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1

A process for establishing a financial assurance plan for LLW disposal facilities  

SciTech Connect (OSTI)

This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided.

Smith, P. [EG and G Idaho, Inc., Idaho Falls, ID (United States). National Low-Level Waste Management Program

1993-04-01T23:59:59.000Z

2

Review of the EPA's radionuclide release analyses from LLW disposal trenches used in support of proposed dose limits in 40 CFR 193  

SciTech Connect (OSTI)

The April 1989 draft EPA standard for low-level waste (LLW) disposal, 40 CFR 193, would require disposal site performance to satisfy very stringent dose-limit criteria. The EPA suggests that these limits can be achieved by relying extensively on waste solidification before disposal. The EPA justifies the achievability of the proposed criteria based on performance assessment analyses in the general context of trench burial of the LLW. The core models implemented in those analyses are codified in the EPA's PRESTO family of codes. Because a key set of models for predicting potential releases are the leach-and-transport models from a disposal trench, these have been reviewed for completeness and applicability to trench disposal methods. The overall conclusion of this review is that the generic analyses performed by the EPA are not sufficiently comprehensive to support the proposed version of 40 CFR 193. More rigorous analyses may find the draft standard criteria to be unattainable.

Pescatore, C.; Sullivan, T.M.

1991-11-01T23:59:59.000Z

3

Review of the EPA`s radionuclide release analyses from LLW disposal trenches used in support of proposed dose limits in 40 CFR 193  

SciTech Connect (OSTI)

The April 1989 draft EPA standard for low-level waste (LLW) disposal, 40 CFR 193, would require disposal site performance to satisfy very stringent dose-limit criteria. The EPA suggests that these limits can be achieved by relying extensively on waste solidification before disposal. The EPA justifies the achievability of the proposed criteria based on performance assessment analyses in the general context of trench burial of the LLW. The core models implemented in those analyses are codified in the EPA`s PRESTO family of codes. Because a key set of models for predicting potential releases are the leach-and-transport models from a disposal trench, these have been reviewed for completeness and applicability to trench disposal methods. The overall conclusion of this review is that the generic analyses performed by the EPA are not sufficiently comprehensive to support the proposed version of 40 CFR 193. More rigorous analyses may find the draft standard criteria to be unattainable.

Pescatore, C.; Sullivan, T.M.

1991-11-01T23:59:59.000Z

4

WDS.cdr  

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

Waste Data System Waste Data System The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant, or WIPP, is responsible for the safe disposal of the nation's defense-related transuranic (TRU) waste. Keeping track of thousands of waste containers disposed at WIPP and in temporary storage at sites across the country can be a challenge. To meet this challenge, DOE has developed an information system for keeping all data related to

5

Control of water infiltration into near surface LLW disposal units. Progress report on field experiments at a humid region site, Beltsville, Maryland: Volume 8  

SciTech Connect (OSTI)

This study`s objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care.

Schulz, R.K. [California Univ., Los Angeles, CA (United States); Ridky, R.W. [Maryland Univ., College Park, MD (United States). Dept. of Geology; O`Donnell, E. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-04-01T23:59:59.000Z

6

Control of water infiltration into near surface LLW disposal units: Progress report on field experiments at a humid region site, Beltsville, Maryland  

SciTech Connect (OSTI)

This study`s objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care.

Schulz, R.K. [Univ. of California, Los Angeles, CA (United States); Ridky, R.W. [Univ. of Maryland, College Park, MD (United States). Dept. of Chemistry; O`Donnell, E. [Nuclear Regulatory Commission, Washington, DC (United States)

1996-08-01T23:59:59.000Z

7

Control of water infiltration into near surface LLW (low level waste) disposal units: Annual report, October 1985-September 1986  

SciTech Connect (OSTI)

In the humid eastern part of the United States, trench covers have, in general, failed to prevent some of the incident precipitation from percolating downward to buried wastes. It is the purpose of the present work to investigate and demonstrate a procedure or technique that will control water infiltration to buried wastes regardless of above or below ground disposal. Results to date show the proposed procedure to be very promising and are applicable to shallow land burial as well as above ground disposal (e.g., Tumulus). In essence, the technique combines engineered or positive control of run-off, along with a vegetative cover, and is named ''bioengineering management''. To investigate control of infiltration, lysimeters are being used to make complete water balance measurements. The studies have been underway at the Maxey Flats, Kentucky, low-level waste disposal facility for the past three seasonal years. When the original Maxey Flats site closure procedure is followed, it is necessary to pump large amounts of water out of the lysimeters to prevent the water table from rising closer than 2 meters from the surface. Using the bioengineering management procedure, no pumping is required. As a result of the encouraging initial findings in the rather small-scale lysimeters at Maxey Flats, a large-scale facility for demonstration of the bioengineering management technique has been constructed at Beltsville, Maryland. This facility is now operational with the demonstration and data collection underway. 6 refs., 15 figs.

Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

1987-04-01T23:59:59.000Z

8

RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report  

SciTech Connect (OSTI)

A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: • Department of Energy Order 435.1, “Radioactive Waste Management,” requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan • Environmental assessment supporting the National Environmental Policy Act • Nuclear safety • Safeguards and security • Emplacement operations • Requirements for commissioning • General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

Annette L. Schafer

2012-06-01T23:59:59.000Z

9

Modeling the Hydrogeochemical Transport of Radionuclides through Engineered Barriers System in the Proposed LLW Disposal Site of Taiwan - 12082  

SciTech Connect (OSTI)

A proposed site for final disposal of low-level radioactive waste located in Daren Township of Taitung County along the southeastern coast has been on the selected list in Taiwan. The geology of the Daren site consists of argillite and meta-sedimentary rocks. A mined cavern design with a tunnel system of 500 m below the surface is proposed. Concrete is used as the main confinement material for the engineered barrier. To investigate the hydrogeochemical transport of radionuclides through engineered barriers system, HYDROGEOCHEM5.0 model was applied to simulate the complex chemical interactions among radionuclides, the cement minerals of the concrete, groundwater flow, and transport in the proposed site. The simulation results showed that the engineered barriers system with the side ditch efficiently drained the ground water and lowered the concentration of the concrete degradation induced species (e.g., hydrogen ion, sulfate, and chloride). The velocity of groundwater observed at side ditch gradually decreased with time due to the fouling of pore space by the mineral formation of ettringite and thaumasite. The short half-life of Co-60, Sr-90 and Cs-137 significantly reduced the concentrations, whereas the long half-life of I-129(1.57x10{sup 7} years) and Am-241(432 years) remain stable concentrations at the interface of waste canister and concrete barrier after 300 years. The mineral saturation index (SI) was much less than zero due to the low aqueous concentration of radionuclide, so that the precipitation formation of Co-60, Sr-90, I-129, Cs-137 and Am-241 related minerals were not found. The effect of adsorption/desorption (i.e., surface complexation model) could be a crucial geochemical mechanism for the modeling of liquid-solid phase behavior of radionuclide in geochemically dynamic environments. Moreover, the development of advanced numerical models that are coupled with hydrogeochemical transport and dose assessment of radionuclide is required in the future. (authors)

Lin, Wen-Sheng [Hydrotech Research Institute, National Taiwan University, Taipei, Taiwan (China); Liu, Chen-Wuing; Tsao, Jui-Hsuan [Department of Bioenvironmental Systems Engineering, National Taiwan University, Taipei, Taiwan (China); Li, Ming-Hsu [Institute of Hydrological and Oceanic Sciences, National Central University, Jhongli, Taiwan (China)

2012-07-01T23:59:59.000Z

10

LLW Dumpster study: Task 009  

SciTech Connect (OSTI)

Over a span of several years, the public has reported visible leakage emanating from ten cubic yard Dumpsters used to transport Low Level Radioactive Wastes (LLW) from LANL generation sites to the disposal site at TA-54, Area G. The purpose of this study was to: Investigate probable causes of leakages, Inspect existing Dumpsters in the fields Propose immediate short-range solutions to the problem, and Propose long-range solutions based on predicted future requirements. Field investigations indicated that LLW is handled carefully and professional at the individual generation sites and again during pick-up delivery, and disposal at TA-54. It was also apparent, however, that Dumpsters not designed for LLW service are used to store this radioactive material for extended time periods while being subjected to the full range of Northern New Mexico weather conditions. All Dumpsters inspected had 1/8 in to 2 in gaps in their closures (loading doors and discharge ramps) through which driving rain or melting snow could easily enter. Seven Dumpsters were located outside secure areas. No cases of actual contamination were discovered, only the appearance of contamination i.e. the dripping of collected rainwater or melting ice and snow from Dumpsters being transported over public roads.

Frye, J.A. [Thompson (T.K.), Inc., White Rock, NM (United States)

1989-08-01T23:59:59.000Z

11

International Recycling of LLW Metals  

SciTech Connect (OSTI)

Melting of radioactive scrap metal has been successfully practiced for more than 15 years, with approximately 60,000 tons of steel being processed into beneficial reuse applications. This process has converted radioactive scrap metal at a licensed facility into useful products such as shield blocks, security barriers and shield containers. These products are used within the nuclear industry, such as nuclear power plants, waste disposal facilities and high-energy physics research facilities. Recycling provides the following benefits by comparison with direct disposal: - Preserving metal resources. - Conserving valuable Low Level Waste (LLW) disposal site resources, thereby extending disposal site life. - Reducing the cost of metal products to end users by using materials less expensive than virgin metals. This paper outlines international metal recycling practices implemented at EnergySolutions' Bear Creek Facility in Oak Ridge, Tennessee. (authors)

Eshleman, T.; Jansen, J. [EnergySolutions (United States); Shinya, Sawada [KEK - High Energy Accelerator Research Organization (Japan)

2008-07-01T23:59:59.000Z

12

Development Of Strategy For The Management Of LLW In The United Kingdom  

SciTech Connect (OSTI)

The Nuclear Decommissioning Authority (NDA) is a UK non-departmental public body with a remit to clean up the civil public sector nuclear legacy. Much work has been done to date on developing contractor competition for the management of NDA-owned sites, including the UK's principal disposal facility: the Low Level Waste Repository (LLWR) in Cumbria. The competition goals and principles are integrated with the framework for the development of a UK Low Level Waste (LLW) management plan, through which the NDA will deliver its commitments to UK Government and stakeholders. Nexia Solutions has undertaken work for the NDA in assessing strategic options and scenarios for the management and disposal of current UK LLW. The volumetric, radiological and strategic limitations of existing disposition routes have been assessed against the inventories and characteristics of LLW forecast to arise. A number of potential alternative scenarios and variants for future LLW management have been modelled and assessed. (authors)

Wareing, A.S. [Nexia Solutions Ltd, Risley, Warrington, Cheshire, WA (United Kingdom); Fisher, J. [Nuclear Decommissioning Authority, Herdus House, Westlakes Science and Technology Park, Moor Row, Cumbria, CA24 3HU (United Kingdom)

2008-07-01T23:59:59.000Z

13

LLW Forum meeting report  

SciTech Connect (OSTI)

This document reports the details of the Quarterly Meeting of the Low- Level Radioactive Waste Forum held in San Diego, California during January 23-25, 1991. Topics discussed include: State and Compact Progress Reports; Legal Updates; Update on Technical Assistance; Advanced Notice of Proposed Rulemaking Regarding Surcharge Rebates; Update on TCC Activities; NRC Update; Disposal of Commercial Mixed Waste; Update on EPA Activities; ACNW Working Group on Mixed Waste; National Profile on Mixed Waste; Commercial Perspective on Mixed Waste; Update on DOT Activities; Source Terms; Materials and Waste; Storage: and Waste Acceptance Criteria and Packaging.

NONE

1991-12-31T23:59:59.000Z

14

LLW Notes, Volume 12, Number 3  

SciTech Connect (OSTI)

Contents include articles entitled: California DHS sues US Interior Department to compel land transfer; LLW Forum holds winter meeting; LLW Forum waste information working group meets; LLW Forum regulatory issues discussion group meets; Envirocare investigation transferred to feds; Host state TCC meets in Laughlin, Nevada; BLM to require new permit for California site testing; Federal agencies and committees; Pena sworn in as Energy Secretary, Grumbly departs DOE; U.S. Supreme Court tackles property rights issues; GAO to study DOI`s actions; Congress scrutinizes FY `98 budget requests; and Senate committee passes high-level waste bill: Clinton threatens to veto.

Norris, C.; Brown, H. [eds.; Colsant, J.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-03-01T23:59:59.000Z

15

LLW notes, Vol. 11, No. 2  

SciTech Connect (OSTI)

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

NONE

1996-03-01T23:59:59.000Z

16

LLW notes. Volume 11, No.8  

SciTech Connect (OSTI)

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive `LLW Notes`. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

NONE

1996-12-01T23:59:59.000Z

17

Greater-than-Class C low-level radioactive waste characterization. Appendix E-2: Mixed GTCC LLW assessment  

SciTech Connect (OSTI)

Mixed greater-than-Class C low-level radioactive waste (mixed GTCC LLW) is waste that combines two characteristics: it is radioactive, and it is hazardous. This report uses information compiled from Greater-Than-Class C Low-Level Radioactive Waste Characterization: Estimated Volumes, Radionuclide Activities, and Other Characteristics (DOE/LLW 1 14, Revision 1), and applies it to the question of how much and what types of mixed GTCC LLW are generated and are likely to require disposal in facilities jointly regulated by the DOE and the NRC. The report describes how to classify a RCRA hazardous waste, and then applies that classification process to the 41 GTCC LLW waste types identified in the DOE/LLW-114 (Revision 1). Of the 41 GTCC LLW categories identified, only six were identified in this study as potentially requiring regulation as hazardous waste under RCRA. These wastes can be combined into the following three groups: fuel-in decontamination resins, organic liquids, and process waste consisting of lead scrap/shielding from a sealed source manufacturer. For the base case, no mixed GTCC LLW is expected from nuclear utilities or sealed source licensees, whereas only 177 ml of mixed GTCC LLW are expected to be produced by other generators through the year 2035. This relatively small volume represents approximately 40% of the base case estimate for GTCC wastes from other generators. For these other generators, volume estimates for mixed GTCC LLW ranged from less than 1 m{sup 3} to 187 m{sup 3}, depending on assumptions and treatments applied to the wastes.

Kirner, N.P. [Ebasco Environmental, Idaho Falls, ID (United States)

1994-09-01T23:59:59.000Z

18

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

SciTech Connect (OSTI)

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

19

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2014-06-01T23:59:59.000Z

20

Disposal of low-level and mixed low-level radioactive waste during 1990  

SciTech Connect (OSTI)

Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data.

Not Available

1993-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities.

Porter, C.L.; Widmayer, D.A.

1995-09-01T23:59:59.000Z

22

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-04-01T23:59:59.000Z

23

Remote-Handled Low-Level Waste Disposal Project Code of Record  

SciTech Connect (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-06-01T23:59:59.000Z

24

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) | Department of  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. On February 17, 2011, DOE issued the Draft Environmental Impact Statement (EIS) for the Disposal of Greater-Than-Class C (GTCC) Low-Level Radioactive Waste (LLRW) and GTCC-Like Waste (Draft EIS, DOE/EIS-0375D) for public review and comment. DOE is inviting public comments on this Draft EIS during a 120-day public comment period, from the date of publication of the EIS's Notice of Availability in the Federal Register. During the comment

25

Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC§ 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.

Danny Anderson

2014-07-01T23:59:59.000Z

26

LLW Notes: Volume 10, Number 7  

SciTech Connect (OSTI)

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-10-01T23:59:59.000Z

27

LLW notes: Volume 10, Number 5  

SciTech Connect (OSTI)

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

NONE

1995-07-01T23:59:59.000Z

28

LLW notes: Volume 10, Number 6  

SciTech Connect (OSTI)

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-09-01T23:59:59.000Z

29

NNSS Waste Disposal Proves Vital Resource for DOE Complex | Department of  

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

NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex March 20, 2013 - 12:00pm Addthis The Area 5 Radioactive Waste Management Site The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels.

30

A Fresh Look at Greater Confinement Boreholes for Greater-Than-Class C Low-Level Radioactive Waste Disposal  

SciTech Connect (OSTI)

The United States Federal government has responsibility for disposal of low-level radioactive waste (LLW) with concentrations of radionuclides that exceed limits established by the United States Nuclear Regulatory Commission (NRC) for Class C LLW. Since Greater-Than-Class-C (GTCC) LLW is from activities licensed by NRC or NRC Agreement States, a disposal facility by law must be licensed by NRC. The United States (U.S.) Department of Energy (DOE) has the responsibility to site, design, construct, operate, decommission, and provide long-term care for GTCC LLW disposal facilities. On May 11, 2005, DOE issued an advance notice of intent to begin preparation of an Environmental Impact Statement (EIS) for GTCC LLW disposal. Since the initiation of the EIS, analysis has focused on compiling the inventory of commercial GTCC LLW and DOE GTCC-like wastes, reviewing disposal technologies, and other preliminary studies. One of the promising disposal technologies being considered is intermediate depth greater confinement boreholes. Greater confinement boreholes have been used effectively to safely dispose of long-lived radioactive waste at the Nevada Test Site (NTS). The DOE took a fresh look at global experiences with the use of greater confinement borehole disposal, including current considerations being given for future applications in the U.S., and concluded that the U.S. is positioned to benefit from international collaboration on borehole disposal technology, and could ultimately become a pilot project, if the technology is selected. (authors)

Tonkay, D.W.; Joyce, J.L. [U.S. Department of Energy, Office of Disposal Operations, Washington, DC (United States); Cochran, J.R. [Sandia National Laboratories1, Albuquerque, NM (United States)

2007-07-01T23:59:59.000Z

31

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect (OSTI)

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

32

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?  

SciTech Connect (OSTI)

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change.

Devgun, J.S. [Argonne National Lab., IL (United States); Larson, G.S. [Midwest Low-Level Radioactive Waste Commission, St. Paul, MN (United States)

1995-12-31T23:59:59.000Z

33

LLW Notes, vol. 9, no. 1. February/March 1994  

SciTech Connect (OSTI)

LLW Notes is published ten times each year and is distributed to Low- Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies.

NONE

1994-03-01T23:59:59.000Z

34

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) ...  

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the...

35

LLW Notes, Volume 12, Number 7  

SciTech Connect (OSTI)

Contents include articles entitled: House votes 309 to 107 to approve Texas compact; Nebraska governor hosts LLRW meeting; Southeast Compact considers funding proposal; Chem-Nuclear explores options re SC revenue requirements; Legislation sets revenue requirements for Barnwell; TCC meets: Supports CA request for technical assistance; DOE approves part of California`s technical assistance request; State legislators discuss LLRW management for OH, IL, NC; Washington governor re Potential New Hanford Role; Federal court enjoins DOE from excluding WCS on new disposal; Appellate court in favor of DOE in surcharge rebates dispute; Hearing set for October in Ward Valley case; court rejects federal motion to dismiss Ward Valley suit; NE sues commission re veto over export authorizations; US Supreme Court dismisses line-item veto challenge; Department of Interior Inspector General investigation requested; USEC privatization plan approved; DOD finalizes LLRW disposal charter; Clinton nominates six DOE appointees; Congress moves FUSRAP to Army Corps of Engineers; Schaefer named interim director of USGS: Nichols leaves EPA: NRC Commissioner Rogers` term expires; NRC: CA ``Well-Quantified`` to license Ward Valley facility; EPA objects to state permit for Louisiana facility; Petitions submitted to EPA oppose Shintech permits; ECOS draft recommendations re Enviro programs; Legislation introduced to prohibit spent fuel shipments to the Goshutes; and HLW legislation ready for floor action.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-09-01T23:59:59.000Z

36

Review of private sector and Department of Energy treatment, storage, and disposal capabilities for low-level and mixed low-level waste  

SciTech Connect (OSTI)

Private sector capacity for treatment, storage, and disposal (TSD) of various categories of radioactive waste has been researched and reviewed for the Idaho National Engineering Laboratory (INEL) by Lockheed Idaho Technologies Company, the primary contractor for the INEL. The purpose of this document is to provide assistance to the INEL and other US Department of Energy (DOE) sites in determining if private sector capabilities exist for those waste streams that currently cannot be handled either on site or within the DOE complex. The survey of private sector vendors was limited to vendors currently capable of, or expected within the next five years to be able to perform one or more of the following services: low-level waste (LLW) volume reduction, storage, or disposal; mixed LLW treatment, storage, or disposal; alpha-contaminated mixed LLW treatment; LLW decontamination for recycling, reclamation, or reuse; laundering of radioactively-contaminated laundry and/or respirators; mixed LLW treatability studies; mixed LLW treatment technology development. Section 2.0 of this report will identify the approach used to modify vendor information from previous revisions of this report. It will also illustrate the methodology used to identify any additional companies. Section 3.0 will identify, by service, specific vendor capabilities and capacities. Because this document will be used to identify private sector vendors that may be able to handle DOE LLW and mixed LLW streams, it was decided that current DOE capabilities should also be identified. This would encourage cooperation between DOE sites and the various states and, in some instances, may result in a more cost-effective alternative to privatization. The DOE complex has approximately 35 sites that generate the majority of both LLW and mixed LLW. Section 4.0 will identify these sites by Operations Office, and their associated LLW and mixed LLW TSD units.

Willson, R.A.; Ball, L.W.; Mousseau, J.D.; Piper, R.B.

1996-03-01T23:59:59.000Z

37

National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

Peggy Hinman

2010-10-01T23:59:59.000Z

38

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory  

SciTech Connect (OSTI)

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Dorries, Alison M [Los Alamos National Laboratory

2010-11-09T23:59:59.000Z

39

Data from studies of previous radioactive waste disposal in Massachusetts Bay  

SciTech Connect (OSTI)

This report presents the results of studies conducted in Massachusetts Bay during 1981 and 1982. Included are data from: (1) a side scan sonar survey of disposal areas in the Bay that was carried out by the National Oceanic and Atmospheric Administration (NOAA) for EPA; (2) Collections of sediment and biota by NOAA for radiochemical analysis by EPA; (3) collections of marketplace seafood samples by the Food and Drug Administration (FDA) for radioanalysis by both FDA and EPA; and (4) a radiological monitoring survey of LLW disposal areas by EPA to determine whether there should be any concern for public health resulting from previous LLW disposals in the Bay.

Curtis, W.R.; Mardis, H.M.

1984-12-01T23:59:59.000Z

40

A Comprehensive Solution for Managing TRU and LLW From Generation to Final Disposition - 13205  

SciTech Connect (OSTI)

A LANL multi-disciplinary team faced the challenge of building and delivering a waste information system capable of managing radioactive, hazardous, and industrial waste from cradle to grave. The result is the Waste Compliance and Tracking System (WCATS) a flexible, adaptive system that has allowed LANL to consolidate its legacy applications into one system, and leverage the advantages of managing all waste types within a single scalable enterprise application. Key functionality required for robust waste operations, include: waste characterization, waste identification, transportation, inventory management, waste processing, and disposal. In order to maintain data quality, field operations such as waste identification, surveillance checklists, wall-to-wall inventory assessments, waste transfers, shipment pickup and receipt, and simple consolidation operations are captured by the operator or technician using mobile computers. Work flow is managed via end-user defined work paths, to ensure that unit operations are performed in the correct order. Regulatory compliance reports and algorithms are provided to support typical U.S. EPA, DOT, NRC, and DOE requirements, including the EPA hazardous waste manifest, NRC LLW manifest, DOE nuclear material at risk, RCRA TSDF inventory rules, and so forth. The WCATS application has allowed LANL to migrate and consolidate its disparate legacy applications. The design and implementation is generalized so that facility owners can customize the user interface, setup facilities and unit operations (i.e., treatment, storage, disposal, characterization, and administrative), define inventory compliance rules, and establish custom work flow requirements. (authors)

Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)] [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.  

SciTech Connect (OSTI)

Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

2007-01-01T23:59:59.000Z

42

WRAP low level waste (LLW) glovebox operational test report  

SciTech Connect (OSTI)

The Low Level Waste (LLW) Process Gloveboxes are designed to: receive a 55 gallon drum in an 85 gallon overpack in the Entry glovebox (GBIOI); and open and sort the waste from the 55 gallon drum, place the waste back into drum and relid in the Sorting glovebox (GB 102). In addition, waste which requires further examination is transferred to the LLW RWM Glovebox via the Drath and Schraeder Bagiess Transfer Port (DO-07-201) or sent to the Sample Transfer Port (STC); crush the drum in the Supercompactor glovebox (GB 104); place the resulting puck (along with other pucks) into another 85 gallon overpack in the Exit glovebox (GB 105). The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved from the entry glovebox to the exit glovebox, the Operator will track an items location using a barcode reader and enter any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolution`s (described below) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

Kersten, J.K.

