Disposal: Science and Theory "Ante un brote brotes de IIAP #12;Disposal: Science and Theory · En 2004, se despoblaron 100 millones de aves en todo el

Benson, Eric R.

Note: This page contains sample records for the topic "brine disposal system" 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

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Las recomendaciones de campo se la espuma #12;Disposal: Science and Theory · Múltiples especies de aves pueden despoblarse con espuma cesación #12;Disposal: Science and Theory · Dentro de una especie, pueden existir variaciones ­ Los ánades

Benson, Eric R.

162

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Opciones para la producción de espuma espuma · Sistemas de boquilla #12;Disposal: Science and Theory Requisitos estimados: · Tiempo: 2 a 3 compactas ­ Equipo de respuesta propio de la industria Espuma de aire comprimido #12;Disposal: Science

Benson, Eric R.

163

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Summary · Foam is currently a viable ­ Foam application directly to cage #12;Disposal: Science and Theory Legal Status of Foam · Procedure depopulation, culling, and euthanasia #12;Disposal: Science and Theory Acknowledgements · USDA AICAP2 · USDA

Benson, Eric R.

164

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Mass Emergency Composting · Basic ­ Create carcass and litter windrow #12;Disposal: Science and Theory Mass Emergency Composting · Basic cover ­ Clean and disinfect house ­ Sample for virus again #12;Disposal: Science and Theory Mass

Benson, Eric R.

165

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Gassing is a preferred #12;Disposal: Science and Theory Carbon Dioxide Gassing · Carbon dioxide (CO2) one of the standard sensitivity time #12;Disposal: Science and Theory · Argon-CO2 gas depopulation evaluated under laboratory

Benson, Eric R.

166

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Foam Generator Setup · Drop off foam generator cart at one end of house #12;Disposal: Science and Theory Foam Generator Setup · Trailer parked generator attached to hose #12;Disposal: Science and Theory Foam Generation Begins · Team of two to operate

Benson, Eric R.

167

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory 2004 ­ Participación de Bud Malone y la espuma 2009 ­ Ninguna ventaja para el gas Breve historia de la espuma #12;Disposal: Science sistema de boquilla ¿Qué es la espuma? #12;Disposal: Science and Theory · La espuma puede incluir: ­ Una

Benson, Eric R.

168

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory 0 20 40 60 80 100 Compostaje #12;Disposal: Science and Theory · Delmarva fue de las primeras granjas en realizar el compostaje de en EE.UU. en los próximos 10 años. Pionera en compostaje en Delaware #12;Disposal: Science and Theory

Benson, Eric R.

169

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Procedimiento básico ­ Desarrollar una pila de carcasas y lecho. Compostaje masivo de emergencia #12;Disposal: Science and Theory de emergencia #12;Disposal: Science and Theory · Desarrollar planes antes de que ocurra una

Benson, Eric R.

170

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Composting · Composting is defined drop #12;Disposal: Science and Theory Composting · Optimal composting ­ Carbon to nitrogen ratio (C;Disposal: Science and Theory Compost Composition · A variety of supplemental carbon materials have been

Benson, Eric R.

171

Power System Equipment Module Test Project  

DOE Green Energy (OSTI)

The technology of electric power generation when applying the binary process to hydrothermal resources had not yet been demonstrated in the United States. Accordingly, on November 10, 1977, the Electric Power Research Institute and the Department of Energy, acting through the Lawrence Berkeley Laboratory, agreed to cofund the Power System Equipment Module Test Project. The Power System Equipment Module Test Project consisted of a field test program to accomplish the objectives listed below while heating hydrocarbon fluids to above their critical points, expanding these fluids, and subsequently, condensing them below their critical points: (1) Verify the performance of state-of-the-art heat exchangers in geothermal service; (2) Verify the heat exchangers' performance heating either selected pure light hydrocarbons or selected mixtures of light hydrocarbons in the vicinity of their respective critical pressures and temperatures; (3) Establish overall heat transfer coefficients that might be used for design of commercial-size geothermal power plants using the same geothermal brine and light hydrocarbon working fluids; (4) Perform and investigate the above under representative fluid operating conditions during which the production wells would be pumped. The project was accomplished by diverting approximately 200 gpm of the flow from one of Magma Power Company's geothermal wells in the East Mesa Geothermal Field. After the heat was removed from the geothermal brine flow, the cooled flow was returned to Magma Power Company and recombined with the main brine stream for disposal by reinjection. Approximately five thermal megawatts was transferred from geothermal brine to hydrocarbon working fluids in a closed system. This heat was removed from the working fluids in a condenser and subsequently rejected to the environment by a wet cooling tower. The thermodynamic performance of both the working fluids and the system components was measured during the test program to achieve the project's objectives.

Schilling, J.R.

1980-12-01T23:59:59.000Z

172

Application of freshwater and brine polymer flooding in the North Burbank Unit, Osage County, Oklahoma  

SciTech Connect

A freshwater polymer-flood project was implemented in a 1,440-acre area of the North Burbank Unit (NBU) in 1980 with sequential injection of 4.2 million Ibm of polyacrylamide and 4.0 million Ibm of a 2.9% aluminum citrate crosslinking solution. Response to polymer flooding has been very pronounced, with ultimate incremental oil recovery projected to exceed 2.5 MMSTB of oil and total project oil expected to be 4.5 MMSTB. A crosslinked polymer-flood process for use in brine was developed that displays equally favorable performance characteristics as the freshwater polymer-flooding system.

Moffitt, P.D.; Zornes, D.R.; Moradi-Araghi, A.; McGovern, J.M. (Phillips Petroleum Co., Bartlesville, OK (United States))

1993-05-01T23:59:59.000Z

173

Modeling brine-rock interactions in an enhanced geothermal system deep fractured reservoir at Soultz-Sous-Forets (France): a joint approach using two geochemical codes: frachem and toughreact  

E-Print Network (OSTI)

rock interactions in enhanced geothermal systems (EGS).31 th Workshop on Geothermal Reservoir Engineering, 301998). Computer modeling for geothermal systems: predicting

Andre, Laurent; Spycher, Nicolas; Xu, Tianfu; Vuataz, Francois-D.; Pruess, Karsten.

2006-01-01T23:59:59.000Z

174

Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report  

SciTech Connect

Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases.

1979-07-01T23:59:59.000Z

175

Integrated Used Nuclear Fuel Storage, Transportation, and Disposal ...  

ORNL 2011-G00239/jcn UUT-B ID 201102603 09.2011 Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Technology Summary

176

Sample storage/disposal study  

SciTech Connect

Radioactive waste from defense operations has accumulated at the Hanford Site`s underground waste tanks since the late 1940`s. Each tank must be analyzed to determine whether it presents any harm to the workers at the Hanford Site, the public or the environment. Analyses of the waste aids in the decision making process in preparation of future tank waste stabilization procedures. Characterization of the 177 waste tanks on the Hanford Site will produce a large amount of archived material. This also brings up concerns as to how the excess waste tank sample material from 325 and 222-S Analytical Laboratories will be handled. Methods to archive and/or dispose of the waste have been implemented into the 222-S and 325 Laboratory procedures. As the amount of waste characterized from laboratory analysis grows, an examination of whether the waste disposal system will be able to compensate for this increase in the amount of waste needs to be examined. Therefore, the need to find the safest, most economically sound method of waste storage/disposal is important.

Valenzuela, B.D.

1994-09-29T23:59:59.000Z

177

Impact-driven pressure management via targeted brine extraction Conceptual studies of CO2 storage in saline formations  

E-Print Network (OSTI)

Combining Brine Extraction, desalination, and Residual-Brinebeneficial use such as desalination for drinking water

Birkholzer, J.T.

2013-01-01T23:59:59.000Z

178

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark  

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

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

179

Environmental assessment of the brine pipeline replacement for the Strategic Petroleum Reserve Bryan Mound Facility in Brazoria County, Texas  

SciTech Connect

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0804, for the proposed replacement of a deteriorated brine disposal pipeline from the Strategic Petroleum Reserve (SPR) Bryan Mound storage facility in Brazoria County, Texas, into the Gulf of Mexico. In addition, the ocean discharge outfall would be moved shoreward by locating the brine diffuser at the end of the pipeline 3.5 miles offshore at a minimum depth of 30 feet. The action would occur in a floodplain and wetlands; therefore, a floodplain/wetlands assessment has been prepared in conjunction with this EA. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969 (42 USC. 4321, et seg.). Therefore, the preparation of an Environmental Impact Statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact (FONSI). This FONSI also includes a Floodplain Statement of Findings in accordance with 10 CFR Part 1022.

Not Available

1993-09-01T23:59:59.000Z

180

Radiation chemistry of salt-mine brines and hydrates. [Gamma radiation  

Science Conference Proceedings (OSTI)

Certain aspects of the radiation chemistry of NaCl-saturated MgCl/sub 2/ solutions and MgCl/sub 2/ hydrates at temperatures in the range of 30 to 180/sup 0/C were investigated through experiments. A principal objective was to establish the values for the yields of H/sub 2/ (G(H/sub 2/)) and accompanying oxidants in the gamma-ray radiolysis of concentrated brines that might occur in waste repositories in salt. We concluded that G(H/sub 2/) from gamma-irradiated brine solution into a simultaneously irradiated, deaerated atmosphere above the solution is between 0.48 and 0.49 over most of the range 30 to 143/sup 0/C. The yield is probably somewhat lower at the lower end of this range, averaging 0.44 at 30 to 45/sup 0/C. Changes in the relative amounts of MgCl/sub 2/ and NaCl in the NaCl-saturated solutions have negligible effects on the yield. The yield of O/sub 2/ into the same atmosphere averages 0.13, independent of the temperature and brine composition, showing that only about 50% of the radiolytic oxidant that was formed along with the H/sub 2/ was present as O/sub 2/. We did not identify the species that compose the remainder of the oxidant. We concluded that the yield of H/sub 2/ from a gamma-irradiated brine solution into a simultaneously irradiated atmosphere containing 5 to 8% air in He may be greater than the yield in deaerated systems by amounts ranging from 0% for temperatures of 73 to 85/sup 0/C, to about 30 and 40% for temperatures in the ranges 100 to 143/sup 0/C and 30 to 45/sup 0/C, respectively. We did not establish the mechanism whereby the air affected the yields of H/sub 2/ and O/sub 2/. The values found in this work for G(H/sub 2/) in deaerated systems are in approximate agreement with the value of 0.44 for the gamma-irradiation yield of H/sub 2/ in pure H/sub 2/O at room temperature. They are also in agreement with the values predicted by extrapolation from the findings of previous researchers for the value for G(H/sub 2/) in 2 M NaCl solutions at room temperature.

Jenks, G.H.; Walton, J.R.; Bronstein, H.R.; Baes, C.F. Jr.

1981-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

disposal_cell.cdr  

Office of Legacy Management (LM)

With the With the April 24, 1997, ceremonial ground-breaking for disposal facility construction, the Weldon Spring Site Remedial Action Project (WSSRAP) moved into the final stage of cleanup, treatment, and disposal of uranium- processing wastes. The cleanup of the former uranium- refining plant consisted of three primary operations: Demolition and removal of remaining concrete pads and foundations that supported the 44 structures and buildings on site Treatment of selected wastes Permanent encapsulation of treated and untreated waste in an onsite engineered disposal facility In September l993, a Record of Decision (ROD) was signed by the U.S. Environmental Protection Agency (EPA) and the U.S. Department of Energy (DOE), with concurrence by the Missouri Department of Natural

182

Analysis of anions in geological brines using ion chromatography  

DOE Green Energy (OSTI)

Ion chromatographic procedures for the determination of the anions bromide, sulfate, nitrite, nitrate, phosphate, and iodide in brine samples have been developed and are described. The techniques have been applied to the analysis of natural brines, and geologic evaporites. Sample matrices varied over a range from 15,000 mg/L to 200,000 mg/L total halogens, nearly all of which is chloride. The analyzed anion concentrations ranged from less than 5 mg/L in the cases of nitrite, nitrate, and phosphate, to 20,000 mg/L in the case of sulfate. A technique for suppressing chloride and sulfate ions to facilitate the analysis of lower concentration anions is presented. Analysis times are typically less than 20 minutes for each procedure and the ion chromatographic results compare well with those obtained using more time consuming classical chemical analyses. 10 references, 14 figures.

Merrill, R.M.

1985-03-01T23:59:59.000Z

183

Fluid sampling and chemical modeling of geopressured brines containing methane. Final report, March 1980-February 1981  

DOE Green Energy (OSTI)

The development of a flowthrough sampler capable of obtaining fluid samples from geopressured wells at temperatures up to 400/sup 0/F and pressures up to 20,000 psi is described. The sampler has been designed, fabricated from MP35N alloy, laboratory tested, and used to obtain fluid samples from a geothermal well at The Geysers, California. However, it has not yet been used in a geopressured well. The design features, test results, and operation of this device are described. Alternative sampler designs are also discussed. Another activity was to review the chemistry and geochemistry of geopressured brines and reservoirs, and to evaluate the utility of available computer codes for modeling the chemistry of geopressured brines. The thermodynamic data bases for such codes are usually the limiting factor in their application to geopressured systems, but it was concluded that existing codes can be updated with reasonable effort and can usefully explain and predict the chemical characteristics of geopressured systems, given suitable input data.

Dudak, B.; Galbraith, R.; Hansen, L.; Sverjensky, D.; Weres, O.

1982-07-01T23:59:59.000Z

184

Pioneering Nuclear Waste Disposal  

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

PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOECAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of...

185

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

186

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

187

Removal of hydrogen sulfide from simulated geothermal brines by reaction with oxygen. Final report, October 6, 1975-February 4, 1977  

DOE Green Energy (OSTI)

A process for controlling hydrogen sulfide emissions and corrosivity in geothermal systems has been evaluated on a small laboratory pilot plant scale and shown to be technically feasible. The hydrogen sulfide was oxidized by oxygen injected directly into a 11.4-liter-(3-gallon)-per-minute flowing stream of simulated geothermal brine. The oxidation of the sulfide was complete at oxygen:sulfide mole ratios of 1.25:1 to 1.5:1, depending on temperature and total dissolved solids in the brine. The reaction products were free sulfur, sulfite and sulfate. The ratio of these was dependent upon the oxygen:sulfide mole ratios; but, generally, more than 80% of the sulfide was converted to sulfate, approximately 10% to free sulfur and less than 10% to sulfite.

Wilson, J.S.; King, J.E.; Bullard, G.R.

1977-04-01T23:59:59.000Z

188

On-line tests of organic additives for the inhibition of the precipitation of silica from hypersaline geothermal brine II. Tests of nitrogen-containing compounds, silanes, and additional ethoxylated compounds  

DOE Green Energy (OSTI)

Several new classes of organic compounds have been screened as potential geothermal scale control agents by examining their effect on the precipitation of silica from Magmamax No. 1 brine. The substances were tested using the Lawrence Livermore Laboratory Brine Treatment Test System at the Niland, California, Test Site. Solutions of the test substances were injected into flowing brine at 210{sup 0}C, the brine was flashed to 125{sup 0}C, and then the kinetics of solids and silica precipitation from effluent brine held at 90{sup 0}C were measured. Three new types of compounds were shown to have activity as precipitation inhibitors: polyethylene imines, polyethyloxazalines, and quaternary ammonium compounds containing polyoxyethylene. Among the latter, Ethoquad 18/25, which is methyl-polyoxyethylene(15) octadecylammonium chloride, is the leading candidate antiscalant. It is a more powerful inhibitor of silica precipitation than the pure polyoxyethylene polymers, and it apparently has no high temperature solubility limitations. Measurements were made of the concentrations of monomeric silica and the effect of addition of inhibitor at various points in the Brine Treatment Test System. Five different silane compounds showed no activity toward silica.

Harrar, J.E.; Locke, F.E.; Otto, C.H. Jr.; Lorensen, L.E.; Frey, W.P.

1979-06-01T23:59:59.000Z

189

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Previous Research · Composting, et.al. 2005; Bendfeldt et al., 2006; DeRouchey et al., 2005) #12;Disposal: Science and Theory: Science and Theory Scientific Validation of Composting · Experiment 1 Impact of foam on composting

Benson, Eric R.

190

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Field recommendations based of activity ­ Corticosterone ­ EEG, ECG and motion studies · Large scale testing ­ Field scale units Science of Foam #12;Disposal: Science and Theory Cessation Time · Multiple bird species can be depopulated

Benson, Eric R.

191

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · Se ubica el carretón con el enfriamiento Ventiladores de túnel de viento #12;Disposal: Science and Theory · Se estaciona el remolque en uno: Science and Theory · Se usa un equipo de dos personas para hacer funcionar el sistema: ­ Operario del

Benson, Eric R.

192

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory · El compostaje se define como la: Science and Theory · Compostaje óptimo ­ Relación carbono/nitrógeno (C:N): 20:1 a 35:1 ­ Contenido de Compostaje #12;Disposal: Science and Theory · Se ha utilizado satisfactoriamente una variedad de materiales

Benson, Eric R.

193

Disposal: Science and Theory Disposal: Science and Theory  

E-Print Network (OSTI)

Disposal: Science and Theory #12;Disposal: Science and Theory Table of Contents · Why Depopulate? · Depopulation Methods · Basics of Foam · Types of Foam Equipment · Science Behind Foam · Implementing Foam Depopulation · Use of Foam in the Field · Conclusions #12;Disposal: Science and Theory "When HPAI outbreaks

Benson, Eric R.

194

Hydrocarbons associated with brines from geopressured wells  

DOE Green Energy (OSTI)

Efforts to determine the concentration of the cryocondensates in fluids of the various USDOE Geopressured wells a function of production volume. The wells are visited monthly as they are operating and samples are reported taken cryogenically during each visit. A gas scrubbing system continuously sample the gas streams of the wells in the intergas scrubbing system continuously sample the gas streams of the wells in the intervals between visit. Results obtained are to correlated the production of the collected compounds with reservoir and well production characteristics.

Not Available

1991-10-15T23:59:59.000Z

195

Brine pH Modification Scale Control Technology. 2. A Review.pdf | Open  

Open Energy Info (EERE)

Brine pH Modification Scale Control Technology. 2. A Review.pdf Brine pH Modification Scale Control Technology. 2. A Review.pdf Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Brine pH Modification Scale Control Technology. 2. A Review.pdf Abstract A variety of processes has been deployed at geothermalfields to inhibit or control siliceous scale deposition. It has beenknown for decades that the kinetics of silicic acid polymerizationis retarded when the pH of an aqueous solution is decreased.Therefore, a potential method for controlling siliceous scalingfrom geothermal brine is treatment with acid. Early attempts tocontrol siliceous scaling in geothermal brine-handling equipmentby retarding polymerization led to the belief that the pHhad to be reduced to < 4. Acidifying brine was discourageddue to corrosion concerns.

196

Trace metal speciation in saline waters affected by geothermal brines. [GEOCHEM  

DOE Green Energy (OSTI)

A description is given of the chemical equilibrium computer program GEOCHEM, which has been developed to calculate trace element speciation in soil, irrigation, drainage, or Salton Sea waters affected by geothermal brine. GEOCHEM is applied to irrigation water-brine mixtures and to Salton Sea water-brine mixtures in order to compute the chemical speciation of the elements Cd, Cu, Hg, Ni, Pb, and Zn, along with the oxyanions of As and B. The results suggest that the computer simulation can have an important effect on a program for managing brine spills. Appendices include published papers on related research.

Sposito, G.; Page, A.L.

1977-11-01T23:59:59.000Z

197

Research and development of a 3 MW power plant from the design, development, and demonstration of a 100 KW power system utilizing the direct contact heat exchanger concept for geothermal brine recovery project. Final report  

DOE Green Energy (OSTI)

The design phase for the 100 KW unit consumed the months of May through November 1978, with the final design selected as having a direct contact boiler and condenser, a single-stage radial inflow induction turbine-generator using isopentane as the working fluid, and a single cell ejector-type cooling tower. The unit was constructed on two, forty-foot flatbed trailers between the months of October 1978 and June 1979. Systems start-up testing, in-field modifications, unit operation, and performance testing were performed between July and December 1979. AP and L (Arkansas Power and Light) personnel assumed responsibility of the unit at that time and conducted further maintenance, operations, and testing through August 1980.

Huebner, A.W.; Wall, D.A.; Herlacher, T.L.

1980-09-01T23:59:59.000Z

198

Dredged and Fill Material Disposal (North Dakota) | Department of Energy  

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

Dredged and Fill Material Disposal (North Dakota) Dredged and Fill Material Disposal (North Dakota) Dredged and Fill Material Disposal (North Dakota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State North Dakota Program Type Siting and Permitting This chapter provides regulations for the disposal of dredged and fill

199

Chapter 37 Land Disposal Restrictions (Kentucky) | Department...  

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

7 Land Disposal Restrictions (Kentucky) Chapter 37 Land Disposal Restrictions (Kentucky) Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor...