1998-02-19T23:59:59.000Z

43

Low-level radioactive waste disposal operations at Los Alamos National Laboratory  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) generates Low-Level Radioactive Waste (LLW) from various activities: research and development, sampling and storage of TRU wastes, decommissioning and decontamination of facilities, and from LANL`s major role in stockpile stewardship. The Laboratory has its own active LLW disposal facility located at Technical Area 54, Area G. This paper will identify the current operations of the facility and the issues pertaining to operating a disposal facility in today`s compliance and cost-effective environment.

Stanford, A.R.

1997-02-01T23:59:59.000Z

44

LLW Forum meeting report, April 18--19, 1991  

SciTech Connect (OSTI)

The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently- operating low-level radioactive waste facilities. This quarterly meeting was held on April 18-19, 1991.

NONE

1991-12-31T23:59:59.000Z

45

LLW Forum meeting report, October 20--22, 1997  

SciTech Connect (OSTI)

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20--22, 1997. Twenty-six Forum Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Discussion with NRC Commissioner McGaffigan; Regulatory issues session; Executive session; LLW forum business session; DOE low-level waste management program; Transportation of radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE`s strategy for waste management; Relicensing Envirocare; Draft agreement for uniform application of manifesting procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February 1998; Resolutions; and Attendance.

Norris, C.; Brown, H. [eds.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-12-31T23:59:59.000Z

46

DOE Selects Two Contractors for Multiple-Award Waste Disposal Contract |  

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

Two Contractors for Multiple-Award Waste Disposal Two Contractors for Multiple-Award Waste Disposal Contract DOE Selects Two Contractors for Multiple-Award Waste Disposal Contract April 12, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) awarded two fixed price unit rate Indefinite Delivery/Indefinite Quantity (ID/IQ) multiple-award contracts for the permanent disposal of Low-Level Waste (LLW) and Mixed-Low Level Waste (MLLW) today to EnergySolutions, LLC and Waste Control Specialists, LLC. The goal of these contracts is to establish a vehicle that allows DOE sites to place timely, competitive and cost-effective task orders for the permanent disposal of: Class A, B, and C LLW and MLLW 11e(2) byproduct material Technology Enhanced Naturally Occurring Radioactive Material

47

Justification Of The Use Of Boreholes For Disposal Of Sealed Radiological Sources  

SciTech Connect (OSTI)

Soon there will be only 14 states in two compacts that are able to dispose of Low Level Waste (LLW): the Northwest and Rocky Mountain compact with disposal options in Richland, Washington, and the Atlantic compact with disposal options in Barnwell, South Carolina. How do states not in one of the two compacts dispose of their LLW? The Off-Site Source Recovery Project can take possession and dispose of some of the unwanted transuranic sources at the Waste Isolation Pilot Plant (WIPP). However, there will be no path forward for states outside of the two compacts for disposal of their non-transuranic LLW. A solution that has been much discussed, debated and researched, but has not been put into wide scale practice, is the borehole disposal concept. It is the author's position that companies that drill and explore for oil have been disposing of sources in borehole-like structures for years. It should be noted that these companies are not purposely disposing of these sources, but the sources are irretrievable and must be abandoned. Additionally, there are Nuclear Regulatory Commission (NRC) regulations that must be followed to seal the well that contains the lost and abandoned source. According to the NRC Event Notification Reports database, there were a minimum of 29 reports of lost and abandoned sources in oil wells between December 1999 and October 2006. The sources were lost at depths between 2,018-18,887 feet, or 600-5,750 meters. The companies that are performing explorations with the aid of sealed radiological sources must follow regulation 10 CFR Part 39. Subsection 15 outlines the procedures that must be followed if sources are determined to be irretrievable and abandoned in place. If the NRC allows and has regulations in place for oil companies, why can't states and/or companies be allowed to dispose of LLW in a similar fashion?

Zarling, John [Los Alamos National Laboratory; Johnson, Peter [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

48

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities  

SciTech Connect (OSTI)

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country`s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today`s standards. This report summarizes each site`s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US.

Birk, S.M.

1997-10-01T23:59:59.000Z

49

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

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

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

50

DOE to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal  

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

to Weigh Alternatives for Greater Than Class C Low-Level Waste to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal DOE to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal July 20, 2007 - 2:55pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that it will evaluate disposal options for Greater Than Class C (GTCC) low-level radioactive waste (LLW) generated from the decommissioning of nuclear power plants, medical activities and nuclear research. DOE delivered to the Federal Register this week a Notice of Intent (NOI) to prepare an Environmental Impact Statement (EIS), which will evaluate how and where to safely dispose of GTCC LLW that is currently stored at commercial nuclear power plants and other generator sites across the country. The Energy Policy Act of 2005 requires DOE to report to Congress on its evaluation of

51

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

2009-03-01T23:59:59.000Z

52

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

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

4 4 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-4 i (and ii) DRAFT XX-XX-XX LLW Maintenance Guide Revision 0, XX-XX-XX Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3.1 Objectives . . . . . . . . . . . . . . . . . . . . . . . . .

53

An Update On Waste Control Specialists' 2004 License Application For Safe Disposal Of Class A, B, and C Low-Level Radioactive Waste In Texas  

SciTech Connect (OSTI)

On December 10, 2007, Waste Control Specialists LLC (WCS) received notification that the Executive Director of the Texas Commission on Environmental Quality (TCEQ) had prepared an interim draft license and made a preliminary decision that it met all statutory and regulatory requirements for safe disposal of low-level radioactive waste (LLW) at the WCS' site in Texas. Pursuant to this interim draft license, WCS will be authorized to dispose Class A, B, and C LLW in two enhanced near-surface landfills at WCS' 5.4-square-kilometer (1,338-acre) treatment, storage, and disposal (TSD) site in Andrews County, Texas (Fig. 1). One landfill will be dedicated to LLW generated within the member/party states of the Texas Compact (Texas and Vermont), while the other will be dedicated to LLW generated by the federal government. The calculated annual peak dose to the maximally exposed member of the general public, i.e., an adjacent resident, from any of the proposed LLW-disposal landfills occurs approximately 36,400 years after closure and is 0.034 milli-sievert (mSv) (3.4 milli-rem (mrem)), which is less than 14 percent of the applicable regulatory limit of 25 mSv (25 mrem). The draft license will be published in February 2008, which will be followed by 12 months of public hearings, and three months for preparation of the final license. Based on this schedule, the final license is due in May 2009. When opened, the WCS site will achieve a national milestone; it will be the first new Compact LLW-disposal site in the USA to open under the Low-Level Radioactive Waste Policy Act of 1980, as amended in 1985. (authors)

Baltzer, R.; Eriksson, L. [Waste Control Specialists LLC, Three Lincoln Centre, Dallas, Texas (United States)

2008-07-01T23:59:59.000Z

54

Replacement Capability for Disposal of Remote-Handled Low-Level Waste Generated at the Department of Energys Idaho Site  

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

Environmental Assessment Environmental Assessment for the Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the Department of Energy's Idaho Site August 2011 DOE/EA-1793 Draft Environmental Assessment for the Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the Department of Energy's Idaho Site August 2011 v EXECUTIVE SUMMARY The U.S. Department of Energy (DOE) proposes to provide replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Historically, INL has disposed of this LLW onsite. However, the existing disposal area located within the INL Radioactive Waste Management Complex will undergo

55

Operating Experience and Lessons Learned in the Use of Soft-Sided Packaging for Transportation and Disposal of Low Activity Radioactive Waste  

SciTech Connect (OSTI)

This paper describes the operating experience and lessons learned at U.S. Department of Energy (DOE) sites as a result of an evaluation of potential trailer contamination and soft-sided packaging integrity issues related to the disposal of low-level and mixed low-level (LLW/MLLW) radioactive waste shipments. Nearly 4.3 million cubic meters of LLW/MLLW will have been generated and disposed of during fiscal year (FY) 2010 to FY 2015—either at commercial disposal sites or disposal sites owned by DOE. The LLW/MLLW is packaged in several different types of regulatory compliant packaging and transported via highway or rail to disposal sites safely and efficiently in accordance with federal, state, and local regulations and DOE orders. In 1999, DOE supported the development of LLW containers that are more volumetrically efficient, more cost effective, and easier to use as compared to metal or wooden containers that existed at that time. The DOE Idaho National Engineering and Environmental Laboratory (INEEL), working in conjunction with the plastic industry, tested several types of soft-sided waste packaging systems that meet U.S. Department of Transportation requirements for transport of low specific activity and surface contaminated objects. Since then, soft-sided packaging of various capacities have been used successfully by the decontamination and decommissioning (D&D) projects to package, transport, and dispose D&D wastes throughout the DOE complex. The joint team of experts assembled by the Energy Facility Contractors Group from DOE waste generating sites, DOE and commercial waste disposal facilities, and soft-sided packaging suppliers conducted the review of soft-sided packaging operations and transportation of these packages to the disposal sites. As a result of this evaluation, the team developed several recommendations and best practices to prevent or minimize the recurrences of equipment contamination issues and proper use of soft-sided packaging for transport and disposal of waste.

Kapoor, A. [DOE; Gordon, S. [NSTec; Goldston, W. [Energy Solutions

2013-07-08T23:59:59.000Z

56

Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds  

SciTech Connect (OSTI)

This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance objectives are applicable to the disposal of DOE-generated LLW at any DOE-operated site after the finalization of the order in September 1988. At the Hanford Site, DOE, Richland Operations Office (RL) has issued a site-specific supplement to DOE Order 5820.2A, DOE-RL 5820.2A (DOE 1993), which provides additiona I ce objectives that must be satisfied.

Wood, M.I.; Khaleel, R.; Rittmann, P.D.; Lu, A.H.; Finfrock, S.H.; DeLorenzo, T.H. [Westinghouse Hanford Co., Richland, WA (United States); Serne, R.J.; Cantrell, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01T23:59:59.000Z

57

Septage Disposal, Licensure (Montana)  

Broader source: Energy.gov [DOE]

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

58

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

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

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

59

EA-1793: Replacement Capability for Disposal of Remote-handled Low-level  

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

793: Replacement Capability for Disposal of Remote-handled 793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site Summary This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Public Comment Opportunities Submit Comments to: Mr. Chuck Ljungberg 1955 Fremont Avenue, Mailstop 1216 Idaho Falls, ID 83415 Electronic mail: rhllwea@id.doe.gov Documents Available for Download December 21, 2011 EA-1793: Finding of No Significant Impact Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive

60

Format and Content Guide for DOE Low-Level Waste Disposal Facility  

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

2 2 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-2 i DRAFT XX-XX-XX LLW PA and CA Format and Content Guide Revision 0, XX-XX-XX Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS List of Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v List of Acronyms and Abbreviations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v PART A: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Note: This page contains sample records for the topic "wds llw disposal" 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

Geochemical studies of commercial low-level radioactive waste disposal sites  

SciTech Connect (OSTI)

The results of source term characterization studies for the commercially operated low-level waste (LLW) disposal sites located in the eastern United States are used to provide an understanding of the importance of hydrological and geochemical factors in controlling the mechanics of leachate formation, evolution of leachate compositions, microbial degradation of organic waste and development of anoxia in the trenches, and the nature and extent of leaching of waste materials. The varying degrees of the intensity of these processes, as determined by the different site characteristics, are clearly reflected in the contrasting leachate geochemistries of Maxey Flats and West Valley trenches, as compared to those of Barnwell and Sheffield trenches. These are important geochemical considerations which not only define LLW source terms but also shed light on the nature and extent of geochemical changes that are likely to occur along a redox gradient outside of the trench environment.

Dayal, R.; Pietrzak, R.F.; Clinton, J.H.

1986-06-01T23:59:59.000Z

62

Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

Boyd D. Christensen

2012-05-01T23:59:59.000Z

63

Control of water infiltration into near surface low-level waste disposal units. Final report on field experiments at a humid region site, Beltsville, Maryland  

SciTech Connect (OSTI)

This study`s objective was to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work was carried out in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (70 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration were investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management.

Schulz, R.K.; Ridky, R.W.; O`Donnell, E.

1997-09-01T23:59:59.000Z

64

20 - Nuclear Waste Disposal  

Science Journals Connector (OSTI)

Disposal options are outlined, including geological and near-surface disposal. Alternative disposal options are briefly considered. The multi-barrier system is described, including the natural geological barrier and the engineered barrier system. The roles of both EBS and NGB are discussed. Worldwide disposal experience is reviewed and acceptance criteria for disposal are analysed.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

65

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513  

SciTech Connect (OSTI)

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Mohamed, Yasser T. [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Laboratories and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)

2013-07-01T23:59:59.000Z

66

Use of a Shielded High Resolution Gamma Spectrometry System to Segregate LLW from Contact Handleable ILW Containing Plutonium - 13046  

SciTech Connect (OSTI)

Dounreay Site Restoration Limited (DSRL) have a number of drums of solid waste that may contain Plutonium Contaminated Material. These are currently categorised as Contact Handleable Intermediate Level Waste (CHILW). A significant fraction of these drums potentially contain waste that is in the Low Level Waste (LLW) category. A Canberra Q2 shielded high resolution gamma spectrometry system is being used to quantify the total activity of drums that are potentially in the LLW category in order to segregate those that do contain LLW from CHILW drums and thus to minimise the total volume of waste in the higher category. Am-241 is being used as an indicator of the presence of plutonium in the waste from its strong 59.54 keV gamma-ray; a knowledge of the different waste streams from which the material originates allows a pessimistic waste 'fingerprint' to be used in order to determine an upper limit to the activities of the weak and non-gamma-emitting plutonium and associated radionuclides. This paper describes the main features of the high resolution gamma spectrometry system being used by DSRL to perform the segregation of CHILW and LLW and how it was configured and calibrated using the Canberra In-Situ Object Counting System (ISOCS). It also describes how potential LLW drums are selected for assay and how the system uses the existing waste stream fingerprint information to determine a reliable upper limit for the total activity present in each measured drum. Results from the initial on-site commissioning trials and the first measurements of waste drums using the new monitor are presented. (authors)

Lester, Rosemary; Wilkins, Colin [Canberra UK Ltd, Unit 1 B528.1, Harwell Science Campus, Oxfordshire OX11 0DF (United Kingdom)] [Canberra UK Ltd, Unit 1 B528.1, Harwell Science Campus, Oxfordshire OX11 0DF (United Kingdom); Chard, Patrick [Canberra UK Ltd, Forss Business and Technology park, Thurso, Caithness KW14 7UZ (United Kingdom)] [Canberra UK Ltd, Forss Business and Technology park, Thurso, Caithness KW14 7UZ (United Kingdom); Jaederstroem, Henrik; LeBlanc, Paul; Mowry, Rick [Canberra Industries, Inc., 800 Research Parkway, Meriden, Connecticut, 06450 (United States)] [Canberra Industries, Inc., 800 Research Parkway, Meriden, Connecticut, 06450 (United States); MacDonald, Sanders; Gunn, William [Dounreay Site Restoration Limited, Dounreay, Thurso, Caithness, KW14 7TZ (United Kingdom)] [Dounreay Site Restoration Limited, Dounreay, Thurso, Caithness, KW14 7TZ (United Kingdom)

2013-07-01T23:59:59.000Z

67

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada  

SciTech Connect (OSTI)

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

NSTec Environmental Restoration

2009-07-31T23:59:59.000Z

68

Time of Compliance for Disposal of Low-Level Radioactive Waste  

Broader source: Energy.gov [DOE]

Time of Compliance for Disposal of Low-Level Radioactive Waste Roger Seitz*, Savannah River National Laboratory ; Andrew Wallo, U.S. Department of Energy Abstract: The United States Department of Energy (DOE) has more than 25 years of experience conducting and overseeing performance assessments (PAs) for low-level waste (LLW) and mixed LLW from on-going operations, decommissioning and environmental restoration activities. DOE considers performance assessments (PAs) as one contributor to defense-in-depth arguments for safe disposal of LLW. In a risk-informed, performance-based approach to PA, it is necessary to address the time frames over which PA results are sufficiently meaningful to be used for a strict determination of compliance (i.e., a time of compliance). DOE has taken the position that, for near-surface disposal, 1,000 years is an appropriate time of compliance, but the potential for peak impacts after that time need to also be addressed. From an implementation perspective, 1,000 years is considered as a transition in the interpretation of results from use as a quantitative, decision-maker (“yes or no” compliance) to an increasingly qualitative role informing decisions in conjunction with all of the other contributors to the safety basis. This position is based on a number of technical and policy considerations with a major factor being the decreasing quantitative meaningfulness of PA results in the context of the increasing speculation and uncertainties as time frames on the order of hundreds and thousands of years are considered. The technical and policy considerations for the DOE position and considerations for implementation will be discussed.

69

Defense-in-Depth, How Department of Energy Implements Radiation Protection in Low Level Waste Disposal  

Broader source: Energy.gov [DOE]

Defense-in-Depth, How Department of Energy Implements Radiation Protection in Low Level Waste Disposal Linda Suttora*, U.S. Department of Energy ; Andrew Wallo, U.S. Department of Energy Abstract: The United States Department of Energy (DOE) has adopted an integrated protection system for the safety of radioactive waste disposal similar to the concept of a safety case that is used internationally. This approach has evolved and been continuously improved as a result of many years of experience managing low-level waste (LLW) and mixed LLW from on-going operations, decommissioning and environmental restoration activities at 29 sites around the United States. The integrated protection system is implemented using a defense-in-depth approach taking into account the combination of natural and engineered barriers, performance objectives, long-term risk assessments, maintenance of those assessments based on the most recent information to ascertain continued compliance, site-specific waste acceptance criteria based on the risk assessment and a commitment to continuous improvement. There is also a strong component of stakeholder involvement. The integrated protection system approach will be discussed to demonstrate the commitment to safety for US DOE disposal.

70

Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

David Duncan

2011-05-01T23:59:59.000Z

71

Waste Disposal | Department of Energy  

Office of Environmental Management (EM)

Disposal Waste Disposal Trucks transport debris from Oak Ridges cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility....

72

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site  

SciTech Connect (OSTI)

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01T23:59:59.000Z

73

slc_disposal.cdr  

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

74

Waste Disposal (Illinois)  

Broader source: Energy.gov [DOE]

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

75

Performance assessment methodology and preliminary results for low-level radioactive waste disposal in Taiwan.  

SciTech Connect (OSTI)

Sandia National Laboratories (SNL) and Taiwan's Institute for Nuclear Energy Research (INER) have teamed together to evaluate several candidate sites for Low-Level Radioactive Waste (LLW) disposal in Taiwan. Taiwan currently has three nuclear power plants, with another under construction. Taiwan also has a research reactor, as well as medical and industrial wastes to contend with. Eventually the reactors will be decomissioned. Operational and decommissioning wastes will need to be disposed in a licensed disposal facility starting in 2014. Taiwan has adopted regulations similar to the US Nuclear Regulatory Commission's (NRC's) low-level radioactive waste rules (10 CFR 61) to govern the disposal of LLW. Taiwan has proposed several potential sites for the final disposal of LLW that is now in temporary storage on Lanyu Island and on-site at operating nuclear power plants, and for waste generated in the future through 2045. The planned final disposal facility will have a capacity of approximately 966,000 55-gallon drums. Taiwan is in the process of evaluating the best candidate site to pursue for licensing. Among these proposed sites there are basically two disposal concepts: shallow land burial and cavern disposal. A representative potential site for shallow land burial is located on a small island in the Taiwan Strait with basalt bedrock and interbedded sedimentary rocks. An engineered cover system would be constructed to limit infiltration for shallow land burial. A representative potential site for cavern disposal is located along the southeastern coast of Taiwan in a tunnel system that would be about 500 to 800 m below the surface. Bedrock at this site consists of argillite and meta-sedimentary rocks. Performance assessment analyses will be performed to evaluate future performance of the facility and the potential dose/risk to exposed populations. Preliminary performance assessment analyses will be used in the site-selection process and to aid in design of the disposal system. Final performance assessment analyses will be used in the regulatory process of licensing a site. The SNL/INER team has developed a performance assessment methodology that is used to simulate processes associated with the potential release of radionuclides to evaluate these sites. The following software codes are utilized in the performance assessment methodology: GoldSim (to implement a probabilistic analysis that will explicitly address uncertainties); the NRC's Breach, Leach, and Transport - Multiple Species (BLT-MS) code (to simulate waste-container degradation, waste-form leaching, and transport through the host rock); the Finite Element Heat and Mass Transfer code (FEHM) (to simulate groundwater flow and estimate flow velocities); the Hydrologic Evaluation of Landfill performance Model (HELP) code (to evaluate infiltration through the disposal cover); the AMBER code (to evaluate human health exposures); and the NRC's Disposal Unit Source Term -- Multiple Species (DUST-MS) code (to screen applicable radionuclides). Preliminary results of the evaluations of the two disposal concept sites are presented.

Arnold, Bill Walter; Chang, Fu-lin (Institute of Nuclear Energy Research, Taiwan); Mattie, Patrick D.; Knowlton, Robert G.; Chuang, W-S (Institute of Nuclear Energy Research, Taiwan); Chi, L-M (Institute of Nuclear Energy Research, Taiwan); Jow, Hong-Nian; Tien, Norman C. (Institute of Nuclear Energy Research, Taiwan); Ho, Clifford Kuofei

2006-02-01T23:59:59.000Z

76

Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans  

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

3 3 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans U.S. DEPARTMENT OF ENERGY DOE G 435.1-3 i DRAFT XX-XX-XX LLW Closure Plan Format and Content Guide Revision 0, XX-XX-XX Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans CONTENTS PART A: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1. PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2. ORGANIZATION OF DOCUMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3. BACKGROUND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.1 Closure Objectives and Relationship to Other Programs . . . . . . . . . . . . . . . . . . . . . . 2 3.2

77

Material Disposal Areas  

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

78

Disposal Information - Hanford Site  

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

Email Page | Print Print Page |Text Increase Font Size Decrease Font Size Disposal of Radioactive Waste at Hanford The Hanford Site operates lined, RCRA Subtitle C land...

79

Performance assessment for the class L-II disposal facility  

SciTech Connect (OSTI)

This draft radiological performance assessment (PA) for the proposed Class L-II Disposal Facility (CIIDF) on the Oak Ridge Reservation (ORR) has been prepared to demonstrate compliance with the requirements of the US Department of Energy Order 5820.2A. This PA considers the disposal of low-level radioactive wastes (LLW) over the operating life of the facility and the long-term performance of the facility in providing protection to public health and the environment. The performance objectives contained in the order require that the facility be managed to accomplish the following: (1) Protect public health and safety in accordance with standards specified in environmental health orders and other DOE orders. (2) Ensure that external exposure to the waste and concentrations of radioactive material that may be released into surface water, groundwater, soil, plants, and animals results in an effective dose equivalent (EDE) that does not exceed 25 mrem/year to a member of the public. Releases to the atmosphere shall meet the requirements of 40 CFR Pt. 61. Reasonable effort should be made to maintain releases of radioactivity in effluents to the general environment as low as reasonably achievable. (1) Ensure that the committed EDEs received by individual who inadvertently may intrude into the facility after the loss of active institutional control (100 years) will not exceed 100 mrem/year for continuous exposure of 500 mrem for a single acute exposure. (4) Protect groundwater resources, consistent with federal, state, and local requirements.

NONE

1997-03-01T23:59:59.000Z

80

Disposal of boiler ash  

SciTech Connect (OSTI)

As more boilers are converted from oil to solid fuels such as coal, the quantity of ash requiring disposal will increase dramatically. The factors associated with the development of land disposal systems for ash landfills are presented, including ash characterization, site selection procedures, design parameters, and costs.

Atwell, J.S.

1981-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Municipal Sludge disposal economics  

Science Journals Connector (OSTI)

Municipal Sludge disposal economics ... Atmospheric emissions of elements on particles from the Parkway sewage-sludge incinerator ... Atmospheric emissions of elements on particles from the Parkway sewage-sludge incinerator ...

Jerry Jones; David Bomberger, Jr.; F Lewis; Joel Jacknow

1977-01-01T23:59:59.000Z

82

Radiological performance assessment for the E-Area Vaults Disposal Facility  

SciTech Connect (OSTI)

The E-Area Vaults (EAVs) located on a 200 acre site immediately north of the current LLW burial site at Savannah River Site will provide a new disposal and storage site for solid, low-level, non-hazardous radioactive waste. The EAV Disposal Facility will contain several large concrete vaults divided into cells. Three types of structures will house four designated waste types. The Intermediate Level Non-Tritium Vaults will receive waste radiating greater than 200 mR/h at 5 cm from the outer disposal container. The Intermediate Level Tritium Vaults will receive waste with at least 10 Ci of tritium per package. These two vaults share a similar design, are adjacent, share waste handling equipment, and will be closed as one facility. The second type of structure is the Low Activity Waste Vaults which will receive waste radiating less than 200 mR/h at 5 cm from the outer disposal container and containing less than 10 Ci of tritium per package. The third facility, the Long Lived Waste Storage Building, provides covered, long term storage for waste containing long lived isotopes. Two additional types of disposal are proposed: (1) trench disposal of suspect soil, (2) naval reactor component disposal. To evaluate the long-term performance of the EAVs, site-specific conceptual models were developed to consider: (1) exposure pathways and scenarios of potential importance; (2) potential releases from the facility to the environment; (3) effects of degradation of engineered features; (4) transport in the environment; (5) potential doses received from radionuclides of interest in each vault type.

Cook, J.R.; Hunt, P.D. [Westinghouse Savannah River Co., Aiken, SC (United States)

1994-04-15T23:59:59.000Z

83

Hazardous Waste Disposal Sites (Iowa)  

Broader source: Energy.gov [DOE]

These sections contain information on fees and monitoring relevant to operators of hazardous waste disposal sites.

84

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark  

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

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

85

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

86

Enhancing RESRAD-OFFSITE for Low Level Waste Disposal Facility Performance Assessment  

Broader source: Energy.gov [DOE]

Enhancing RESRAD-OFFSITE for Low Level Waste Disposal Facility Performance Assessment Charley Yu*, Argonne National Laboratory ; Emmanuel Gnanapragasam, Argonne National Laboratory; Carlos Corredor, U.S. Department of Energy; W. Alexander Williams, U.S. Department of Energy Abstract: The RESRAD-OFFSITE code was developed to evaluate the radiological dose and excess cancer risk to an individual who is exposed while located within or outside the area of initial (primary) contamination. The primary contamination, which is the source of all releases modeled by the code, is assumed to be a layer of soil. The code considers the release of contamination from the source to the atmosphere, to surface runoff, and to groundwater. The radionuclide leaching was modeled as a first order (without transport) release using radionuclide distribution coefficient and infiltration rate calculated from water balance (precipitation, surface runoff, evapotranspiration, etc.). Recently, a new source term model was added the RESRAD-OFFSITE code so that it can be applied to the evaluation of Low Level Waste (LLW) disposal facility performance assessment. This new improved source term model include (1) first order with transport, (2) equilibrium desorption (rinse) release, and (3) uniform release (constant dissolution). With these new source release options, it is possible to simulate both uncontainerized (soil) contamination and containerized (waste drums) contamination. A delay time in the source release was also added to the code. This allows modeling the LLW container degradation as a function of time. The RESRAD-OFFSITE code also allows linking to other codes using improved flux and concentration input options. Additional source release model such as diffusion release may be added later. In addition, radionuclide database with 1252 radionuclides (ICRP 107) and the corresponding dose coefficients (DCFPAK 3.02) and the Department of Energy’s new gender- and age-averaged Reference Person dose coefficients (DOE-STD-1196-2011) which is based on the US census data will be added to the next version of RESRAD-OFFSITE code.

87

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

88

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

89

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

90

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

91

Disposable Electrochemical Immunosensor Diagnosis Device Based...  

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

Disposable Electrochemical Immunosensor Diagnosis Device Based on Nanoparticle Probe and Immunochromatographic Strip. Disposable Electrochemical Immunosensor Diagnosis Device Based...

92

Oxidation-induced geochemical changes in trench leachates from the Maxey Flats low-level radioactive waste disposal site  

SciTech Connect (OSTI)

A knowledge of extra-trench processes related to oxidation-induced geochemical changes that are likely to occur when iron-rich, anoxic trench waters encounter an oxidizing environment along a redox gradient is essential for modeling radionuclide transport at low-level waste (LLW) disposal sites. The results of laboratory oxidation experiments on several trench leachates from the Maxey Flats site show that, upon oxidation, a series of geochemical changes were initiated that resulted in a drastically different solute geochemistry, involving oxidation of ferrous iron and subsequent precipitation of ferric oxyhydroxide, changes in alkalinity and acidity, a drastic increase in redox potential (Eh), and generally relatively little change in the concentrations of /sup 60/Co, /sup 137/Cs, and /sup 85/Sr in solution. The observations made in this study have important geochemical implications for the modeling of LLW sites in that the source term as an input parameter cannot be assumed to be constant, both spatially and temporally. The acid-generating potential and buffering capacity of an anoxic source term are important geochemical controls that maintain a balance between acidity and alkalinity and largely determine the nature and extent of oxidation-induced geochemical changes likely to occur along a redox gradient. The presence of organic chelating agents can alter the source term geochemistry to such an extent that authigenic ferric oxyhydroxide, which represents a geochemical discontinuity at the redox interface along leachate migration paths, proves to be a relatively ineffective sink for radionuclides.

Dayal, R.; Pietrzak, R.F.; Clinton, J.H.

1986-02-01T23:59:59.000Z

93

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

94

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

95

The incandescent disposal system  

SciTech Connect (OSTI)

The electrotechnology device being introduced to the low-level waste market is an Incandescent Disposal System (IDS) for volume reduction and vitrification. The process changes the composition of the waste material, usually long molecular chains, into simple molecules and elements. It renders the volume of low-level wastes to a manageable solid vitrified residue, carbon black, and a water discharge. The solid material, which has been vitrified if silica is introduced into the waste stream, is an ideal inert filler. The carbon black is non-leaching and is readily available for vitrification as it comes out of the IDS.

Smith, R.G.

1996-03-01T23:59:59.000Z

96

Converter waste disposal study  

SciTech Connect (OSTI)

The importance of waste management and disposal issues to the converting and print industries is demonstrated by the high response rate to a survey of US and Canadian converters and printers. The 30-item questionnaire measured the impact of reuse, recycling, source reduction, incineration, and landfilling on incoming raw-material packaging, process scrap, and waste inks, coatings, and adhesives. The results indicate that significant amounts of incoming packaging materials are reused in-house or through supplier take-back programs. However, there is very little reuse of excess raw materials and process scrap, suggesting the need for greater source reduction within these facilities as the regulatory climate becomes increasingly restrictive.

Schultz, R.B. (RBS Technologies, Inc., Skokie, IL (United States))

1993-07-01T23:59:59.000Z

97

Enhancing RESRAD-OFFSITE for Low Level Waste Disposal Facility Performance Assessment  

Broader source: Energy.gov [DOE]

Abstract: The RESRAD-OFFSITE code was developed to evaluate the radiological dose and excess cancer risk to an individual who is exposed while located within or outside the area of initial (primary) contamination. The primary contamination, which is the source of all releases modeled by the code, is assumed to be a layer of soil. The code considers the release of contamination from the source to the atmosphere, to surface runoff, and to groundwater. The radionuclide leaching was modeled as a first order (without transport) release using radionuclide distribution coefficient and infiltration rate calculated from water balance (precipitation, surface runoff, evapotranspiration, etc.). Recently, a new source term model was added the RESRAD-OFFSITE code so that it can be applied to the evaluation of Low Level Waste (LLW) disposal facility performance assessment. This new improved source term model include (1) first order with transport, (2) equilibrium desorption (rinse) release, and (3) uniform release (constant dissolution). With these new source release options, it is possible to simulate both uncontainerized (soil) contamination and containerized (waste drums) contamination. A delay time in the source release was also added to the code. This allows modeling the LLW container degradation as a function of time. The RESRAD-OFFSITE code also allows linking to other codes using improved flux and concentration input options. Additional source release model such as diffusion release may be added later. In addition, radionuclide database with 1252 radionuclides (ICRP 107) and the corresponding dose coefficients (DCFPAK 3.02) and the Department of Energy’s new gender- and age-averaged Reference Person dose coefficients (DOE-STD-1196-2011) which is based on the US census data will be added to the next version of RESRAD-OFFSITE code

98

Pioneering Nuclear Waste Disposal  

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

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

99

Pioneering Nuclear Waste Disposal  

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

100

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network [OSTI]

Laboratory Waste Disposal HAZARDOUS GLASS Items that could cut or puncture skin or trash- can without any treatment. Hazardous Glass and Plastic: Items that can puncture, cut or scratch if disposed of in normal trash containers. Pasteur pipettes Other pipettes and tips (glass or plastic) Slides and cover

Sheridan, Jennifer

Note: This page contains sample records for the topic "wds llw disposal" 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

Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3  

SciTech Connect (OSTI)

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. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

2013-07-29T23:59:59.000Z

102

Recommendation 212: Evaluate additional storage and disposal...  

Office of Environmental Management (EM)

212: Evaluate additional storage and disposal options Recommendation 212: Evaluate additional storage and disposal options The ORSSAB encourages DOE to evaluate additional storage...

103

Transmittal Memo for Disposal Authorization Statement | Department...  

Office of Environmental Management (EM)

Disposal Facility Federal Review Group (LFRG) has conducted a review of the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) 2009 performance assessment (PA) in...

104

ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS...  

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

4: PROPERTY DISPOSAL RECORDS (Revision 2) ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) These records pertain to the sales by agencies of real and...

105

PROPERTY DISPOSAL RECORDS | Department of Energy  

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

PROPERTY DISPOSAL RECORDS PROPERTY DISPOSAL RECORDS These records pertain to the sales by agencies of real and personal property surplus to the needs of the Government PROPERTY...

106

Optimization of Waste Disposal - 13338  

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

107

Evaluation of Groundwater Impacts to Support the National Environmental Policy Act Environmental Assessment for the INL Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

The groundwater impacts have been analyzed for the proposed RH-LLW disposal facility. A four-step analysis approach was documented and applied. This assessment compared the predicted groundwater ingestion dose to the more restrictive of either the 25 mrem/yr all pathway dose performance objective, or the maximum contaminant limit performance objective. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives. The analysis was prepared to support the NEPA-EA for the top two ranking of the proposed RH-LLW sites. As such, site-specific conditions were incorporated for each set of results generated. These site-specific conditions were included to account for the transport of radionuclides through the vadose zone and through the aquifer at each site. Site-specific parameters included the thickness of vadose zone sediments and basalts, moisture characteristics of the sediments, and aquifer velocity. Sorption parameters (Kd) were assumed to be very conservative values used in Track II analysis of CERCLA sites at INL. Infiltration was also conservatively assumed to represent higher rates corresponding to disturbed soil conditions. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives.

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

2011-08-01T23:59:59.000Z

108

Evaluation of Groundwater Impacts to Support the National Environmental Policy Act Environmental Assessment for the INL Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

The groundwater impacts have been analyzed for the proposed RH-LLW disposal facility. A four-step analysis approach was documented and applied. This assessment compared the predicted groundwater ingestion dose to the more restrictive of either the 25 mrem/yr all pathway dose performance objective, or the maximum contaminant limit performance objective. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives. The analysis was prepared to support the NEPA-EA for the top two ranking of the proposed RH-LLW sites. As such, site-specific conditions were incorporated for each set of results generated. These site-specific conditions were included to account for the transport of radionuclides through the vadose zone and through the aquifer at each site. Site-specific parameters included the thickness of vadose zone sediments and basalts, moisture characteristics of the sediments, and aquifer velocity. Sorption parameters (Kd) were assumed to be very conservative values used in Track II analysis of CERCLA sites at INL. Infiltration was also conservatively assumed to represent higher rates corresponding to disturbed soil conditions. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives.

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

2011-12-01T23:59:59.000Z

109

Tank Waste Disposal Program redefinition  

SciTech Connect (OSTI)

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

110

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

111

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers  

SciTech Connect (OSTI)

The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs.

Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

1988-01-01T23:59:59.000Z

112

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network [OSTI]

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

113

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

114

EA-1793: Final Environmental Assessment | Department of Energy  

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

low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Historically, INL has disposed of this LLW onsite at a...

115

Electrochemical Apparatus with Disposable and Modifiable Parts  

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

116

Optimizing High Level Waste Disposal  

SciTech Connect (OSTI)

If society is ever to reap the potential benefits of nuclear energy, technologists must close the fuel-cycle completely. A closed cycle equates to a continued supply of fuel and safe reactors, but also reliable and comprehensive closure of waste issues. High level waste (HLW) disposal in borosilicate glass (BSG) is based on 1970s era evaluations. This host matrix is very adaptable to sequestering a wide variety of radionuclides found in raffinates from spent fuel reprocessing. However, it is now known that the current system is far from optimal for disposal of the diverse HLW streams, and proven alternatives are available to reduce costs by billions of dollars. The basis for HLW disposal should be reassessed to consider extensive waste form and process technology research and development efforts, which have been conducted by the United States Department of Energy (USDOE), international agencies and the private sector. Matching the waste form to the waste chemistry and using currently available technology could increase the waste content in waste forms to 50% or more and double processing rates. Optimization of the HLW disposal system would accelerate HLW disposition and increase repository capacity. This does not necessarily require developing new waste forms, the emphasis should be on qualifying existing matrices to demonstrate protection equal to or better than the baseline glass performance. Also, this proposed effort does not necessarily require developing new technology concepts. The emphasis is on demonstrating existing technology that is clearly better (reliability, productivity, cost) than current technology, and justifying its use in future facilities or retrofitted facilities. Higher waste processing and disposal efficiency can be realized by performing the engineering analyses and trade-studies necessary to select the most efficient methods for processing the full spectrum of wastes across the nuclear complex. This paper will describe technologies being evaluated at Idaho National Laboratory and the facilities we’ve designed to evaluate options and support optimization.

Dirk Gombert

2005-09-01T23:59:59.000Z

117

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

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

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...

118

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

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

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

119

Spent Fuel Disposal Trust Fund (Maine)  

Broader source: Energy.gov [DOE]

Any licensee operating a nuclear power plant in this State shall establish a segregated Spent Nuclear Fuel Disposal Trust Fund in accordance with this subchapter for the eventual disposal of spent...

120

Deep Borehole Disposal Research: Demonstration Site Selection...  

Office of Environmental Management (EM)

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...

Note: This page contains sample records for the topic "wds llw disposal" 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

Generic Argillite/Shale Disposal Reference Case  

E-Print Network [OSTI]

of eastern Devonian gas shale: Society of PetroleumShale Disposal Reference Case August 2014 Borehole activity: Oil and gas

Zheng, Liange

2014-01-01T23:59:59.000Z

122

Environmental waste disposal contracts awarded  

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

123

DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER  

SciTech Connect (OSTI)

The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting the DOE waste canisters and their contents from damage/degradation by the external environment. The disposal containers also interface with the SNF by limiting access of moderator and oxidizing agents to the waste. The disposal containers interface with the Ex-Container System's emplacement drift disposal container supports. The disposal containers interface with the Canister Transfer System, Waste Emplacement System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and remediation of the disposal container.

F. Habashi

1998-06-26T23:59:59.000Z

124

Enhancements to Generic Disposal System Modeling Capabilities...  

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

disposal system modeling and analysis capability that takes advantage of high-performance computing (HPC) environments to simulate the important multi-physics phenomena and...

125

Environmental Restoration Disposal Facility - Hanford Site  

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

Receiving and Processing Facility Waste Sampling and Characterization Facility Waste Treatment Plant Environmental Restoration Disposal Facility Email Email Page | Print Print...

126

Operational Issues at the Environmental Restoration Disposal...  

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

Disposal Facility at Idaho National Laboratory Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Briefing: Summary and Recommendations of EM Landfill Workshop...

127

Finding of No Significant Impact for the Offsite Transportation of Certain Low-Level and Mixed Radioactive Waste from Savannah River Site for Treatment and Disposal at Commercial and Government Facilities, DOE/EA-1308 (02/15/01)  

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

Finding of No Significant Impact Finding of No Significant Impact for the Offsite Transportation of Certain Low-level and Mixed Radioactive Waste from the Savannah River Site for Treatment and Disposal at Commercial and Government Facilities Agency: U. S. Department of Energy Action: Finding of No Significant Impact Summary: The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1308) to analyze the potential environmental impacts associated with the proposed offsite transportation of certain low-level radioactive waste (LLW) and mixed (i.e., hazardous and radioactive) low-level radioactive waste (MLLW) from the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the action is not a major Federal action significantly affecting

128

Plutonium Equivalent Inventory for Belowground Radioactive Waste at the Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Many aspects of the management of this waste are conducted at Technical Area 54 (TA-54); Area G plays a key role in these management activities as the Laboratory's only disposal facility for low-level radioactive waste (LLW). Furthermore, Area G serves as a staging area for transuranic (TRU) waste that will be shipped to the Waste Isolation Pilot Plant for disposal. A portion of this TRU waste is retrievably stored in pits, trenches, and shafts. The radioactive waste disposed of or stored at Area G poses potential short- and long-term risks to workers at the disposal facility and to members of the public. These risks are directly proportional to the radionuclide inventories in the waste. The Area G performance assessment and composite analysis (LANL, 2008a) project long-term risks to members of the public; short-term risks to workers and members of the public, such as those posed by accidents, are addressed by the Area G Documented Safety Analysis (LANL, 2011a). The Documented Safety Analysis uses an inventory expressed in terms of plutonium-equivalent curies, referred to as the PE-Ci inventory, to estimate these risks. The Technical Safety Requirements for Technical Area 54, Area G (LANL, 2011b) establishes a belowground radioactive material limit that ensures the cumulative projected inventory authorized for the Area G site is not exceeded. The total belowground radioactive waste inventory limit established for Area G is 110,000 PE-Ci. The PE-Ci inventory is updated annually; this report presents the inventory prepared for 2011. The approach used to estimate the inventory is described in Section 2. The results of the analysis are presented in Section 3.

French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [WPS: WASTE PROJECTS AND SERVICES

2012-04-18T23:59:59.000Z

129

Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site  

SciTech Connect (OSTI)

In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.

Church, A.; Gordon, J.; Montrose, J. K.

2002-02-26T23:59:59.000Z

130

Used Fuel Disposition Campaign Disposal  

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

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

131

14 - Lubricant use and disposal  

Science Journals Connector (OSTI)

Abstract: Criteria are defined for optimum machine-specific selection of conventional, high-performance and specialty lubricants. Lubrication consolidation is indicated as a means of rationalisation of inventories. Intended use of lubricants may be compromised by oxidation, water and air contamination, additive depletion and accumulation of contaminants, including wear debris, and biological degradation. Strategic oil analysis is described from simple in-shop sensory inspections to primary on-site standard testing and more comprehensive secondary testing methods as an operational maintenance tool for machine and lubricant condition monitoring to estimate remaining lubricant life time and prevent premature machine failure. The disposal of spent lubricants, including waste oil legislation and management, and re-refining technologies, are discussed.

Jan C.J. Bart; Emanuele Gucciardi; Stefano Cavallaro

2013-01-01T23:59:59.000Z

132

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network [OSTI]

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency left intentionally blank.] #12;Prepared for the U.S. Department of Energy PNNL-SA-69994 under Contract DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL

133

Asset Management Equipment Disposal Form -Refrigerant Recovery  

E-Print Network [OSTI]

enters the waste stream with the charge intact (e.g., motor vehicle air conditioners, refrigeratorsAsset Management Equipment Disposal Form - Refrigerant Recovery Safe Disposal Requirements Under refrigeration, cold storage warehouse refrigeration, chillers, and industrial process refrigeration) has to have

Sin, Peter

134

Title II Disposal Sites Annual Report  

Broader source: Energy.gov [DOE]

This report presents the results of long-term surveillance and maintenance activities conducted by the DOE Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements.

135

Tritium waste disposal technology in the US  

SciTech Connect (OSTI)

Tritium waste disposal methods in the US range from disposal of low specific activity waste along with other low-level waste in shallow land burial facilities, to disposal of kilocurie amounts in specially designed triple containers in 65' deep augered holes located in an aird region of the US. Total estimated curies disposed of are 500,000 in commercial burial sites and 10 million curies in defense related sites. At three disposal sites in humid areas, tritium has migrated into the ground water, and at one arid site tritium vapor has been detected emerging from the soil above the disposal area. Leaching tests on tritium containing waste show that tritium in the form of HTO leaches readily from most waste forms, but that leaching rates of tritiated water into polymer impregnated concrete are reduced by as much as a factor of ten. Tests on improved tritium containment are ongoing. Disposal costs for tritium waste are 7 to 10 dollars per cubic foot for shallow land burial of low specific activity tritium waste, and 10 to 20 dollars per cubic foot for disposal of high specific activity waste. The cost of packaging the high specific activity waste is 150 to 300 dollars per cubic foot. 18 references.

Albenesius, E.L.; Towler, O.A.

1983-01-01T23:59:59.000Z

136

Land Management and Disposal | Department of Energy  

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

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

137

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

SciTech Connect (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

138

Low-Level Waste Disposal Facility Federal Review Group Manual...  

Office of Environmental Management (EM)

Low-Level Waste Disposal Facility Federal Review Group Manual Low-Level Waste Disposal Facility Federal Review Group Manual This Revision 3 of the Low-Level Waste Disposal Facility...

139

Salt caverns for oil field waste disposal.  

SciTech Connect (OSTI)

Salt caverns used for oil field waste disposal are created in salt formations by solution mining. When created, caverns are filled with brine. Wastes are introduced into the cavern by pumping them under low pressure. Each barrel of waste injected to the cavern displaces a barrel of brine to the surface. The brine is either used for drilling mud or is disposed of in an injection well. Figure 8 shows an injection pump used at disposal cavern facilities in west Texas. Several types of oil field waste may be pumped into caverns for disposal. These include drilling muds, drill cuttings, produced sands, tank bottoms, contaminated soil, and completion and stimulation wastes. Waste blending facilities are constructed at the site of cavern disposal to mix the waste into a brine solution prior to injection. Overall advantages of salt cavern disposal include a medium price range for disposal cost, large capacity and availability of salt caverns, limited surface land requirement, increased safety, and ease of establishment of individual state regulations.

Veil, J.; Ford, J.; Rawn-Schatzinger, V.; Environmental Assessment; RMC, Consultants, Inc.

2000-07-01T23:59:59.000Z

140

International Collaboration Activities in Different Geologic Disposal Environments  

Broader source: Energy.gov [DOE]

This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign.  To date, UFD’s International Disposal R...

Note: This page contains sample records for the topic "wds llw disposal" 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

Used Fuel Disposition Campaign Disposal Research and Development...  

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

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...

142

A novel nanoparticle-based disposable electrochemical immunosensor...  

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

nanoparticle-based disposable electrochemical immunosensor for diagnosis of exposure to toxic organophosphorus agents. A novel nanoparticle-based disposable electrochemical...

143

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

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

Monticello, Utah, Disposal Cell Cover Monitoring the Performance of an Alternative Landfill Cover at the Monticello, Utah, Uranium Mill Tailings Disposal Site Monitoring the...

144

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

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

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

145

The Salt Defense Disposal Investigations (SDDI)  

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

146

Acquisition, Use, and Disposal of Real Estate  

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

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

147

Policy Issues in Nuclear Waste Disposal  

Science Journals Connector (OSTI)

The Congressional Research Service, in an issue brief on nuclear waste disposal, compactly described a common assessment when it noted that “nuclear waste has sometimes been called the Achilles’ heel of the nu...

2005-01-01T23:59:59.000Z

148

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

149

Available Options for Waste Disposal [and Discussion  

Science Journals Connector (OSTI)

...vitrified high-activity waste in properly selected deep...alternatives to present projects of waste disposal, but rather as...benefits will be different. Long-term storage of either spent fuel or vitrified waste, although not an alternative...

1986-01-01T23:59:59.000Z

150

US nuclear waste: Widespread problem of disposal  

Science Journals Connector (OSTI)

... individual states in the United States to develop facilities for disposal of low-level radioactive waste produced by ... produced by nuclear reactors, industry and biomdical research and treatment. The federal Low-Level ...

Christopher Earl

1984-07-19T23:59:59.000Z

151

CSMRI Bagged Soil Disposal Summary Report  

E-Print Network [OSTI]

.......................................................................................................................... 1 4. Landfill Acceptance and Equipment Appendix G Daily GPS Coordinants of Disposal Location at BFI Foothills Landfill Appendix H Ambient Landfill (Stoller 2005a). After review of the dose assessment report, the CDPHE approved shipment

152

Disposable Bioreactors: Maturation into Pharmaceutical Glycoprotein Manufacturing  

Science Journals Connector (OSTI)

To summarise: the range of disposable bioreactors available on the market offers flexible, cost efficient and time-saving solutions from early process development to large-scale production. Table 1 gives an overv...

René Brecht

2010-01-01T23:59:59.000Z

153

Pesticide fate in an aboveground disposal system  

E-Print Network [OSTI]

PESTICIDE FATE IN AN ABOVEGROUND DISPOSAL SYSTEM A Thesis by BRIAN RICHARD VANDERGLAS Submitted to the Graduate College of Texas A 8 M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE May 'l988... Major Subject: Soil Science PESTICIDE FATE IN AN ABOVEGROUND DISPOSAL SYSTEM A Thesis by BRIAN RICHARD VANDERGLAS Approved as to style and content by: K. W. Brown (Chair of Committee) John M. Sweeten (Member) Jack D. Price (Member) E. C. A...

Vanderglas, Brian Richard

2012-06-07T23:59:59.000Z

154

Title I Disposal Sites Annual Report  

Broader source: Energy.gov [DOE]

This report presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements.

155

Clean Cities: National Clean Fleets Partner: Advanced Disposal Services  

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

156

Generic Disposal System Modeling, Fiscal Year 2011 Progress Report |  

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

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

157

Microsoft Word - SRSSaltWasteDisposal.doc  

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

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.