200

Waste Disposal (Illinois) | Department of Energy  

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

Waste Disposal (Illinois) Waste Disposal (Illinois) Eligibility Commercial Construction Industrial Utility Program Information Illinois Program Type Environmental Regulations This...

Note: This page contains sample records for the topic "brine disposal system" 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

ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS...  

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

DISPOSAL RECORDS (Revision 2) More Documents & Publications Records Management Handbook PROPERTY DISPOSAL RECORDS ADMINISTRATIVE RECORDS SCHEDULE 9: TRAVEL AND...

202

Solute-travel time estimates for tile-drained fields. III. Removal of a geothermal brine spill from soil by leaching  

DOE Green Energy (OSTI)

The time required to leach a slug of saline, sodic geothermal brine from the point of injection to the tile outlet of an artificially drained field is calculated. Sprinkler, complete, and partial ponding leaching methods are compared as a function of drain spacing and initial location of the spill, with ponding requiring more water but less time to leach brine out of the system for all situations except where the brine spill occurs near the midpoint between tile lines. Calculation results are presented in dimensionless parameters which scale the drainage system dimensions and the soil water transport properties. A simple calculation is proposed to estimate the volume of leaching fluid required to remove excess Na/sup +/ from the exchange complex, and was found to be in good agreement with the results of laboratory soil column experiments. For fine-textured soils in the Imperial Valley of California it may require up to 30 pore volumes of leaching fluid to lower Na/sup +/ concentrations if saturated gypsum solution is used in reclamation. The results of these calculations suggest that reclamation of fine textured soils could require a prohibitive amount of time unless the brine spill is localized around a drain.

Jury, W.A.; Weeks, L.V.

1978-01-16T23:59:59.000Z

203

Mapping of a reactor coolant effluent ground disposal test using an infrared imaging system and ground water potential and temperature measurements  

SciTech Connect

The concept of reactor effluent disposal to ground in infiltration trenches was proposed by Nelson and Alkire in 1963. At that time the available data indicated that radionuclide infiltration rates were probably adequate for trench disposal and that decontamination factors of 10 to 100 should be obtainable. Field tests at 100-F Area 1965 and 100-D Area 1967 have indicated that the infiltration rates are adequate and DF`s of from 2.5 for {sup 51}Cr to 7276 for {sup 65}Zn were obtained during the 100-D test. The purpose of this report is to present the results and interpretations of data from studies conducted over a reactor coolant effluent disposal test site. Data presented in this report were collected over the 100-C Area test in which a significant percentage of the reactor coolant effluent was disposed to an existing trench for a five-month period. Results of infrared thermal surveys and ground water temperature and potential measurements collected during this test are presented.

Eliason, J.R.

1969-04-10T23:59:59.000Z

204

Community Geothermal Technology Program: Electrodeposition of minerals in geothermal brine  

DOE Green Energy (OSTI)

Objective was to study the materials electrodeposited from geothermal brine, from the HGP-A well in Puna, Hawaii. Due to limitations, only one good set of electrodeposited material was obtained; crystallography indicates that vaterite forms first, followed by calcite and then perhaps aragonite as current density is increased. While the cost to weight ratio is reasonable, the deposition rate is very slow. More research is needed, such as reducing the brittleness. The electrodeposited material possibly could be used as building blocks, tables, benches, etc. 49 figs, 4 tabs, 7 refs.

Not Available

1990-12-31T23:59:59.000Z

205

FGD By-Product Disposal Manual, Fourth Edition  

Science Conference Proceedings (OSTI)

This manual presents an objective, systematic methodology for evaluating potential flue gas desulfurization (FGD) sludge disposal sites and design approaches. A completely updated edition, the manual provides new information and references on existing industry disposal practices, regulatory constraints and trends, FGD sludge properties, and waste management system costs.

1995-08-11T23:59:59.000Z

206

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

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

1995-10-24T23:59:59.000Z

207

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

208

Kinetics of silica deposition from simulated geothermal brines  

DOE Green Energy (OSTI)

Supersaturated brines were passed through columns packed with several forms of silica (crystalline ..cap alpha.. quartz, polycrystalline ..cap alpha.. quartz, and porous Vycor). Also, silica deposition on ThO/sub 2/ microspheres and titanium powder was studied under controlled conditions of supersaturation, pH, temperature, and salinity. The residence time was varied by adjustments of flow rate and column length. The silica contents of the input and effluent solutions were determined colorimetrically by a molybdate method which does not include polymers without special pretreatment. Essentially identical deposition behavior was observed once the substrate was thoroughly coated with amorphous silica and the BET surface area of the coated particles was taken into account. The reaction rate is not diffusion limited in the columns. The silica deposition is a function of the monomeric Si(OH)/sub 4/ concentration in the brine. The deposition on all surfaces examined was spontaneously nucleated. The dependence on the supersaturation concentration, hydroxide ion concentration, surface area, temperature and salinity were examined. Fluoride was shown to have no effect at pH 5.94 and low salinity. The empirical rate law which describes the data in 1 m NaCl in the pH range 5-7 and temperatures from 60 to 120/sup 0/C is given.

Bohlmann, E.G.; Mesmer, R.E.; Berlinski, P.

1980-03-01T23:59:59.000Z

209

Trace metal speciation in saline waters affected by geothermal brines. Final technical report. [GEOCHEM  

DOE Green Energy (OSTI)

The computer program GEOCHEM was developed and applied to calculate the speciation of trace elements, such as Li, B, Mn, Co, Ni, Cu, Zn, Pb, and As, in mixtures of geothermal brines with soil waters. A typical speciation calculation involved the simultaneous consideration of about 350 inorganic and organic complexes and about 80 possible solid phases that could form among the macro- and microconstituents in the mixtures. The four geothermal brines chosen for study were from the East Mesa, Heber, and Salton Sea KGRA's. Two examples of East Mesa brine were employed in order to illustrate the effect of brine variability within a given KGRA. The soil waters chosen for study were the Holtville, Rosita, and Vint soil solutions and the Vail 4 drain water. These waters were mixed with the four brines to produce 1%, 5%, and 10% brine combinations. The combinations then were analyzed with the help of GEOCHEM and were interpreted in the context of two proposed general contamination scenarios. The results of the speciation calculations pointed to the great importance, in brine, of sulfide as a precipitating agent for trace metals and of borate as a trace metal-complexing ligand. In general, precipitation and/or exchange adsorption in soil were found to reduce the levels of trace metals well below harmful concentrations. The principal exceptions were Li and B, which did not precipitate and which were at or very hear harmful levels in the soil water-brine mixtures.

Sposito, G.

1979-07-01T23:59:59.000Z

210

Analysis of hydrocarbon removal methods for the management of oilfield brines and produced waters  

E-Print Network (OSTI)

According to the Texas Railroad Commission (TRC), ????over 250 billion gallons of produced water is taken out of Texas Soil every year, and more than 35% of this water is not currently fit to use.?? Therefore, it can be assumed that domestically and globally, the petroleum industries challenge has been to develop a high-tech and cost effective method to purify the large volumes of oilfield brines and produced water. Currently, most of the produced water requires several pre- and post- treatment methods to aide in reducing fouling of membranes, separation of components, increasing influent and effluent quality, and preventing unwanted work stoppage during the desalination process. As a result, the pre- and post- treatment conditioning of the produced water affects the economics and scale-up (i.e. residence times, absorption capacity, etc??) of the varying processes parameters. Therefore, this research focuses on developing an economic analysis and determining the adsorption capacity of an organoclay system to remove oil.

Furrow, Brendan Eugene

2005-08-01T23:59:59.000Z

211

Corrosivity of geothermal brines. Progress report for period ending September 1977. Final report  

DOE Green Energy (OSTI)

Results of studies carried out principally during FY 1976 and FY 1977 on the corrosion of ferrous materials in synthetic geothermal brines are summarized. A survey of prior work on electrochemical aspects of the corrosion of iron and carbon steel in chloride solutions is presented, and some of the results of these investigations are summarized. The principal results of the present studies are then recapitulated. Included are measurements of the corrosion potential, corrosion rate, and polarization behavior of iron and carbon steel in deaerated 4 M NaCl over the pH range from 1 to 11 at temperatures up to 100/sup 0/C in a conventional Pyrex electrochemical cell. The effect of pH on hydrolysis, precipitation, and electrochemical reactivity of ferrous and ferric ions in 4 M NaCl at 25/sup 0/C is presented, and implications for plant operation are discussed. Details of a refreshed, stirred titanium autoclave system are described; the system permits electrochemical measurements to be made up to at least 200/sup 0/in corrosive aqueous saline media. The effect of pH (from pH equals 7 to pH equals 2) and temperature (from 25/sup 0/ to 200/sup 0/C) on the corrosion rate of type A212B carbon steel in deaerated 4 M NaCl is described. A relatively simple numerical correlation describes the data over the entire temperature and pH range. The spontaneous corrosion potentials and pitting potentials of types 304 and 316 stainless steel were measured in deaerated 4 M NaCl at pH equals 5 from 25/sup 0/ to 200/sup 0/C, and the data demonstrate the borderline stability of austenitic stainless steel for brine service. Finally, conclusions and recommendations for further studies are presented.

Posey, F.A.; Palko, A.A.; Bacarella, A.L.

1978-03-01T23:59:59.000Z

212

WEB RESOURCE: Nuclear Waste Disposal  

Science Conference Proceedings (OSTI)

May 10, 2007 ... The complete "Yucca Mountain Resource Book" is also available for download at this site. Citation: Nuclear Waste Disposal. 2007. Nuclear ...

213

Waste disposal and renewable resources.  

E-Print Network (OSTI)

?? Purpose/aim: The purpose of this dissertation is to find out the effect of waste disposal on environment and to explore the effect of renewable… (more)

Hai, Qu; PiaoYi, Sun

2013-01-01T23:59:59.000Z

214

Continuing disposal of coal ash  

Science Conference Proceedings (OSTI)

The large volume of power-plant coal ash produced and stricter Federal water pollution controls are making ash disposal increasingly difficult for utilities. The protection of surface and ground water quality required in the Resource conservation and Recovery Act of 1976 (RCRA) and the Federal Water Pollution Control Act's Clean Water Act (CWA) amendments of 1977 have raised the cost of disposal to a level where an acceptable method must be found. The Electric Power Research Institute's Coal Ash Disposal Manual (EPRI-FM--1257) describes-ash chemistry, disposal site selection, site monitoring and reclamation, and other information of interest to utilities that are making cost estimates and procedure evaluations. (DCK)

Lihach, N.; Golden, D.

1980-03-01T23:59:59.000Z

215

Treatment and Disposal of Unanticipated 'Scavenger' Wastewater  

Science Conference Proceedings (OSTI)

The Savannah River Site often generates wastewater for disposal that is not included as a source to one of the site's wastewater treatment facilities that are permitted by the South Carolina Department of Health and Environmental Control. The techniques used by the SRS contract operator (Westinghouse Savannah River Company) to evaluate and treat this unanticipated 'scavenger' wastewater may benefit industries and municipalities who experience similar needs. Regulations require that scavenger wastewater be treated and not just diluted. Each of the pollutants that are present must meet effluent permit limitations and/or receiving stream water quality standards. if a scavenger wastewater is classified as 'hazardous' under the Resource Conservation and Recovery Act (RCRA) its disposal must comply with RCRA regulations. Westinghouse Savannah River Company obtained approval from SCDHEC to dispose of scavenger wastewater under specific conditions that are included within the SRS National Pollutant Discharge Elimination System permit. Scavenger wastewater is analyzed in a laboratory to determine its constituency. Pollutant values are entered into spreadsheets that calculate treatment plant removal capabilities and instream concentrations. Disposal rates are computed, ensuring compliance with regulatory requirements and protection of treatment system operating units. Appropriate records are maintained in the event of an audit.

Payne, W.L.

2003-09-15T23:59:59.000Z

216

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

217

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

218

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network (OSTI)

2/07 WASTE DISPOSAL SECTION CORNELL UNIVERSITY PROCEDURE for DISPOSAL of RADIOACTIVE MATERIALS This procedure has been developed to ensure the safety of those individuals who handle radioactive waste identified hazardous waste, or other unusual issues require special consideration. Contact the Department

Manning, Sturt

219

Frio II Brine Pilot: Report on GEOSEQ Activities  

Science Conference Proceedings (OSTI)

LBNL's GEOSEQ project is a key participant in the Frio IIbrine pilot studying geologic sequestration of CO2. During During theinjection phase of the Frio-II brine pilot, LBNL collected multiple datasets including seismic monitoring, hydrologic monitoring and geochemicalsampling. These data sets are summarized in this report including allCASSM (continuous active source seismic monitoring) travel time data,injection pressure and flow rate data and gaseous sampling and tracerdata. Additional results from aqueous chemistry analysis performed by theU. S. Geological Survey (USGS) are summarized. Post injectionmodification of the flow model for Frio II is shown. Thesemodificationsare intended to facilitate integration with the monitoring data andincorporation of model heterogeneity. Current activities of LBNL's GEOSEQproject related to the Frio II test are shown, including development of anew petrophysical model for improved interpretation of seismic monitoringdata and integration of this data with flow modeling.

Daley, T.M.; Freifeld, B.M.; Ajo-Franklin, J.B.; Doughty, C.; Benson, S.M.

2007-11-17T23:59:59.000Z

220

Research, Development, and Demonstration Roadmap for Deep Borehole Disposal  

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

Research, Development, and Demonstration Roadmap for Deep Borehole Research, Development, and Demonstration Roadmap for Deep Borehole Disposal Research, Development, and Demonstration Roadmap for Deep Borehole Disposal This roadmap is intended to advance deep borehole disposal (DBD) from its current conceptual status to potential future deployment as a disposal system for spent nuclear fuel (SNF) and high-level waste (HLW). The objectives of the DBD RD&D roadmap include providing the technical basis for fielding a DBD demonstration project, defining the scientific research activities associated with site characterization and postclosure safety, as well as defining the engineering demonstration activities associated with deep borehole drilling, completion, and surrogate waste canister emplacement. Research, Development, and Demonstration Roadmap for Deep Borehole Disposal

Note: This page contains sample records for the topic "brine disposal system" from the National Library of EnergyBeta (NLEBeta).
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221

Low level tank waste disposal study  

SciTech Connect

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

Mullally, J.A.

1994-09-29T23:59:59.000Z

222

UNREVIEWED DISPOSAL QUESTION EVALUATION: WASTE DISPOSAL IN ENGINEERED TRENCH #3  

SciTech Connect

Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Hamm, L.; Smith, F.; Flach, G.; Hiergesell, R.; Butcher, T.

2013-07-29T23:59:59.000Z

223

Buoyancy effects on upward brine displacement caused by CO2 injection  

SciTech Connect

Upward displacement of brine from deep reservoirs driven by pressure increases resulting from CO{sub 2} injection for geologic carbon sequestration may occur through improperly sealed abandoned wells, through permeable faults, or through permeable channels between pinch-outs of shale formations. The concern about upward brine flow is that, upon intrusion into aquifers containing groundwater resources, the brine may degrade groundwater. Because both salinity and temperature increase with depth in sedimentary basins, upward displacement of brine involves lifting fluid that is saline but also warm into shallower regions that contain fresher, cooler water. We have carried out dynamic simulations using TOUGH2/EOS7 of upward displacement of warm, salty water into cooler, fresher aquifers in a highly idealized two-dimensional model consisting of a vertical conduit (representing a well or permeable fault) connecting a deep and a shallow reservoir. Our simulations show that for small pressure increases and/or high-salinity-gradient cases, brine is pushed up the conduit to a new static steady-state equilibrium. On the other hand, if the pressure rise is large enough that brine is pushed up the conduit and into the overlying upper aquifer, flow may be sustained if the dense brine is allowed to spread laterally. In this scenario, dense brine only contacts the lower-most region of the upper aquifer. In a hypothetical case in which strong cooling of the dense brine occurs in the upper reservoir, the brine becomes sufficiently dense that it flows back down into the deeper reservoir from where it came. The brine then heats again in the lower aquifer and moves back up the conduit to repeat the cycle. Parameter studies delineate steady-state (static) and oscillatory solutions and reveal the character and period of oscillatory solutions. Such oscillatory solutions are mostly a curiosity rather than an expected natural phenomenon because in nature the geothermal gradient prevents the cooling in the upper aquifer that occurs in the model. The expected effect of upward brine displacement is either establishment of a new hydrostatic equilibrium or sustained upward flux into the bottom-most region of the upper aquifer.

Oldenburg, C.M.; Rinaldi, A.

2010-01-15T23:59:59.000Z

224

Health Risks Associated with Disposal of Depleted Uranium  

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

Disposal DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Disposal of Depleted Uranium A discussion of risks associated with disposal...

225

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

Science Conference Proceedings (OSTI)

The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.

Esh, David W.; Bradford, Anna H. [U.S. Nuclear Regulatory Commission, Two White Flint North, MS T7J8, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2008-01-15T23:59:59.000Z

226

Documents: Disposal of DUF6 Conversion Products  

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

DUF6 Conversion Products Search Documents: Search PDF Documents View a list of all documents Disposal of DUF6 Conversion Products PDF Icon Engineering Analysis for Disposal of...

227

Environmental Risks of Depleted UF6 Disposal  

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

Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Disposal A discussion of the environmental impacts...

228

Assessment of Preferred Depleted Uranium Disposal Forms  

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

. . 7 3.2 PRELIMINARY ASSESSMENT OF DU DISPOSAL AT OTHER SITES . . . . . . . . . . 8 3.3 COSTS OF PRODUCTION, TRANSPORTATION, AND DISPOSAL OF DU WASTE FORMS . . . . . . . . . . ....

229

PROPERTY DISPOSAL RECORDS | Department of Energy  

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

DISPOSAL RECORDS More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) Records Management Handbook Inspection Report: INS-O-02-01...

230

Demilitarization and disposal technologies for conventional munitions and energetic materials  

SciTech Connect

Technologies for the demilitarization and disposal of conventional munitions and energetic materials are presented. A hazard separation system has been developed to remove hazardous subcomponents before processing. Electronic component materials separation processes have been developed that provide for demilitarization as well as the efficient recycling of materials. Energetic materials demilitarization and disposal using plasma arc and molten metal technologies are currently being investigated. These regulatory compliant technologies will allow the recycling of materials and will also provide a waste form suitable for final disposal.

Lemieux, A.A.; Wheelis, W.T.; Blankenship, D.M.

1994-09-01T23:59:59.000Z

231

WIPP - Pioneering Nuclear Waste Disposal  

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

Waste Disposal Cover Page and Table of Contents Closing the Circle The Long Road to WIPP - Part 1 The Long Road to WIPP - Part 2 Looking to the Future Related Reading and The...

232

Solid Waste Disposal Act (Texas)  

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

The Texas Commission on Environmental Quality is responsible for the regulation and management of municipal solid waste and hazardous waste. A fee is applied to all solid waste disposed in the...

233

Recovery of Fresh Water Resources from Desalination of Brine Produced During Oil and Gas Production Operations  

SciTech Connect

Management and disposal of produced water is one of the most important problems associated with oil and gas (O&G) production. O&G production operations generate large volumes of brine water along with the petroleum resource. Currently, produced water is treated as a waste and is not available for any beneficial purposes for the communities where oil and gas is produced. Produced water contains different contaminants that must be removed before it can be used for any beneficial surface applications. Arid areas like west Texas produce large amount of oil, but, at the same time, have a shortage of potable water. A multidisciplinary team headed by researchers from Texas A&M University has spent more than six years is developing advanced membrane filtration processes for treating oil field produced brines The government-industry cooperative joint venture has been managed by the Global Petroleum Research Institute (GPRI). The goal of the project has been to demonstrate that treatment of oil field waste water for re-use will reduce water handling costs by 50% or greater. Our work has included (1) integrating advanced materials into existing prototype units and (2) operating short and long-term field testing with full size process trains. Testing at A&M has allowed us to upgrade our existing units with improved pre-treatment oil removal techniques and new oil tolerant RO membranes. We have also been able to perform extended testing in 'field laboratories' to gather much needed extended run time data on filter salt rejection efficiency and plugging characteristics of the process train. The Program Report describes work to evaluate the technical and economical feasibility of treating produced water with a combination of different separation processes to obtain water of agricultural water quality standards. Experiments were done for the pretreatment of produced water using a new liquid-liquid centrifuge, organoclay and microfiltration and ultrafiltration membranes for the removal of hydrocarbons from produced water. The results of these experiments show that hydrocarbons from produced water can be reduced from 200 ppm to below 29 ppm level. Experiments were also done to remove the dissolved solids (salts) from the pretreated produced water using desalination membranes. Produced water with up to 45,000 ppm total dissolved solids (TDS) can be treated to agricultural water quality water standards having less than 500 ppm TDS. The Report also discusses the results of field testing of various process trains to measure performance of the desalination process. Economic analysis based on field testing, including capital and operational costs, was done to predict the water treatment costs. Cost of treating produced water containing 15,000 ppm total dissolved solids and 200 ppm hydrocarbons to obtain agricultural water quality with less than 200 ppm TDS and 2 ppm hydrocarbons range between $0.5-1.5 /bbl. The contribution of fresh water resource from produced water will contribute enormously to the sustainable development of the communities where oil and gas is produced and fresh water is a scarce resource. This water can be used for many beneficial purposes such as agriculture, horticulture, rangeland and ecological restorations, and other environmental and industrial application.