158

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect (OSTI)

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

159

Electrochemical apparatus comprising modified disposable rectangular cuvette  

DOE Patents [OSTI]

Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

2013-09-10T23:59:59.000Z

160

Generic Deep Geologic Disposal Safety Case | Department of Energy  

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

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

Note: This page contains sample records for the topic "wds llw disposal" 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

Predictive calculations to assess the long-term effect of cementitious materials on the pH and solubility of uranium(VI) in a shallow land disposal environment  

SciTech Connect (OSTI)

One proposed method of low-level radioactive waste (LLW) disposal is to mix the radioactive waste streams with cement, place the mixture in steel barrels, and dispose of the barrels in near-surface unsaturated sediments. Cement or concrete is frequently used in burial grounds, because cement porewaters are buffered at high pH values and lanthanides and actinides; are very insoluble in highly alkaline environments. Therefore, leaching of these contaminants from the combined cement/low-level radioactive waste streams will at least initially be retarded. The calculations performed in this study demonstrate that the pH of cement porewaters will be maintained at a value greater than 10 for 10,000 years under Hanford specific hydrogeochemical conditions. Ten thousand years is the period generally studied in longterm performance assessments per regulatory guidance. The concentrations of dissolved hexavalent uranium [U(VI)], the valence form of dissolved U usually present in oxidizing surface and groundwaters, are also constrained by the high pH and predicted solution compositions over the 10,000-year period, which is favorable from a long-term performance perspective.

Criscenti, L.J.; Serne, R.J.; Krupka, K.M. [Pacific Northwest Lab., Richland, WA (United States); Wood, M.I. [Westinghouse Hanford Company, Richland, WA (United States)

1996-09-01T23:59:59.000Z

162

The disposal of orphan wastes using the greater confinement disposal concept  

SciTech Connect (OSTI)

In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ``home`` for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ``special-case`` or ``orphan`` wastes. This paper describes an ongoing project sponsored by the DOE`s Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes can be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs.

Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (USA); Dickman, P.T. [Department of Energy, Las Vegas, NV (USA). Nevada Operations Office

1991-02-01T23:59:59.000Z

163

Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect (OSTI)

This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the southwest corner of the Idaho Nuclear Technology and Engineering Center (INTEC). At Site 5, large area and smaller-scale detailed surveys were performed. At Site 34, a large area survey was performed. The purpose of the surveys was to define the topography of the interface between the surficial alluvium and underlying basalt. Seismic data were first collected and processed using seismic refraction tomographic inversion. Three-dimensional images for both sites were rendered from the data to image the depth and velocities of the subsurface layers. Based on the interpreted top of basalt data at Site 5, a more detailed survey was conducted to refine depth to basalt. This report briefly covers relevant issues in the collection, processing and inversion of the seismic refraction data and in the imaging process. Included are the parameters for inversion and result rendering and visualization such as the inclusion of physical features. Results from the processing effort presented in this report include fence diagrams of the earth model, for the large area surveys and iso-velocity surfaces and cross sections from the detailed survey.

Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

2011-04-01T23:59:59.000Z

164

Status of UFD Campaign International Activities in Disposal Research |  

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

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.

165

On-Site Disposal Facility Inspection Report  

Office of Legacy Management (LM)

72.1 0614 On-Site Disposal Facility Inspection Report June 2014 6319-D6320 8972.2 0614 East Face Cell 1 West Face Cell 1 6319D-6322 6319D-6346 8972.3 0614 North Face Cell 1...

166

Low-level-waste-disposal methodologies  

SciTech Connect (OSTI)

This report covers the followng: (1) history of low level waste disposal; (2) current practice at the five major DOE burial sites and six commercial sites with dominant features of these sites and radionuclide content of major waste types summarized in tables; (3) site performance with performance record on burial sites tabulated; and (4) proposed solutions. Shallow burial of low level waste is a continuously evolving practice, and each site has developed its own solutions to the handling and disposal of unusual waste forms. There are no existing national standards for such disposal. However, improvements in the methodology for low level waste disposal are occurring on several fronts. Standardized criteria are being developed by both the Nuclear Regulatory Commission (NRC) and by DOE. Improved techniques for shallow burial are evolving at both commercial and DOE facilities, as well as through research sponsored by NRC, DOE, and the Environmental Protection Agency. Alternatives to shallow burial, such as deeper burial or the use of mined cavities is also being investigated by DOE.

Wheeler, M.L.; Dragonette, K.

1981-01-01T23:59:59.000Z

167

COUEB N T ED Safe Disposal of  

E-Print Network [OSTI]

COUEB N T ED Safe Disposal of Household Chemicals: Protect Yourself and Your Community see inside Minutes The 2010 census asks 10 questions that most households can answer in 10 minutes! You will be asked the name, age, gender, race, ethnic group (if Hispanic), and relationship of all persons living at your

Liskiewicz, Maciej

168

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

Office of Legacy Management (LM)

materials from the Slick RockOld North Continent site and the Slick RockUnion Carbide site were disposed of in this dedicated disposal cell. The Department of Energys...

169

INNOVATIVE DISPOSAL PRACTICES AT THE NEVADA TEST SITE TO MEET...  

National Nuclear Security Administration (NNSA)

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs E.F. Di Sanza, J.T. Carilli U.S. Department of Energy National...

170

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

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

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...

171

Maintenance Guide for DOE Low-Level Waste Disposal Facility ...  

Office of Environmental Management (EM)

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

172

Nuclear Waste Disposal: Can the Geologist Guarantee Isolation?  

Science Journals Connector (OSTI)

...to check whether waste disposal really does need an almost...been reported recently at Maxey Flats (Kentucky) (26...radioactive waste burial site, inside a fractured rock...effect of the geological disposal is to con-centrate 3530...

G. de Marsily; E. Ledoux; A. Barbreau; J. Margat

1977-08-05T23:59:59.000Z

173

Slide 1  

Office of Environmental Management (EM)

www.energy.govEM 4 USDOE LLW DISPOSAL Fernald Los Alamos National Laboratory Technical Area 54, Area G Portsmouth Paducah Idaho National Laboratory Idaho CERCLA Disposal...

174

Document  

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

Disposal Phase Final Supplemental Environmental Impact Statement (WIPP SEIS-II, DOEEIS-0026-S-2, September 1997). DOE is disposing of Hanford's LLW and MLLW onsite, consistent...

175

Acceptance of Classified Excess Components for Disposal at Area 5  

SciTech Connect (OSTI)

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

Poling, Jeanne [National Security Technologies, LLC (United States); Saad, Max [Sandia National Lab., NM (United States)

2012-04-09T23:59:59.000Z

176

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

Broader source: Energy.gov [DOE]

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

177

Disposability Assessment: Aluminum-Based Spent Nuclear Fuel Forms  

SciTech Connect (OSTI)

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

178

Landfill Disposal of CCA-Treated Wood with Construction and  

E-Print Network [OSTI]

Landfill Disposal of CCA-Treated Wood with Construction and Demolition (C&D) Debris: Arsenic phased out of many residential uses in the United States, the disposal of CCA-treated wood remains. Catastrophic events have also led to the concentrated disposal of CCA-treated wood, often in unlined landfills

Florida, University of

179

Chapter 8 - Coal Combustion Residue Disposal Options  

Science Journals Connector (OSTI)

Abstract Coal combustion residues (CCRs) are presently regulated as solid waste (Subtitle D) under the Resource Conservation Recovery Act. Such classification promotes beneficial use by end-users i.e. mitigating excessive liability. According to the US Environmental Protection agency (USEPA), about 131 million tons of coal combustion residuals—including 71 million tons of fly ash, 20 million tons of bottom ash and boiler slag, and 40 million tons of flue gas desulfurization (FGD) material—were generated in the US in 2007. Of this, approximately 36% was disposed of in landfills, 21% was disposed of in surface impoundments, 38% was beneficially reused, and 5% was used as minefill. Stringent regulation, as Subtitle C (hazardous waste), would impose a perceived liability upon end-users; greatly reducing beneficial use opportunities. Mandatory use of synthetic liners—would not have prevented dike wall failure and fails to consider inherent engineering characteristics of CCRs.

Richard W. Goodwin

2014-01-01T23:59:59.000Z

180

Technical and philosophical aspects of ocean disposal  

E-Print Network [OSTI]

Di sposai . Geological aspects Physical aspects Chemical aspects Biological aspects CHAPTER II. TECHNICAL ASPECTS OF OCEAN DISPOSAL Types of Waste Materials. Dredged materiais. Industrial wastes, DomestIc sewage wa tes Solid wastes Radloact..., can reduce the passage of light through the water column and cause damaging effects to the marine ecosystem. Each of five major oceans has pronounced gyral, or circular current motion (Fiaure 1. 1). The North Atlantic current system is comprised...

Zapatka, Marchi Charisse

1976-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Geochemical aspects of radioactive waste disposal  

SciTech Connect (OSTI)

The book addresses various topics related to the geochemistry of waste disposal: natural radioactivity, kinds of radioactive waste, details of possible disposal sites, low-level waste, uranium mill tailing, natural analogs, waste forms, and engineered barriers. Emphasis throughout is on the importance of natural analogs, the behavior of elements resembling those to be put in a waste repository as they occur in natural situations where the temperature, pressure, and movement of ground water are similar to those expected near a repository. The author is convinced that conclusions drawn from the study of analog elements are directly applicable to predictions about radionuclide behavior, and that the observed near-immobility of most of these elements in comparable geologic environments is good evidence that radioactive waste can be disposed of underground with negligible effects on the biosphere. Much of his own research has been in this area, and the best parts of the book are the descriptions of his work on trace elements in the salt minerals at the Waste Isolation Pilot Plant in southeastern New Mexico, on the movement of radionuclides and their daughter elements from the famous Precambrian reactor at Oklahoma in Gabon, and on the distribution of analog elements in rocks near the contacts of igneous intrusions.

Brookins, D.G.

1984-01-01T23:59:59.000Z

182

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

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

183

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

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

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

184

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

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

185

DOE Applauds Opening of Historic Disposal Facility | Department of Energy  

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

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

186

Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc  

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

187

Review of Yucca Mountain Disposal Criticality Studies  

SciTech Connect (OSTI)

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] [ORNL; Wagner, John C [ORNL] [ORNL

2011-01-01T23:59:59.000Z

188

Summary - Disposal Practices at the Nevada Test Site  

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

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

189

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

190

Deep Borehole Disposal Research: Demonstration Site Selection Guidelines,  

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

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

191

LANL completes excavation of 1940s waste disposal site  

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

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

192

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

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

193

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

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

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

194

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

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

195

Disposal Practices at the Nevada Test Site 2008  

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

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

196

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE's Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site's waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-01-01T23:59:59.000Z

197

Mixed waste disposal facilities at the Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a key installation of the US Department of Energy (DOE). The site is managed by DOE`s Savannah River Field Office and operated under contract by the Westinghouse Savannah River Company (WSRC). The Site`s waste management policies reflect a continuing commitment to the environment. Waste minimization, recycling, use of effective pre-disposal treatments, and repository monitoring are high priorities at the site. One primary objective is to safely treat and dispose of process wastes from operations at the site. To meet this objective, several new projects are currently being developed, including the M-Area Waste Disposal Project (Y-Area) which will treat and dispose of mixed liquid wastes, and the Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF), which will store, treat, and dispose of solid mixed and hazardous wastes. This document provides a description of this facility and its mission.

Wells, M.N.; Bailey, L.L.

1991-12-31T23:59:59.000Z

198

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

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

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

199

Reactor Pressure Vessel Head Packaging & Disposal  

SciTech Connect (OSTI)

Reactor Pressure Vessel (RPV) Head replacements have come to the forefront due to erosion/corrosion and wastage problems resulting from the susceptibility of the RPV Head alloy steel material to water/boric acid corrosion from reactor coolant leakage through the various RPV Head penetrations. A case in point is the recent Davis-Besse RPV Head project, where detailed inspections in early 2002 revealed significant wastage of head material adjacent to one of the Control Rod Drive Mechanism (CRDM) nozzles. In lieu of making ASME weld repairs to the damaged head, Davis-Besse made the decision to replace the RPV Head. The decision was made on the basis that the required weld repair would be too extensive and almost impractical. This paper presents the packaging, transport, and disposal considerations for the damaged Davis-Besse RPV Head. It addresses the requirements necessary to meet Davis Besse needs, as well as the regulatory criteria, for shipping and burial of the head. It focuses on the radiological characterization, shipping/disposal package design, site preparation and packaging, and the transportation and emergency response plans that were developed for the Davis-Besse RPV Head project.

Wheeler, D. M.; Posivak, E.; Freitag, A.; Geddes, B.

2003-02-26T23:59:59.000Z

200

Municipal solid waste disposal in Portugal  

SciTech Connect (OSTI)

In recent years municipal solid waste (MSW) disposal has been one of the most important environmental problems for all of the Portuguese regions. The basic principles of MSW management in Portugal are: (1) prevention or reduction, (2) reuse, (3) recovery (e.g., recycling, incineration with heat recovery), and (4) polluter-pay principle. A brief history of legislative trends in waste management is provided herein as background for current waste management and recycling activities. The paper also presents and discusses the municipal solid waste management in Portugal and is based primarily on a national inquiry carried out in 2003 and directed to the MSW management entities. Additionally, the MSW responsibility and management structure in Portugal is presented, together with the present situation of production, collection, recycling, treatment and elimination of MSW. Results showed that 96% of MSW was collected mixed (4% was separately collected) and that 68% was disposed of in landfill, 21% was incinerated at waste-to-energy plants, 8% was treated at organic waste recovery plants and 3% was delivered to sorting. The average generation rate of MSW was 1.32 kg/capita/day.

Magrinho, Alexandre [Mechanical Engineering Department, Escola Superior de Tecnologia de Setubal, Campus IPS, Estefanilha, Setubal (Portugal); Didelet, Filipe [Mechanical Engineering Department, Escola Superior de Tecnologia de Setubal, Campus IPS, Estefanilha, Setubal (Portugal); Semiao, Viriato [Mechanical Engineering Department, Instituto Superior Tecnico, Av. Rovisco Pais, 1049-001 Lisbon (Portugal)]. E-mail: ViriatoSemiao@ist.utl.pt

2006-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Iraq nuclear facility dismantlement and disposal project  

SciTech Connect (OSTI)

The Al Tuwaitha nuclear complex near Baghdad contains a significant number of nuclear facilities from Saddam Hussein's dictatorship. Because of past military operations, lack of upkeep and looting there is now an enormous radioactive waste problem at Al Tuwaitha. Al Tuwaitha contains uncharacterised radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals. The current security situation in Iraq hampers all aspects of radioactive waste management. Further, Iraq has never had a radioactive waste disposal facility, which means that ever increasing quantities of radioactive waste and material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS has funded the International Atomic Energy Agency (IAEA) to provide technical assistance to the GOI via a Technical Cooperation Project. Program coordination will be provided by the DOS, consistent with U.S. and GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and for providing waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for the vast majority of the implementation of the NDs Program. (authors)

Cochran, J.R.; Danneels, J. [Sandia National Laboratories, Albuquerque, NM (United States); Kenagy, W.D. [U.S. Department of State, Bureau of International Security and Nonproliferation, Office of Nuclear Energy, Safety and Security, Washington, DC (United States); Phillips, C.J.; Chesser, R.K. [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX (United States)

2007-07-01T23:59:59.000Z

202

Will new disposal regulations undo decades of progress?  

SciTech Connect (OSTI)

In 1980, the Belville Amendments to RCRA instructed EPA to 'conduct a detailed and comprehensive study and submit a report' to Congress on the 'adverse effects on human health and the environment, if any, of the disposal and utilization' of coal ash. In both 1988 and 1999, EPA submitted reports to Congress and recommended coal ash should not be regulated as hazardous waste. After the failure of a Tennesse power plant's coal ash disposal facility, EPA will be proposing new disposal regulations.

Ward, J. [John Ward Inc. (United States)

2009-07-01T23:59:59.000Z

203

Remedial Action and Waste Disposal Conduct of OperationsMatrix  

SciTech Connect (OSTI)

This Conduct of Operations (CONOPS) matrix incorporates the Environmental Restoration Disposal Facility (ERDF) CONOPS matrix (BHI-00746, Rev. 0). The ERDF CONOPS matrix has been expanded to cover all aspects of the RAWD project. All remedial action and waste disposal (RAWD) operations, including waste remediation, transportation, and disposal at the ERDF consist of construction-type activities as opposed to nuclear power plant-like operations. In keeping with this distinction, the graded approach has been applied to the developmentof this matrix.

M. A. Casbon.

1999-05-24T23:59:59.000Z

204

Commercial low-level radioactive waste disposal in the US  

SciTech Connect (OSTI)

Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going.

Smith, P.

1995-10-01T23:59:59.000Z

205

Selected biological investigations on deep sea disposal of industrial wastes  

E-Print Network [OSTI]

found at an actual disposal site with respect to waste dilution with time. This technique was incorporated into the standard 96-hour bioassay test to afford a means of obtaining preliminary information regarding the bioaccumulation of each waste... with time from the 16 ocean dispose 1 study by Ball (1973) Laboratory dilution setup used to simulate conditions found at an actual disposal site with regard to waste dilution. 18 20 CHAPTER I INTRODUCTION Until recently man haS considered...

Page, Sandra Lea

2012-06-07T23:59:59.000Z

206

System design for disposal of tritium at TFTR  

SciTech Connect (OSTI)

The Tokamak Fusion Test Reactor (TFTR) has cleanup systems which convert tritium gas to the oxide form and absorb it on molecular sieve beds. These beds are regenerated by transferring their moisture content to disposable sieve beds. Preparing this sieve for disposal can be awkward and hazardous. Monitoring the tritium and moisture content of the disposable sieve is not straightforward. Modifications to the regeneration system at the TFTR are being made to address these concerns and others relating to maintainability.

Tuohy, J.M.; Cherdack, R.; Lacy, N.H.

1988-09-01T23:59:59.000Z

207

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

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

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

208

Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF...  

Open Energy Info (EERE)

Treatment, Storage and Disposal Facilities (TSDF) Guidance Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

209

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

Broader source: Energy.gov [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...

210

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect (OSTI)

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

211

Canister design for deep borehole disposal of nuclear waste .  

E-Print Network [OSTI]

??The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories… (more)

Hoag, Christopher Ian.

2006-01-01T23:59:59.000Z

212

Fees For Disposal Of Hazardous Waste Or Substances (Alabama)  

Broader source: Energy.gov [DOE]

The article lists annual payments to be made to counties, restrictions on disposal of hazardous waste, additional fees collected by counties and penalties.

213

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

Bailey, L.L.

1991-01-01T23:59:59.000Z

214

The Hazardous Waste/Mixed Waste Disposal Facility  

SciTech Connect (OSTI)

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy`s (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency`s (EPA`s) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996.

Bailey, L.L.

1991-12-31T23:59:59.000Z

215

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

Office of Environmental Management (EM)

Site, Lowman, Idaho More Documents & Publications Title I Disposal Sites Annual Report Long-Term Surveillance and Maintenance Program 2003 Report Revegetation of the Rocky Flats...

216

Disposal Practices at the Savannah River Site | Department of...  

Office of Environmental Management (EM)

Site More Documents & Publications Compilation of ETR Summaries Disposal Practices at the Nevada Test Site 2008 Briefing: DOE EM ITR Landfill Assessment Project Lessons Learned...

217

Solid Waste Disposal Facilities (Massachusetts) | Department of Energy  

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

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

218

Sludge utilization and disposal in Virginia  

SciTech Connect (OSTI)

This state-of-the-art study was initiated to determine the problem issues, present knowledge about the issues, and additional research needs in the area of land disposal of municipal sewage sludge. Three questionnaires were developed to survey technically oriented professional, county extension agents, and Virginia NPDES permit holders to obtain these groups' views on problems and deficiencies needing further investigation. Another phase of the study was to conduct an extensive review of the literature on the subject of land application of sewage sludge. Listings of pertinent literature relating to land application with specific interest toward potentially toxic metals, pathogens, nitrogen, and phosphorus were obtained and reviewed. Additional research is needed in the following areas: a method that accurately estimates metal availability within the soil; a method to determine the potential for a disease outbreak from controlled application of treated municipal sewage sludge; a more precise method of N-balancing; the impact of P loading on water quality.

Martens, D.C.; McCart, G.D.; Reneau, R.B. Jr; Simpson, T.W.; Ban-Kiat, T.

1982-10-01T23:59:59.000Z

219

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network [OSTI]

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

220

1 INSTRODUCTION In the concept of geological radioactive waste disposal,  

E-Print Network [OSTI]

1 INSTRODUCTION In the concept of geological radioactive waste disposal, argillite is being of the radioactive waste disposal, the host rock will be subjected to various thermo-hydro-mechanical loadings, thermal solicitation comes from the heat emitting from the radioactive waste packages. On one hand

Boyer, Edmond

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

A model approach to radioactive waste disposal at Sellafield  

E-Print Network [OSTI]

A model approach to radioactive waste disposal at Sellafield R. 5. Haszeldine* and C. Mc of the great environmentalproblems of our age is the safe disposal of radioactive waste for geological time periods. Britain is currently investigating a potential site for underground burial of waste, near

Haszeldine, Stuart

222

User Guide for Disposal of Unwanted Items and Electronic Waste  

E-Print Network [OSTI]

is the Recycle department at 502-6808 o For more information on the UCSF Sustainability program visit: http://sustainability.ucsf.edu/stay_informed/recycling_resources consulting support Ensuring proper reuse, recycle, or disposal Maintaining regulatory and policy compliance metal and wood o Waste/trash management o Recycle, reuse or disposal of materials D&S does not process o

Mullins, Dyche

223

Solid waste disposal options: an optimum disposal model for the management of municipal solid waste  

E-Print Network [OSTI]

and compostable material was generally burned in backyards. In 1970, the Clean Air Act was passed restricting the burning of leaves and other yard waste. ' These wastes were then disposed in landfills. As landfills reached capacity, commu- nities composted... separation pro- grams because of their "throw-away" mentality. " ~ln in r ttgtt Incineration is the controlled burning of the combustible fraction of solid waste. The first electrical generating station in the United States that was fueled by solid waste...

Haney, Brenda Ann

2012-06-07T23:59:59.000Z

224

2009 Performance Assessment for the Saltstone Disposal Facility |  

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

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]

225

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

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

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

226

DOE - Office of Legacy Management -- Cheney Disposal Cell - 008  

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

Cheney Disposal Cell - 008 Cheney Disposal Cell - 008 FUSRAP Considered Sites Site: Cheney Disposal Cell (008) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: All of the uranium mill tailings and other residual radioactive materials from the former Grand Junction uranium mill site were disposed of in this dedicated disposal cell. The cell is authorized to remain open until 2003 to accept any additional byproduct materials from Title I UMTRA sites and the Monticello, Utah site; e.g. materials from additional vicinity properties that may be identified. The Department of Energy¿s Grand Junction Office is responsible for Long Term Surveillance and Maintenance

227

Summary - Disposal Practices at the Savannah River Site  

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

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

228

Low-Level Waste Disposal Facility Federal Review Group Manual  

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

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

229

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

230

OAK RIDGE CERCLA DISPOSAL FACILITY ACHIEVES SAFETY MILESTONE | Department  

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

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

231

Drilling Waste Management Fact Sheet: Offsite Disposal at Commercial  

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

232

Research, Development, and Demonstration Roadmap for Deep Borehole Disposal  

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

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

233

Generic Argillite/Shale Disposal Reference Case  

SciTech Connect (OSTI)

Radioactive waste disposal in a deep subsurface repository hosted in clay/shale/argillite is a subject of widespread interest given the desirable isolation properties, geochemically reduced conditions, and widespread geologic occurrence of this rock type (Hansen 2010; Bianchi et al. 2013). Bianchi et al. (2013) provides a description of diffusion in a clay-hosted repository based on single-phase flow and full saturation using parametric data from documented studies in Europe (e.g., ANDRA 2005). The predominance of diffusive transport and sorption phenomena in this clay media are key attributes to impede radionuclide mobility making clay rock formations target sites for disposal of high-level radioactive waste. The reports by Hansen et al. (2010) and those from numerous studies in clay-hosted underground research laboratories (URLs) in Belgium, France and Switzerland outline the extensive scientific knowledge obtained to assess long-term clay/shale/argillite repository isolation performance of nuclear waste. In the past several years under the UFDC, various kinds of models have been developed for argillite repository to demonstrate the model capability, understand the spatial and temporal alteration of the repository, and evaluate different scenarios. These models include the coupled Thermal-Hydrological-Mechanical (THM) and Thermal-Hydrological-Mechanical-Chemical (THMC) models (e.g. Liu et al. 2013; Rutqvist et al. 2014a, Zheng et al. 2014a) that focus on THMC processes in the Engineered Barrier System (EBS) bentonite and argillite host hock, the large scale hydrogeologic model (Bianchi et al. 2014) that investigates the hydraulic connection between an emplacement drift and surrounding hydrogeological units, and Disposal Systems Evaluation Framework (DSEF) models (Greenberg et al. 2013) that evaluate thermal evolution in the host rock approximated as a thermal conduction process to facilitate the analysis of design options. However, the assumptions and the properties (parameters) used in these models are different, which not only make inter-model comparisons difficult, but also compromise the applicability of the lessons learned from one model to another model. The establishment of a reference case would therefore be helpful to set up a baseline for model development. A generic salt repository reference case was developed in Freeze et al. (2013) and the generic argillite repository reference case is presented in this report. The definition of a reference case requires the characterization of the waste inventory, waste form, waste package, repository layout, EBS backfill, host rock, and biosphere. This report mainly documents the processes in EBS bentonite and host rock that are potentially important for performance assessment and properties that are needed to describe these processes, with brief description other components such as waste inventory, waste form, waste package, repository layout, aquifer, and biosphere. A thorough description of the generic argillite repository reference case will be given in Jové Colon et al. (2014).

Zheng, Liange; Jov& #233; Colon, Carlos; Bianchi, Marco; Birkholzer, Jens

2014-08-08T23:59:59.000Z

234

Selection of a method for disposing of leachate grout  

SciTech Connect (OSTI)

A major component of the selected remedy for the remediation of the Maxey Flats Disposal Site (MFDS) is the removal, solidification, and on-site disposal of an estimated 3000000 gal of trench leachate. The Record of Decision (ROD) and its predecessor, the Maxey Flats Feasibility Study Report, proposed as a representative process option that the trench leachate be solidified in the form of large (8 x 8 x 4 ft) concrete blocks and disposed of in trenches. The U.S. Environmental Protection Agency (EPA) had recent experience with this method when solidifying and disposing of {approximately}300000 gal of leachate that was stored in above-ground tanks at the MFDS. The EPA experience proved the capability of a U.S. Nuclear Regulatory Commission (NRC)-approved grout mix to satisfy the requirements of 10CFR61.55-56 for the Class-A liquid waste at the site, i.e., the leachate. However, a technical evaluation of the overall solidification/disposal process implemented by the EPA identified some steps that should be improved if this method is to be implemented safely and efficiently for the solidification and disposal of trench leachate as part of the remedial action. In the light of the EPA experience, the present study modified the option proposed in the ROD to make it more workable. This study also evaluated other methods, including three methods for above grade disposal.

Cockrell, R.G.

1994-12-31T23:59:59.000Z

235

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

2012-07-01T23:59:59.000Z

236

LLW Notes, Volume 12, Number 8  

SciTech Connect (OSTI)

Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical analysis of LLRW facility; Southeast Compact suspends funding for NC facility development; NC governor and Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators` group revises radioactive waste policy; Internal documents discuss administration`s policy on Ward Valley; BLM issues EA for Ward Valley testing; California DHS, NRC criticize DOI`s testing protocols; Army removes training mines from Ward Valley site; The 1997 gubernatorial elections and a look ahead to 1998; Court throws out case challenging Pennsylvania`s siting law; DOE files notice of appeal in WCS suit; Central Compact moves to dismiss ``Veto`` authority suit; Congress exempts NAS from FACA; Judge sets schedule for Ward Valley case; Court won`t order DOE to accept spent fuel by deadline; NRC chairman expresses concern re CERCLA reauthorization; Senators question EPA`s guidance on remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed into law; and Senate confirms 5 of 6 DOE appointees.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-12-31T23:59:59.000Z

237

LLW Notes, Volume 12, Number 5  

SciTech Connect (OSTI)

Contents include articles entitled: USGS report supports previous conclusions re tritium migration at Beatty; Ohio selects new contractor for screening; Maine Yankee`s future uncertain; Southeast Compact limits funds for North Carolina project; California, Energy, and Interior exchange correspondence on Ward Valley testing; TCC meets in Salt Lake City, Utah; Garner named executive director and forum participant for Northwest Compact; Seventh Circuit upholds Energy Secretary`s determination re distribution of surcharge rebates; US Ecology sues Nebraska re wetlands mitigation; US Supreme Court hears line-item veto challenge; Court rules NAS must provide public access; WCS sues Envirocare of Texas; DOE and Envirocare sign consent agreement; NRC issues performance assessment guidance; NRC to publish final decommissioning rule; House subcommittee passes Texas Consent Act; Environmental justice bill introduced in the House; and International nuclear safety body established.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-06-01T23:59:59.000Z

238

LLW Notes supplement, Volume 12, Number 6  

SciTech Connect (OSTI)

Contents include articles related to environmental justice concerns and Title VI, entitled as follows: Civil Rights Act of 1964; Exec order on environmental justice; Applicability to states; Philosophical differences -- Environmental justice and Title VI; Ambiguities in existing Title VI guidance; Clarification of existing Title VI guidance; Federal financial assistance; Administrative complaints vs. lawsuits; Effect and disparate impact; Termination, suspension or refusal to grant federal financial assistance; DOJ guidance defines environmental justice; NEJAC meets, adopts far-reaching resolution re siting; Indigenous Peoples Resolution No. 23; and States meet, support environmental justice concept and express concerns about federal approach and composition of NEJAC.

NONE

1997-07-01T23:59:59.000Z

239

LLW Notes, Volume 12, Number 6  

SciTech Connect (OSTI)

Contents include articles entitled: GAO concludes most Ward Valley SEIS issues previously addressed; Midwest compact halts facility development; Texas publishes proposal to issue WCS radioactive materials license; Central Compact issues export authorizations over NE`s objection; Nebraska governor to host LLRW summit; California regulators reassured re US ecology facility in WA; Southeast Compact augments funding for North Carolina; State and compact calendar of events; IAEA Director General to UN: reexamine nuclear power; DOI convenes meetings on Ward Valley Title VI complaint; California BLM: Tribes fully represented and consulted; MW, NE, and SW file amici curiae briefs in Ward Valley suit; Court denies state`s motion for protective order; WCS files suit against Envirocare and others; States attack DOE`s claim re lack of authority to store spent fuel; House committee passes Texas legislation; Ward Valley land transfer bill introduced in Senate; Senate committee holds hearing on Ward Valley legislation and related GAO report; NRDC threatens to sue DOE re Envirocare; NRC chair criticizes Deputy Interior Secretary`s use of Ward Valley fact sheet; Utility consortium submits license application for storage on Goshute land to NRC; Envirocare cited for SNM violation; EPA begins audit; and EPA rejects Title VI claim re Texas site.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-07-01T23:59:59.000Z

240

LLW Notes, Volume 12, Number 9  

SciTech Connect (OSTI)

Contents include articles entitled: Senators criticize DOE use of Envirocare and Molten Metal; Officials express concern re implications of WCS ruling; DOE files notice of appeal in WCS suit; WCS responds to critics re implications of ruling; Background: Prior correspondence between the Senators and DOE re Envirocare; Waste control specialists authorized to conduct additional operations at Texas site; Molten Metal files for bankruptcy protection; Envirocare of Texas receives first approval for hazardous waste permit; Envirocare of Utah applies to NRC for SNM license; NRDC alleges death threats and financial intimidation by Envirocare; DOE and NRC sign off on external regulation pilot program; and NRDC requests Inspector General probe re Envirocare.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.

1997-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

LLW Notes, Volume 12, Number 4  

SciTech Connect (OSTI)

Contents include articles entitled: Texas Authority`s funding pending before conference committee: Auditor`s report favors authority; Revisions likely for Illinois siting law; Midwest Compact votes on Ohio fundings: Less approved than requested; Walter Sturgeon named executive director of North Carolina authority; New forum participant for Massachusetts; CRCPD holds fifth workshop for LLRW regulators; DOD generators hold annual meeting; State legislators` LLRW working group meets; NRC Chairman Jackson responds to proposal to amend the Policy Act; US Ecology uses to recover costs and lost profits and/or to compel Ward Valley land transfer; New suit against Envirocare and others alleges unlawful business practices; Federal court finds line-item veto unconstitutional; States/utilities seek to escrow nuclear waste payments; High-level waste bill passes Senate; NRC releases decommissioning rule; EPA Region VI re La Paz Agreement; EPA, NRC debate NRC`s decommissioning rule: No progress re approaches to risk harmonization; and Mousseau heads DOE`s national low-level waste management program.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-04-01T23:59:59.000Z

242

On-Site Disposal Facility Inspection Report  

Office of Legacy Management (LM)

8947.1 8947.1 09/13 On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 09/13 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 09/13 North Face Cell 1 North Drainage (looking west) 6319D-6206 6319D-6205 8947.4 09/13 East Face Cell 2 West Face Cell 2 6319D-6230 6319D-6209 8947.5 09/13 East Face Cell 3 West Face Cell 3 6319D-6229 6319D-6210 8947.6 09/13 East Face Cell 4 West Face Cell 4 6319D-6227 6319D-62111 8947.7 09/13 East Face Cell 5 West Face Cell 5 6319D-6226 6319D-6213 8947.8 09/13 East Face Cell 6 6319D-6214 6319D-6225 West Face Cell 6 8947.9 09/13 East Face Cell 7 6319D-6215 6319D-6223 West Face Cell 7 8947.10 09/13 East Face Cell 8 6319D-6217 6319D-6220 West Face Cell 8 8947.11 09/13 South Face Cell 8 6319D-6219 6319D-6218 South Drainage (looking west) 8947.12 09/13

243

Fluorescent ballast and lamp disposal issues  

SciTech Connect (OSTI)

All around the world, governments, utility companies, and private businesses are attempting to reduce the amount of energy consumed. In the US alone, new economic strategies and programs are being created to facilitate this process. For instance, the recent enactment of the National Energy Policy Act, the Environmental Protection Agency`s (EPA) Green Lights Program, and a surge of utility involvement in Demand Side Management (DSM) Commercial/Industrial Direct Install and Rebate Programs. Many of these problems target commercial/industrial lighting system retrofits as one of the most cost effective avenues for reducing the consumption of energy. Due to this trend, hundreds of millions of lighting ballasts and lamps are being discarded. The benefits of these programs result in enormous reductions in fossil fuels (and subsequent carbon dioxide, sulfur dioxide, and nitrogen oxide emissions) required to generate the displaced electricity. Throughout the US, however, there is an increasing concern for the environmental impacts surrounding the accelerated disposal of both lighting ballasts and lamps. Regulations initially established were for a one by one, retirement (failure) process rather than promoted obsolescence and forced retirement of lamp groups or entire systems (truckloads of old technologies). Recognizing this trend and the potential negative environmental effects, federal, state, and local regulators are reevaluating the impacts and are being asked to promulgate policies to specifically address this situation.

Leishman, D.L. [Alta Resource Management Services, Inc., Springfield, MA (United States)

1996-12-01T23:59:59.000Z

244

Disposal of Rocky Flats residues as waste  

SciTech Connect (OSTI)

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

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

1993-03-01T23:59:59.000Z

245

Disposal of Rocky Flats residues as waste  

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

246

Rules and Regulations for the Disposal of Low-Level Radioactive Waste (Nebraska)  

Broader source: Energy.gov [DOE]

These regulations, promulgated by the Department of Environmental Quality, contain provisions pertaining to the disposal of low-level radioactive waste, disposal facilities, and applicable fees.

247

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal...  

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

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine...

248

Systems engineering programs for geologic nuclear waste disposal  

SciTech Connect (OSTI)

The design sequence and system programs presented begin with general approximate solutions that permit inexpensive analysis of a multitude of possible wastes, disposal media, and disposal process properties and configurations. It then continues through progressively more precise solutions as parts of the design become fixed, and ends with repository and waste form optimization studies. The programs cover both solid and gaseous waste forms. The analytical development, a program listing, a users guide, and examples are presented for each program. Sensitivity studies showing the effects of disposal media and waste form thermophysical properties and repository layouts are presented as examples.

Klett, R. D.; Hertel, Jr., E. S.; Ellis, M. A.

1980-06-01T23:59:59.000Z

249

Analysis of alternatives for immobilized low activity waste disposal  

SciTech Connect (OSTI)

This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

Burbank, D.A.

1997-10-28T23:59:59.000Z

250

Demilitarization and disposal technologies for conventional munitions and energetic materials  

SciTech Connect (OSTI)

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

251

Integrated process for coalbed brine disposal  

SciTech Connect (OSTI)

A brine disposal process is described that converts the brine stream of a coalbed gas producing site into clean water for agricultural use, combustion products and water vapor that can be released into the atmosphere and dry solids that can be recycled for industrial consumption. The process uses a reverse osmosis unit, a submerged combustion evaporator and a pulse combustion dryer. Pretreatment of the brine feedstream is necessary to prevent fouling of the membranes of the reverse osmosis unit and to separate from the brine stream hazardous metal and other constituents that may make the permeate from the reverse osmosis unit unsuitable for agricultural or other use. A chemical modeling code is used to calculate the saturation states of solids that may precipitate and foul the reverse osmosis membranes. Sodium carbonate is added to the brine to precipitate carbonates of Ba, Ca, Mg and Sr prior to filtration, acidification, and passage into the reverse osmosis unit. Optimization of the process in terms of types and amounts of additives is possible with analysis using the modeling code. The minimum amounts of additives to prevent scaling are calculated. In a typical operation, a brine feedstream of 1,000 m{sup 3}/day (6,290 bpd) that may have a total dissolved salt concentration (TDS) of 7,000 ppm will be separated into a permeate stream of 750 m{sup 3}/day (4,718 bpd) with a TDS of 400 ppm and a concentrated brine stream of 250 m{sup 3}/day (1,573 bpd) with a TDS of 26,800 ppm. The submerged combustion evaporator will concentrate this latter stream to a concentration of 268,000 ppm and reduce the volume to 25 m{sup 3}/day (158 bpd). The pulse combustion dryer can dry the concentrated brine mixture to a low moisture salt. Energy costs to operate the reverse osmosis unit are primarily the pumping costs.

Brandt, H. [AQUATECH Services, Inc., Fair Oaks, CA (United States)]|[California Univ., Davis, CA (United States). Dept. of Mechanical Engineering; Bourcier, W.L.; Jackson, K.J. [Lawrence Livermore National Lab., CA (United States)

1994-03-01T23:59:59.000Z

252

A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of  

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

A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear safety and security, non-proliferation, and nuclear energy technology we must develop an effective strategy and workable plan for the safe and secure management and disposal of used nuclear fuel and nuclear waste. That is why I asked General Scowcroft and Representative Hamilton to draw on their

253

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

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

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

254

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

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

255

Disposing of nuclear waste in a salt bed  

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

Disposing of nuclear waste in a salt bed Disposing of nuclear waste in a salt bed 1663 Los Alamos science and technology magazine Latest Issue:November 2013 All Issues » submit Disposing of nuclear waste in a salt bed Decades' worth of transuranic waste from Los Alamos is being laid to rest at the Waste Isolation Pilot Plant in southeastern New Mexico March 25, 2013 Disposing of nuclear waste in a salt bed Depending on the impurities embedded within it, the salt from WIPP can be anything from a reddish, relatively opaque rock to a clear crystal like the one shown here. Ordinary salt effectively seals transuranic waste in a long-term repository Transuranic waste, made of items such as lab coats and equipment that have been contaminated by radioactive elements heavier than uranium, is being shipped from the Los Alamos National Laboratory to a long-term storage

256

Repository Reference Disposal Concepts and Thermal Load Management Analysis  

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

Repository Reference Disposal Concepts and Thermal Load Management Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are identified: 1) "open" where extended ventilation can remove heat for many years following waste emplacement underground; and 2) "enclosed" modes for clay/shale and salt media where waste packages are emplaced in direct or close contact with natural or engineered materials which may have temperature limits that constrain thermal

257

Disposal Systems Evaluations and Tool Development - Engineered Barrier  

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

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

258

Integration of EBS Models with Generic Disposal System Models | Department  

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

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

259

Integration of EBS Models with Generic Disposal System Models | Department  

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

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

260

Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) |  

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

Southwestern Low-Level Radioactive Waste Disposal Compact (South Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) < Back Eligibility Utility Investor-Owned Utility Industrial Construction Municipal/Public Utility Rural Electric Cooperative Fuel Distributor Program Info State South Dakota Program Type Siting and Permitting Provider Southwestern Low-Level Radioactive Waste Commission This legislation authorizes the state's entrance into the Southwestern Low-Level Radioactive Waste Disposal Compact, which provides for the cooperative management of low-level radioactive waste. The Compact is administered by a commission, which can regulate and impose fees on in-state radioactive waste generators. The states of Arizona, California,

Note: This page contains sample records for the topic "wds llw disposal" 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

Shell keeps its options open for disposing of Brent Spar  

Science Journals Connector (OSTI)

... Brent Spar, may lead to similar disposal of 50 deep-water oil installations in UK offshore waters that are next in line for decommissioning, Johnston says. "No one knows ... this would have on the marine environment."

Ehsan Masood

1995-08-03T23:59:59.000Z

262

Waste Disposal Site and Radioactive Waste Management (Iowa)  

Broader source: Energy.gov [DOE]

This section describes the considerations of the Commission in determining whether to approve the establishment and operation of a disposal site for nuclear waste. If a permit is issued, the...

263

Proof of Proper Solid Waste Disposal (West Virginia)  

Broader source: Energy.gov [DOE]

This rule provides guidance to persons occupying a residence or operating a business establishment in this state regarding the approved method of providing proof of proper solid waste disposal to...

264

Burning Chemical Waste Disposal Site: Investigation, Assessment and Rehabilitation  

Science Journals Connector (OSTI)

A series of underground fires on a site previously used for disposal of chemical wastes from the nylon industry was causing a nuisance and restricting the commercial development of the site and adjacent areas....

D. L. Barry; J. M. Campbell; E. H. Jones

1990-01-01T23:59:59.000Z

265

A microelectronic design for low-cost disposable chemical sensors  

E-Print Network [OSTI]

This thesis demonstrates the novel concept and design of integrated microelectronics for a low-cost disposable chemical sensor. The critical aspects of this chemical sensor are the performance of the microelectronic chip ...

Laval, Stuart S. (Stuart Sean), 1980-

2004-01-01T23:59:59.000Z

266

Figure ES2. Annual Indices of Real Disposable Income, Vehicle...  

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

ES2 Figure ES2. Annual Indices of Real Disposable Income, Vehicle-Miles Traveled, Consumer Price Index (CPI-U), and Real Average Retail Gasoline Price, 1978-2004, 1985100...

267

Nuclear Waste Disposal: Yucca Blowup Theory Bombs, Says Study  

Science Journals Connector (OSTI)

...leaked into the storage area, the depleted uranium would quickly saturate it, making...disposing of the 400,000 tons of depleted uranium left over from the arms race...andotherbranches ofthe Public Health Service must demonstrate that...

Gary Taubes

1996-03-22T23:59:59.000Z

268

Canister design for deep borehole disposal of nuclear waste  

E-Print Network [OSTI]

The objective of this thesis was to design a canister for the disposal of spent nuclear fuel and other high-level waste in deep borehole repositories using currently available and proven oil, gas, and geothermal drilling ...

Hoag, Christopher Ian

2006-01-01T23:59:59.000Z

269

Design and Installation of a Disposal Cell Cover Field Test ...  

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

through March 3, 2011, Phoenix, Arizona. C.H. Benson, W.J. Waugh, W.H. Albright, G.M. Smith, R.P. Bush Design and Installation of a Disposal Cell Cover Field Test More Documents...

270

Draft Environmental Impact Statement for the Disposal of Greater...  

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

Friday, February 18, 2011 Draft Environmental Impact Statement for the Disposal of Greater-Than-Class C Low-Level Radioactive Waste and GTCC-Like Waste WASHINGTON The...

271

Disposable Bioreactors for Inoculum Production and Protein Expression  

Science Journals Connector (OSTI)

Table 1 summarizes the disposable bioreactors available on the market today for animal cells and culture volumes from 2.5 mL up to 500 L. If traditional ...

Regine Eibl; Dieter Eibl

2007-01-01T23:59:59.000Z

272

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

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

273

Land disposal of water treatment plant sludge -- A feasibility analysis  

SciTech Connect (OSTI)

In this study, the following alternative disposal methods for the Buffalo Pound Water Treatment Sludge were evaluated: landfilling, discharge into sanitary sewers, long-term lagooning, use in manufacturing, co-composting, alum recovery and land application. Land application was chosen at the best disposal alternative. Preliminary design resulted in a 1% dry alum sludge loading rate (25 tonnes/ha), requiring 35 ha over a nine-year period and a phosphorus fertilizer supplement of about 50kg/ha.

Viraraghavan, T.; Multon, L.M.; Wasylenchuk, E.J.

1998-07-01T23:59:59.000Z

274

Geological Disposal Concept Selection Aligned with a Voluntarism Process - 13538  

SciTech Connect (OSTI)

The UK's Radioactive Waste Management Directorate (RWMD) is currently at a generic stage in its implementation programme. The UK site selection process is a voluntarist process and, as yet, no communities have decided to participate. RWMD has set out a process to describe how a geological disposal concept would be selected for the range of higher activity wastes in the UK inventory, including major steps and decision making points, aligned with the stages of the UK site selection process. A platform of information is being developed on geological disposal concepts at various stages of implementation internationally and, in order to build on international experience, RWMD is developing its approach to technology transfer. The UK has a range of different types of higher activity wastes with different characteristics; therefore a range of geological disposal concepts may be needed. In addition to identifying key aspects for considering the compatibility of different engineered barrier systems for different types of waste, RWMD is developing a methodology to determine minimum separation distances between disposal modules in a co-located geological disposal facility. RWMD's approach to geological disposal concept selection is intended to be flexible, recognising the long term nature of the project. RWMD is also committed to keeping alternative radioactive waste management options under review; an approach has been developed and periodic reviews of alternative options will be published. (authors)

Crockett, Glenda; King, Samantha [Nuclear Decommissioning Authority, Building 587, Curie Avenue, Harwell Oxford, Didcot, Oxfordshire, OX11 0RH (United Kingdom)] [Nuclear Decommissioning Authority, Building 587, Curie Avenue, Harwell Oxford, Didcot, Oxfordshire, OX11 0RH (United Kingdom)

2013-07-01T23:59:59.000Z

275

University of Delaware Laboratory Chemical Waste Disposal Guide ALL CHEMICAL WASTE MUST BE DISPOSED OF THROUGH THE  

E-Print Network [OSTI]

experiments and procedures Non-Returnable gas cylinders Batteries Spent solvents, Stains, Strippers, Thinners, Fertilizers Formaldehyde and Formalin Solutions Mercury containing items (other heavy metals) Liquid OR SMALL CONTAINERS IMPORTANT: DO NOT DISPOSE OF REACTIVE, AIR SENSITIVE, OR OXIDIZER SAMPLES

Firestone, Jeremy

276

Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance  

Broader source: Energy.gov [DOE]

Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance

277

Analysis of environmental regulations governing the disposal of geothermal wastes in California  

SciTech Connect (OSTI)

Federal and California regulations governing the disposal of sludges and liquid wastes associated with the production of electricity from geothermal resources were evaluated. Current disposal practices, near/far term disposal requirements, and the potential for alternate disposal methods or beneficial uses for these materials were determined. 36 refs., 3 figs., 15 tabs. (ACR)

Royce, B.A.

1985-09-01T23:59:59.000Z

278

Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the various technologies available. It is hoped that the resulting research can build a bridge between technology transfer research and waste disposal research in order to enhance the exchange of more sustainable solutions in future.

Dorn, Thomas, E-mail: thomas.dorn@uni-rostock.de [University of Rostock, Faculty of Agricultural and Environmental Sciences, Department Waste Management, Justus-v.-Liebig-Weg 6, 18059 Rostock (Germany); Nelles, Michael, E-mail: michael.nelles@uni-rostock.de [University of Rostock, Faculty of Agricultural and Environmental Sciences, Department Waste Management, Justus-v.-Liebig-Weg 6, 18059 Rostock (Germany); Flamme, Sabine, E-mail: flamme@fh-muenster.de [University of Applied Sciences Muenster, Corrensstrasse 25, 48149 Muenster (Germany); Jinming, Cai [Hefei University of Technology, 193 Tunxi Road, 230009 Hefei (China)

2012-11-15T23:59:59.000Z

279

Disposal of oil field wastes into salt caverns: Feasibility, legality, risk, and costs  

SciTech Connect (OSTI)

Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of oil field wastes, the risks to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne`s research indicates that disposal of oil field wastes into salt caverns is feasible and legal. The risk from cavern disposal of oil field wastes appears to be below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

Veil, J.A. [Argonne National Lab., Washington, DC (United States). Water Policy Program

1997-10-01T23:59:59.000Z

280

Microsoft Word - Other Template.docx  

National Nuclear Security Administration (NNSA)

Laney 2010 Laney, C., 2010, U.S. Ecology, personal communication (email) to G. Roles, Science Applications International Corporation, "RE: Waste disposal at the LLW site in...