David B. Burnett; Mustafa Siddiqui

2006-12-29T23:59:59.000Z

234

Neutron formation temperature gauge and neutron activation analysis brine flow meter. Final report, October 1, 1976--March 31, 1978  

DOE Green Energy (OSTI)

Feasibility studies of nuclear techniques applicable to the determination of geothermal formation temperature and two-phase brine flow downhole have been performed. The formation temperature gauging technique involves injection of fast neutrons into the formation and analysis of the moderated slow neutron energy distribution by appropriately filtered neutron detectors. The scientific feasibility of the method has been demonstrated by analytical computational and experimental evaluation of the system response. A data analysis method has been developed to determine unambiguously the temperature, neutron absorption cross section and neutron moderating power of an arbitrary medium. The initial phase of a program to demonstrate the engineering feasibility of the technique has been performed. A sonde mockup was fabricated and measurements have been performed in a test stand designed to simulate a geothermal well. The results indicate that the formation temperature determined by this method is independent of differences between the temperature in the borehole fluid and the formation, borehole fluid density, and borehole fluid salinity. Estimates of performance specifications for a formation temperature sonde have been made on the basis of information obtained in this study and a conceptual design of a logging system has been developed. The technique for the determination of fluid flow in a well is based on neutron activation analysis of elements present in the brine. An analytical evaluation of the method has been performed. The results warrant further, experimental evaluation.

Vagelatos, N.; Steinman, D.K.; John, J.

1978-03-31T23:59:59.000Z

235

Scenarios of the TWRS low-level waste disposal program  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 Area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pretreating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1994-10-01T23:59:59.000Z

236

Chemical Speciation of Heterogeneously Reduced Pu in Synthetic Brines  

Science Conference Proceedings (OSTI)

X-ray absorption fine structure (XAFS) spectroscopy has been used to determine the speciation of Pu precipitates prepared by the heterogeneous reduction of Pu(VI) with Al and Fe in 5M NaCl and an ERDA-6 brine, a simulant from the Waste Isolation Pilot Plant in Carlsbad, New Mexico. NaOCl was added to some of these solutions to determine its effect on Pu speciation. Analysis of the Pu LIII spectra showed that all solids consisted of PuO2+x?y(OH)2y •zH2O, compounds with characteristics identical to those prepared by hydrolysis and with Pu?O and Pu?Pu distances identical to those treated at elevated temperature. Additionally, reduction with Al gave compounds with different site distributions than reduction with Fe, and reduction with Al or the addition of NaOCl appeared to suppress the formation of oxo groups and their associated Pu(V) sites.

Ding, Mei; Conca, James L.; Den Auwer, Christophe J.; Gabitov, Rinat I.; Hess, Nancy J.; Paviet-Hartmann, Patricia; Palmer, Phillip D.; LoPresti, Vin; Conradson, Steven D.

2006-07-01T23:59:59.000Z

237

POLYTETRAFLUOROETHYLENE-RICH POLYPHENLENESULFIDE BLEND TOP COATINGS FOR MITIGATING CORROSION OF CARBON STEEL IN 300 DEGREE CELCIUS BRINE.  

DOE Green Energy (OSTI)

We evaluated usefulness of a coating system consisting of an underlying polyphenylenesulfide (PPS) layer and top polytetrafluoroethylene (PTFE)-blended PPS layer as low friction, water repellent, anti-corrosion barrier film for carbon steel steam separators in geothermal power plants. The experiments were designed to obtain information on kinetic coefficient of friction, surface free energy, hydrothermal oxidation, alteration of molecular structure, thermal stability, and corrosion protection of the coating after immersing the coated carbon steel coupons for up to 35 days in CO{sub 2}-laden brine at 300 C. The superficial layer of the assembled coating was occupied by PTFE self-segregated from PPS during the melt-flowing process of this blend polymer; it conferred an outstanding slipperiness and water repellent properties because of its low friction and surface free energy. However, PTFE underwent hydrothermal oxidation in hot brine, transforming its molecular structure into an alkylated polyfluorocarboxylate salt complex linked to Na. Although such molecular transformation increased the friction and surface free energy, and also impaired the thermal stability of PTFE, the top PTFE-rich PPS layer significantly contributed to preventing the permeation of moisture and corrosive electrolytes through the coating film, so mitigating the corrosion of carbon steel.

SUGAMA, T.; JUNG, D.

2006-06-01T23:59:59.000Z

238

Tank Waste Disposal Program redefinition  

SciTech Connect

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

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

1991-10-01T23:59:59.000Z

239

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

240

Low and medium level radioactive waste disposal in France  

Science Conference Proceedings (OSTI)

ANDRA, as the national radioactive waste management agency of France, was created in 1979 as part of the French Atomic Energy, Commission and is responsible for radioactive waste disposal. Legislation passed on December 30, 1991 gave ANDRA greater autonomy and responsibility for radioactive waste management by making it a Public Service Company separate from the CEA and by placing it under the supervisory authority of the Ministries of Industry, of the Environment and of Research. The legislation specifically delegates the following responsibilities to ANDRA: (1) establishment of specifications for radioactive waste solidification and disposal; (2) design, siting and construction of new waste disposal facilities; (3) disposal facility operations; and (4) participation in research on, and design and construction of, isolation systems for long lived waste.

Potier, J.M.

1994-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Depleted uranium disposal options evaluation  

SciTech Connect

The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D. [Science Applications International Corp., Idaho Falls, ID (United States). Waste Management Technology Div.

1994-05-01T23:59:59.000Z

242

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

243

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Issued on January 11, 2013, the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High Level Radioactive Waste.pdf More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and

244

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste The Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel and high-level radioactive waste from civilian nuclear power generation, defense, national security and other activities. Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste More Documents & Publications Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste

245

CX-010401: Categorical Exclusion Determination  

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

Replace Brine Disposal System Header to West Hackberry Brine Tanks CX(s) Applied: B1.3 Date: 04/22/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

246

Electrochemical Apparatus with Disposable and Modifiable Parts  

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

Electrochemical Apparatus with Disposable and Modifiable Parts Electrochemical Apparatus with Disposable and Modifiable Parts Electrochemical Apparatus with Disposable and Modifiable Parts The invention also includes electrochemical apparatus that can interface with optical instrumentation. If the working electrode is transparent, light from an optical fiber may be directed through the working electrode and into a cuvette. July 3, 2013 Electrochemical Apparatus with Disposable and Modifiable Parts Available for thumbnail of Feynman Center (505) 665-9090 Email Electrochemical Apparatus with Disposable and Modifiable Parts Applications: Electrochemical experiments in solution Electrochemical experiments on surfaces Bulk electrolysis experiments Fuel cells Corrosion studies Academic Labs Teaching and research Benefits: Incorporates disposable, commercially available cuvettes

247

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network (OSTI)

Laboratory Waste Disposal HAZARDOUS GLASS Items that could cut or puncture skin or trash- can liners. This waste stream must be boxed to protect custodial staff. It goes directly to the landfill lined cardboard box. Tape seams with heavy duty tape to contain waste. Limit weight to 20 lbs. Or

Sheridan, Jennifer

248

Pore-Level Modeling of Carbon Dioxide Sequestration in Brine Fields  

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

Pore-Level Modeling of Carbon Dioxide Sequestration in Brine Fields Pore-Level Modeling of Carbon Dioxide Sequestration in Brine Fields M. Ferer, (mferer@wvu.edu) Department of Physics, West Virginia University, Morgantown, WV 26506-6315, Grant S. Bromhal, (bromhal@netl.doe.gov) US DOE, National Energy Technology Laboratory, Morgantown, WV 26507-0880; and Duane H. Smith, (dsmith@netl.doe.gov) US DOE, National Energy Technology Laboratory, Morgantown, WV 26507-0880 & Department of Physics, West Virginia University. Underground injection of gas is a common practice in the oil and gas industry. Injection into deep, brine-saturated formations is a commercially proven method of sequestering CO 2 . However, it has long been known that displacement of a connate fluid by a less viscous fluid produces unstable displacement fronts with significant fingering. This fingering allows only a

249

Acceptance test procedure: RMW Land Disposal Facility Project W-025  

SciTech Connect

This ATP establishes field testing procedures to demonstrate that the electrical/instrumentation system functions as intended by design for the Radioactive Mixed Waste Land Disposal Facility. Procedures are outlined for the field testing of the following: electrical heat trace system; transducers and meter/controllers; pumps; leachate storage tank; and building power and lighting.

Roscha, V. [Westinghouse Hanford Co., Richland, WA (United States)

1994-12-12T23:59:59.000Z

250

DISPOSAL OF RADIOACTIVE WASTE ON LAND  

SciTech Connect

Two years' consideration of the disposal problem by the National Research Council Committee on Waste Disposal has led to certain conclusions which are presented. Waste may be safely disposed of at many sites in the United States but conversely there are many large areas in which it is unlikely that disposal sites can be found as, for example, the Atlantic seaboard. The research to ascertain feasibility of disposal hss for the most part not yet been done. The most practical immediate solution of the problem suggests disposal in cavities mined in salt beds or domes. Disposal could be greatly simplified if the waste could be gotten into solid form of relatively insoluble character. Disposal in porous beds underground has capabilities of taking large volumes but will require considerable research to mske the waste compatible with such an environment. The main difficulty with this method at present is to prevent clogging of pore space as waste is pumped in. (auth)

Hess, H.H.; Thurston, W.R.

1958-06-01T23:59:59.000Z

251

Disposal of NORM waste in salt caverns  

Science Conference Proceedings (OSTI)

Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

1998-07-01T23:59:59.000Z

252

ASSESSMENT OF TECHNETIUM LEACHABILITY IN CEMENT STABILIZED BASIN 43 GROUNDWATER BRINE  

SciTech Connect

This report is an initial report on the laboratory effort executed under RPP-PLAN-33338, Test Plan for the Assessment of Technetium Leachability in Cement-Stabilized Basin 43 Groundwater Brine. This report delineates preliminary data obtained under subcontract 21065, release 30, from the RJ Lee Group, Inc., Center for Laboratory Sciences. The report is predicated on CLS RPT-816, Draft Report: Assessment of Technetium Leachability in Cement Stabilized Basin 43 Groundwater Brine. This document will be revised on receipt of the final RJ Lee Group, Inc., Center for Laboratory Sciences report, which will contain data subjected to quality control and quality assurance criteria.

COOKE GA; DUNCAN JB; LOCKREM LL

2008-09-30T23:59:59.000Z

253

Changes in Vegetation at the Monticello, Utah, Disposal Site...  

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

Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal...

254

Disposal Practices at the Nevada Test Site 2008 | Department...  

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

Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at...

255

FAQ 42-What are the potential environmental impacts from disposal...  

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

disposal of depleted uranium as an oxide? What are the potential environmental impacts from disposal of depleted uranium as an oxide? Disposal as oxide could result in adverse...

256

Repository Reference Disposal Concepts and Thermal Load Management...  

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

Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists...

257

Calcium Isotopic Variation in Marine Evaporites and Carbonates: Applications to Late Miocene Mediterranean Brine Chemistry and Late Cenozoic Calcium Cycling in the Oceans  

E-Print Network (OSTI)

Field: Geochemistry Studies in Isotope Geology Professors J.Isotopes and Brine Evolution ……………………………………………………………….. 3.2.1 General geology andIsotopes and Brine Evolution 3.2.1 General geology and

Hensley, Tabitha Michele

2006-01-01T23:59:59.000Z

258

Waste disposal options report. Volume 1  

SciTech Connect

This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01T23:59:59.000Z

259

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

260

Decontamination of Reactor Systems and Contaminated Components for Disposal or Refurbishment: Developments and Experience with the EPRI DFD Chemical Decontamination Process  

Science Conference Proceedings (OSTI)

This report describes recent developments using the EPRI (Decontamination for Decommissioning (DFD) dilute chemical decontamination process on reactor coolant systems and components. The nuclear industry has now used the process for a variety of applications, from cleaning small components to full system decontamination of retired plants. The report documents substantial savings in radiation exposures during decommissioning work and discusses the benefits of using the process to reduce radioactive waste ...

2001-11-05T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

REGULATIONS ON PHOTOVOLTAIC MODULE DISPOSAL AND RECYCLING.  

Science Conference Proceedings (OSTI)

Environmental regulations can have a significant impact on product use, disposal, and recycling. This report summarizes the basic aspects of current federal, state and international regulations which apply to end-of-life photovoltaic (PV) modules and PV manufacturing scrap destined for disposal or recycling. It also discusses proposed regulations for electronics that may set the ground of what is to be expected in this area in the near future. In the US, several states have started programs to support the recycling of electronic equipment, and materials destined for recycling often are excepted from solid waste regulations during the collection, transfer, storage and processing stages. California regulations are described separately because they are different from those of most other states. International agreements on the movement of waste between different countries may pose barriers to cross-border shipments. Currently waste moves freely among country members of the Organization of Economic Cooperation and Development (OECD), and between the US and the four countries with which the US has bilateral agreements. However, it is expected, that the US will adopt the rules of the Basel Convention (an agreement which currently applies to 128 countries but not the US) and that the Convection's waste classification system will influence the current OECD waste-handling system. Some countries adopting the Basel Convention consider end-of-life electronics to be hazardous waste, whereas the OECD countries consider them to be non-hazardous. Also, waste management regulations potentially affecting electronics in Germany and Japan are mentioned in this report.

FTHENAKIS,V.

2001-01-29T23:59:59.000Z

262

Environmental waste disposal contracts awarded  

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

Environmental contracts awarded locally Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste clean-up contracts. April 3, 2012 Worker moves drums of transuranic (TRU) waste at a staging area A worker stages drums of transuranic waste at Los Alamos National Laboratory's Technical Area 54. the Lap ships such drums to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) in Southern New Mexico. The Lab annually averages about 120 shipments of TRU waste to WIPP. Contact Small Business Office (505) 667-4419 Email "They will be valuable partners in the Lab's ability to dispose of the waste safely and efficiently." Small businesses selected for environmental work at LANL

263

Risk assessment of nonhazardous oil-field waste disposal in salt caverns.  

Science Conference Proceedings (OSTI)

Salt caverns can be formed in underground salt formations incidentally as a result of mining or intentionally to create underground chambers for product storage or waste disposal. For more than 50 years, salt caverns have been used to store hydrocarbon products. Recently, concerns over the costs and environmental effects of land disposal and incineration have sparked interest in using salt caverns for waste disposal. Countries using or considering using salt caverns for waste disposal include Canada (oil-production wastes), Mexico (purged sulfates from salt evaporators), Germany (contaminated soils and ashes), the United Kingdom (organic residues), and the Netherlands (brine purification wastes). In the US, industry and the regulatory community are pursuing the use of salt caverns for disposal of oil-field wastes. In 1988, the US Environmental Protection Agency (EPA) issued a regulatory determination exempting wastes generated during oil and gas exploration and production (oil-field wastes) from federal hazardous waste regulations--even though such wastes may contain hazardous constituents. At the same time, EPA urged states to tighten their oil-field waste management regulations. The resulting restrictions have generated industry interest in the use of salt caverns for potentially economical and environmentally safe oil-field waste disposal. Before the practice can be implemented commercially, however, regulators need assurance that disposing of oil-field wastes in salt caverns is technically and legally feasible and that potential health effects associated with the practice are acceptable. In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. It investigated regulatory issues; the types of oil-field wastes suitable for cavern disposal; cavern design and location considerations; and disposal operations, closure and remediation issues. It determined that if caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they could, from technical and legal perspectives, be suitable for disposing of oil-field wastes. On the basis of these findings, ANL subsequently conducted a preliminary risk assessment on the possibility that adverse human health effects (carcinogenic and noncarcinogenic) could result from exposure to contaminants released from the NOW disposed of in salt caverns. The methodology for the risk assessment included the following steps: identifying potential contaminants of concern; determining how humans could be exposed to these contaminants; assessing contaminant toxicities; estimating contaminant intakes; and estimating human cancer and noncancer risks. To estimate exposure routes and pathways, four postclosure cavern release scenarios were assessed. These were inadvertent cavern intrusion, failure of the cavern seal, failure of the cavern through cracks, failure of the cavern through leaky interbeds, and partial collapse of the cavern roof. Assuming a single, generic, salt cavern and generic oil-field wastes, potential human health effects associated with constituent hazardous substances (arsenic, benzene, cadmium, and chromium) were assessed under each of these scenarios. Preliminary results provided excess cancer risk and hazard index (for noncancer health effects) estimates that were well within the EPA target range for acceptable exposure risk levels. These results lead to the preliminary conclusion that from a human health perspective, salt caverns can provide an acceptable disposal method for nonhazardous oil-field wastes.

Elcock, D.

1998-03-10T23:59:59.000Z

264

A study of hydrocarbons associated with brines from DOE geopressured wells  

DOE Green Energy (OSTI)

Accomplishments are summarized on the following tasks: distribution coefficients and solubilities, DOE design well sampling, analysis of well samples, review of theoretical models of geopressured reservoir hydrocarbons, monitor for aliphatic hydrocarbons, development of a ph meter probe, DOE design well scrubber analysis, removal and disposition of gas scrubber equipment at Pleasant Bayou Well, and disposition of archived brines.

Keeley, D.F.

1993-01-01T23:59:59.000Z

265

A study of hydrocarbons associated with brines from DOE geopressured wells. Final report  

DOE Green Energy (OSTI)

Accomplishments are summarized on the following tasks: distribution coefficients and solubilities, DOE design well sampling, analysis of well samples, review of theoretical models of geopressured reservoir hydrocarbons, monitor for aliphatic hydrocarbons, development of a ph meter probe, DOE design well scrubber analysis, removal and disposition of gas scrubber equipment at Pleasant Bayou Well, and disposition of archived brines.

Keeley, D.F.

1993-07-01T23:59:59.000Z

266

Recovery 2011 CSPG CSEG CWLS Convention 1 Brine-methane Substitution: The Seismic Response of Coalbeds  

E-Print Network (OSTI)

an important source of natural gas (Shi and Durucan, 2005). The production of the CBM takes place when coal seam using a tank model which assumes that there is no variation of the reservoir properties). For the Gassmann fluid substitution, we assume a pore fluid of 100% brine as the initial condition and calculate

Ferguson, Robert J.

267

Development of the EPRI DFDX Chemical Decontamination Process: A New Process for the Chemical Decontamination of Nuclear Systems and Components for Disposal or Refurbishment  

Science Conference Proceedings (OSTI)

This report describes the development of the EPRI DFDX process for the chemical decontamination of reactor coolant systems and components. This new process is an enhancement of the EPRI DFD process, which utility operators have used widely for decontamination of retired reactors and plant components. The process uses electrochemical ion exchange technology, which reduces the volume of secondary radioactive waste by a factor of up to 10. The project team has completed development, filed a patent applicati...

2002-09-26T23:59:59.000Z

268

CO2–brine–caprock interaction: Reactivity experiments on Eau Claire shale and a review of relevant literature  

SciTech Connect

Long term containment of stored CO2 in deep geological reservoirs will depend on the performance of the caprock to prevent the buoyant CO2 from escaping to shallow drinking water aquifers or the ground surface. Here we report new laboratory experiments on CO2-brine-caprock interactions and a review of the relevant literature. The Eau Claire Formation is the caprock overlying the Mount Simon sandstone formation, one of the target geological CO2 storage reservoirs in the Midwest USA region. Batch experiments of Eau Claire shale dissolution in brine were conducted at 200 C and 300 bars to test the extent of fluid-rock reactions. Scanning electron microscopy (SEM) and X-ray diffraction (XRD) analysis indicate minor dissolution of K-feldspar and anhydrite, and precipitation of pore-filling and pore-bridging illite and/or smectite, and siderite in the vicinity of pyrite. We also reviewed relevant reactivity experiments, modeling work, and field observations in the literature in an attempt to help define the framework for future studies on the geochemical systems of the caprock overlain on geological CO2 storage formations. Reactivity of the caprock is generally shown to be low and limited to the vicinity of the CO2-caprock interface, and is related to the original caprock mineralogical and petrophysical properties. Stable isotope studies indicate that CO2 exists in both free phase and dissolved phase within the caprock. Carbonate and feldspar dissolution is reported in most studies, along with clay and secondary carbonate precipitation. Currently, research is mainly focused on the micro-fracture scale geochemistry of the shaly caprock. More attention is required on the potential pore scale reactions that may become significant given the long time scale associated with geological carbon storage

Liua, Faye; Lua, Peng; Griffith, Craig; Hedges, Sheila W.; Soong, Yee; Hellevang, Helge; Zhua,Chen

2012-01-01T23:59:59.000Z

269

CX-002829: Categorical Exclusion Determination | Department of...  