Note: This page contains sample records for the topic "wds llw disposal" 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

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

SciTech Connect (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

282

Unique method of ash disposal can benefit marine life  

SciTech Connect (OSTI)

As more communities turn to waste-to-energy facilities to help solve their solid waste disposal problems, the amount of ash created by these facilities increases. Incineration of solid waste produces particulate residues which are often rich in lead, cadmium, copper, and zinc because of the concentration which occurs as a result of reduction. It has been shown that such metals can sometimes be leached from ash residues, giving rise to special concerns that incineration ashes be disposed of in an environmentally acceptable manner. In urban coastal areas where landfills are few and increasingly distant, ocean disposal of stabilized incineration residues (SIR) may provide an acceptable alternative to current landfill practices. In May 1985, a research program was initiated at the Marine Sciences Research Center to examine the feasibility of utilizing SIR for artificial reef construction in the ocean. Results of these studies showed that particulate incineration residues could be combined with cement to form a solid block possessing physical properties necessary for ocean disposal. The stabilized residues were subjected to regulatory extraction protocols, and in no instance did the metal concentrations in the leachates exceed the regulatory limits for toxicity. Bioassays revealed no adverse effects on the phytoplankton communities exposed to elutriate concentrations higher than could be encountered under normal disposal conditions. The success of the laboratory studies resulted in securing the necessary permits for the placement of an artificial habitat constructed using SIR in coastal wasters. Results from this program are described.

Roethel, F.J.; Breslin, V.T. (State Univ. of New York, Stony Brook (USA))

1988-10-01T23:59:59.000Z

283

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion  

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

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars August 1, 2012 - 12:00pm Addthis For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory’s (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation’s few repositories for U-233 and other special nuclear materials dating back to the Manhattan Project. For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory's (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation's few repositories for U-233 and other special nuclear materials

284

Laboratory to demolish excavation enclosures at Material Disposal Area B  

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

Excavation Enclosures At MDA B Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Communications Office (505) 667-7000 "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

285

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

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

00: Managing Treatment, Storage, and Disposal of Radioactive 00: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY This EIS evaluates the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008 EIS-0200: Amendment to the Record of Decision Treatment and Storage of Transuranic Waste

286

Laboratory to demolish excavation enclosures at Material Disposal Area B  

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

Excavation enclosures at MDA B Excavation enclosures at MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Colleen Curran Communications Office (505) 664-0344 Email "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

287

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

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

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY Final Waste Management Programmatic Environmental Impact Statement examines the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008

288

Laboratory to demolish excavation enclosures at Material Disposal Area B  

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

Excavation Enclosures At MDA B Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. Contact Communications Office (505) 667-7000 "We look forward to the day we officially turn the property over for the benefit of our community." Work is beginning this week LOS ALAMOS, New Mexico, November 1, 2012-Los Alamos National Laboratory

289

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

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

Gas, Heat, Water, Sewerage Collection and Disposal, and Street Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) Gas, Heat, Water, Sewerage Collection and Disposal, and Street Railway Companies (South Carolina) < Back Eligibility Agricultural Commercial Construction Industrial Installer/Contractor Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State South Carolina Program Type Generating Facility Rate-Making Siting and Permitting Provider South Carolina Public Service Commission This legislation applies to public utilities and entities furnishing natural gas, heat, water, sewerage, and street railway services to the public. The legislation addresses rates and services, exemptions, investigations, and records. Article 4 (58-5-400 et seq.) of this

290

EM's Richland Operations Office Celebrates Disposal Achievement in 2013 |  

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

EM's Richland Operations Office Celebrates Disposal Achievement EM's Richland Operations Office Celebrates Disposal Achievement in 2013 EM's Richland Operations Office Celebrates Disposal Achievement in 2013 December 24, 2013 - 12:00pm Addthis Workers sample a well used to monitor groundwater at the Hanford site. Workers sample a well used to monitor groundwater at the Hanford site. Workers separate a glove box for removal from Hanford’s Plutonium Finishing Plant. Workers separate a glove box for removal from Hanford's Plutonium Finishing Plant. Workers sample a well used to monitor groundwater at the Hanford site. Workers separate a glove box for removal from Hanford's Plutonium Finishing Plant. RICHLAND, Wash. - EM's Richland Operations Office's 2013 accomplishments ranged from cleaning up buildings and waste sites to treating a record

291

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion  

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

EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars EM Plan Accelerates Uranium-233 Disposal, Saves Taxpayers Half Billion Dollars August 1, 2012 - 12:00pm Addthis For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory’s (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation’s few repositories for U-233 and other special nuclear materials dating back to the Manhattan Project. For more than 50 years, the uranium-233 (U-233) supply has been stored at the Oak Ridge National Laboratory's (ORNL) Building 3019. The facility, located near the center of the ORNL campus, is owned by EM and one of the nation's few repositories for U-233 and other special nuclear materials

292

Crystalline ceramics: Waste forms for the disposal of weapons plutonium  

SciTech Connect (OSTI)

At present, there are three seriously considered options for the disposition of excess weapons plutonium: (i) incorporation, partial burn-up and direct disposal of MOX-fuel; (ii) vitrification with defense waste and disposal as glass ``logs``; (iii) deep borehole disposal (National Academy of Sciences Report, 1994). The first two options provide a safeguard due to the high activity of fission products in the irradiated fuel and the defense waste. The latter option has only been examined in a preliminary manner, and the exact form of the plutonium has not been identified. In this paper, we review the potential for the immobilization of plutonium in highly durable crystalline ceramics apatite, pyrochlore, monazite and zircon. Based on available data, we propose zircon as the preferred crystalline ceramic for the permanent disposition of excess weapons plutonium.

Ewing, R.C.; Lutze, W. [New Mexico Univ., Albuquerque, NM (United States); Weber, W.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-05-01T23:59:59.000Z

293

Earth melter and method of disposing of feed materials  

SciTech Connect (OSTI)

An apparatus, and method of operating the apparatus, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials.

Chapman, Christopher C. (Richland, WA)

1994-01-01T23:59:59.000Z

294

Subproject L-045H 300 Area Treated Effluent Disposal Facility  

SciTech Connect (OSTI)

The study focuses on the project schedule for Project L-045H, 300 Area Treated Effluent Disposal Facility. The 300 Area Treated Effluent Disposal Facility is a Department of Energy subproject of the Hanford Environmental Compliance Project. The study scope is limited to validation of the project schedule only. The primary purpose of the study is to find ways and means to accelerate the completion of the project, thereby hastening environmental compliance of the 300 Area of the Hanford site. The 300 Area'' has been utilized extensively as a laboratory area, with a diverse array of laboratory facilities installed and operational. The 300 Area Process Sewer, located in the 300 Area on the Hanford Site, collects waste water from approximately 62 sources. This waste water is discharged into two 1500 feet long percolation trenches. Current environmental statutes and policies dictate that this practice be discontinued at the earliest possible date in favor of treatment and disposal practices that satisfy applicable regulations.

Not Available

1991-06-01T23:59:59.000Z

295

Classified Component Disposal at the Nevada National Security Site  

SciTech Connect (OSTI)

The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012.

Poling, J. [NSTec; Arnold, P. [NSTec; Saad, M. [SNL; DiSanza, F.; Cabble, K. [NNSA/NSO

2012-11-05T23:59:59.000Z

296

Idaho CERCLA Disposal Facility at Idaho National Laboratory  

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

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

297

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria  

SciTech Connect (OSTI)

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

W. Mahlon Heileson

2006-10-01T23:59:59.000Z

298

Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites  

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

Annual Site Inspection and Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites November 2012 LMS/S09415 ENERGY Legacy Management U.S. DEPARTMENT OF Sherwood, Washington, Disposal Site, 2012 Sherwood, Washington, Disposal Site, 2012 L-Bar, New Mexico, Disposal Site, 2012 L-Bar, New Mexico, Disposal Site, 2012 Bluewater, New Mexico, Disposal Site, 2012 Bluewater, New Mexico, Disposal Site, 2012 Maybell West, Colorado, Disposal Site, 2012 Maybell West, Colorado, Disposal Site, 2012 This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy,

299

BLT-EC (Breach, Leach Transport, and Equilibrium Chemistry), a finite-element model for assessing the release of radionuclides from low-level waste disposal units: Background, theory, and model description  

SciTech Connect (OSTI)

Performance assessment models typically account for the processes of sorption and dissolution-precipitation by using an empirical distribution coefficient, commonly referred to as K{sub d} that combines the effects of all chemical reactions between solid and aqueous phases. In recent years, however, there has been an increasing awareness that performance assessments based solely on empirically based K{sub d} models may be incomplete, particularly for applications involving radionuclides having sorption and solubility properties that are sensitive to variations in the in-situ chemical environment. To accommodate variations in the in-situ chemical environment, and to assess its impact on radionuclide mobility, it is necessary to model radionuclide release, transport, and chemical processes in a coupled fashion. This modeling has been done and incorporated into the two-dimensional, finite-element, computer code BLT-EC (Breach, Leach, Transport, Equilibrium Chemistry). BLT-EC is capable of predicting container degradation, waste-form leaching, and advective-dispersive, multispecies, solute transport. BLT-EC accounts for retardation directly by modeling the chemical processes of complexation, sorption, dissolution-precipitation, ion-exchange, and oxidation-reduction reactions. In this report we: (1) present a detailed description of the various physical and chemical processes that control the release and migration of radionuclides from shallow land LLW disposal facilities; (2) formulate the mathematical models that represent these processes; (3) outline how these models are incorporated and implemented in BLT-EC; and (4) demonstrate the application of BLT-EC on a set of example problems.

MacKinnon, R.J.; Sullivan, T.M. [Brookhaven National Lab., Upton, NY (United States); Simonson, S.A. [Massachusetts Inst. of Technology, Cambridge, MA (United States); Suen, C.J. [California State Univ., Fresno, CA (United States)

1995-08-01T23:59:59.000Z

300

Ministers block disposal of oil rigs at sea  

Science Journals Connector (OSTI)

... ministers last week ended three years of public controversy about the fate of disused oil rigs in the northeast Atlantic ocean. They decided that most will have to be dismantled ... all environmentalist groups. Oil companies, on the other hand, were disappointed. The UK Offshore Operators Association said the decision to outlaw deep-sea disposal of oil and gas ...

Ehsan Masood

1998-07-30T23:59:59.000Z

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


301

Disposal of soluble salt waste from coal gasification  

SciTech Connect (OSTI)

This paper addresses pollutants in the form of soluble salts and resource recovery in the form of water and land. A design for disposal of soluble salts has been produced. The interactions of its parameters have been shown by a process design study. The design will enable harmonious compliance with United States Public Laws 92-500 and 94-580, relating to water pollution and resource recovery. In the disposal of waste salt solutions, natural water resources need not be contaminated, because an encapsulation technique is available which will immobilize the salts. At the same time it will make useful landforms available, and water as a resource can be recovered. There is a cost minimum when electrodialysis and evaporation are combined, which is not realizable with evaporation alone, unless very low-cost thermal energy is available or unless very high-cost pretreatment for electrodialysis is required. All the processes making up the proposed disposal process are commercially available, although they are nowhere operating commercially as one process. Because of the commercial availability of the processes, the proposed process may be a candidate 'best commercially available treatment' for soluble salt disposal.

McKnight, C.E.

1980-06-01T23:59:59.000Z

302

Design of a Large Explosive Ordnance Disposal Robot  

Science Journals Connector (OSTI)

The explosive ordnance disposal robot (EOD robot) can replace man to reconnoiter, remove and deal with explosives or other dangerous articles in the dangerous environment. We design a large EOD robot which is constituted by the vehicle body, the mechanical ... Keywords: EOD robot, vehicle body, mechanical hand, vision system

Boyu Wei; Junyao Gao; Jianguo Zhu; Kejie Li

2009-10-01T23:59:59.000Z

303

Support of the Iraq nuclear facility dismantlement and disposal program  

SciTech Connect (OSTI)

Available in abstract form only. Full text of publication follows: Iraq's former nuclear facilities contain large quantities of radioactive materials and radioactive waste. The Iraq Nuclear Facility Dismantlement and Disposal Program (the Iraq NDs Program) is a new program to decontaminate and permanently dispose of radioactive wastes in Iraq. The NDs Program is led by the Government of Iraq, under International Atomic Energy Agency (IAEA) auspices, with guidance and assistance from a number of countries. The U.S. participants include Texas Tech University and Sandia National Laboratories. A number of activities are ongoing under the broad umbrella of the Iraq NDs Program: drafting a new nuclear law that will provide the legal basis for the cleanup and disposal activities; assembly and analysis of existing data; characterization of soil contamination; bringing Iraqi scientists to the world's largest symposium on radioactive waste management; touring U.S. government and private sector operating radwaste disposal facilities in the U.S., and hosting a planning workshop on the characterization and cleanup of the Al-Tuwaitha Nuclear Facility. (authors)

Coates, Roger [International Atomic Energy Agency - IAEA, Wagramer Strasse 5, P.O. Box 100 - 1400 Vienna (Austria); Cochran, John; Danneels, Jeff [Sandia National Laboratories (United States); Chesser, Ronald; Phillips, Carlton; Rogers, Brenda [Center for Environmental Radiation Studies, Texas Tech University, Lubbock, TX 79409 (United States)

2007-07-01T23:59:59.000Z

304

On-Farm Storage and Disposal of Sorghum Grain.  

E-Print Network [OSTI]

APRIL 1963 ON-FARM - STORAGE AND DISPOSAL OF SORGHUM GRAIN -- THE AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS TEXAS AGRICULTURAL EXPERIMENT STATION R. E. PATTERSON. DIRECTOR. COLLEGE ST+TION, TEXAS IN COOPERATION WITH THE U. S. DEPARTMENT... OF AGRICULTURE summary The sorghum storage space. Utilization increases resulted from an increased awareness and acceptance by feeders and millers...

Brown, Charles W.; Moore, Clarence A.

1963-01-01T23:59:59.000Z

305

Pyroprocessing oxide spent nuclear fuels for efficient disposal  

SciTech Connect (OSTI)

Pyrochemical processing as a means for conditioning spent nuclear fuels for disposal offers significant advantages over the direct disposal option. The advantages include reduction in high-level waste volume; conversion of most of the high-level waste to a low-level waste in which nearly all the transuranics (TRU) have been removed; and incorporation of the TRUs into a stable, highly radioactive waste form suitable for interim storage, ultimate destruction, or repository disposal. The lithium process has been under development at Argonne National Laboratory for use in pyrochemical conditioning of spent fuel for disposal. All of the process steps have been demonstrated in small-scale (0.5-kg simulated spent fuel) experiments. Engineering-scale (20-kg simulated spent fuel) demonstration of the process is underway, and small-scale experiments have been conducted with actual spent fuel from a light water reactor (LWR). The lithium process is simple, operates at relatively low temperatures, and can achieve high decontamination factors for the TRU elements. Ordinary materials, such as carbon steel, can be used for process containment.

McPheeters, C.C.; Pierce, R.D.; Mulcahey, T.P. [Argonne National Lab., IL (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

306

Disposal of CCA-treated Wood: An Evaluation of  

E-Print Network [OSTI]

Disposal of CCA-treated Wood: An Evaluation of Existing and Alternative Management Options (FINAL CHARACTERISTICS OF CCA-TREATED WOOD ASH II.1 Sample Preparation 10 II.2 Laboratory Methods 15 II.3 Laboratory Results 24 CHAPTER III, SORTING TECHNOLOGIES FOR SEPARATING TREATED WOOD FROM UNTREATED WOOD III.1

Florida, University of

307

The College of Engineering Electronic Media Disposal Policy  

E-Print Network [OSTI]

The College of Engineering Electronic Media Disposal Policy COE­EMD­01 1.0 Purpose The purpose of Engineering employees, contractors, consultants, temporary personnel, and other workers responsible electronic information on the medium, such as a computer, personal hand held device, audio or video player

Demirel, Melik C.

308

Long-Term Performance of Uranium Tailings Disposal Cells - 13340  

SciTech Connect (OSTI)

Recently, there has been interest in the performance and evolution of Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell covers because some sites are not compliant with groundwater standards. Field observations of UMTRA disposal cells indicate that rock covers tend to become vegetated and that saturated conductivities in the upper portion of radon barriers may increase due to freeze/thaw cycles and biointrusion. This paper describes the results of modeling that addresses whether these potential changes and transient drainage of moisture in the tailings affect overall performance of the disposal cells. A numerical unsaturated/saturated 3-dimensional flow model was used to simulate whether increases in saturated conductivities in radon barriers with rock covers affect the overall performance of the disposal cells using field data from the Shiprock, NM, UMTRA site. A unique modeling approach allowed simulation with daily climatic conditions to determine changes in moisture and moisture flux from the disposal cell. Modeling results indicated that increases in the saturated conductivity at the top of radon barrier do not influence flux from the tailings with time because the tailings behave similar hydraulically to the radon barrier. The presence of a thin layer of low conductivity material anywhere in the cover or tailings restricts flux in the worst case to the saturated conductivity of that material. Where materials are unsaturated at depth within the radon barrier of tailings slimes, conductivities are typically less than 10{sup -8} centimeters per second. If the low conductivity layer is deep within the disposal cell, its saturated properties are less likely to change with time. The significance of this modeling is that operation and maintenance of the disposal cells can be minimized if they are allowed to progress to a natural condition with some vegetation and soil genesis. Because the covers and underlying tailings have a very low saturated hydraulic conductivity after transient drainage, eventually the amount of moisture leaving the tailings has a negligible effect on groundwater quality. Although some of the UMTRA sites are not in compliance with the groundwater standards, the explanation may be legacy contamination from mining, or earlier higher fluxes from the tailings or unlined processing ponds. Investigation of other legacy sources at the UMTRA sites may help explain persistent groundwater contamination. (authors)

Bostick, Kent; Daniel, Anamary; Pill, Ken [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States)] [Professional Project Services, Inc., 1100 Bethel Valley Road, Oak Ridge, TN, 37922 (United States); Tachiev, Georgio; Noosai, Nantaporn; Villamizar, Viviana [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)] [Florida International University, 10555 W. Flagler St., EC 2100, Miami FL, 33174 (United States)

2013-07-01T23:59:59.000Z

309

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

SciTech Connect (OSTI)

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

310

Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) |  

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

Preliminary Report on Dual-Purpose Canister Disposal Alternatives Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel (SNF) in existing dual-purpose canisters (DPCs) and other types of storage casks. The first phase includes a set of preliminary disposal concepts and associated technical analyses, identification of additional R&D needs, and a recommendation to proceed with the next phase of the evaluation effort. Preliminary analyses indicate that DPC direct disposal could be technically feasible, at least for certain disposal concepts. DPC disposal concepts include the salt concept, and emplacement

311

Analysis of mineral trapping for CO2 disposal in deep aquifers  

E-Print Network [OSTI]

of Mineral Trapping for CO2 Disposal in Deep Aquifers Tianfue~mail: Tianfu Xu@lbl. gov) CO2 disposal into deep aquiferspermit significant sequestration of CO2. We performed batch

Xu, Tianfu

2014-01-01T23:59:59.000Z

312

DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN,  

E-Print Network [OSTI]

i DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN, CHAOPRAYA Sludge (FS) management and lacking of data on FS collection, treatment and disposal. Nevertheless, FS

Richner, Heinz

313

Environmental Protection Problems Connected to the Disposal of Ammunition and Explosives by Open Pit Burning  

Science Journals Connector (OSTI)

At the end of its functional life time, in service ammunition has to be disposed, as welt as the war time ammunition and explosives which are still beiing recovered. Formerly the conventional way of disposing amm...

Drs N. H. A. van Ham; A. Verweij

1990-01-01T23:59:59.000Z

314

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry  

Science Journals Connector (OSTI)

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry ... Various aspects of nuclear waste disposal are discussed for their value in providing pedagogical examples. ... Radioactivity, Radiation, and the Chemistry of Nuclear Waste ...

Gregory R. Choppin

1994-01-01T23:59:59.000Z

315

Format and Content Guide for DOE Low-Level Waste Disposal Facility...  

Office of Environmental Management (EM)

Format and Content Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments...

316

Format and Content Guide for DOE Low-Level Waste Disposal Facility...  

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

and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure...

317

Classification and disposal of radioactive wastes: History and legal and regulatory requirements  

SciTech Connect (OSTI)

This document discusses the laws and regulations in the United States addressing classification of radioactive wastes and the requirements for disposal of different waste classes. This review emphasizes the relationship between waste classification and the requirements for permanent disposal.

Kocher, D.C.

1990-01-01T23:59:59.000Z

318

Risk assessment involving the land disposal of animal waste on Central Texas dairies  

E-Print Network [OSTI]

with nutrient disposal on two central Texas dairies. Risks were identified by using producer and researcher knowledge to create graphic representations of the disposal systems. These representations, known as event and fault trees, were used in conjunction...

Lee, Thomas Chadwick

2012-06-07T23:59:59.000Z

319

E-Print Network 3.0 - alternative disposal options Sample Search...  

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

within the park, up... the dredging area to the disposal site via a 10 or 12" diameter pipeline. Alternatively, if the dredgeate 12... ;EXECUTIVE SUMMARY ii was to be disposed...

320

Concept study: Use of grout vaults for disposal of long-length contaminated equipment  

SciTech Connect (OSTI)

Study considers the potential for use of grout vaults for disposal of untreated long length equipment removed from waste tanks. Looks at ways to access vaults, material handling, regulatory aspects, and advantages and disadvantages of vault disposal.

Clem, D.K.

1994-09-21T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Assessment of Disposal Options for DOE-Managed High-Level Radioactive...  

Office of Environmental Management (EM)

Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and Spent Nuclear Fuel Assessment of Disposal Options for DOE-Managed High-Level Radioactive Waste and...

322

Geochemical factors affecting radionuclide transport through near and far fields at a Low-Level Waste Disposal Site  

SciTech Connect (OSTI)

The concentration of low-level waste (LLW) contaminants in groundwater is determined by the amount of contaminant present in the solid waste, rate of release from the waste and surrounding barriers, and a number of geochemical processes including adsorption, desorption, diffusion, precipitation, and dissolution. To accurately predict radionuclide transport through the subsurface, it is essential that the important geochemical processes affecting radionuclide transport be identified and, perhaps more importantly, accurately quantified and described in a mathematically defensible manner.

Kaplan, D.I.; Seme, R.J. [Pacific Northwest Lab., Richland, WA (United States); Piepkho, M.G. [Westinghouse Hanford Co., Richland, WA (United States)

1995-03-01T23:59:59.000Z

323

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

SciTech Connect (OSTI)

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

Arnold, P.

2012-10-31T23:59:59.000Z

324

Environmental regulations and technology: use and disposal of municipal waste-water sludge  

SciTech Connect (OSTI)

The document describes the five major sludge use/disposal options currently available--land application, distribution and marketing of sludge products, land-filling, incineration, and ocean disposal--and factors influencing their selection and implementation. It also provides an initial framework for evaluating sludge use/disposal alternatives, and describes accepted and proven use/disposal technologies and Federal regulations pertinent to sludge management.

Not Available

1984-09-01T23:59:59.000Z

325

Amended Record of Decision for the Department of Energy's Final Programmatic Environmental Impact Statement for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the U.S. (DOE/EIS-0310) (08/13/04)  

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

0 0 Federal Register / Vol. 69, No. 156 / Friday, August 13, 2004 / Notices (LLW), mixed low-level waste (MLLW), Transuranic (TRU) waste, and immobilized low activity waste to support clean up at Hanford and to assist other DOE sites in completing their cleanup programs. DOE decided in the ROD to (1) limit the volumes of LLW and MLLW received at Hanford from other sites for disposal; (2) dispose of LLW in lined disposal facilities, a practice already used for MLLW; (3) construct and operate a lined, combined-use disposal facility (previously referenced in this Notice of Intent as the ''Integrated Disposal Facility'') in Hanford's 200 East Area for disposal of LLW and MLLW, and further limit offsite waste receipts until the IDF is constructed; (4) treat LLW and MLLW

326

River Protection Project (RPP) Tank Waste Retrieval and Disposal Mission Technical Baseline Summary Description  

SciTech Connect (OSTI)

This document is one of the several documents prepared by Lockheed Martin Hanford Corp. to support the U. S. Department of Energy's Tank Waste Retrieval and Disposal mission at Hanford. The Tank Waste Retrieval and Disposal mission includes the programs necessary to support tank waste retrieval; waste feed, delivery, storage, and disposal of immobilized waste; and closure of the tank farms.

DOVALLE, O.R.