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

CX-002829: Categorical Exclusion Determination West Hackberry Brine Disposal Wells Control Systems Upgrade CX(s) Applied: B1.7 Date: 06212010 Location(s): West...

270

Particle measurement and brine chemistry at the Salton Sea Deep Well  

DOE Green Energy (OSTI)

The Advanced Brine Chemistry Project, a part of the US Department of Energy's Geothermal Energy Program, is addressing operating problems associated with scaling and corrosion at geothermal power plants. Under this project, Pacific Northwest Laboratory conducted a series of tests at the Salton Sea Deep Well, which has one of the highest solids contents in the world. The purpose of the tests was to evaluate monitoring instrumentation under field conditions and relate particulate formation to the brine chemistry. The instrumentation, was evaluated under scaling geothermal conditions using two different principles: ultrasonic reflection and laser light scattering. The following conclusions were drawn from the instrumentation testing and brine chemistry and particulate analyses. (1) Using reflected ultrasonic impulses to detect suspended particles has been demonstrate for on-line application in a geothermal brine with strong scaling tendencies. Advantages over laser light scattering include improved high-temperature durability for the transducer and longer operation with less maintenance. (2) Counting and sizing particles using laser light scattering requires constant maintenance in geothermal applications. (3) Silica is the dominant scale species and appears in amounts orders of magnitude greater than other minor species such as barium sulfate. (4) The silica that formed at high temperatures and short residence times is very gelatinous and difficult to filter out of the brine. (5) Correlation of instrument readings with particle collection data was difficult because conditions on the filter (i.e., temperature, flowrate, and pressure) could not be maintained constant for long enough intervals to obtain comparable information. 5 refs., 27 figs., 2 tabs.

Robertus, R.J.; Kindle, C.H.; Sullivan, R.G.; Shannon, D.W.

1991-09-01T23:59:59.000Z

271

Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)  

SciTech Connect

This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.

Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.

1986-06-01T23:59:59.000Z

272

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

273

Idaho CERCLA Disposal Facility at Idaho National Laboratory  

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

Idaho Operations Idaho Operations Review of the Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory By Craig H. Benson, PhD, PE; William H. Albright, PhD; David P. Ray, PE, and John Smegal Sponsored by: The Office of Engineering and Technology (EM-20) 5 December 2007 i TABLE OF CONTENTS 1. INTRODUCTION 1 2. OBJECTIVE AND SCOPE 1 3. LINE OF INQUIRY NO. 1 2 3.1 Containerized Waste 2 3.2 Compacted Mixtures of Soil and Debris 3 3.3 Final Cover Settlement 3 3.4 Leachate Collection System and Leak Detection Zone Monitoring 4 4. LINE OF INQUIRY NO. 2 4 5. LINE OF INQUIRY NO. 3 5 6. SUMMARY OF RECOMMENDATIONS 6 7. ACKNOWLEDGEMENTS 6 FIGURES 7 1 1. INTRODUCTION The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility authorized by the US

274

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

275

Readiness Assessment Plan, Hanford 200 areas treated effluent disposal facilities  

SciTech Connect

This Readiness Assessment Plan documents Liquid Effluent Facilities review process used to establish the scope of review, documentation requirements, performance assessment, and plant readiness to begin operation of the Treated Effluent Disposal system in accordance with DOE-RLID-5480.31, Startup and Restart of Facilities Operational Readiness Review and Readiness Assessments.

Ulmer, F.J.

1995-02-06T23:59:59.000Z

276

Comparison of low-level waste disposal programs of DOE and selected international countries  

SciTech Connect

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada`s first demonstration LLW disposal facility.

Meagher, B.G. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Cole, L.T. [Cole and Associates (United States)

1996-06-01T23:59:59.000Z

277

UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1  

SciTech Connect

This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system`s designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy.

NONE

1995-10-01T23:59:59.000Z

278

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

279

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

280

Countercurrent direct contact heat exchange process and system  

DOE Patents (OSTI)

Recovery of energy from geothermal brines and other hot water sources by direct contact heat exchange with a working fluid, such as a hydrocarbon working fluid, e.g. isobutane. The process and system consists of a plurality of stages, each stage including mixing and settling units. In the first stage, hot brine and arm working fluid are intimately mixed and passed into a settler wherein the brine settles to the bottom of the settler and the hot working fluid rises to the top. The hot working fluid is passed to a heat engine or turbine to produce work and the working fluid is then recycled back into the system. The system is comprised of a series of stages each containing a settler and mixer, and wherein the working fluid and the brine flow in a countercurrent manner through the stages to recover the heat from the brine in increments and raise the temperature of the working fluid in increments.

Wahl, III, Edward F. (Claremont, CA); Boucher, Frederic B. (San Juan Capistrano, CA)

1979-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

NONE

1996-08-01T23:59:59.000Z

282

Disposal Authorization Statement | Department of Energy  

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

and closure of the SDF, and is a requirement under the Department of Energy's (DOE) Radioactive Waste Management Manual 435.1-1. Disposal Authorization Statement More...

283

Operational Issues at the Environmental Restoration Disposal...  

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

ERDF is operated by Stoller Corporation (Stoller) under subcontract to Washington Closure Hanford (WCH). Currently, six disposal cells comprise the ERDF, with four more...

284

Date: ____________ MATERIAL FOR HAZARDOUS WASTE DISPOSAL  

E-Print Network (OSTI)

Feb 2003 Date: ____________ MATERIAL FOR HAZARDOUS WASTE DISPOSAL 1) Source: Bldg: ________________________________________ Disinfection? cc YES, Autoclaved (each container tagged with `Treated Biomedical Waste') cc YES, Chemical

Sinnamon, Gordon J.

285

Brine flow up a borehole caused by pressure perturbation from CO2 storage: Static and dynamic evaluations  

E-Print Network (OSTI)

flow model for carbon dioxide and brine, in Proceedings 9 thGeological Storage of Carbon Dioxide, in: S.J. Baines andGeological Storage of Carbon Dioxide, Geological Society,

Birkholzer, J.T.

2012-01-01T23:59:59.000Z

286

Used Fuel Disposition Campaign Disposal  

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

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

287

Recovery Act: Molecular Simulation of Dissolved Inorganic Carbons for Underground Brine CO2 Sequestration  

SciTech Connect

To further our understanding and develop the method for measuring the DICs under geological sequestration conditions, we studied the infrared spectra of DICs under high pressure and temperature conditions. First principles simulations of DICs in brine conditions were performed using a highly optimized ReaxFF-DIC forcefield. The thermodynamics stability of each species were determined using the 2PT method, and shown to be consistent with the Reax simulations. More importantly, we have presented the IR spectra of DIC in real brine conditions as a function of temperature and pressure. At near earth conditions, we find a breaking of the O-C-O bending modes into asymmetric and symmetric modes, separated by 100cm{sup -1} at 400K and 5 GPa. These results can now be used to calibrate FTIR laser measurements.

Goddard, William

2012-11-30T23:59:59.000Z

288

Prelimiary investigation desalting of geothermal brines in the Imperial Valley of California  

SciTech Connect

The Imperial Valley Project is an applied research program to provide geologic, hydrologic, engineering, and economic information necessary for development of the geothermal resources of the delta of the lower Colorado River. It is suggested that a desalting pilot plant be associated with the project to develop an economic desalting process if 2 to 3% geothermal brine is produced. The process will be unconventional in that waste heat must be rejected to atmosphere in wet or dry cooling towers. The presence of large amounts of CO/sub 2/, H/sub 2/S, and silica will require gas removal and silicascale control equipment. The plant would process up to 75,000 gallons of brine per day. (MCW)

Spiewak, I.; Hise, E.C.; Reed, S.A.; Thompson, S.A.

1970-03-01T23:59:59.000Z

289

Aromatic hydrocarbons associated with brines from geopressured wells. Annual report, fiscal 1985  

DOE Green Energy (OSTI)

Samples of cryocondensates - materials condensed at - 78.5/sup 0/C were taken on a regular basis from the gas stream for the USDOE geopressured wells. Most of the data has been taken from the Gladys McCall well as it has flowed on a regular and almost continous basis. The cryocondensates, not the ''condensate'' from gas wells, are almost exclusively aromatic hydrocarbons, primarily benzene, toluene, ethylbenzene, and the xylenes, but contain over 95 compounds, characterized using gas chromatographic-mass spectroscopy. The solubility in water and brine of benezene, toluene, ethylbenzene and o-xylene, some of the components of the cryocondensate, as well as distribution coefficients between water or brine and a standard oil have been measured. 25 refs.

Keeley, D.F.; Meriwether, J.R.

1985-01-01T23:59:59.000Z

290

Scientific Considerations Related to Regulation Development for CO2 Sequestration in Brine Formations  

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

SCIENTIFIC CONSIDERATIONS RELATED TO REGULATION SCIENTIFIC CONSIDERATIONS RELATED TO REGULATION DEVELOPMENT FOR CO 2 SEQUESTRATION IN BRINE FORMATIONS Chin-Fu Tsang (cftsang@lbl.gov; (510) 486-5782) Sally M. Benson (smbenson@lbl.gov; (510) 486-7071) Earth Sciences Division, Ernest Orlando Lawrence Berkeley National Laboratory One Cyclotron Road, MS 90-1116, Berkeley, CA 94720 Bruce Kobelski (kobelski.bruce@epa.gov) Robert Smith (smith.robert-eu@epamail.epa.gov) U.S. Environmental Protection Agency Office of Drinking Water and Ground Water, Washington D.C. Introduction Reduction of atmospheric emissions of CO 2 (DOE, 1999a) through injection of CO 2 into in deep brine formations is being actively studied both in the U.S. and internationally. If this technology is to be employed broadly enough to make a significant impact on global

291

Comparison of selected oil-field brines from fields in the Permian basin, West Texas-southeast New Mexico  

SciTech Connect

Stiff diagrams of oil-field brines from the west Texas Permian basin are identifiable within the geological framework. Plotted from a simple analysis of three cations and three anions, older Paleozoic waters can be categorized as either 'pristine' or modified, usually by a later influx of Permian or early Pennsylvanian water. These different plots can be segregated by geologic province. The Permian brines differ by age and also by environment (shelf, basin, etc.).

White, H.G. III

1992-04-01T23:59:59.000Z

292

Chemical Disposal The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program  

E-Print Network (OSTI)

Chemical Disposal Dec, 2011 Chemicals: The Office of Environmental Health & Safety operates a Chemical Waste Disposal Program where all University chemical waste is picked up and sent out for proper disposal. (There are some chemicals that they will not take because of their extreme hazards

Machel, Hans

293

Biochemical solubilization of toxic salts from residual geothermal brines and waste waters  

DOE Patents (OSTI)

A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed, The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts, For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates.

Premuzic, Eugene T. (East Moriches, NY); Lin, Mow S. (Rocky Point, NY)

1994-11-22T23:59:59.000Z

294

Biochemical solubilization of toxic salts from residual geothermal brines and waste waters  

DOE Patents (OSTI)

A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed. The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts. For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates. 54 figs.

Premuzic, E.T.; Lin, M.S.

1994-11-22T23:59:59.000Z

295

Use of inhibitors for scale control in brine-producing gas and oil wells  

SciTech Connect

Field and laboratory work have shown that calcium-carbonate scale formation in waters produced with natural gas and oil can be prevented by injection of phosphonate inhibitor into the formation, even if the formation is sandstone without calcite binging material. Inhibitor squeeze jobs have been carried out on DOE's geopressured-geothermal Gladys McCall brine-gas well and GRI's co-production wells in the Hitchcock field. Following the inhibitor squeeze on Gladys McCall, the well produced over five million barrels of water at a rate of approximately 30,000 BPD without calcium-carbonate scaling. Before the inhibitor squeeze, the well could not be produced above 15,000 BPD without significant scale formation. In the GRI brine-gas co-production field tests, inhibitor squeezes have been used to successfully prevant scaling. Laboratory work has been conducted to determine what types of oil field waters are subject to scaling. This research has led to the development of a saturation index and accompanying nomographs which allow prediction of when scale will develop into a problem in brine production.

Tomson, M.B.; Prestwich, S.

1986-01-01T23:59:59.000Z

296

Petroleum Engineering Techniques for HLW Disposal  

Science Conference Proceedings (OSTI)

This paper describes why petroleum engineering techniques are of importance and can be used for underground disposal of HLW (high-level radioactive waste). It is focused on rock salt as a geological host medium in combination with disposal of the HLW canisters in boreholes drilled from the surface. Both permanent disposal and disposal with the option to retrieve the waste are considered. The paper starts with a description of the disposal procedure. Next disposal in deep boreholes is treated. Then the possible use of deviated boreholes and of multiple boreholes is discussed. Also waste isolation aspects and the implications of the HLW heat generation are treated. It appears that the use of deep boreholes can be beneficial, and also that--to a certain extent--borehole deviation offers possibilities. The benefits of using multiple boreholes are questionable for permanent disposal, while this technique cannot be applied for retrievable disposal. For the use of casing material, the additional temperature rise due to the HLW heat generation must be taken into account.

van den Broek, W. M. G. T.

2002-02-25T23:59:59.000Z

297

? Disposal concepts (“enclosed”): crystalline, clay/shale,  

E-Print Network (OSTI)

salt, deep borehole (Re: January, 2012 briefing) ? Thermal analysis for mined, “enclosed ” concepts ? Finite element analysis for generic salt repository (waste package size up to 32-PWR) ? “Open ” disposal concept development: shale unbackfilled, sedimentary backfilled, and hard-rock unsaturated (waste package sizes up to 32-PWR) ? Thermal analysis for mined, “open ” concepts ? Cost estimation for 5 disposal concepts ? Summary and conclusions

Ernest Hardin (snl; Jim Blink; Harris Greenberg (llnl; Joe Carter (srnl; Rob Howard (ornl

2012-01-01T23:59:59.000Z

298

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

299

Land Management and Disposal | Department of Energy  

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

Land Management and Disposal Land Management and Disposal Land Management and Disposal Land Management and Disposal 42 USC 2201(g), Section 161(g), of the AEA 42 USC Section 2224, Section 174 DOE, July 2004, Real Property Desk Guide Requirements: Document Title P.L. 83-703 (68 Stat. 919), Section 161g Grants Special Authority as Required in the Act to Acquire, Sell, Dispose, etc., of Real Property in Furtherance of the Department's Mission (Under the Atomic Energy Act of 1954) P.L. 95-91, 91 Stat. 578 (Sections 302 and 347) Department of Energy Organizational Act of 1977, Delegated Authority for Real Property P.L. 106-580 Federal Property and Administrative Services Act of 1949, As Amended P.L. 105-85 Federal Property and Administrative Services Act of 1949, As Amended 10 CFR 770 Transfer of Real Property at Defense Nuclear Facilities for Economic Development

300

Basis for Identification of Disposal Options for R and D for Spent Nuclear  

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

Basis for Identification of Disposal Options for R and D for Spent Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study that spans a suite of behavior characteristics that impose a broad range of potential conditions on the design of the repository, the engineered barrier, and the waste. Salt, clay/shale, and granitic rocks represent a reasonable cross-section of behavior. Granitic rocks are also the primary basement rock to consider for deep borehole disposal. UFD is developing generic system analysis capability and general experimental data related to mined geologic disposal in the three

Note: This page contains sample records for the topic "brine disposal system" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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301

Advanced Membrane Filtration Technology for Cost Effective Recovery of Fresh Water from Oil & Gas Produced Brine  

SciTech Connect

This study is developing a comprehensive study of what is involved in the desalination of oil field produced brine and the technical developments and regulatory changes needed to make the concept a commercial reality. It was originally based on ''conventional'' produced water treatment and reviewed (1) the basics of produced water management, (2) the potential for desalination of produced brine in order to make the resource more useful and available in areas of limited fresh water availability, and (3) the potential beneficial uses of produced water for other than oil production operations. Since we have begun however, a new area of interest has appeared that of brine water treatment at the well site. Details are discussed in this technical progress report. One way to reduce the impact of O&G operations is to treat produced brine by desalination. The main body of the report contains information showing where oil field brine is produced, its composition, and the volume available for treatment and desalination. This collection of information all relates to what the oil and gas industry refers to as ''produced water management''. It is a critical issue for the industry as produced water accounts for more than 80% of all the byproducts produced in oil and gas exploration and production. The expense of handling unwanted waste fluids draws scarce capital away for the development of new petroleum resources, decreases the economic lifetimes of existing oil and gas reservoirs, and makes environmental compliance more expensive to achieve. More than 200 million barrels of produced water are generated worldwide each day; this adds up to more than 75 billion barrels per year. For the United States, the American Petroleum Institute estimated about 18 billion barrels per year were generated from onshore wells in 1995, and similar volumes are generated today. Offshore wells in the United States generate several hundred million barrels of produced water per year. Internationally, three barrels of water are produced for each barrel of oil. Production in the United States is more mature; the US average is about 7 barrels of water per barrel of oil. Closer to home, in Texas the Permian Basin produces more than 9 barrels of water per barrel of oil and represents more than 400 million gallons of water per day processed and re-injected.

David B. Burnett

2005-09-29T23:59:59.000Z

302

Combination gas producing and waste-water disposal well  

DOE Patents (OSTI)

The present invention is directed to a waste-water disposal system for use in a gas recovery well penetrating a subterranean water-containing and methane gas-bearing coal formation. A cased bore hole penetrates the coal formation and extends downwardly therefrom into a further earth formation which has sufficient permeability to absorb the waste water entering the borehole from the coal formation. Pump means are disposed in the casing below the coal formation for pumping the water through a main conduit towards the water-absorbing earth formation. A barrier or water plug is disposed about the main conduit to prevent water flow through the casing except for through the main conduit. Bypass conduits disposed above the barrier communicate with the main conduit to provide an unpumped flow of water to the water-absorbing earth formation. One-way valves are in the main conduit and in the bypass conduits to provide flow of water therethrough only in the direction towards the water-absorbing earth formation.

Malinchak, Raymond M. (McKeesport, PA)

1984-01-01T23:59:59.000Z

303

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER  

SciTech Connect

The purpose of ''Design Analysis for the Defense High-Level Waste Disposal Container'' analysis is to technically define the defense high-level waste (DHLW) disposal container/waste package using the Waste Package Department's (WPD) design methods, as documented in ''Waste Package Design Methodology Report'' (CRWMS M&O [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000a). The DHLW disposal container is intended for disposal of commercial high-level waste (HLW) and DHLW (including immobilized plutonium waste forms), placed within disposable canisters. The U.S. Department of Energy (DOE)-managed spent nuclear fuel (SNF) in disposable canisters may also be placed in a DHLW disposal container along with HLW forms. The objective of this analysis is to demonstrate that the DHLW disposal container/waste package satisfies the project requirements, as embodied in Defense High Level Waste Disposal Container System Description Document (SDD) (CRWMS M&O 1999a), and additional criteria, as identified in Waste Package Design Sensitivity Report (CRWMS M&Q 2000b, Table 4). The analysis briefly describes the analytical methods appropriate for the design of the DHLW disposal contained waste package, and summarizes the results of the calculations that illustrate the analytical methods. However, the analysis is limited to the calculations selected for the DHLW disposal container in support of the Site Recommendation (SR) (CRWMS M&O 2000b, Section 7). The scope of this analysis is restricted to the design of the codisposal waste package of the Savannah River Site (SRS) DHLW glass canisters and the Training, Research, Isotopes General Atomics (TRIGA) SNF loaded in a short 18-in.-outer diameter (OD) DOE standardized SNF canister. This waste package is representative of the waste packages that consist of the DHLW disposal container, the DHLW/HLW glass canisters, and the DOE-managed SNF in disposable canisters. The intended use of this analysis is to support Site Recommendation reports and to assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the Development Plan ''Design Analysis for the Defense High-Level Waste Disposal Container'' (CRWMS M&O 2000c) with no deviations from the plan.

G. Radulesscu; J.S. Tang

2000-06-07T23:59:59.000Z

304

On-line tests of organic additives for the inhibition of the precipitation of silica from hypersaline geothermal brine IV. Final tests of candidate additives  

DOE Green Energy (OSTI)

The Lawrence Livermore Laboratory Brine Treatment Test System at Niland, Imperial Valley, California, has been used to evaluate a number of cationic polymers and surfactants as scale control agents. An initial group of compounds was narrowed to four on the basis of their activity as silica precipitation inhibitors. Three of these and certain combinations of compounds were then given a 40-h test to determine their effectiveness in retarding scales formed at 220, 125, and 90/sup 0/C. The best single compound was Corcat P-18 (Cordova Chemical Co. polyethylene imine, M.W. approx. = 1800). It had no effect on the scale at 220/sup 0/C, but it reduced the scales at 125 and 90/sup 0/C by factors of 4 and 18, respectively, and it also has activity as a corrosion inhibitor. Other promising compounds are PAE HCl (Dynapol poly(aminoethylene, HCl salt)), which also somewhat reduces the 220/sup 0/C scale; Ethoquad 18/25 (Armak methyl polyoxyethylene(15) octadecylammonium chloride); and Mirapol A-15 (a Miranol Chemical polydiquaternary compound). The best additive formulation for the brines of the Salton Sea Geothermal Field appears to be a mixture of one of these silica precipitation inhibitors with a small amount of hydrochloric acid and a phosphonate crystalline deposit inhibitor. Speculations are presented as to the mechanism of inhibition of silica precipitation and recommendations for further testing of these additives.

Harrar, J.E.; Locke, F.E.; Otto, C.H. Jr.; Lorensen, L.E.; Frey, W.P.; Snell, E.O.

1980-02-01T23:59:59.000Z

305

Large Component Removal/Disposal  

Science Conference Proceedings (OSTI)

This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

Wheeler, D. M.

2002-02-27T23:59:59.000Z

306

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

307

Evaluation of Membrane Treatment Technology to Optimize and Reduce Hypersalinity Content of Produced Brine for Reuse in Unconventional Gas Wells  

E-Print Network (OSTI)

Over 18 billion barrels of waste fluids are generated annually from oil and gas production in the United States. As a large amount of water is used for oilfield operations, treating and reusing produced water can cut the consumption of fresh water in well sites. This research has helped to develop a membrane process train for a mobile produced water treatment unit for treating oilfield produced brine for reuse. To design the process train, over 30 sets of combination tests at pilot laboratory scale were performed using pretreatment, microfiltration and nanofiltration processes. Membrane performance was selected based on high flux separation efficiency, high tolerance for solids and fluid treatments. Over 95 % solids rejection and greater than 80 % oil removal efficiency were obtained in all these tests. Process train (pre-treatment and membrane) performance was monitored by chemical analysis of permeate and models fitting experimental data for the process. From the results, hydrocarbon rejection was analyzed; total organic carbon rejection was 47.9 %, total carbon content averaged 37.3 % rejection and total inorganic carbon rejection was at 3.66 %. BTEX removal efficiency ranged from 0.98 % to 52.7 % with the progressive pretreatment methods of using cartridge filters. The nanofiltration membrane showed significant reduction in total dissolved solids and in both anionic and cationic species. The process train is seen to follow a sequence of treatment from cartridge and oil removal filter treatment to microfiltration treatment to ultrafiltration, followed by nanofiltration for the purpose of this research. Further research still needs to be done on to determine the kind of analytical test which will give real time feedback on effectiveness of filters. In summary, the process train developed by TAMU-GPRI possesses distinct advantages in treating oilfield produced brine using membrane technology. These advantages include high quality of permeate, reduced sludge and the possibility of total recycle water systems. The small space requirement, moderate capital costs and ease of operation associated with the use of the mobile unit membrane technology also makes it a very competitive alternative to conventional technologies.

Eboagwu, Uche

2011-08-01T23:59:59.000Z

308

Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)  

SciTech Connect

New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

Cook, J

2005-05-26T23:59:59.000Z

309

Theory and practice of brine processing by industrial-scale magnetic ion polarization and optimization of personal-scale passive solar desalination.  

E-Print Network (OSTI)

??In the first section of this work we hope to add to the science of brine management in desalination. We have undertaken a feasibility analysis… (more)

Wofsey, Michael Henry

2010-01-01T23:59:59.000Z

310

Gas, Heat, Water, Sewerage Collection and Disposal, and Street...  

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

Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies...

311

DOE - Office of Legacy Management -- Estes Gulch Disposal Cell...  

Office of Legacy Management (LM)

Estes Gulch Disposal Cell - 010 FUSRAP Considered Sites Site: Estes Gulch Disposal Cell (010) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

312

DOE - Office of Legacy Management -- Burro Canyon Disposal Cell...  

Office of Legacy Management (LM)

Burro Canyon Disposal Cell - 007 FUSRAP Considered Sites Site: Burro Canyon Disposal Cell (007) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

313

Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...  

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

Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of Long-Term Performance Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of...

314

Idaho CERCLA Disposal Facility at Idaho National Laboratory ...  

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

Idaho CERCLA Disposal Facility at Idaho National Laboratory Idaho CERCLA Disposal Facility at Idaho National Laboratory Full Document and Summary Versions are available for...

315

Erosion Control and Revegetation at DOE's Lowman Disposal Site...  

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

Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and...

316

Biological Weed Control at the Sherwood, Washington, Disposal...  

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

Services Ecosystem Management Team Biological Weed Control at the Sherwood, Washington, Disposal Site Biological Weed Control at the Sherwood, Washington, Disposal Site...

317

Acquisition, Use, and Disposal of Real Estate | Department of...  

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

Use, and Disposal of Real Estate More Documents & Publications Acquisition, Use, and Disposal of Real Estate OPAM Policy Acquisition Guides Chapter 17 - Special Contracting Methods...

318

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive...  

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

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste...

319

EA-1097: Solid waste Disposal - Nevada Test Site, Nye County...  

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

7: Solid waste Disposal - Nevada Test Site, Nye County, Nevada EA-1097: Solid waste Disposal - Nevada Test Site, Nye County, Nevada SUMMARY This EA evaluates the environmental...

320

New Facility Will Test Disposal Cell Cover Renovation | Department...  

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

Services Ecosystem Management Team New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation Calibration Facilities...

Note: This page contains sample records for the topic "brine disposal system" 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

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...

322

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect

The current baseline plan for RH TRU (remote-handled transuranic) waste disposal is to package the waste in special canisters for emplacement in the walls of the waste disposal rooms at the Waste Isolation Pilot Plant (WIPP). The RH waste must be emplaced before the disposal rooms are filled by contact-handled waste. Issues which must be resolved for this plan to be successful include: (1) construction of RH waste preparation and packaging facilities at large-quantity sites; (2) finding methods to get small-quantity site RH waste packaged and certified for disposal; (3) developing transportation systems and characterization facilities for RH TRU waste; (4) meeting lag storage needs; and (5) gaining public acceptance for the RH TRU waste program. Failure to resolve these issues in time to permit disposal according to the WIPP baseline plan will force either modification to the plan, or disposal or long-term storage of RH TRU waste at non-WIPP sites. The recommended strategy is to recognize, and take the needed actions to resolve, the open issues preventing disposal of RH TRU waste at WIPP on schedule. It is also recommended that the baseline plan be upgraded by adopting enhancements such as revised canister emplacement strategies and a more flexible waste transport system.

Bild, R.W. [Sandia National Lab., Albuquerque, NM (United States). Program Integration Dept.

1994-07-01T23:59:59.000Z

323

Spent fuel characteristics & disposal considerations  

SciTech Connect

The fuel used in commercial nuclear power reactors is uranium, generally in the form of an oxide. The gas-cooled reactors developed in England use metallic uranium enclosed in a thin layer of Magnox. Since this fuel must be processed into a more stable form before disposal, we will not consider the characteristics of the Magnox spent fuel. The vast majority of the remaining power reactors in the world use uranium dioxide pellets in Zircaloy cladding as the fuel material. Reactors that are fueled with uranium dioxide generally use water as the moderator. If ordinary water is used, the reactors are called Light Water Reactors (LWR), while if water enriched in the deuterium isotope of hydrogen is used, the reactors are called Heavy Water reactors. The LWRs can be either pressurized reactors (PWR) or boiling water reactors (BWR). Both of these reactor types use uranium that has been enriched in the 235 isotope to about 3.5 to 4% total abundance. There may be minor differences in the details of the spent fuel characteristics for PWRs and BWRs, but for simplicity we will not consider these second-order effects. The Canadian designed reactor (CANDU) that is moderated by heavy water uses natural uranium without enrichment of the 235 isotope as the fuel. These reactors run at higher linear power density than LWRs and produce spent fuel with lower total burn-up than LWRs. Where these difference are important with respect to spent fuel management, we will discuss them. Otherwise, we will concentrate on spent fuel from LWRs.

Oversby, V.M.

1996-06-01T23:59:59.000Z

324

The Salt Defense Disposal Investigations (SDDI)  

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

Salt Defense Disposal Investigations (SDDI) Salt Defense Disposal Investigations (SDDI) will utilize a newly mined Underground Research Lab (URL) in WIPP to perform a cost effective, proof-of-principle field test of the emplacement of heat-generating radioactive waste and validate modeling efforts. The goals of the SDDI Thermal Test are to: * Demonstrate a proof-of-principle concept for in-drift disposal in salt. * Investigate, in a specific emplacement concept, the response of the salt to heat. * Develop a full-scale response for run-of- mine (ROM) salt. * Develop a validated coupled process model for disposal of heat-generating wastes in salt. * Evaluate the environmental conditions of the

325

Acquisition, Use, and Disposal of Real Estate  

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

Chapter 17.3 (March 2011) Chapter 17.3 (March 2011) 1 Acquisition, Use, and Disposal of Real Estate References DEAR 917.74 - Acquisition, Use, and Disposal of Real Estate DOE Directives DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets, or current version DOE Order 430.1B, Real Property Asset Management, or current version Overview This section provides internal Departmental information and DOE and NNSA points of contact for issues dealing with real estate acquisition, use, and disposal for cost reimbursement and fixed price contracts when in performance of the contract, the contractor will acquire or proposes to acquire use of real property. Background DEAR Subpart 917.74 - Acquisition, Use, and Disposal of Real Estate provides the policy and

326

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

2000-06-01T23:59:59.000Z

327

Waste disposal options report. Volume 2  

SciTech Connect

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

Russell, N.E.; McDonald, T.G.; Banaee, J.; Barnes, C.M.; Fish, L.W.; Losinski, S.J.; Peterson, H.K.; Sterbentz, J.W.; Wenzel, D.R.

1998-02-01T23:59:59.000Z

328

Method of Disposing of Corrosive Gases  

DOE Patents (OSTI)

Waste gas containing elemental fluorine is disposed of in the disclosed method by introducing the gas near the top of a vertical chamber under a downward spray of caustic soda solution which contains a small amount of sodium sulfide.

Burford, W.B. III; Anderson, H.C.

1950-07-11T23:59:59.000Z

329

Economic assessment of CO? capture and disposal  

E-Print Network (OSTI)

A multi-sector multi-region general equilibrium model of economic growth and emissions is used to explore the conditions that will determine the market penetration of CO2 capture and disposal technology.

Eckaus, Richard S.; Jacoby, Henry D.; Ellerman, A. Denny.; Leung, Wing-Chi.; Yang, Zili.

330

A disposable, self-administered electrolyte test  

E-Print Network (OSTI)

This thesis demonstrates the novel concept that it is possible to make a disposable, self-administered electrolyte test to be introduced to the general consumer market. Although ion specific electrodes have been used to ...

Prince, Ryan, 1977-

2003-01-01T23:59:59.000Z

331

UCSD Geothermal Chemical Modeling Project: DOE Advanced Brine Chemistry Program. [University of California at San Diego (UCSD)  

DOE Green Energy (OSTI)

DOE funding to the UCSD Chemical Modeling Group supports research to provide computer models which will reliably characterize the equilibrium chemistry of geothermal brines (solution, solid and gas phases) under variable thermodynamic conditions. With this technology, it will be possible to rapidly and inexpensively predict the chemical behavior of geothermal brines during various resource recovery stages; exploration, production, plant energy extraction and rejection as well as in ancillary programs such as mineral recovery. Our modeling technology is based on recent progress in the physical chemistry of concentrated aqueous solutions. The behavior of these fluids has not been predicted from first principle theories. However, because of the importance of concentrated brines to many industrial and natural processes, there have been numerous efforts to develop accurate phenomenological expressions for predicting the chemical behavior of these brines. One of the most successful of these efforts is that of Pitzer and coworkers. Incorporating the semiempirical equations of Pitzer, we have shown at UCSD that we can create highly accurate models of brine-solid-gas chemistry.

Moeller, N.; Weare, J.H.

1992-04-01T23:59:59.000Z

332

Development of direct heat exchangers for geothermal brines. Final report, October 4, 1977--June 30, 1978  

DOE Green Energy (OSTI)

A series of experiments during a period of eight months was conducted with the existing Direct Contact Heat Exchanger (DCHX) Loop in order to better understand the thermal and hydraulic characteristics of the equipment. Modifications were made to the equipment which were designed to improve heat transfer and reduce the cost of the heat exchangers. Additional changes were made to the equipment to conduct turbine experiments, condenser experiments, and carryover tests. Further studies of the amounts of dissolved isobutane in the geothermal brine and methods of recovering this dissolved isobutane were also made. The procedures used and the results of the tests performed are presented.

Urbanek, M.W.

1978-01-01T23:59:59.000Z

333

Electric power generation using geothermal brine resources for a proof-of-concept facility  

DOE Green Energy (OSTI)

A report is given of the initial phase of a proof-of-concept project to establish the technical, environmental, and economic feasibility of utilizing hot brine resources for electric energy production and other industrial applications. Included in the report are the following: summary, conclusions, and recommendations; site selection; Heber site description; development of design bases for an experimental facility and a 10 MWe(Net) generating unit; description of facilities; safety analysis; environmental considerations; implementation plan and schedule; and conceptual capital cost estimate.

Not Available

1976-01-01T23:59:59.000Z

334

Effect of shale-water recharge on brine and gas recovery from geopressured reservoirs  

DOE Green Energy (OSTI)

The concept of shale-water recharge has often been discussed and preliminary assessments of its significance in the recovery of geopressured fluids have been given previously. The present study uses the Pleasant Bayou Reservoir data as a base case and varies the shale formation properties to investigate their impact on brine and gas recovery. The parametric calculations, based on semi-analytic solutions and finite-difference techniques, show that for vertical shale permeabilities which are at least of the order of 10/sup -5/ md, shale recharge will constitute an important reservoir drive mechanism and will result in much larger fluid recovery than that possible in the absence of shale dewatering.

Riney, T.D.; Garg, S.K.; Wallace, R.H. Jr.

1985-01-01T23:59:59.000Z

335

Scenarios of the TWRS low-level waste disposal program. Revision 1  

Science Conference Proceedings (OSTI)

As a result of past Department of Energy (DOE) weapons material production operations, Hanford now stores nuclear waste from processing facilities in underground tanks on the 200 area plateau. An agreement between the DOE, the Environmental Protection Agency (EPA), and the Washington state Department of Ecology (the Tri-Party Agreement, or TPA) establishes an enforceable schedule and a technical framework for recovering, processing, solidifying, and disposing of the Hanford tank wastes. The present plan includes retrieving the tank waste, pre-treating the waste to separate into low level and high level streams, and converting both streams to a glass waste form. The low level glass will represent by far the largest volume and lowest quantity of radioactivity (i.e., large volume of waste chemicals) of waste requiring disposal. The low level glass waste will be retrievably stored in sub-surface disposal vaults for several decades. If the low level disposal system proves to be acceptable, the disposal site will be closed with the low level waste in place. If, however, at some time the disposal system is found to be unacceptable, then the waste can be retrieved and dealt with in some other manner. WHC is planning to emplace the waste so that it is retrievable for up to 50 years after completion of the tank waste processing. Acceptability of disposal of the TWRS low level waste at Hanford depends on technical, cultural, and political considerations. The Performance Assessment is a major part of determining whether the proposed disposal action is technically defensible. A Performance Assessment estimates the possible future impact to humans and the environment for thousands of years into the future. In accordance with the TPA technical strategy, WHC plans to design a near-surface facility suitable for disposal of the glass waste.

NONE

1995-01-01T23:59:59.000Z

336

Optimal evaluation of infectious medical waste disposal companies using the fuzzy analytic hierarchy process  

SciTech Connect

Ever since Taiwan's National Health Insurance implemented the diagnosis-related groups payment system in January 2010, hospital income has declined. Therefore, to meet their medical waste disposal needs, hospitals seek suppliers that provide high-quality services at a low cost. The enactment of the Waste Disposal Act in 1974 had facilitated some improvement in the management of waste disposal. However, since the implementation of the National Health Insurance program, the amount of medical waste from disposable medical products has been increasing. Further, of all the hazardous waste types, the amount of infectious medical waste has increased at the fastest rate. This is because of the increase in the number of items considered as infectious waste by the Environmental Protection Administration. The present study used two important findings from previous studies to determine the critical evaluation criteria for selecting infectious medical waste disposal firms. It employed the fuzzy analytic hierarchy process to set the objective weights of the evaluation criteria and select the optimal infectious medical waste disposal firm through calculation and sorting. The aim was to propose a method of evaluation with which medical and health care institutions could objectively and systematically choose appropriate infectious medical waste disposal firms.

Ho, Chao Chung, E-mail: ho919@pchome.com.tw [Department of Industrial Management, National Taiwan University of Science and Technology, Taipei, Taiwan (China)

2011-07-15T23:59:59.000Z

337

Capacity Investigation of Brine-Bearing Sands of the Frio Formation for Geologic Sequestration of CO2  

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

Capacity Investigation of Brine-Bearing Sands of the Frio Capacity Investigation of Brine-Bearing Sands of the Frio Formation for Geologic Sequestration of CO 2 Christine Doughty (cadoughty@lbl.gov; 510-486-6453) Karsten Pruess (k_pruess@lbl.gov; 510-486-6732) Sally M. Benson (smbenson@lbl.gov; 510-486-5875) Lawrence Berkeley National Laboratory 1 Cyclotron Rd, MS 90-1116 Berkeley, CA 94720 Susan D. Hovorka (susan.hovorka@beg.utexas.edu; 512-471-4863) Paul R. Knox (paul.knox@beg.utexas.edu; 512-471-7313) Bureau of Economic Geology P.O. Box X, The University of Texas Austin, TX 78713 Christopher T. Green (ctgreen@ucdavis.edu; 530-752-1372) University of California, Hydrologic Sciences 1 Shields Ave. Davis, CA 95616 Abstract The capacity of fluvial brine-bearing formations to sequester CO 2 is investigated using numerical simulations of CO

338

Brine migration test report: Asse Salt Mine, Federal Republic of Germany: Technical report  

Science Conference Proceedings (OSTI)

This report presents a summary of Brine Migration Tests which were undertaken at the Asse mine of the Federal Republic of Germany (FRG) under a bilateral US/FRG agreement. This experiment simulates a nuclear waste repository at the 800-m (2624-ft) level of the Asse salt mine in the Federal Republic of Germany. This report describes the Asse salt mine, the test equipment, and the pretest properties of the salt in the mine and in the vicinity of the test area. Also included are selected test data (for the first 28 months of operation) on the following: brine migration rates, thermomechaical behavior of the salt (including room closure, stress reading, and thermal profiles), borehole gas pressures, and borehole gas analyses. In addition to field data, laboratory analyses of pretest salt properties are included in this report. The operational phase of these experiments was completed on October 4, 1985, with the commencement of cooldown and the start of posttest activities. 7 refs., 68 figs., 48 tabs.

Coyle, A.J.; Eckert, J.; Kalia, H.

1987-01-01T23:59:59.000Z

339

Subsurface Ice and Brine Sampling Using an Ultrasonic/Sonic Gopher for Life Detection and Characterization  

E-Print Network (OSTI)

There is growing evidence for ice and fluids near the surface of Mars with potential discharge of brines, which may preserve a record of past life on the planet. Proven techniques to sample Mars subsurface will be critical for future NASA astrobiology missions that will search for such records. The required technology studies are underway in the McMurdo Dry valleys, Antarctica, which is serving as a Mars analog. The ice layer on Lake Vida in the dry valleys is estimated to be 20-meter thick where below 16-m depth there is a mix of ice and brine, which has never been sampled directly due to logistical constraints. A novel light weight, low power ultrasonic/sonic driller/corer (USDC) mechanism was developed that overcomes the need for high axial loads required by drilling via conventional techniques. The USDC was modified to produce an Ultrasonic/Sonic Gopher that is being developed to core down to the 20-m depth for in situ analysis and sample collection. Coring ice at-20 o C as in Lake Vida suggests that it is a greater challenge and current efforts are focused on the problems of ice core cutting, ice chip handling and potential ice melt (and refreezing) during drilling. An analytical model and a prototype are being developed with an effort to

Y. Bar-cohen; S. Sherrit; Z. Chang; L. Wessel; X. Bao; P. T. Doran; C. H. Fritsen; F. Kenig; C. P. Mckay; A. Murray; T. Peterson

2004-01-01T23:59:59.000Z

340

Clean Cities: National Clean Fleets Partner: Advanced Disposal Services  

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

Advanced Advanced Disposal Services to someone by E-mail Share Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Facebook Tweet about Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Twitter Bookmark Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Google Bookmark Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Delicious Rank Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on Digg Find More places to share Clean Cities: National Clean Fleets Partner: Advanced Disposal Services on AddThis.com... Goals & Accomplishments Partnerships National Clean Fleets Partnership National Parks Initiative Electric Vehicle Infrastructure Training Program Advanced Vehicle Technology Competitions

Note: This page contains sample records for the topic "brine disposal system" 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

New constraints on methane fluxes and rates of anaerobic methane oxidation in a Gulf of Mexico brine pool via in situ mass spectrometry  

E-Print Network (OSTI)

New constraints on methane fluxes and rates of anaerobic methane oxidation in a Gulf of Mexico Keywords: Methane flux Mass spectrometer Brine pool Methane oxidation Gulf of Mexico a b s t r a c t Deep report direct measurements of methane concentrations made in a Gulf of Mexico brine pool located

Girguis, Peter R.