1999-12-29T23:59:59.000Z

327

ASSESSING GHG EMISSIONS FROM SLUDGE TREATMENT AND DISPOSAL ROUTES THE METHOD BEHIND GESTABOUES TOOL  

E-Print Network [OSTI]

ASSESSING GHG EMISSIONS FROM SLUDGE TREATMENT AND DISPOSAL ROUTES ­ THE METHOD BEHIND GESTABOUES TOOL Pradel M., Reverdy, A.L. ORBIT2012 1 Assessing GHG emissions from sludge treatment and disposal. These different disposal routes as well as the sludge treatments produce greenhouse gases (GHG). To help

Boyer, Edmond

328

New Review of Nuclear Waste Disposal Calls for Early Test in New Mexico  

Science Journals Connector (OSTI)

...WIPP spent fuel disposal demonstration...licensing and site selection could...date. Waste disposal will not be inexpen-sive...such as those at Maxey Flats, Kentucky...long-term waste disposal facili-ties...formation at the WIPP site. Satisfying...

WILLIAM D. METZ

1978-03-31T23:59:59.000Z

329

Microbial activity of trench leachates from shallow-land, low-level radioactive waste disposal sites.  

Science Journals Connector (OSTI)

...samples collected from disposal sites at Maxey Flats, Ky., and West...trenches at the disposal sites of Maxey Flats, Ky., West Valley...trench water at the Maxey Flats low-level radioactive waste disposal site, p. 747-761...

A J Francis; S Dobbs; B J Nine

1980-07-01T23:59:59.000Z

330

Environmental Impact of Wastewater Disposal in the Florida Keys, Monroe County Tom Higginbotham  

E-Print Network [OSTI]

Environmental Impact of Wastewater Disposal in the Florida Keys, Monroe County Tom Higginbotham University of Florida Soil and Water Science #12;Environmental Impact of Wastewater Disposal in the Florida affecting the normally oligotrophic marine waters. Typical methods of wastewater disposal include large

Ma, Lena

331

Alternative Chemicals and Improved Disposal-End Management Practices for CCA-treated Wood  

E-Print Network [OSTI]

Alternative Chemicals and Improved Disposal-End Management Practices for CCA-treated Wood (FINAL.7 Costs 54 II.8 Feedback from Wood Treaters and Large-End Users 56 CHAPTER III, DISPOSAL.3 Resource Book for the Wood Disposal Sector 85 CHAPTER IV IV.1 Conclusion and Recommendations IV.2

Florida, University of

332

Generation, Use, Disposal, and Management Options for CCA-Treated Wood  

E-Print Network [OSTI]

Generation, Use, Disposal, and Management Options for CCA-Treated Wood May 1998 Helena Solo, INVENTORY OF CCA-TREATED WOOD IN FLORIDA II.1 Characteristics of the Florida Wood Treatment Industry in 1996 10 II.2 Generation and Disposal of Cca-treated Wood 14 II.3 Disposal Reservoirs for Cca-treated Wood

Florida, University of

333

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

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

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

334

The Effects of CO2 Disposal on Marine Nitrification Processes  

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

Effects of CO Effects of CO 2 Disposal on Marine Nitrification Processes Michael H. Huesemann (michael.huesemann@pnl.gov, 360-681-3618) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Ann D. Skillman (ann.skillman@pnl.gov, 360-681-3649) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Eric A. Crecelius (eric.crecelius@pnl.gov, 360-681-3604) Pacific Northwest National Laboratory - Marine Sciences Laboratory 1529 West Sequim Bay Road Sequim, WA 98382 Abstract In an attempt to reduce the threat of global warming, it has been proposed that the rise of atmospheric carbon dioxide concentrations be reduced by the ocean disposal of CO 2 from the flue gases of fossil fuel-fired power plants. The release of large amounts of

335

LANL demolishes first containment dome at disposal area  

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

LANL Demolishes First Containment Dome LANL Demolishes First Containment Dome LANL demolishes first containment dome at disposal area It once housed thousands of drums of radioactive waste that have been shipped to the Waste Isolation Pilot Plant for disposal. September 30, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

336

Operational Issues at the Environmental Restoration Disposal Facility at Hanford  

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

Hanford Operations Hanford Operations Evaluating Operational Issues at the Environmental Restoration Disposal Facility at Hanford By Craig H. Benson, PhD, PE; William H. Albright, PhD; and David P. Ray, PE Sponsored by: The Office of Engineering and Technology (EM-20) 17 June 2007 i TABLE OF CONTENTS EXECUTIVE SUMMARY ii ACKNOWLEDGEMENTS iv INTRODUCTION 1 BACKGROUND 1 Environmental Restoration Disposal Facility 1 Source of Concern 2 LINES OF INQUIRY 2 1. Validate Scope of Identified Problems 2 2. Assess Contractor Evaluation of the Elevated Leachate Level on the Landfill Liner 3 3. Evaluate Adequacy of Landfill Performance in View of the Discovered Falsified Compaction Data and Potential Leachate Level Problems 4

337

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Delivers First Radioactive Waste Shipment to Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and

338

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

339

WIPP Reaches Milestone „ First Disposal Room Filled  

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

WIPP Reaches Milestone - First Disposal Room Filled CARLSBAD, N.M., September 4, 2001 - The U.S. Department of Energy's (DOE) Carlsbad Field Office today announced that Room 7 of Panel 1 at the Waste Isolation Pilot Plant (WIPP), the first underground room used for disposal operations, has been filled to capacity with transuranic waste. The milestone was reached at about 3:30 p.m. on August 24, as Waste Handling personnel emplaced a shipment of waste from the Idaho National Engineering and Environmental Laboratory. On August 25, Underground Operations personnel completed installation of a chain link mesh barrier and cloth drape across the entrance to the room to officially declare the area "closed." The first shipment of waste, which came

340

Field study of disposed solid wastes from advanced coal processes  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid waste produced by advanced coal processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites have been selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's site using waste from Midwest Grain's FBC unit in central Illinois. A fourth site is under consideration at the Dakota Gasification Company in North Dakota. The first two tasks of this project involved the development of test plans and obtaining site access.

Not Available

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" 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

Integrated process for coalbed brine and methane disposal  

SciTech Connect (OSTI)

This paper describes a technology and project to demonstrate and commercialize a brine disposal process for converting the brine stream of a coalbed gas producing site into clean water for agricultural use and dry solids that can be recycled for industrial consumption. The process also utilizes coalbed methane (CBM) released from coal mining for the combustion process thereby substantially reducing the potential for methane emissions to the atmosphere. The technology is ideally suited for the treatment and disposal of produced brines generated from the development of coal mines and coalbed methane resources worldwide. Over the next 10 to 15 years, market potential for brine elimination equipment and services is estimated to be in the range of $1 billion.

Byam, J.W. Jr.; Tait, J.H.; Brandt, H.

1996-12-31T23:59:59.000Z

342

Regulatory requirements affecting disposal of asbestos-containing waste  

SciTech Connect (OSTI)

Many U.S. Department of Energy (DOE) facilities are undergoing decontamination and decommissioning (D&D) activities. The performance of these activities may generate asbestos-containing waste because asbestos was formerly used in many building materials, including floor tile, sealants, plastics, cement pipe, cement sheets, insulating boards, and insulating cements. The regulatory requirements governing the disposal of these wastes depend on: (1) the percentage of asbestos in the waste and whether the waste is friable (easily crumbled or pulverized); (2) other physical and chemical characteristics of the waste; and (3) the State in which the waste is generated. This Information Brief provides an overview of the environment regulatory requirements affecting disposal of asbestos-containing waste. It does not address regulatory requirements applicable to worker protection promulgated under the Occupational Safety and Health Act (OSHAct), the Mining Safety and Health Act (MSHA), or the Toxic Substances Control Act (TSCA).

NONE

1995-11-01T23:59:59.000Z

343

Drilling Waste Management Fact Sheet: Disposal in Salt Caverns  

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

Salt Caverns Salt Caverns Fact Sheet - Disposal in Salt Caverns Introduction to Salt Caverns Underground salt deposits are found in the continental United States and worldwide. Salt domes are large, fingerlike projections of nearly pure salt that have risen to near the surface. Bedded salt formations typically contain multiple layers of salt separated by layers of other rocks. Salt beds occur at depths of 500 to more than 6,000 feet below the surface. Schematic Drawing click to view larger image Schematic Drawing of a Cavern in Domal Salt Schematic Drawing click to view larger image Schematic Drawing of a Cavern in Bedded Salt Salt caverns used for oil field waste disposal are created by a process called solution mining. Well drilling equipment is used to drill a hole

344

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Portsmouth Site Delivers First Radioactive Waste Shipment to Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the

345

Myth of nuclear explosions at waste disposal sites  

SciTech Connect (OSTI)

Approximately 25 years ago, an event is said to have occurred in the plains immediately west of the southern Ural mountains of the Soviet Union that is being disputed to this very day. One person says it was an explosion of nuclear wastes buried in a waste disposal site; other people say it was an above-ground test of an atomic weapon; still others suspect that an alleged contaminated area (of unknown size or even existence) is the result of a series of careless procedures. Since the event, a number of articles about the disposal-site explosion hypothesis written by a Soviet exile living in the United Kingdom have been published. Although the Soviet scientist's training and background are in the biological sciences and his knowledge of nuclear physics or chemistry is limited, people who oppose the use of nuclear energy seem to want to believe what he says without question. The work of this Soviet biologist has received wide exposure both in the United Kingdom and the United States. This report presents arguments against the disposal-site explosion hypothesis. Included are discussions of the amounts of plutonium that would be in a disposal site, the amounts of plutonium that would be needed to reach criticality in a soil-water-plutonium mixture, and experiments and theoretical calculations on the behavior of such mixtures. Our quantitative analyses show that the postulated nuclear explosion is so improbable that it is essentially impossible and can be found only in the never-never land of an active imagination. 24 references, 14 figures, 5 tables.

Stratton, W.R.

1983-10-01T23:59:59.000Z

346

Disposal of Draeger Tubes at Savannah River Site  

SciTech Connect (OSTI)

The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed.

Malik, N.P.

2000-10-13T23:59:59.000Z

347

Pyramiding tumuli waste disposal site and method of construction thereof  

DOE Patents [OSTI]

An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

Golden, Martin P. (Hamburg, NY)

1989-01-01T23:59:59.000Z

348

Iraq nuclear facility dismantlement and disposal project (NDs Project).  

SciTech Connect (OSTI)

The Al Tuwaitha nuclear complex near Baghdad contains a number of facilities from Saddam Hussan's nuclear weapons program. Past military operations, lack of upkeep and looting have created an enormous radioactive waste problem at the Al Tuwaitha complex, which contains various, uncharacterized radioactive wastes, yellow cake, sealed radioactive sources, and contaminated metals that must be constantly guarded. Iraq has never had a radioactive waste disposal facility and the lack of a disposal facility means that ever increasing quantities of radioactive material must be held in guarded storage. The Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) has been initiated by the U.S. Department of State (DOS) to assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials, while building human capacities so that the GOI can manage other environmental cleanups in their country. The DOS is funding the IAEA to provide technical assistance via Technical Cooperation projects. Program coordination will be provided by the DOS, consistent with GOI policies, and Sandia National Laboratories will be responsible for coordination of participants and waste management support. Texas Tech University will continue to provide in-country assistance, including radioactive waste characterization and the stand-up of the Iraq Nuclear Services Company. The GOI owns the problems in Iraq and will be responsible for implementation of the NDs Program.

Cochran, John Russell

2010-06-01T23:59:59.000Z

349

Hanford land disposal restrictions plan for mixed wastes  

SciTech Connect (OSTI)

Since the early 1940s, the Hanford Site has been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 (RCRA) and the Atomic Energy Act. The State of Washington Department of Ecology (Ecology), the US Environmental Protection Agency (EPA), and the US Department of Energy (DOE) have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) to bring Hanford Site Operations into compliance with dangerous waste regulations. The Tri-Party Agreement was amended to require development of the Hanford Land Disposal Restrictions Plan for Mixed Wastes (this plan) to comply with land disposal restrictions requirements for radioactive mixed waste. The Tri-Party Agreement requires, and the this plan provides, the following sections: Waste Characterization Plan, Storage Report, Treatment Report, Treatment Plan, Waste Minimization Plan, a schedule, depicting the events necessary to achieve full compliance with land disposal restriction requirements, and a process for establishing interim milestones. 34 refs., 28 figs., 35 tabs.

Not Available

1990-10-01T23:59:59.000Z

350

Disposal of Greater-than-Class C Low-Level Radioactive Waste  

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

Disposal of Low-Level Radioactive Waste Disposal of Low-Level Radioactive Waste EVS prepared a draft environmental impact statement (EIS) for disposal of greater-than-Class C low-level radioactive waste (GTCC LLRW). The EVS Division prepared a draft environmental impact statement (EIS) for disposal of greater-than-Class C low-level radioactive waste (GTCC LLRW) for the DOE Office of Environmental Management. DOE is now finalizing this EIS and is including a preferred alternative. DOE intends that the final EIS will provide information to support the selection of disposal method(s) and site(s) for GTCC LLRW and GTCC-like waste. In general, GTCC LLRW is not acceptable for near-surface disposal. Typically, the waste form and disposal methods must be different from and more stringent than those specified for Class C LLRW. For GTCC LLRW, the

351

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

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

352

Strategy for the Management and Disposal of Used Nuclear Fuel and  

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

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

353

Soil Segregation Methods for Reducing Transportation and Disposal Costs - 13544  

SciTech Connect (OSTI)

At Formerly Utilized Sites Remedial Action Program (FUSRAP) sites where the selected alternative for contaminated soil is excavation and off-site disposal, the most significant budget items of the remedial action are the costs for transportation and disposal of soil at an off-site facility. At these sites, the objective is to excavate and dispose of only those soils that exceed derived concentration guideline levels. In situ soil segregation using gross gamma detectors to guide the excavation is often challenging at sites where the soil contamination is overlain by clean soil or where the contaminated soil is located in isolated, subsurface pockets. In addition, data gaps are often identified during the alternative evaluation and selection process, resulting in increased uncertainty in the extent of subsurface contamination. In response, the U.S. Army Corps of Engineers, Buffalo District is implementing ex situ soil segregation methods. At the remediated Painesville Site, soils were excavated and fed through a conveyor-belt system, which automatically segregated them into above- and below-cleanup criteria discharge piles utilizing gamma spectroscopy. At the Linde Site and the Shallow Land Disposal Area (SLDA) Site, which are both in the remediation phase, soils are initially segregated during the excavation process using gross gamma detectors and then transported to a pad for confirmatory manual surveying and sampling. At the Linde Site, the ex situ soils are analyzed on the basis of a site-specific method, to establish compliance with beneficial reuse criteria that were developed for the Linde remediation. At the SLDA Site, the ex situ soils are surveyed and sampled based on Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) final status survey guidance to demonstrate compliance with the derived concentration guideline levels. At all three sites, the ex situ soils that meet the site- specific DCGLs are retained on-site and used as backfill material. This paper describes the ex situ soil segregation methods, the considerations of each method, and the estimated cost savings from minimizing the volume of soil requiring transportation and off-site disposal. (authors)

Frothingham, David; Andrews, Shawn; Barker, Michelle; Boyle, James; Buechi, Stephen; Graham, Marc; Houston, Linda; Polek, Michael; Simmington, Robert; Spector, Harold [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States)] [U.S. Army Corps of Engineers, Buffalo District, 1776 Niagara St., Buffalo, NY 14207 (United States); Elliott, Robert 'Dan' [U.S. Army Reserve, 812A Franklin St.,Worcester, MA 01604 (United States)] [U.S. Army Reserve, 812A Franklin St.,Worcester, MA 01604 (United States); Durham, Lisa [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)] [Argonne National Laboratory, Environmental Science Division, 9700 S. Cass Ave., Argonne, IL 60439 (United States)

2013-07-01T23:59:59.000Z

354

CCA-Treated wood disposed in landfills and life-cycle trade-offs with waste-to-energy and MSW landfill disposal  

E-Print Network [OSTI]

CCA-Treated wood disposed in landfills and life-cycle trade-offs with waste-to-energy and MSW in waste-to-energy (WTE) facilities. In other countries, the predominant disposal option for wood, others have not, and the product continues to enter the waste stream from construction, demolition

Florida, University of

355

Deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

2009-07-01T23:59:59.000Z

356

Design and Installation of a Disposal Cell Cover Field Test  

SciTech Connect (OSTI)

The U.S. Department of Energy’s Office of Legacy Management (LM) initiated a cover assessment project in September 2007 to evaluate an inexpensive approach to enhancing the hydrological performance of final covers for disposal cells. The objective is to accelerate and enhance natural processes that are transforming existing conventional covers, which rely on low-conductivity earthen barriers, into water balance covers, that store water in soil and release it as soil evaporation and plant transpiration. A low conductivity cover could be modified by deliberately blending the upper layers of the cover profile and planting native shrubs. A test facility was constructed at the Grand Junction, Colorado, Disposal Site to evaluate the proposed methodology. The test cover was constructed in two identical sections, each including a large drainage lysimeter. The test cover was constructed with the same design and using the same materials as the existing disposal cell in order to allow for a direct comparison of performance. One test section will be renovated using the proposed method; the other is a control. LM is using the lysimeters to evaluate the effectiveness of the renovation treatment by monitoring hydrologic conditions within the cover profile as well as all water entering and leaving the system. This paper describes the historical experience of final covers employing earthen barrier layers, the design and operation of the lysimeter test facility, testing conducted to characterize the as-built engineering and edaphic properties of the lysimeter soils, the calibration of instruments installed at the test facility, and monitoring data collected since the lysimeters were constructed.

Benson, C.H. [University of Wisconsin–Madison, Madison, Wisconsin; Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, Colorado; Albright, W.H. [Desert Research Institute, Reno, Nevada; Smith, G.M. [Geo-Smith Engineering, Grand Junction, Colorado; Bush, R.P. [U.S. Department of Energy, Grand Junction, Colorado

2011-02-27T23:59:59.000Z

357

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect (OSTI)

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

358

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect (OSTI)

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

359

Nuclear disarmament, disposal of military plutonium and international security problems  

SciTech Connect (OSTI)

One of the major issues of the current debate deals with the question: what does real nuclear disarmament actually involve? It becomes more and more obvious for many experts that it can no longer be limited to the reduction or elimination of delivery vehicles alone, but must necessarily cove the warheads and the fissile materials recovered from them, which should totally or partially be committed to peaceful use and placed under appropriate international safeguards, thus precluding their re-use for as weapons. There are various options as to how to solve the problems of disposal of fissile materials released from weapons. The optimal choice can only be made on the basis of a thorough study. This study should treat the disposal of weapon-grade plutonium and weapon-grade uranium as separate problems. The possible options for plutonium disposition currently discussed are as follows: (a) Storage in a form or under conditions not suitable for use in the production of new types of nuclear weapons. This option seems to be most natural and inevitable at the first phase, subject to determination of storage period, volume, and technology. Besides, the requirements of the international nuclear weapons nonproliferation regime could be met easily. Safe, secure, and controlled temporary storage may provide an appropriate solution of disposal of weapon-grade plutonium in the near future. (b) Energy utilization (conversion) of weapon-grade plutonium. The most efficient option of utilization of plutonium appears to be for nuclear power generation. This option does not exclude storage, but considers it as a temporary phase, which can, however, be a prolonged one: its length is determined by the political decisions made and possibilities existing to transfer plutonium for processing.

Slipchenko, V.S.; Rybatchenkov, V. [Ministry of Foreign Affairs of the Russian Federation, Moscow (Russian Federation). Arms Control and Disarmament Dept.

1995-12-31T23:59:59.000Z

360

Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF4)  

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

6 6 Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF 4 ) Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering activities, contact: Director, Environmental Assessment Division Argonne National Laboratory Argonne, Illinois 60439-4832

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361

SENSITIVITY ANALYSIS FOR SALTSTONE DISPOSAL UNIT COLUMN DEGRADATION ANALYSES  

SciTech Connect (OSTI)

PORFLOW related analyses supporting a Sensitivity Analysis for Saltstone Disposal Unit (SDU) column degradation were performed. Previous analyses, Flach and Taylor 2014, used a model in which the SDU columns degraded in a piecewise manner from the top and bottom simultaneously. The current analyses employs a model in which all pieces of the column degrade at the same time. Information was extracted from the analyses which may be useful in determining the distribution of Tc-99 in the various SDUs throughout time and in determining flow balances for the SDUs.

Flach, G.

2014-10-28T23:59:59.000Z

362

Thermodynamic data management system for nuclear waste disposal performance assessment  

SciTech Connect (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

363

Regulation of geological disposal of high-level radioactive waste  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission has been actively developing needed regulations over the last two years for the geological disposal of high-level radioactive waste. Technical criteria are about to be published in the form of a proposed regulation. The waste packages, underground facility, and geologic setting form the major elements of any geologic repository and the basis of a multibarrier system. Performance objectives and supporting technical criteria have been developed for each of these repository elements to provide benchmarks for scientists and engineers working in each of these major areas. 9 refs.

White, L.A.

1981-11-01T23:59:59.000Z

364

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

Basis for Section 3116 Determination for Salt Waste Disposal at the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site The Secretary of Energy is making this 3116 Determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) [1]. This 3116 Determination concerns the disposal of separated, solidified low-activity radioactive salt waste at the Savannah River Site (SRS) near Aiken, South Carolina. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site More Documents & Publications EIS-0082-S2: Amended Record of Decision Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

365

Disposal Facility Reaches 15-Million-Ton Milestone | Department of Energy  

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

Disposal Facility Reaches 15-Million-Ton Milestone Disposal Facility Reaches 15-Million-Ton Milestone Disposal Facility Reaches 15-Million-Ton Milestone July 30, 2013 - 12:00pm Addthis Matt McCormick, manager of the Richland Operations Office, commends a large group of Hanford workers for the 15-million-ton milestone at a public event at the Environmental Restoration Disposal Facility. Matt McCormick, manager of the Richland Operations Office, commends a large group of Hanford workers for the 15-million-ton milestone at a public event at the Environmental Restoration Disposal Facility. RICHLAND, Wash. - EM's Environmental Restoration Disposal Facility (ERDF) - a massive landfill for low-level radioactive and hazardous waste at the Hanford site - has achieved a major cleanup milestone. Since beginning operations in 1996, workers supporting the Richland

366

GRR/Section 18-AK-c - Waste Disposal Permit Process | Open Energy  

Open Energy Info (EERE)

AK-c - Waste Disposal Permit Process AK-c - Waste Disposal Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-AK-c - Waste Disposal Permit Process 18AKC - WasteDisposalPermitProcess (1).pdf Click to View Fullscreen Contact Agencies Alaska Department of Environmental Conservation Regulations & Policies AS 46.03.110 Waste Disposal Permit Regulations 18 AAC 60.200 et seq Triggers None specified Click "Edit With Form" above to add content 18AKC - WasteDisposalPermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Alaska Department of Environmental Conservation (DEC) is responsible

367

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

Basis for Section 3116 Determination for Salt Waste Disposal at the Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site The Secretary of Energy is making this 3116 Determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA) [1]. This 3116 Determination concerns the disposal of separated, solidified low-activity radioactive salt waste at the Savannah River Site (SRS) near Aiken, South Carolina. Basis for Section 3116 Determination for Salt Waste Disposal at the Savannah River Site More Documents & Publications EIS-0082-S2: Amended Record of Decision Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

368

Overview of Low-Level Waste Disposal Operations at the Nevada Test Site  

SciTech Connect (OSTI)

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office Environmental Management Program is charged with the responsibility to carry out the disposal of on-site and off-site generated low-level radioactive waste at the Nevada Test Site. Core elements of this mission are ensuring that disposal take place in a manner that is safe and cost-effective while protecting workers, the public, and the environment. This paper focuses on giving an overview of the Nevada Test Site facilities regarding currant design of disposal. In addition, technical attributes of the facilities established through the site characterization process will be further described. An update on current waste disposal volumes and capabilities will also be provided. This discussion leads to anticipated volume projections and disposal site requirements as the Nevada Test Site disposal operations look towards the future.

DOE /Navarro

2007-02-01T23:59:59.000Z

369

The Texas Solution to the Nation's Disposal Needs for Irradiated Hardware - 13337  

SciTech Connect (OSTI)

The closure of the disposal facility in Barnwell, South Carolina, to out-of-compact states in 2008 left commercial nuclear power plants without a disposal option for Class B and C irradiated hardware. In 2012, Waste Control Specialists LLC (WCS) opened a highly engineered facility specifically designed and built for the disposal of Class B and C waste. The WCS facility is the first Interstate Compact low-level radioactive waste disposal facility to be licensed and operated under the Low-level Waste Policy Act of 1980, as amended in 1985. Due to design requirements of a modern Low Level Radioactive Waste (LLRW) facility, traditional methods for disposal were not achievable at the WCS site. Earlier methods primarily utilized the As Low as Reasonably Achievable (ALARA) concept of distance to accomplish worker safety. The WCS method required the use of all three ALARA concepts of time, distance, and shielding to ensure the safe disposal of this highly hazardous waste stream. (authors)

Britten, Jay M. [Waste Control Specialists LLC, Andrews, TX 79714 (United States)] [Waste Control Specialists LLC, Andrews, TX 79714 (United States)

2013-07-01T23:59:59.000Z

370

Oil field waste disposal in salt caverns: An information website  

SciTech Connect (OSTI)

Argonne National Laboratory has completed the construction of a Website for the US Department of Energy (DOE) that provides detailed information on salt caverns and their use for disposing of nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM). Specific topics in the Website include the following: descriptions of salt deposits and salt caverns within the US, salt cavern construction methods, potential types of wastes, waste emplacement, regulatory issues, costs, carcinogenic and noncarcinogenic human health risks associated with postulated cavern release scenarios, new information on cavern disposal (e.g., upcoming meetings, regulatory issues, etc.), other studies supported by the National Petroleum Technology Office (NPTO) (e.g., considerations of site location, cavern stability, development issues, and bedded salt characterization in the Midland Basin), and links to other associated Web sites. In addition, the Website allows downloadable access to reports prepared on the topic that were funded by DOE. Because of the large quantities of NOW and NORM wastes generated annually by the oil industry, information presented on this Website is particularly interesting and valuable to project managers, regulators, and concerned citizens.