342

THE DISPOSAL OF POWER REACTOR WASTE INTO DEEP WELLS  

SciTech Connect

Disposal of wastes from the processing of solid fuel elements and from solid blanket elements is discussed. The subjects considered include extraction of uranium by several methods, the removal of element jackets, the treatment of uraxium -zirconium fuel elements, disposal into deep wells, the hydraulics of wells, thermal considerations of disposal aquifers regional hydrology, potential deep-well disposal areas in the U. S., aud the cost of disposal. (J.R.D.)

de Laguna, W.; Blomeke, J.O.

1957-06-13T23:59:59.000Z

343

Proceedings of the 1981 subseabed disposal program. Annual workshop  

Science Conference Proceedings (OSTI)

The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal.

Not Available

1982-01-01T23:59:59.000Z

344

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY  

SciTech Connect

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

345

Geothermal-brine modeling - prediction of mineral solubilities in natural waters: the Na-K-Mg-Ca-H-Cl-SO{sub 4}-OH-HCO{sub 3} CO{sub 3}-CO{sub 2}-H{sub 2}O system to high ionic strengths at 25{sup 0}C  

DOE Green Energy (OSTI)

The mineral solubility model of Harvie and Weare (1980) is extended to the eight component system, Na-K-Ca-Mg-H-Cl-SO{sub 4}-OH-HCO{sub 3}-CO{sub 3}-CO{sub 2}-H{sub 2}O at 25{sup 0}C to high concentrations. The model is based on the semi-empirical equations of Pitzer (1973) and co-workers for the thermodynamics of aqueous electrolyte solutions. The model is parameterized using many of the available isopiestic, electromotive force, and solubility data available for many of the subsystems. The predictive abilities of the model are demonstrated by comparison to experimental data in systems more complex than those used in parameterization. The essential features of a chemical model for aqueous electrolyte solutions and the relationship between pH and the equilibrium properties of a solution are discussed.

Weare, J.H.

1981-01-01T23:59:59.000Z

346

Microsoft Word - SRSSaltWasteDisposal.doc  

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

Salt Waste Disposal - References - §3116 Determination (RWR NDAA of 2005) Salt Waste Disposal - References - §3116 Determination (RWR NDAA of 2005) Doc. No. Filename Title Main Document References 1. 2005 RWR DAA §3116 NDAA.pdf "Ronald W. Regan National Defense Authorization Act for FY 2005," Section 3116, 2004. 2. CBU-PIT-2004-00024 CBU-PIT-2004-00024.pdf Ledbetter, L. S., CBU-PIT-2004-00024, 12/01/04 - December Monthly WCS Curie and Volume Inventory Report," Revision 0, December 9, 2004. 3. CBU-PIT-2005-00031 CBU-PIT-2005-00031.pdf Rios-Armstrong, M. A., CBU-PIT-2005-00031, "Decontaminated Salt Solution Volume to be transferred to the Saltstone Disposal Facility from Salt Treatment and Disposition Activities," Revision 0, February 13, 2005.

347

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect

We have developed a phased strategy that defines specific program-management activities and critical documentation for producing radioactive waste forms, from pyrochemical processing of spent nuclear fuel, that will be acceptable for geologic disposal by the US Department of Energy. The documentation of these waste forms begins with the decision to develop the pyroprocessing technology for spent fuel conditioning and ends with production of the last waste form for disposal. The need for this strategy is underscored by the fact that existing written guidance for establishing the acceptability for disposal of radioactive waste is largely limited to borosilicate glass forms generated from the treatment of aqueous reprocessing wastes. The existing guidance documents do not provide specific requirements and criteria for nonstandard waste forms such as those generated from pyrochemical processing operations.

Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Laidler, J.J.; McPheeters, C.C. [Argonne National Lab., IL (United States)

1994-09-01T23:59:59.000Z

348

Environmental restoration waste materials co-disposal  

Science Conference Proceedings (OSTI)

Co-disposal of radioactive and hazardous waste is a highly efficient and cost-saving technology. The technology used for final treatment of soil-washing size fractionization operations is being demonstrated on simulated waste. Treated material (wasterock) is used to stabilize and isolate retired underground waste disposal structures or is used to construct landfills or equivalent surface or subsurface structures. Prototype equipment is under development as well as undergoing standardized testing protocols to prequalify treated waste materials. Polymer and hydraulic cement solidification agents are currently used for geotechnical demonstration activities.

Phillips, S.J.; Alexander, R.G.; England, J.L.; Kirdendall, J.R.; Raney, E.A.; Stewart, W.E. [Westinghouse Hanford Co., Richland, WA (United States); Dagan, E.B.; Holt, R.G. [Dept. of Energy, Richland, WA (United States). Richland Operations Office

1993-09-01T23:59:59.000Z

349

Generic Deep Geologic Disposal Safety Case | Department of Energy  

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

Deep Geologic Disposal Safety Case Deep Geologic Disposal Safety Case Generic Deep Geologic Disposal Safety Case The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW). Potential disposal options include mined disposal in a variety of geologic media (e.g., salt, shale, granite), and deep borehole disposal in basement rock. The Generic Safety Case is intended to be a source of information to provide answers to questions that may arise as the U.S. works to develop strategies to dispose of current and future inventories of UNF and HLW. DOE is examining combinations of generic geologic media and facility designs that could potentially support

350

Introduction to electric energy conversion systems for geothermal energy resources  

SciTech Connect

The types of geothermal energy conversion systems in use are classified as follows: direct, dry steam; separated steam; single-flash steam; double-flash steam; multi-flash steam; brine/Freon binary cycle; and brine/isobutane binary cycle. The thermodynamics of each of these is discussed with reference to simplified flow diagrams. Typical existing power plants are identified for each type of system. (MHR)

DiPippo, R.

1978-06-01T23:59:59.000Z

351

Civilian Radioactive Waste Management System Requirements Document...  

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

Management System Requirements Document More Documents & Publications Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 FY 2007 Total...

352

Freeze resistant buoy system  

DOE Patents (OSTI)

A freeze resistant buoy system includes a tail-tube buoy having a thermally insulated section disposed predominantly above a waterline, and a thermo-siphon disposed predominantly below the waterline.

Hill, David E. (Knoxville, TN); Rodriguez, Jr., Miguel (Oak Ridge, TN); Greenbaum, Elias (Knoxville, TN); Klett, James W. (Knoxville, TN)

2007-08-21T23:59:59.000Z

353

Reducing Foreign Lithium Dependence through Co-Production of Lithium from Geothermal Brine  

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

Foreign Lithium Dependence through Co-Production of Lithium from Foreign Lithium Dependence through Co-Production of Lithium from Geothermal Brine Kerry Klein 1 , Linda Gaines 2 1 New West Technologies LLC, Washington, DC, USA 2 Center for Transportation Research, Argonne National Laboratory, Argonne, IL, USA KEYWORDS Mineral extraction, zinc, silica, strategic metals, Imperial Valley, lithium ion batteries, electric- drive vehicles, battery recycling ABSTRACT Following a 2009 investment of $32.9 billion in renewable energy and energy efficiency research through the American Recovery and Reinvestment Act, President Obama in his January 2011 State of the Union address promised deployment of one million electric vehicles by 2015 and 80% clean energy by 2035. The United States seems poised to usher in its bright energy future,

354

A Methodology for Measuring the Rate of Reaction of CO2 with Brine-Rock Mixtures  

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

Methodology for Measuring the Rate of Reaction of CO Methodology for Measuring the Rate of Reaction of CO 2 with Brine-Rock Mixtures Nicholas B. Janda (nbj2@po.cwru.edu; 216-368-2648) Philip W. Morrison, Jr. (pwm5@po.cwru.edu; 216-368-4238) Department of Chemical Engineering Case Western Reserve University 10900 Euclid Avenue Cleveland, OH 44106-7217 Beverly Z. Saylor (bzs@po.cwru.edu; 216-368-3763) Gerald Matisoff (gxm4@po.cwru.edu; 216-368-3677) Department of Geological Sciences Case Western Reserve University 10900 Euclid Avenue Cleveland, OH 44106-7216 Introduction Storage of carbon dioxide in deep, porous, and permeable reservoir rocks is one of the most promising technologies for reducing emissions of greenhouse gases to the atmosphere. Although oil and gas reservoirs are a sensible first step for sequestration of carbon dioxide in geologic

355

Status of UFD Campaign International Activities in Disposal Research |  

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

Status of UFD Campaign International Activities in Disposal Status of UFD Campaign International Activities in Disposal Research Status of UFD Campaign International Activities in Disposal Research Several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics (clay/shale, granite), most of which were very different from those studied in the United States. The DOE recognizes that close international collaboration is a beneficial and cost effective strategy for advancing disposal science. This report describes the active collaboration opportunities available to U.S. researchers, and presents specific cooperative research activities that have been recently initiated within DOE's disposal research program.

356

Process for the disposal of alkali metals  

SciTech Connect

Large quantities of alkali metals may be safely reacted for ultimate disposal by contact with a hot concentrated caustic solution. The alkali metals react with water in the caustic solution in a controlled reaction while steam dilutes the hydrogen formed by the reaction to a safe level.

Lewis, Leroy C. (Arco, ID)

1977-01-01T23:59:59.000Z

357

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS  

SciTech Connect

The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

THIELGES, J.R.; CHASTAIN, S.A.

2007-06-21T23:59:59.000Z

358

A disposable capillary electrophoresis microchip with an indium tin oxide decoupler/amperometric detector  

Science Conference Proceedings (OSTI)

We have fabricated a capillary electrophoresis (CE) chip-based electrochemical detection (ECD) system for measurements of the dopamine, catechol, DNA ladder, and hydrogen peroxide, respectively. The microfabricated CE-ECD systems are adequate for a disposable ... Keywords: Capillary electrophoresis, Electrochemical detection, ITO, Microchip, PDMS

Ju-Ho Kim; C. J. Kang; D. Jeon; Yong-Sang Kim

2005-03-01T23:59:59.000Z

359

Low-Level Waste Disposal Facility Federal Review Group Manual  

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

This Revision 3 of the Low-Level Waste Disposal  Facility Federal Review Group (LFRG) Manual was prepared primarily to include review criteria for the review of transuranic (TRU) waste disposal...

360

Strategy for the Management and Disposal of Used Nuclear Fuel...  

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

Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level...

Note: This page contains sample records for the topic "brine disposal system" 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

Laboratory to demolish excavation enclosures at Material Disposal...  

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

waste disposal facility. MDA B was used from 1944 to 1948 as a waste disposal site for Manhattan Project and Cold War-era research and production. The Laboratory received 212...

362

UCSC Glassware and Sharps Disposal Matrix Responsibility Color key  

E-Print Network (OSTI)

(Solid Debris) EH&S Lab Safety Services Dispose of Sharps Safely! Includes syringes (with or without debris may be combined. Dispose by completing a Radioactive Waste Tracking Form and affix to the box

California at Santa Cruz, University of

363

Disposal Practices at the Nevada Test Site 2008 | Department...  

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

Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download Disposal Practices at the Nevada Test Site 2008...

364

Disposable Point-of-Care Testing Device for Nucleic Acid ...  

home \\ technologies \\ disposable point of care testing device. Technologies: Ready-to-Sign Licenses: ... Operated by Lawrence Livermore National Security, ...

365

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

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

Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal  Facility Performance Assessments and Composite Analyses

366

Idaho CERCLA Disposal Facility at Idaho National Laboratory ...  

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

Facility at Idaho National Laboratory Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory More Documents & Publications Environmental Management...

367

Integrated Used Nuclear Fuel Storage, Transportation, and Disposal ...  

dry cask storage of used nuclear fuel at existing plant ... achievement of geologic disposal thermal management ... Senior Technology Commercialization Manager ...

368

Materials for Nuclear Waste Disposal and Environmental Cleanup  

Science Conference Proceedings (OSTI)

Symposium, Materials for Nuclear Waste Disposal and Environmental Cleanup ... Secure and Certify Studies to Work on Production of Spiked Plutonium.

369

Acceptance of Classified Excess Components for Disposal at Area 5  

Science Conference Proceedings (OSTI)

This slide-show discusses weapons dismantlement and disposal, issues related to classified waste and their solutions.

Poling, J., and Saad, M.

2012-04-09T23:59:59.000Z

370

CONTAINMENT OF LOW-LEVEL RADIOACTIVE WASTE AT THE DOE SALTSTONE DISPOSAL FACILITY  

SciTech Connect

As facilities look for permanent storage of toxic materials, they are forced to address the long-term impacts to the environment as well as any individuals living in affected area. As these materials are stored underground, modeling of the contaminant transport through the ground is an essential part of the evaluation. The contaminant transport model must address the long-term degradation of the containment system as well as any movement of the contaminant through the soil and into the groundwater. In order for disposal facilities to meet their performance objectives, engineered and natural barriers are relied upon. Engineered barriers include things like the design of the disposal unit, while natural barriers include things like the depth of soil between the disposal unit and the water table. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) in South Carolina is an example of a waste disposal unit that must be evaluated over a timeframe of thousands of years. The engineered and natural barriers for the SDF allow it to meet its performance objective over the long time frame. Some waste disposal facilities are required to meet certain standards to ensure public safety. These type of facilities require an engineered containment system to ensure that these requirements are met. The Saltstone Disposal Facility (SDF) at the Savannah River Site (SRS) is an example of this type of facility. The facility is evaluated based on a groundwater pathway analysis which considers long-term changes to material properties due to physical and chemical degradation processes. The facility is able to meet these performance objectives due to the multiple engineered and natural barriers to contaminant migration.

Jordan, J.; Flach, G.

2012-03-29T23:59:59.000Z

371

Design requirements document for project W-520, immobilized low-activity waste disposal  

SciTech Connect

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Ashworth, S.C.

1998-08-06T23:59:59.000Z

372

Microsoft Word - Appendix C_DisposalCellContents.doc  

Office of Legacy Management (LM)

is 1 to 0.43. 213.28 Sling bags 48 bags. 48.00 SWTP brine as grout pumped placed in the cell 3,697.5 cy. Conversion is 1 to 1. 3,698.00 General hot spots on Chemical Plant site...

373

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal  

Science Conference Proceedings (OSTI)

As a result of the termination of the Yucca Mountain Project, the United States Department of Energy (DOE) has started to explore various alternative avenues for the disposition of used nuclear fuel and nuclear waste. The overall scope of the investigation includes temporary storage, transportation issues, permanent disposal, various nuclear fuel types, processing alternatives, and resulting waste streams. Although geologic disposal is not the only alternative, it is still the leading candidate for permanent disposal. The realm of geologic disposal also offers a range of geologic environments that may be considered, among those clay shale formations. Figure 1-1 presents the distribution of clay/shale formations within the USA. Clay rock/shale has been considered as potential host rock for geological disposal of high-level nuclear waste throughout the world, because of its low permeability, low diffusion coefficient, high retention capacity for radionuclides, and capability to self-seal fractures induced by tunnel excavation. For example, Callovo-Oxfordian argillites at the Bure site, France (Fouche et al., 2004), Toarcian argillites at the Tournemire site, France (Patriarche et al., 2004), Opalinus clay at the Mont Terri site, Switzerland (Meier et al., 2000), and Boom clay at Mol site, Belgium (Barnichon et al., 2005) have all been under intensive scientific investigations (at both field and laboratory scales) for understanding a variety of rock properties and their relations with flow and transport processes associated with geological disposal of nuclear waste. Clay/shale formations may be generally classified as indurated and plastic clays (Tsang et al., 2005). The latter (including Boom clay) is a softer material without high cohesion; its deformation is dominantly plastic. For both clay rocks, coupled thermal, hydrological, mechanical and chemical (THMC) processes are expected to have a significant impact on the long-term safety of a clay repository. For example, the excavation-damaged zone (EDZ) near repository tunnels can modify local permeability (resulting from induced fractures), potentially leading to less confinement capability (Tsang et al., 2005). Because of clay's swelling and shrinkage behavior (depending on whether the clay is in imbibition or drainage processes), fracture properties in the EDZ are quite dynamic and evolve over time as hydromechanical conditions change. To understand and model the coupled processes and their impact on repository performance is critical for the defensible performance assessment of a clay repository. Within the Natural Barrier System (NBS) group of the Used Fuel Disposition (UFD) Campaign at DOE's Office of Nuclear Energy, LBNL's research activities have focused on understanding and modeling such coupled processes. LBNL provided a report in this April on literature survey of studies on coupled processes in clay repositories and identification of technical issues and knowledge gaps (Tsang et al., 2010). This report will document other LBNL research activities within the natural system work package, including the development of constitutive relationships for elastic deformation of clay rock (Section 2), a THM modeling study (Section 3) and a THC modeling study (Section 4). The purpose of the THM and THC modeling studies is to demonstrate the current modeling capabilities in dealing with coupled processes in a potential clay repository. In Section 5, we discuss potential future R&D work based on the identified knowledge gaps. The linkage between these activities and related FEPs is presented in Section 6.

Liu, Hui-Hai; Rutqvist, Jonny; Zheng, Liange; Sonnenthal, Eric; Houseworth, Jim; Birkholzer, Jens

2010-08-31T23:59:59.000Z

374

Environmental Assessment Photovoltaic Solar Project at the Durango, Colorado, Disposal Site  

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

U.S. Department of Energy Office of Legacy Management U.S. Department of Energy Office of Legacy Management DOE/EA 1770 FINDING OF NO SIGNIFICANT IMPACT Photovoltaic Solar Project at the Durango, Colorado, Disposal Site, La Plata County AGENCY: U.S. Department of Energy (DOE), Office of Legacy Management (LM) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: LM prepared an Environmental Assessment (EA) (DOE/EA-1770) that evaluated two action alternatives related to the installation, operation, and removal of a photovoltaic (PV) solar energy system on the Durango, Colorado, Disposal Site and the No Action Alternative. Alternative 1 evaluated the use of the 18-acre (ac) vegetated surface of the disposal cell for the installation of a PV system. The second action alternative (Alternative 2, the Preferred Action) considered the use of the surface of the

375

LEGACY NONCONFORMANCE ISSUE IN SOLID WASTE DISPOSAL  

Science Conference Proceedings (OSTI)

Beginning in 1968 waste from sectioning, sampling, and assaying of reactor fuels was sent to underground burial caissons in the 200-W Area of the Hanford Plant in Richland, Washington. In 2002 a review of inventory records revealed that criticality safety storage limits had been exceeded. This prompted declaration of a Criticality Prevention Specification nonconformance. The corrective action illustrates the difficulties in demonstrating compliance to fissile material limits decades after waste disposal.

ROGERS, C.A.

2002-12-16T23:59:59.000Z

376

The Determinants of Hazardous Waste Disposal Choice:  

E-Print Network (OSTI)

In this paper, we estimate conditional logit models of generator’s choice of waste management facilities (TSDFs) for shipments of halogenated solvent waste documented by the manifests filled out in California in 1995. We find that the probability that a facility is selected as the destination of an off-site shipment of halogenated solvent waste depends on the cost of shipping and disposal at that facility, on measures of existing contamination at the site, and on the track record of the receiving facility. Generators do seem to balance current disposal costs with the likelihood of future liability, should the TSDF become involved in either the state or federal Superfund program. In general, we find no evidence that generators prefer “wealthier ” TSDFs or “larger ” facilities, suggesting that there is a role for smaller, private companies in the management of halogenated solvent waste. When attention is limited to so-called “restricted ” wastes containing halogenated compounds, which cannot be landfilled, the best match between the waste and the treatment offered by the facility may be more important than saving on the cost of disposal, and price may even be interpreted as a signal for quality of the facility. 3

Anna Alberini; John Bartholomew; Anna Alberini; John Bartholomew

1998-01-01T23:59:59.000Z

377

Radioactive waste isolation in salt: geochemistry of brine in rock salt in temperature gradients and gamma-radiation fields - a selective annotated bibliography  

SciTech Connect

Evaluation of the extensive research concerning brine geochemistry and transport is critically important to successful exploitation of a salt formation for isolating high-level radioactive waste. This annotated bibliography has been compiled from documents considered to provide classic background material on the interactions between brine and rock salt, as well as the most important results from more recent research. Each summary elucidates the information or data most pertinent to situations encountered in siting, constructing, and operating a mined repository in salt for high-level radioactive waste. The research topics covered include the basic geology, depositional environment, mineralogy, and structure of evaporite and domal salts, as well as fluid inclusions, brine chemistry, thermal and gamma-radiation effects, radionuclide migration, and thermodynamic properties of salts and brines. 4 figs., 6 tabs.

Hull, A.B.; Williams, L.B.

1985-07-01T23:59:59.000Z

378

Evaluation of Brine-Bearing Sands of the Frio Formation, Upper Texas Gulf Coast for Geological Sequestration of CO2  

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

Evaluation of Brine-Bearing Sands of the Evaluation of Brine-Bearing Sands of the Frio Formation, Upper Texas Gulf Coast for Geological Sequestration of CO 2 S. D. Hovorka (susan.hovorka@beg.utexas.edu; 512-471-4863) Bureau of Economic Geology, P.O. Box X, The University of Texas at Austin, Austin, TX 78713 C. Doughty (CADoughty@lbl.gov; 510-486-6453 ) Lawrence Berkeley National Lab, 1 Cyclotron Road Mailstop 90-1116, Berkeley, CA 94720 P. R. Knox (paul.knox@beg.utexas.edu; 512-471-7313), Bureau of Economic Geology, P.O. Box X, The University of Texas at Austin, Austin, TX 78713 C. T. Green (ctgreen@ucdavis.edu; 510-495-2461) University of California, Hydrologic Sciences, One Shields Ave., Davis, CA 95616 K. Pruess(K_Pruess@lbl.gov; 510-486-6732) Lawrence Berkeley National Lab, 1 Cyclotron Road Mailstop 90-1116,

379

Experimental and Computational Studies of Fluid Flow Phenomena in Carbon Dioxide Sequestration in Brine and Oil Fields  

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

EXPERIMENTAL AND COMPUTATIONAL STUDIES OF FLUID EXPERIMENTAL AND COMPUTATIONAL STUDIES OF FLUID FLOW PHENOMENA IN CARBON DIOXIDE SEQUESTRATION IN BRINE AND OIL FIELDS Chuang Ji ( chuang.ji@netl.doe.gov ) National Energy Technology Laboratory Department of Energy, Morgantown, WV 26507-0880 BOX 5725 Clarkson University Potsdam, NY 13699 Goodarz Ahmadi ( ahmadi@clarkson.edu ) BOX 5725 Clarkson University Potsdam, NY 13699 Duane H. Smith ( duane.smith@netl.doe.gov ) National Energy Technology Laboratory Department of Energy, Morgantown, WV 26507-0880 2 INTRODUCTION Sequestration of CO 2 by injection into deep geological formations is a method to reduce CO 2 emissions into the atmosphere. However, when CO 2 is injected underground, it forms fingers extending into the rock pores saturated with brine or petroleum. This flow

380

Hydrocarbons associated with brines from geopressured wells. Fourth quarterly technical progress report, 1 October 1990--30 December 1990  

DOE Green Energy (OSTI)

The purpose of this research is to determine the concentration of the cryocondensates in fluids of the various USDOE Geopressured wells as a function of production volume, to correlate the production of these compounds with reservoir and well production characteristics, to precisely measure solubilities of cryocondensates components in water and sodium chloride solutions (brines) as a function of ionic strength and temperature and the component`s distribution coefficients between these solutions and oil, to develop models of the reservoir which are consistent with the data obtained, to monitor the wells for the production of aliphatic oils and relate any such production with the data obtained, and to develop a harsh environment pH probe for use in well brines. Results are summarized.

Not Available

1991-01-15T23:59:59.000Z

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381

MANAGING UNCERTAINTIES ASSOCIATED WITH RADIOACTIVE WASTE DISPOSAL: TASK GROUP 4 OF THE IAEA PRISM PROJECT  

Science Conference Proceedings (OSTI)

It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

Seitz, R.

2011-03-02T23:59:59.000Z

382

Understanding Long-Term Solute Transport in Sedimentary Basins: Simulating Brine Migration in the Alberta Basin. Final Report  

Science Conference Proceedings (OSTI)

Mass transport in deep sedimentary basins places important controls on ore formation, petroleum migration, CO2 sequestration, and geochemical reactions that affect petroleum reservoir quality, but large-scale transport in this type of setting remains poorly understood. This lack of knowledge is highlighted in the resource-rich Alberta Basin, where geochemical and hydrogeologic studies have suggested residence times ranging from hundreds of millions of years to less than 5 My, respectively. Here we developed new hydrogeologic models that were constrained by geochemical observations to reconcile these two very different estimates. The models account for variable-density fluid flow, heat transport, solute transport, sediment deposition and erosion, sediment compressibility, and dissolution of salt deposits, including Cl/Br systematics. Prior interpretations of Cl/Br ratios in the Alberta Basin concluded that the brines were derived from evaporatively-concentrated brines that were subsequently diluted by seawater and freshwater; models presented here show that halite dissolution must have contributed strongly as well, which implies significantly greater rates of mass transport. This result confirms that Cl/Br ratios are subject to significant non-uniqueness and thus do not provide good independent indicators of the origin of brines. Salinity and Cl/Br ratios provided valuable new constraints for basin-scale models, however. Sensitivity studies revealed that permeabilities obtained from core- and field-scale tests were appropriate for basin-scale models, despite the differences in scale between the tests and the models. Simulations of groundwater age show that the residence time of porefluids in much of the basin is less than 100 My. Groundwater age increases with depth and approaches 200 My in the deepest part of the basin, but brines are significantly younger than their host rocks throughout the basin.

Alicia M. Wilson

2009-11-30T23:59:59.000Z

383

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site May 15, 2013 - 12:00pm Addthis A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. Macro-packs from the Idaho site are shown here safely and compliantly disposed. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. IDAHO FALLS, Idaho - An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for

384

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

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

DOE Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility June 6, 2013 - 12:00pm Addthis The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. ANDREWS, Texas - DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind. EM Senior Advisor Dave Huizenga and several other federal, state and local officials attended the event at Waste Control Specialists (WCS) in Andrews and witnessed the first container being placed in the new state-of-the-art facility. WCS is a waste processing and disposal company. "I am proud to be here today to celebrate this historic event. We

385

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site May 15, 2013 - 12:00pm Addthis A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. Macro-packs from the Idaho site are shown here safely and compliantly disposed. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. IDAHO FALLS, Idaho - An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for

386

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

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

Applauds Opening of Historic Disposal Facility Applauds Opening of Historic Disposal Facility DOE Applauds Opening of Historic Disposal Facility June 6, 2013 - 12:00pm Addthis The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. The Waste Control Specialists Federal Waste Disposal Facility in Andrews, Texas. ANDREWS, Texas - DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind. EM Senior Advisor Dave Huizenga and several other federal, state and local officials attended the event at Waste Control Specialists (WCS) in Andrews and witnessed the first container being placed in the new state-of-the-art facility. WCS is a waste processing and disposal company. "I am proud to be here today to celebrate this historic event. We

387

Study and testing of direct contact heat exchangers for geothermal brines. Phase II, August 1976--June 1977  

DOE Green Energy (OSTI)

The analytical and experimental studies completed under this project have explored several aspects of geothermal binary power cycles and column type direct contact heat exchangers between geothermal brine and isobutane. A major improvement of the heat exchanger was developed by the combination of the preheater and boiler into a single continuous column. At East Mesa, this new direct contact heat exchanger was tested on geothermal brine in order to correlate the experimental heat transfer data with the theoretical model for use in designing larger plants. Experiments also involved a small radial inflow turbine to produce electricity which marked the first generation of electricity from geothermal brine using a binary cycle. In analytical studies, a comparison of the relationship between column diameter and droplet size was made for both Minard--Johnson and Sakiadis--Johnson model. The Letan--Kehat model for relating column height and temperature profile was analyzed and compared with experimental data. It appears that the experimental results are in good agreement with the theoretical models. A detailed design of a 250 Kw pilot plant incorporating the direct contact heat exchanger was completed. This design with estimated costs for it and a 500 Kw pilot plant is incorporated.

Suratt, W.B.; Lee, C.O.

1978-11-01T23:59:59.000Z

388

Estimation Of Retained Crude Oil Associated With Crushed Salt And Salt Cores In The Presence Of Near-Saturated Brine  

E-Print Network (OSTI)

This paper describes three experiments whose purpose is to determine the amount of retained oil on massive salt surfaces and in crushed salt in the presence of water and brine. These experiments have application to the decommissioning process for the Weeks Island mine. In the first experiment, oil-coated salt cores were immersed in either fresh water or in 85% brine. In the case of both fluids, the oil was completely removed from the cores within several hours. In the second experiment, oil-coated salt pieces were suspended in air and the oil was allowed to drain. The weight of retained oil clinging to the salt was determined. This experiment was used to estimate the total amount of oil clinging to the roofs of the mine. The total amount of oil clinging to the roofs of the mine is estimated to be between 240 and 400 m 3 (1500 and 2500 BBL). In the third experiment, a pan of oil-soaked crushed salt was immersed in 85% brine, and oil removal from the salt was monitored as a function of...

Timothy Hern Energetic; Timothy J. O’hern; Thomas E. Hinkebein; Thomas W. Grasser

1999-01-01T23:59:59.000Z

389

Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc  

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

DOE Issues Statement Concerning Debates Over DOE Issues Statement Concerning Debates Over Waste Disposal in Salt CARLSBAD, N.M., July 24, 2009 - The U.S. Department of Energy and its Carlsbad Field Office recognize and respect the long history that led to the current regulations that govern operations at the Waste Isolation Pilot Plant (WIPP). The WIPP is authorized to ship and dispose of transuranic (TRU) waste that was created by U.S. defense programs. TRU waste is a category of waste strictly defined by legislation and legal agreements. The WIPP mission includes the safe disposal of two types of defense-related TRU waste, contact-handled (CH) and remote-handled (RH). Both consist of tools, rags, protective clothing, sludges, soil and other materials contaminated with radioactive

390

Brine chemistry: scaling and corrosion. Geothermal research study in the Salton Sea region of California  

DOE Green Energy (OSTI)

The purpose of this report is to recommend a reasonable program of brine chemistry research that will result in the development of methods for predicting and controlling scale deposition, and in guidelines for the selection of corrosion-resistant construction materials. First, background information, which is necessary for the understanding of the problems of scaling and corrosion in the Salton Sea KGRA, is presented through a review of the history of geothermal exploration and development in the Salton Sea. Second, literature relevant to the geochemistry of the Salton Sea field is reviewed and important results are emphasized. Third, current research efforts directed toward actual power plant construction are summarized and evaluated. Fourth, research which has been proposed but is not currently funded is discussed. Fifth, because silica scaling has been the most troublesome problem in the past, the basic chemistry of silica and its relationship to scaling is discussed. Sixth, recommendations for future research are made in which a fundamental engineering approach is emphasized. In this approach, experiments would be conducted on actual process equipment and detailed chemical analyses would be performed on site in well-equipped field laboratories. 88 references.

Hoffmann, M.R.

1975-07-01T23:59:59.000Z

391

Time-lapse crosswell seismic and VSP monitoring of injected CO2 ina brine aquifer  

SciTech Connect

Seismic surveys successfully imaged a small scale C02injection (1,600 tons) conducted in a brine aquifer of the Frio Formationnear Houston, Texas. These time-lapse bore-hole seismic surveys,crosswell and vertical seismic profile (VSP), were acquired to monitorthe C02 distribution using two boreholes (the new injection well and apre-existing well used for monitoring) which are 30 m apart at a depth of1500 m. The crosswell survey provided a high-resolution image of the C02distribution between the wells via tomographic imaging of the P-wavevelocity decrease (up to 500 mls). The simultaneously acquired S-wavetomography showed little change in S-wave velocity, as expected for fluidsubstitution. A rock physics model was used to estimate C02 saturationsof 10-20 percent from the P-wave velocity change. The VSP survey resolveda large (-70 percent) change in reflection amplitude for the Friohorizon. This C02 induced reflection amplitude change allowed estimationof the C02 extent beyond the monitor well and on 3 azimuths. The VSPresult is compared with numerical modeling of C02 saturations and isseismically modeled using the velocity change estimated in the crosswellsurvey.

Daley, Thomas M.; Myer, Larry R.; Peterson, J.E.; Majer, E.L.; Hoversten,G.M.

2006-05-30T23:59:59.000Z

392

Radiological Surveys Performed in Support of the Demolition and Bulk Disposal Decommissioning Method  

SciTech Connect

Connecticut Yankee Atomic Power Company is decommissioning the Haddam Neck Plant using the 'Demolition and Bulk Disposal' method, or commonly referred to as 'Rip and Ship'. In general, completing the project using this method entails the removal of all irradiated fuel and highly contaminated systems and components, and the subsequent demolition of the above ground portions of most site structures. Since most structures are removed from site, cost and time savings are realized by virtually eliminating the need for remediation. However, this method of decommissioning creates more waste, both radiological and non-radiological, which must be segregated, packaged and disposed of properly. Prior to demolition, various types of radiological surveys must be performed and work controls put into place to minimize the spread of contamination to other areas of the site, and to prevent the inadvertent release of radioactive materials from the site. This paper will discuss the various types of radiological surveys performed, and controls implemented, in support of the demolition and bulk material disposal decommissioning method, with the emphasis on pre-demolition surveys. Details will be provided on the release criteria, survey design, survey implementation and data analysis on each of the various surveys, as well as a discussion on the controls implemented to prevent the various wastes from inadvertently being shipped to an inappropriate disposal facility. This paper will also strive to provide lessons learned for future projects that utilize the demolition and bulk disposal decommissioning method. (authors)

Yetter, R.F. [Babcock Services, Inc., 1840 Terminal Drive, Richland, WA 99352 (United States); Newson, C.T. [Connecticut Yankee Atomic Power Company, 362 Injun Hollow Road, East Hampton, CT 06424 (United States)

2006-07-01T23:59:59.000Z

393

200 Area Treated Effluent Disposal Facility operational test specification. Revision 2  

Science Conference Proceedings (OSTI)

This document identifies the test specification and test requirements for the 200 Area Treated Effluent Disposal Facility (200 Area TEDF) operational testing activities. These operational testing activities, when completed, demonstrate the functional, operational and design requirements of the 200 Area TEDF have been met. The technical requirements for operational testing of the 200 Area TEDF are defined by the test requirements presented in Appendix A. These test requirements demonstrate the following: pump station No.1 and associated support equipment operate both automatically and manually; pump station No. 2 and associated support equipment operate both automatically and manually; water is transported through the collection and transfer lines to the disposal ponds with no detectable leakage; the disposal ponds accept flow from the transfer lines with all support equipment operating as designed; and the control systems operate and status the 200 Area TEDF including monitoring of appropriate generator discharge parameters.

Crane, A.F.

1995-02-09T23:59:59.000Z

394

RESIDUES FROM COAL CONVERSION AND UTILIZATION: ADVANCED MINERALOGICAL CHARACTERIZATION AND DISPOSED BYPRODUCT DIAGENESIS  

SciTech Connect

The goals of the project are two-fold: (1) to upgrade semi-quantitative X-ray diffraction (QXRD) methods presently used in analyzing complex coal combustion by-product (CCB) systems, with the quantitative Rietveld method, and (2) to apply this method to a set of by-product materials that have been disposed or utilized for a long period (5 years or more) in contact with the natural environment, to further study the nature of CCB diagenesis. The project is organized into three tasks to accomplish these two goals: (1) thorough characterization of a set of previously analyzed disposed by-product materials, (2) development of a set of CCB-specific protocols for Rietveld QXRD, and (3) characterization of an additional set of disposed CCB materials, including application of the protocols for Rietveld QXRD developed in Task 2.

Gregory J. McCarthy; Dean G. Grier

1998-09-01T23:59:59.000Z

395

Review of Yucca Mountain Disposal Criticality Studies  

SciTech Connect

The U.S. Department of Energy (DOE), Office of Civilian Radioactive Waste Management, submitted a license application for construction authorization of a deep geologic repository at Yucca Mountain, Nevada, in June of 2008. The license application is currently under review by the U.S. Nuclear Regulatory Commission. However,on March 3, 2010 the DOE filed a motion requesting withdrawal of the license application. With the withdrawal request and the development of the Blue Ribbon Commission to seek alternative strategies for disposing of spent fuel, the status of the proposed repository at Yucca Mountain is uncertain. What is certain is that spent nuclear fuel (SNF) will continue to be generated and some long-lived components of the SNF will eventually need a disposition path(s). Strategies for the back end of the fuel cycle will continue to be developed and need to include the insights from the experience gained during the development of the Yucca Mountain license application. Detailed studies were performed and considerable progress was made in many key areas in terms of increased understanding of relevant phenomena and issues regarding geologic disposal of SNF. This paper reviews selected technical studies performed in support of the disposal criticality analysis licensing basis and the use of burnup credit. Topics include assembly misload analysis, isotopic and criticality validation, commercial reactor critical analyses, loading curves, alternative waste package and criticality control studies, radial burnup data and effects, and implementation of a conservative application model in the criticality probabilistic evaluation as well as other information that is applicable to operations regarding spent fuel outside the reactor. This paper summarizes the work and significant accomplishments in these areas and provides a resource for future, related activities.

Scaglione, John M [ORNL; Wagner, John C [ORNL

2011-01-01T23:59:59.000Z

396

Technical and economic feasibility of salt-gradient solar ponds at the Truscott Brine Lake of the Red River Chloride Control Project. A report to the House-Senate Committee on Appropriations of the Ninety-Seventh Congress  

DOE Green Energy (OSTI)

The Truscott Brine Lake is being constructed to impound highly brackish water from a number of sources which would normally flow into the Wichita River, a tributary of the Red River in Knox County, Texas. A 35.4-km (22-mile) pipeline is being constructed to carry the brines from their primary source to the Truscott Brine Lake site. The reservoir is designed to contain 100 years of brine emissions from three chloride emission areas in the Wichita River Basin. The solar ponds and power generating facilities would be located in the Bluff Creek Arm of Truscott Brine Lake. The Truscott Brine Lake study includes: survey of suitability of Truscott Lake site, review of solar pond technology, preconceptual design of solar salt pond power plant, and economic evaluation.

Not Available

1982-09-01T23:59:59.000Z

397

Disposal R&D in the Used Fuel Disposition Campaign: A Discussion of Opportunities for Active International Collaboration  

Science Conference Proceedings (OSTI)

For DOE's Used Fuel Disposition Campaign (UFDC), international collaboration is a beneficial and cost-effective strategy for advancing disposal science with regards to multiple disposal options and different geologic environments. While the United States disposal program focused solely on Yucca Mountain tuff as host rock over the past decades, several international programs have made significant progress in the characterization and performance evaluation of other geologic repository options, most of which are very different from the Yucca Mountain site in design and host rock characteristics. Because Yucca Mountain was so unique (e.g., no backfill, unsaturated densely fractured tuff), areas of direct collaboration with international disposal programs were quite limited during that time. The decision by the U.S. Department of Energy to no longer pursue the disposal of high-level radioactive waste and spent fuel at Yucca Mountain has shifted UFDC's interest to disposal options and geologic environments similar to those being investigated by disposal programs in other nations. Much can be gained by close collaboration with these programs, including access to valuable experience and data collected over recent decades. Such collaboration can help to efficiently achieve UFDC's long-term goals of conducting 'experiments to fill data needs and confirm advanced modeling approaches' (by 2015) and of having a 'robust modeling and experimental basis for evaluation of multiple disposal system options' (by 2020). This report discusses selected opportunities of active international collaboration, with focus on both Natural Barrier System (NBS) and Engineered Barrier System (EBS) aspects and those opportunities that provide access to field data (and respective interpretation/modeling) or allow participation in ongoing field experiments. This discussion serves as a basis for the DOE/NE-53 and UFDC planning process for FY12 and beyond.

Birkholzer, J.T.

2011-06-01T23:59:59.000Z

398

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Disposal Research and Development Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

399

Disposal Practices at the Nevada Test Site 2008  

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

Area 5 LLRW & MLLW Disposal Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive

400

Summary - Disposal Practices at the Nevada Test Site  

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

Nevada Test Site, NV Nevada Test Site, NV EM Project: Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been discontinued, but the facility is available for future disposal. The anticipated closure date for Area 3 is 2027. Area 5 is operating and will be expanded to accept future wastes. LLRW and mixed low-level radioactive waste (MLLW) are disposed of in Area 5 in shallow

Note: This page contains sample records for the topic "brine disposal system" 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

DOE - Office of Legacy Management -- Maryland Disposal Site - MD 05  

Office of Legacy Management (LM)

Maryland Disposal Site - MD 05 Maryland Disposal Site - MD 05 FUSRAP Considered Sites Site: MARYLAND DISPOSAL SITE (MD.05 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Baltimore - Vicinity , Maryland MD.05-1 Evaluation Year: 1989 MD.05-1 Site Operations: Proposed disposal site - never developed. MD.05-1 Site Disposition: Eliminated Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): None Indicated Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to MARYLAND DISPOSAL SITE MD.05-1 - Report (DOE/OR/20722-131 Revision 0); Site Plan for the Maryland Disposal Site; April 1989 Historical documents may contain links which are no longer valid or to

402

Deep Borehole Disposal Research: Demonstration Site Selection Guidelines,  

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

Deep Borehole Disposal Research: Demonstration Site Selection Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs The U.S. Department of Energy has been investigating deep borehole disposal as one alternative for the disposal of spent nuclear fuel and other radioactive waste forms, along with research and development for mined repositories in salt, granite, and clay, as part of the used fuel disposition (UFD) campaign. The deep borehole disposal concept consists of drilling a borehole on the order of 5,000 m deep, emplacing waste canisters in the lower part of the borehole, and sealing the upper part of the borehole with bentonite and concrete seals. A reference design of the

403

Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory  

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

INL, Idaho INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Idaho CERCLA Disposal Facility (ICDF) At Idaho National Laboratory (INL) Why DOE-EM Did This Review The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose of LLW and MLW generated from remedial activities at the Idaho National Laboratory (INL). Components of the ICDF include a landfill that is used for disposal of solid waste, an evaporation pond that is used to manage leachate from the landfill and other aqueous wastes (8.3 million L capacity), and a staging and treatment facility. The ICDF is located near the southwest

404

LANL completes excavation of 1940s waste disposal site  

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

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

405

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

406

Low-Level Radioactive Waste Disposal Act (Pennsylvania) | Department of  

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

Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Municipal/Public Utility Local Government Rural Electric Cooperative Transportation Program Info State Pennsylvania Program Type Environmental Regulations Provider Pennsylvania Department of Environmental Protection This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and storage of low-level radioactive waste. Commercial incineration of radioactive wastes is prohibited. Licenses are required for low-level radioactive waste disposal facilities not licensed to accept low-level radioactive waste. Disposal at

407

Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) |  

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

Low-Level Radioactive Waste Disposal Regional Facility Act Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Fees This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental Resources funds to be utilized for disposal facilities. This act ensures that nuclear facilities and the Department comply with the Low-Level Radioactive Disposal Act. The regional facility siting fund is used for reimbursement of expenses

408

B Plant treatment, storage, and disposal (TSD) units inspection plan  

Science Conference Proceedings (OSTI)

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B Plant have been permitted for waste management activities. Included are the following TSD units: Cell 4 Container Storage Area; B Plant Containment Building; Low Level Waste Tank System; Organic Waste Tank System; Neutralized Current Acid Waste (NCAW) Tank System; Low Level Waste Concentrator Tank System. This inspection plan complies with the requirements of WAC 173-303. It addresses both general TSD facility and TSD unit-specific inspection requirements. Sections on each of the TSD units provide a brief description of the system configuration and the permitted waste management activity, a summary of the inspection requirements, and details on the activities B Plant uses to maintain compliance with those requirements.

Beam, T.G.

1996-04-26T23:59:59.000Z

409

Long-length contaminated equipment disposal process path document  

Science Conference Proceedings (OSTI)

The first objective of the LLCE Process Path Document is to guide future users of this system on how to accomplish the cradle-to-grave process for the disposal of long-length equipment. Information will be provided describing the function and approach to each step in the process. Pertinent documentation, prerequisites, drawings, procedures, hardware, software, and key interfacing organizations will be identified. The second objective is related to the decision to lay up the program until funding is made available to complete it or until a need arises due to failure of an important component in a waste tank. To this end, the document will identify work remaining to be completed for each step of the process and open items or issues that remain to be resolved.

McCormick, W.A.

1998-09-30T23:59:59.000Z

410

Technology transfer report: feasibility study for the use of geothermal brine in the Ashdod area, Israel  

DOE Green Energy (OSTI)

The hydrothermal potential of the Ashdod area, Israel, was evaluated to determine its suitability as the low grade energy source required to operate the Ashdod desalination plant. An estimated 1250 cubic meters per hour of 120/sup 0/C brine would be adequate to supply the hot water necessary for operating the desalination plant. Considerable interest in oil exploration in the Ashdod area resulted in the drilling of six wells into the Jurassic formations by Oil Exploration (Investments) Ltd. (OEL) in 1976-1980. A small amount of oil was found in two wells, Ashdod 2 and 5. The remaining wells were abandoned as ''dry holes''. Evaluation of the drill cuttings, cores, and the electric logs defined two lithologic units of potential interest for hydrothermal exploitation, the Zohar and Shderot Dolomites. Investigation of the hydrothermal potential of the Jurassic formations underlying the Ashdod area has revealed that the aquifer temperatures range between 85 and 92/sup 0/C. The hydrologic parameters are not well defined; however the matrix permeability of the dolomites and limestones is probably between 1 and 10 md. This is insufficient permeability for a large scale pumping operation such as the one required to operate the desalination plant. Therefore, successful utilization of the resource requires the presence of significant fractures and/or connected vugs in the formation. The very low well productivity and formation plugging may indicate that permeability of the fracture zones may easily be impaired, suggesting that the fracture zones are not suitable production intervals. Until a test is conducted on a properly completed well, it is not possible to evaluate the deliverability of wells tapping these aquifers. 14 refs., 8 figs.

Benson, S.M.

1984-08-01T23:59:59.000Z

411

Nevada test site experience with greater confinement disposal  

Science Conference Proceedings (OSTI)

At the NTS, we consider Greater Confinement Disposal (GCD) to be a good waste management practice rather than a disposal technology. This is an important distinction because it redefines the nature of GCD. All disposal facilities operate under the principal of ''as low as reasonably achievable'' (ALARA) in reducing personnel and public exposures. ALARA is not a technology or method but a principal put into practice. We view GCD in the same manner.

Dickman, P.T.; Boland, J.R.

1986-01-01T23:59:59.000Z

412

Disposal Cost Savings Considerations in Curie Reduction Programs  

Science Conference Proceedings (OSTI)

In 1996, the Low Level Radioactive Waste (LLW) Disposal Facility in Barnwell, South Carolina, announced a new fee structure for the disposal of radioactive wastes based on waste density, dose rate, and activity (curies). This report provides a detailed discussion of the current Barnwell Disposal Fee Structure along with its cost impact on various types of wastes generated. The report also evaluates various curie reduction options, their practical application, and their cost savings potential to help LLW ...

1998-03-30T23:59:59.000Z

413

ERDA safety practices involving disposal of contaminated real property  

SciTech Connect

A general discussion of the specific procedures for excess disposal outlined in the Property Management Handbook, ERDAM 5301 is given. (LK)

Loop, E.K.

1975-09-01T23:59:59.000Z

414

IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS,...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS, IG-0527 IDAHO OPERATIONS OFFICE...

415

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

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

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

416

Used Fuel Disposition Campaign Disposal Research and Development...  

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

the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF)...

417

Environmental Impacts of Options for Disposal of Depleted Uranium...  

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

study by Oak Ridge National Laboratory evaluated the acceptability of several depleted uranium conversion products at potential LLW disposal sites to provide a basis for DOE...

418

Microsoft Word - SRSSaltWasteDisposal.doc | Department of Energy  

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

Savannah River Site - Tank 48 SRS Review Report 2009 Performance Assessment for the Saltstone Disposal Facility DOE Order 435.1 Performance Assessment Savannah River Site...

419

Spent Fuel Disposal Trust Fund (Maine) | Department of Energy  

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

Program Type Safety and Operational Guidelines Any licensee operating a nuclear power plant in this State shall establish a segregated Spent Nuclear Fuel Disposal Trust Fund...

420

Low-Level Waste Disposal Alternatives Analysis Report  

SciTech Connect

This report identifies and compares on-site and off-site disposal options for the disposal of contract-handled and remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Potential disposal options are screened for viability by waste type resulting in a short list of options for further consideration. The most crediable option are selected after systematic consideration of cost, schedule constraints, and risk. In order to holistically address the approach for low-level waste disposal, options are compiled into comprehensive disposal schemes, that is, alternative scenarios. Each alternative scenario addresses the disposal path for all low-level waste types over the period of interest. The alternative scenarios are compared and ranked using cost, risk and complexity to arrive at the recommended approach. Schedule alignment with disposal needs is addressed to ensure that all waste types are managed appropriately. The recommended alternative scenario for the disposal of low-level waste based on this analysis is to build a disposal facility at the Idaho National Laboratory Site.

Timothy Carlson; Kay Adler-Flitton; Roy Grant; Joan Connolly; Peggy Hinman; Charles Marcinkiewicz

2006-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "brine disposal system" 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

Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National...  

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

INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External...

422

Los Alamos Lab Completes Excavation of Waste Disposal Site Used...  

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

Excavation of Waste Disposal Site Used in the 1940s More Documents & Publications Manhattan Project Truck Unearthed in Recovery Act Cleanup Protecting Recovery Act Cleanup...

423

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...

424

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

Hightower, J.R.; Trabalka, J.R.

2000-02-01T23:59:59.000Z

425

Solid Waste Disposal Facilities (Massachusetts) | Department of Energy  

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

Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Transportation Tribal Government Utility Program Info State Massachusetts Program Type Siting and Permitting Provider Department of Environmental Protection These sections articulate rules for the maintenance and operation of solid waste disposal facilities, as well as site assignment procedures. Applications for site assignment will be reviewed by the Massachusetts Department of Environmental Protection as well as the Department of Public

426

Research into the Characterization of Brackish Water and Disposal of Desalination Reject Water in Saline Aquifers and Depleted Oil and Gas Reservoirs  

E-Print Network (OSTI)

Brackish groundwater is a valuable “drought-proof” resource that is plentiful in much of Texas. If treated by available desalination technologies, brackish groundwater resources could help many regions of Texas cope with pressing water shortages. If put to non-potable uses such as waterflooding, streamflow augmentation, and landscape irrigation, brackish groundwater could free up substantial amounts of drinking water supplies now dedicated to these uses. In 2007, the Texas Legislature passed landmark legislation that should provide greatly expanded opportunities to beneficially use concentrates from the desalination of brackish groundwater or to streamline the disposal as a waste product. House Bill 2654 (passed in the 80th Legislative session) has the promise of making it substantially easier to manage concentrates that result from the desalination of brackish groundwater. The bill authorizes the Texas Commission on Environmental Quality to issue a general statewide permit that allows disposal of nonhazardous brine from desalination operations into Class I injection wells. The bill also streamlines the process of using the concentrates in Class II injection wells for enhanced oil and gas recovery operations. However, more still needs to be done in two key areas: * Learning more about the chemical traits of brackish groundwater in specific circumstances to ensure that concentrates from desalting these resources are not a hazardous waste, * Continuing to develop and implement technologies and management strategies that make these programs most cost-efficient.

Jensen, R.

2008-01-01T23:59:59.000Z

427

Carbon dioxide disposal in solid form  

SciTech Connect

Coal reserves can provide for the world`s energy needs for centuries. However, coal`s long term use may be severely curtailed if the emission of carbon dioxide into the atmosphere is not eliminated. We present a safe and permanent method of carbon dioxide disposal that is based on combining carbon dioxide chemically with abundant raw materials to form stable carbonate minerals. We discuss the availability of raw materials and potential process designs. We consider our initial rough cost estimate of about 3{cents}/kWh encouraging. The availability of a carbon dioxide fixation technology would serve as insurance in case global warming, or the perception of global warming, causes severe restrictions on carbon dioxide emissions. If the increased energy demand of a growing world population is to be satisfied from coal, the implementation of such a technology would quite likely be unavoidable.

Lackner, K.S.; Butt, D.P.; Sharp, D.H. [Los Alamos National Lab., NM (United States); Wendt, C.H. [Auxon Corp., (United States)

1995-12-31T23:59:59.000Z

428

Disposable sludge dewatering container and method  

DOE Patents (OSTI)

This invention is comprised of a device and method for preparing sludge for disposal comprising a box with a thin layer of gravel on the bottom and a thin layer of sand on the gravel layer, an array of perforated piping deployed throughout the gravel layer, and a sump in the gravel layer below the perforated piping array. Standpipes connect the array and sump to an external ion exchanger/fine particulate filter and a pump. Sludge is deposited on the sand layer and dewatered using a pump connected to the piping array, topping up with more sludge as the aqueous component of the sludge is extracted. When the box is full and the free standing water content of the sludge is acceptable, the standpipes are cut and sealed and the lid secured to the box.

Cole, C.M.

1990-12-27T23:59:59.000Z

429

LABORATORY EXPERIMENTS TO SIMULATE CO2 OCEAN DISPOSAL  

SciTech Connect

This Final Technical Report summarizes the technical accomplishments of an investigation entitled ''Laboratory Experiments to Simulate CO{sub 2} Ocean Disposal'', funded by the U.S. Department of Energy's University Coal Research Program. This investigation responds to the possibility that restrictions on greenhouse gas emissions may be imposed in the future to comply with the Framework Convention on Climate Change. The primary objective of the investigation was to obtain experimental data that can be applied to assess the technical feasibility and environmental impacts of oceanic containment strategies to limit release of carbon dioxide (CO{sub 2}) from coal and other fossil fuel combustion systems into the atmosphere. A number of critical technical uncertainties of ocean disposal of CO{sub 2} were addressed by performing laboratory experiments on liquid CO{sub 2} jet break-up into a dispersed droplet phase, and hydrate formation, under deep ocean conditions. Major accomplishments of this study included: (1) five jet instability regimes were identified that occur in sequence as liquid CO{sub 2} jet disintegration progresses from laminar instability to turbulent atomization; (2) linear regression to the data yielded relationships for the boundaries between the five instability regimes in dimensionless Ohnesorge Number, Oh, and jet Reynolds Number, Re, space; (3) droplet size spectra was measured over the full range of instabilities; (4) characteristic droplet diameters decrease steadily with increasing jet velocity (and increasing Weber Number), attaining an asymptotic value in instability regime 5 (full atomization); and (5) pre-breakup hydrate formation appears to affect the size distribution of the droplet phase primary by changing the effective geometry of the jet.

Stephen M. Masutani

1999-12-31T23:59:59.000Z

430

Evaluation of food waste disposal options by LCC analysis from the perspective of global warming: Jungnang case, South Korea  

SciTech Connect

Highlights: > Various food waste disposal options were evaluated from the perspective of global warming. > Costs of the options were compared by the methodology of life cycle assessment and life cycle cost analysis. > Carbon price and valuable by-products were used for analyzing environmental credits. > The benefit-cost ratio of wet feeding scenario was the highest. - Abstract: The costs associated with eight food waste disposal options, dry feeding, wet feeding, composting, anaerobic digestion, co-digestion with sewage sludge, food waste disposer, incineration, and landfilling, were evaluated in the perspective of global warming and energy and/or resource recovery. An expanded system boundary was employed to compare by-products. Life cycle cost was analyzed through the entire disposal process, which included discharge, separate collection, transportation, treatment, and final disposal stages, all of which were included in the system boundary. Costs and benefits were estimated by an avoided impact. Environmental benefits of each system per 1 tonne of food waste management were estimated using carbon prices resulting from CO{sub 2} reduction by avoided impact, as well as the prices of by-products such as animal feed, compost, and electricity. We found that the cost of landfilling was the lowest, followed by co-digestion. The benefits of wet feeding systems were the highest and landfilling the lowest.

Kim, Mi-Hyung, E-mail: mhkim9@snu.ac.kr [Department of Environmental Planning, Graduate School of Environmental Studies, Seoul National University, San 56-1, Sillim-Dong, Gwanak-Gu, Seoul 151-742 (Korea, Republic of); Song, Yul-Eum, E-mail: yesong0724@dongguk.edu [Department of Philosophy, Dongguk University, Pil-Dong 3-Ga, Jung-Gu, Seoul 100-715 (Korea, Republic of); Department of Life Science, Dongguk University, Pil-Dong 3-Ga, Jung-Gu, Seoul 100-715 (Korea, Republic of); Song, Han-Byul, E-mail: kuackyang@ssu.ac.kr [Department of Chemical Engineering, Soongsil University, Sangdo-Ro 369, Dongjak-Gu, Seoul 156-743 (Korea, Republic of); Kim, Jung-Wk, E-mail: kimjw@snu.ac.kr [Department of Environmental Planning, Graduate School of Environmental Studies, Seoul National University, San 56-1, Sillim-Dong, Gwanak-Gu, Seoul 151-742 (Korea, Republic of); Hwang, Sun-Jin, E-mail: sjhwang@khu.ac.kr [Department of Environmental Science and Engineering, Center for Environmental Studies, Kyung Hee University, Seocheon-Dong, Giheung-Gu, Yongin-Si, Gyeonggi-Do 446-701 (Korea, Republic of)

2011-09-15T23:59:59.000Z

431

Recycling and Disposal of Spent Selective Catalytic Reduction Catalyst  

Science Conference Proceedings (OSTI)

Selective catalytic reduction (SCR) technology has become widespread within the utility industry as a means of controlling emissions of nitrogen oxides (NOx). The technology uses a solid catalyst that deactivates over time; and thus significant volumes of catalyst will need regeneration, recycle, or disposal. This study examined issues related to spent catalyst recycle and disposal.

2003-11-12T23:59:59.000Z

432

Summary - Disposal Practices at the Savannah River Site  

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

ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did This Review Disposal operations have been ongoing at the Savannah River Site (SRS) for over 50 years. Active disposal in E-Area, is near the center of the site. Although a wide range of wastes are being managed at the SRS, only low level radioactive wastes (LLRW) are disposed of on site. Wastes are disposed of in unlined slit and engineered trenches, and in low activity waste and intermediate level vaults. Some wastes are isolated in place with grout and all wastes will be covered with a cap that includes a hydraulic barrier to limit precipitation infiltration. The objective of this review was to

433

Low-Level Waste Disposal Facility Federal Review Group Manual  

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

LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP MANUAL REVISION 3 JUNE 2008 (This page intentionally left blank) Low-Level JVllsfe Disposal Fllcili~l' Federal Review Group il1allUlli Revision 3, June 200S Concurrence The Low-Level Waste Disposal Facility Federal Review Group Manual, Revision 3, is approved for use as of the most recent date below. Date Chair, Low-Level Waste Disposal Federal Review Group Andrew WalJo, 1II Deputy Director, Otlice of Nuclear Safety, Quality Assurance, and Environment Department of Energy OHlce of Health, Safety, and Security e C. WilJiams Associate Administrator for Infrastructure and Environment National Nuclear Security Administration Low-Level 'Vaste Disposal Facility Federal Review Group J1aJll/ai

434

NNSA Reaches LEU Disposal Milestone | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Reaches LEU Disposal Milestone | National Nuclear Security Reaches LEU Disposal Milestone | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Reaches LEU Disposal Milestone NNSA Reaches LEU Disposal Milestone November 08, 2004 Aiken, SC NNSA Reaches LEU Disposal Milestone The National Nuclear Security Administration's reached an important

435

OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE | Department  

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

OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE December 1, 2010 - 12:00pm Addthis OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE Oak Ridge, TN - The Environmental Management Waste Management Facility (EMWMF) provides the onsite disposal capability for the majority of cleanup-generated wastes on the Oak Ridge Reservation. EMWMF has continued a long-standing pattern of safe, complaint operations with 3,000 days without a lost workday case since operations commenced on May 28, 2002. The EMWMF has placed 1.5 million tons of waste and fill in the facility. The EMWMF receives waste from many Oak Ridge cleanup projects, including American Recovery and Reinvestment Act-funded projects, multiple

436

Drilling Waste Management Fact Sheet: Offsite Disposal at Commercial  

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

Commercial Disposal Facilities Commercial Disposal Facilities Fact Sheet - Commercial Disposal Facilities Although drilling wastes from many onshore wells are managed at the well site, some wastes cannot be managed onsite. Likewise, some types of offshore drilling wastes cannot be discharged, so they are either injected underground at the platform (not yet common in the United States) or are hauled back to shore for disposal. According to an American Petroleum Institute waste survey, the exploration and production segment of the U.S. oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes in 1985. The report estimates that 28% of drilling wastes are sent to offsite commercial facilities for disposal (Wakim 1987). A similar American Petroleum Institute study conducted ten years later found that the volume of drilling waste had declined substantially to about 150 million bbl.

437

Composite analysis E-area vaults and saltstone disposal facilities  

Science Conference Proceedings (OSTI)

This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

Cook, J.R.

1997-09-01T23:59:59.000Z

438

2009 Performance Assessment for the Saltstone Disposal Facility |  

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

Performance Assessment for the Saltstone Disposal Facility Performance Assessment for the Saltstone Disposal Facility 2009 Performance Assessment for the Saltstone Disposal Facility This Performance Assessment (PA) for the Savannah River Site (SRS) was prepared to support the operation and eventual closure of the Saltstone Disposal Facility (SDF). This PA was prepared to demonstrate compliance with the pertinent requirements of the United States Department of Energy (DOE) Order 435.1, Change 1, Radioactive Waste Management, Chapter IV, and Title 10, of the Code of Federal Regulations (CFR) Part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Subpart C as required by the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, Section 3116. [DOE O 435.1-1, 10 CFR 61, NDAA_3116]

439

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

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

Disposal Research and Development Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW) generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made in the U.S and other nations, but gaps in knowledge still exist. This document provides an evaluation and prioritization of R&D opportunities