Tomasko, D.; Veil, J. A.

1999-12-10T23:59:59.000Z

371

Tritiated wastewater treatment and disposal evaluation for 1995  

SciTech Connect (OSTI)

A second annual summary and analysis of potential processes for the mitigation of tritium contained in process effluent, ground water and stored waste is presented. It was prepared to satisfy the Hanford Federal Facility and Consent Order (Tri-Party Agreement) Milestone M-26-05B. Technologies with directed potential for separation of tritium at present environmental levels are organized into two groups. The first group consists of four processes that have or are undergoing significant development. Of these four, the only active project is the development of membrane separation technology at the Pacific Northwest Laboratory (PNL). Although research is progressing, membrane separation does not present a near term option for the mitigation of tritium. A second grouping of five early stage projects gives an indication of the breadth of interest in low level tritium separation. If further developed, two of these technologies might prove to be candidates for a separation process. At the present, there continues to be no known commercially available process for the practical reduction of the tritium burden in process effluent. Material from last year`s report regarding the occurrence, regulation and management of tritium is updated and included in the appendices of this report. The use of the State Approved Land Disposal Site (SALDS) for disposal of tritiated effluent from the 200 Area Effluent Treatment Facility (ETF) begins in the fall of 1995. This is the most significant event impacting tritium in the environment at the Hanford Site this coming year.

Allen, W.L. [Westinghouse Hanford Co., Richland, WA (United States)

1995-08-01T23:59:59.000Z

372

Low-level radioactive waste disposal facility closure  

SciTech Connect (OSTI)

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

373

Microsoft Word - Panel 5 Disposal Operations Complete.docx  

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

th th re s c th W se lo o s e U.S. D Carls Waste P.O. B Carls CARL hat disposa epository ar hipment wa "All T redit for this heir dedicat Waste Mana The W even dispo ong and can f the 6.2 m igned in 19 With d quivalent o Department bad Field Of e Isolation P Box 3090 bad, New M DOE in P LSBAD, N.M al operation re complete as emplace RU waste m s accomplis tion to perfo agement Pr WIPP unde sal rooms. n hold appr illion cubic 992, has be disposal op of about fou of Energy ffice Pilot Plant Mexico 88221 Fo E Comp anel 5 M., August 1 s in Panel 5 e. Last mo ed in the pa manageme shment," N orming thei rogram con rground is c Each disp roximately 1 feet of TRU en dispose perations in r football fie 1 or Immed pletes D of the W 15, 2011 - T 5 of the Wa nth, the fina nel, which t ent employe ational TRU

374

Use and disposal of waste-water sludge in Illinois. Final report  

SciTech Connect (OSTI)

The United States Environmental Protection Agency (USEPA) proposed Part 503 Rules on sludge were first published in February 1989. Part 503 proposed sludge regulations address five categories of sludge use or disposal: land application, distribution and marketing, monofills, surface disposal sites, and incineration. The report on sludge management in Illinois examines the probable effects that the proposed federal rules on use and disposal of sewage sludge will have on current practices by Illinois publicly owned treatment works outside the City of Chicago.

John, S.F.; Kane, D.N.; Hinesly, T.D.

1992-02-01T23:59:59.000Z

375

Siting of low-level radioactive waste disposal facilities in Texas  

E-Print Network [OSTI]

in the proper geologic environment. The object of disposal is to prevent exposure of the public to radioactive waste in potentially harmful concentrations. The most likely route for buried wastes to reach the public is through the ground- water system... disposal site for low- level radioactive waste is predictability, A disposal site should "be capable of being characterized, modeled, analyzed and monitored" ISiefken, et al. , 1982). Simplicity and homogeneity with respect to hydrogeologic conditions...

Isenhower, Daniel Bruce

2012-06-07T23:59:59.000Z

376

Degradation Of Cementitious Materials Associated With Saltstone Disposal Units  

SciTech Connect (OSTI)

The Saltstone facilities at the DOE Savannah River Site (SRS) stabilize and dispose of low-level radioactive salt solution originating from liquid waste storage tanks at the site. The Saltstone Production Facility (SPF) receives treated salt solution and mixes the aqueous waste with dry cement, blast furnace slag, and fly ash to form a grout slurry which is mechanically pumped into concrete disposal cells that compose the Saltstone Disposal Facility (SDF). The solidified grout is termed “saltstone”. Cementitious materials play a prominent role in the design and long-term performance of the SDF. The saltstone grout exhibits low permeability and diffusivity, and thus represents a physical barrier to waste release. The waste form is also reducing, which creates a chemical barrier to waste release for certain key radionuclides, notably Tc-99. Similarly, the concrete shell of an SDF disposal unit (SDU) represents an additional physical and chemical barrier to radionuclide release to the environment. Together the waste form and the SDU compose a robust containment structure at the time of facility closure. However, the physical and chemical state of cementitious materials will evolve over time through a variety of phenomena, leading to degraded barrier performance over Performance Assessment (PA) timescales of thousands to tens of thousands of years. Previous studies of cementitious material degradation in the context of low-level waste disposal have identified sulfate attack, carbonation influenced steel corrosion, and decalcification (primary constituent leaching) as the primary chemical degradation phenomena of most relevance to SRS exposure conditions. In this study, degradation time scales for each of these three degradation phenomena are estimated for saltstone and concrete associated with each SDU type under conservative, nominal, and best estimate assumptions. The nominal value (NV) is an intermediate result that is more probable than the conservative estimate (CE) and more defensible than the best estimate (BE). The combined effects of multiple phenomena are then considered to determine the most limiting degradation time scale for each cementitious material. Degradation times are estimated using a combination of analytic solutions from literature and numerical simulation codes provided through the DOE Cementitious Barriers Partnership (CBP) Software Toolbox (http://cementbarriers.org). For the SDU 2 design, the roof, wall, and floor components are projected to become fully degraded under Nominal conditions at 3866, 923, and 1413 years, respectively. For SDU 4 the roof and floor are estimated to be fully degraded under Nominal conditions after 1137 and 1407 years, respectively; the wall is assumed to be fully degraded at time zero in the most recent PA simulations. Degradation of these concrete barriers generally occurs from combined sulfate attack and corrosion of embedded steel following carbonation. Saltstone is projected to degrade very slowly by decalcification, with complete degradation occurring in excess of 200,000 years for any SDU type. Complete results are provided.

Flach, G. P; Smith, F. G. III

2013-03-19T23:59:59.000Z

377

System-Level Logistics for Dual Purpose Canister Disposal  

SciTech Connect (OSTI)

The analysis presented in this report investigated how the direct disposal of dual purpose canisters (DPCs) may be affected by the use of standard transportation aging and disposal canisters (STADs), early or late start of the repository, and the repository emplacement thermal power limits. The impacts were evaluated with regard to the availability of the DPCs for emplacement, achievable repository acceptance rates, additional storage required at an interim storage facility (ISF) and additional emplacement time compared to the corresponding repackaging scenarios, and fuel age at emplacement. The result of this analysis demonstrated that the biggest difference in the availability of UNF for emplacement between the DPC-only loading scenario and the DPCs and STADs loading scenario is for a repository start date of 2036 with a 6 kW thermal power limit. The differences are also seen in the availability of UNF for emplacement between the DPC-only loading scenario and the DPCs and STADs loading scenario for the alternative with a 6 kW thermal limit and a 2048 start date, and for the alternatives with a 10 kW thermal limit and 2036 and 2048 start dates. The alternatives with disposal of UNF in both DPCs and STADs did not require additional storage, regardless of the repository acceptance rate, as compared to the reference repackaging case. In comparison to the reference repackaging case, alternatives with the 18 kW emplacement thermal limit required little to no additional emplacement time, regardless of the repository start time, the fuel loading scenario, or the repository acceptance rate. Alternatives with the 10 kW emplacement thermal limit and the DPCs and STADs fuel loading scenario required some additional emplacement time. The most significant decrease in additional emplacement time occurred in the alternative with the 6 kW thermal limit and the 2036 repository starting date. The average fuel age at emplacement ranges from 46 to 88 years. The maximum fuel age at emplacement ranges from 81 to 146 years. The difference in the average and maximum age of fuel at emplacement between the DPC-only and the DPCs and STADs fuel loading scenarios becomes less significant as the repository thermal limit increases and as the repository start date increases. In general, the role of STADs is to store young (30 year or younger) high burnup (45 GWD/MTU or higher) fuel. Recommendations for future study include detailed evaluation of the feasible alternatives with regard to the costs and factors not considered in this analysis, such as worker dose, dose to members of the public, and economic benefits to host entities. It is also recommended to conduct an additional analysis to evaluate the assumption regarding the transportability and disposability of DPCs for the next iteration of the direct disposal of DPCs study.

Kalinina, Elena A.

2014-06-03T23:59:59.000Z

378

Marcellus Shale Natural Gas Drilling Operators' Choice of Wastewater Disposal Method.  

E-Print Network [OSTI]

??As natural gas drilling in the Marcellus Shale region moves forward, the issue of wastewater disposal has risen to the forefront. In 2010, the Pennsylvania… (more)

Edmundson, Caitlyn

2012-01-01T23:59:59.000Z

379

Technical support document for the surface disposal of sewage sludge. Final report  

SciTech Connect (OSTI)

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the surface disposal of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in sewage sludge placed on surface disposal sites. The management practices associated with surface disposal are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through surface disposal are discussed.

Not Available

1992-11-01T23:59:59.000Z

380

Underground Injection Wells as an Option for Disposal of Shale Gas Wastewaters: Policies & Practicality.  

E-Print Network [OSTI]

that are received for injection. We recently received a new permit in VA, but it is for disposal of coalbed methane

Boyer, Elizabeth W.

Note: This page contains sample records for the topic "wds llw disposal" 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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381

Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous...  

Office of Environmental Management (EM)

risks associated with worker safety and the environment (e.g., resource consumption, air pollution, air dispersal) that may be associated with exhumation and re-disposal of...

382

Deep Geologic Nuclear Waste Disposal - No New Taxes - 12469  

SciTech Connect (OSTI)

To some, the perceived inability of the United States to dispose of high-level nuclear waste justifies a moratorium on expansion of nuclear power in this country. Instead, it is more an example of how science yields to social pressure, even on a subject as technical as nuclear waste. Most of the problems, however, stem from confusion on the part of the public and their elected officials, not from a lack of scientific knowledge. We know where to put nuclear waste, how to put it there, how much it will cost, and how well it will work. And it's all about the geology. The President's Blue Ribbon Commission on America's Nuclear Future has drafted a number of recommendations addressing nuclear energy and waste issues (BRC 2011) and three recommendations, in particular, have set the stage for a new strategy to dispose of high-level nuclear waste and to manage spent nuclear fuel in the United States: 1) interim storage for spent nuclear fuel, 2) resumption of the site selection process for a second repository, and 3) a quasi-government entity to execute the program and take control of the Nuclear Waste Fund in order to do so. The first two recommendations allow removal and storage of spent fuel from reactor sites to be used in the future, and allows permanent disposal of actual waste, while the third controls cost and administration. The Nuclear Waste Policy Act of 1982 (NPWA 1982) provides the second repository different waste criteria, retrievability, and schedule, so massive salt returns as the candidate formation of choice. The cost (in 2007 dollars) of disposing of 83,000 metric tons of heavy metal (MTHM) high-level waste (HLW) is about $ 83 billion (b) in volcanic tuff, $ 29 b in massive salt, and $ 77 b in crystalline rock. Only in salt is the annual revenue stream from the Nuclear Waste Fund more than sufficient to accomplish this program without additional taxes or rate hikes. The cost is determined primarily by the suitability of the geologic formation, i.e., how well it performs on its own for millions of years with little engineering assistance from humans. It is critical that the states most affected by this issue (WA, SC, ID, TN, NM and perhaps others) develop an independent multi-state agreement in order for a successful program to move forward. Federal approval would follow. Unknown to most, the United States has a successful operating deep permanent geologic nuclear repository for high and low activity waste, called the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Its success results from several factors, including an optimal geologic and physio-graphic setting, a strong scientific basis, early regional community support, frequent interactions among stakeholders at all stages of the process, long-term commitment from the upper management of the U.S. Department of Energy (DOE) over several administrations, strong New Mexico State involvement and oversight, and constant environmental monitoring from before nuclear waste was first emplaced in the WIPP underground (in 1999) to the present. WIPP is located in the massive bedded salts of the Salado Formation, whose geological, physical, chemical, redox, thermal, and creep-closure properties make it an ideal formation for long-term disposal, long-term in this case being greater than 200 million years. These properties also mean minimal engineering requirements as the rock does most of the work of isolating the waste. WIPP has been operating for twelve years, and as of this writing, has disposed of over 80,000 m{sup 3} of nuclear weapons waste, called transuranic or TRU waste (>100 nCurie/g but <23 Curie/1000 cm{sup 3}) including some high activity waste from reprocessing of spent fuel from old weapons reactors. All nuclear waste of any type from any source can be disposed in this formation better, safer and cheaper than in any other geologic formation. At the same time, it is critical that we complete the Yucca Mountain license application review so as not to undermine the credibility of the Nuclear Regulatory Commission and the scientific commun

Conca, James [RJLee Group, Inc., Pasco WA 509.205.7541 (United States); Wright, Judith [UFA Ventures, Inc., Richland, WA (United States)

2012-07-01T23:59:59.000Z

383

Challenges dealing with depleted uranium in Germany - Reuse or disposal  

SciTech Connect (OSTI)

During enrichment large amounts of depleted Uranium are produced. In Germany every year 2.800 tons of depleted uranium are generated. In Germany depleted uranium is not classified as radioactive waste but a resource for further enrichment. Therefore since 1996 depleted Uranium is sent to ROSATOM in Russia. However it still has to be dealt with the second generation of depleted Uranium. To evaluate the alternative actions in case a solution has to be found in Germany, several studies have been initiated by the Federal Ministry of the Environment. The work that has been carried out evaluated various possibilities to deal with depleted uranium. The international studies on this field and the situation in Germany have been analyzed. In case no further enrichment is planned the depleted uranium has to be stored. In the enrichment process UF{sub 6} is generated. It is an international consensus that for storage it should be converted to U{sub 3}O{sub 8}. The necessary technique is well established. If the depleted Uranium would have to be characterized as radioactive waste, a final disposal would become necessary. For the planned Konrad repository - a repository for non heat generating radioactive waste - the amount of Uranium is limited by the licensing authority. The existing license would not allow the final disposal of large amounts of depleted Uranium in the Konrad repository. The potential effect on the safety case has not been roughly analyzed. As a result it may be necessary to think about alternatives. Several possibilities for the use of depleted uranium in the industry have been identified. Studies indicate that the properties of Uranium would make it useful in some industrial fields. Nevertheless many practical and legal questions are open. One further option may be the use as shielding e.g. in casks for transport or disposal. Possible techniques for using depleted Uranium as shielding are the use of the metallic Uranium as well as the inclusion in concrete. Another possibility could be the use of depleted uranium for the blending of High enriched Uranium (HEU) or with Plutonium to MOX-elements. (authors)

Moeller, Kai D. [Federal Office for Radiation Protection, Bundesamt fuer Strahlenschutz - BFS, Postfach 10 01 49, D-38201 Salzgitter (Germany)

2007-07-01T23:59:59.000Z

384

Options and costs for offsite disposal of oil and gas exploration and production wastes.  

SciTech Connect (OSTI)

In the United States, most of the exploration and production (E&P) wastes generated at onshore oil and gas wells are disposed of or otherwise managed at the well site. Certain types of wastes are not suitable for onsite management, and some well locations in sensitive environments cannot be used for onsite management. In these situations, operators must transport the wastes offsite for disposal. In 1997, Argonne National Laboratory (Argonne) prepared a report that identified offsite commercial disposal facilities in the United States. This information has since become outdated. Over the past year, Argonne has updated the study through contacts with state oil and gas agencies and commercial disposal companies. The new report, including an extensive database for more than 200 disposal facilities, provides an excellent reference for information about commercial disposal operations. This paper describes Argonne's report. The national study provides summaries of the types of offsite commercial disposal facilities found in each state. Data are presented by waste type and by disposal method. The categories of E&P wastes in the database include: contaminated soils, naturally occurring radioactive material (NORM), oil-based muds and cuttings, produced water, tank bottoms, and water-based muds and cuttings. The different waste management or disposal methods in the database involve: bioremediation, burial, salt cavern, discharge, evaporation, injection, land application, recycling, thermal treatment, and treatment. The database includes disposal costs for each facility. In the United States, most of the 18 billion barrels (bbl) of produced water, 149 million bbl of drilling wastes, and 21 million bbl of associated wastes generated at onshore oil and gas wells are disposed of or otherwise managed at the well site. However, under certain conditions, operators will seek offsite management options for these E&P wastes. Commercial disposal facilities are offsite businesses that accept and manage E&P wastes for a fee. Their services include waste management and disposal, transportation, cleaning of vehicles and tanks, disposal of wash water, and, in some cases, laboratory analysis. Commercial disposal facilities offer a suite of waste management methods and technologies.

Puder, M. G.; Veil, J. A.; Environmental Science Division

2007-01-01T23:59:59.000Z

385

Risk assessment of landfill disposal sites - State of the art  

SciTech Connect (OSTI)

A risk assessment process can assist in drawing a cost-effective compromise between economic and environmental costs, thereby assuring that the philosophy of 'sustainable development' is adhered to. Nowadays risk analysis is in wide use to effectively manage environmental issues. Risk assessment is also applied to other subjects including health and safety, food, finance, ecology and epidemiology. The literature review of environmental risk assessments in general and risk assessment approaches particularly regarding landfill disposal sites undertaken by the authors, reveals that an integrated risk assessment methodology for landfill gas, leachate or degraded waste does not exist. A range of knowledge gaps is discovered in the literature reviewed to date. From the perspective of landfill leachate, this paper identifies the extent to which various risk analysis aspects are absent in the existing approaches.

Butt, Talib E. [Sustainability Centre in Glasgow (SCG), George Moore Building, 70 Cowcaddens Road, Glasgow Caledonian University, Glasgow G4 0BA, Scotland (United Kingdom)], E-mail: t_e_butt@hotmail.com; Lockley, Elaine [Be Environmental Ltd. Suite 213, Lomeshaye Business Village, Turner Road, Nelson, Lancashire, BB9 7DR, England (United Kingdom); Oduyemi, Kehinde O.K. [Built and Natural Environment, Baxter Building, University of Abertay Dundee, Bell Street, Dundee DD1 1HG, Scotland (United Kingdom)], E-mail: k.oduyemi@abertay.ac.uk

2008-07-01T23:59:59.000Z

386

Reducing biosolids disposal costs using land application in forested areas  

SciTech Connect (OSTI)

Switching biosolids land application from a reclamation site to a forested site significantly reduced the cost of biosolids disposal at the Savannah River Site. Previous beneficial reuse programs focused on reclamation of existing borrow pits. While extremely beneficial, this program became very costly due to the regulatory requirements for groundwater monitoring, soil monitoring and frequent biosolids analyses. A new program was developed to reuse biosolids in forested areas where the biosolids could be used as a soil conditioner and fertilizer to enhance timber yield. The forested land application site was designed so that groundwater monitoring and soil monitoring could be eliminated while biosolids monitoring and site maintenance were minimized. Monitoring costs alone were reduced by 80%. Capital costs for site preparation were also significantly reduced since there was no longer a need for expensive groundwater monitoring wells.

Huffines, R.L.

1995-11-01T23:59:59.000Z

387

Disposal of radioactive waste from nuclear research facilities  

E-Print Network [OSTI]

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Maxeiner, H; Kolbe, E

2003-01-01T23:59:59.000Z

388

Tritiated wastewater treatment and disposal evaluation for 1994  

SciTech Connect (OSTI)

This report discusses and analyzes information and issues regarding tritium and tritium management. It was prepared in response to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-05A for the evaluation of tritiated wastewater treatment and disposal. The key elements of the report are summarized as follows: Discharge of tritiated water is regulated worldwide. Differences exist in discharge limits and in regulatory philosophy from country to country and from state to state in the United States. Tritium from manmade sources is emitted into the atmosphere and discharged into the ground or directly to the oceans and to waterways that empty into the oceans. In 1989, reported worldwide emissions of tritium from nuclear power generating plants totaled almost 1,000,000 Curies (Ci).

Not Available

1994-08-01T23:59:59.000Z

389

LABORATORY EXPERIMENTS TO SIMULATE CO2 OCEAN DISPOSAL  

SciTech Connect (OSTI)

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

390

Field study of disposed solid wastes from advanced coal processes  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells.

Not Available

1992-01-01T23:59:59.000Z

391

Disposal of Hazardous Medical Waste Policy and Procedures Commencement Date: 27 November, 1996  

E-Print Network [OSTI]

Manipulation Advisory Committee's publication, Guidelines for the Storage, Transport and Disposal of Medical" and must comply with the Guidelines for the Storage, Transport and Disposal of Medical Waste issued of their chemical, biological or physical properties. Sharps Means objects or devices having acute rigid corners

392

Granite Recrystallization The Key to an Alternative Strategy for HLW Disposal? Fergus G.F. Gibb  

E-Print Network [OSTI]

JD, U.K. ABSTRACT An alternative strategy is proposed for the disposal of spent nuclear fuel (SNF HLWs, such as spent reactor fuel, to `cool' for a period (usually a few decades) prior to disposal potentially damaging temperature rises. Secondly, the waste contains sufficient quantities of very long lived

Sheffield, University of

393

Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility  

SciTech Connect (OSTI)

This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

BURBANK, D.A.

2000-08-31T23:59:59.000Z

394

Impacts of Shale Gas Wastewater Disposal on Water Quality in Western Pennsylvania  

E-Print Network [OSTI]

States, oil and gas wastewater is managed through recycling of the wastewater for shale gas operations of the wastewater.7 However, options for the proper disposal and management of the wastewater that is not recycledImpacts of Shale Gas Wastewater Disposal on Water Quality in Western Pennsylvania Nathaniel R

Jackson, Robert B.

395

Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas  

SciTech Connect (OSTI)

This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

B. C. Rogers; P. L. Walter (Rogers and Associates Engineering Corporation); R. D. Baird

1999-08-01T23:59:59.000Z

396

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells  

E-Print Network [OSTI]

Graphene sheets fabricated from disposable paper cups as a catalyst support material for fuel cells Hong Zhao and T. S. Zhao* Disposable paper-cups are used for the formation of graphene sheets with Fe2+ as a catalyst. The proposed synthesis strategy not only enables graphene sheets to be produced in high yield

Zhao, Tianshou

397

Solution Speciation of Plutonium and Americium at an Australian Legacy Radioactive Waste Disposal Site  

Science Journals Connector (OSTI)

During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. ... It should also be taken into account that, at some sites, such as the Maxey Flats disposal site,(19) codisposed organic contaminants have been implicated in actinide mobilization. ...

Atsushi Ikeda-Ohno; Jennifer J. Harrison; Sangeeth Thiruvoth; Kerry Wilsher; Henri K. Y. Wong; Mathew P. Johansen; T. David Waite; Timothy E. Payne

2014-08-15T23:59:59.000Z

398

wastewater_sink_disposal_guidance.docx Revision Date: 10/26/2012 Page 1 of 3  

E-Print Network [OSTI]

wastewater_sink_disposal_guidance.docx Revision Date: 10/26/2012 Page 1 of 3 LABORATORY & BUILDING limitations and prohibitions established by the local wastewater treatment authority, the Massachusetts Water for wastewater disposal purposes is strictly prohibited. Hazardous Wastes: Hazardous wastes are prohibited from

Heller, Eric

399

Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell  

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

Crews Overcome Challenges to Safely Dispose 1-Million-Pound Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell American Recovery and Reinvestment Act cleanup crews at the Idaho site recently disposed of a hot cell as heavy as nine fully loaded Boeing 737s. Unlike the aircrafts, the 1-million-pound concrete structure moved about two miles per hour on a trailer with 224 tires towed by a semi-truck. Workers safely transported the cell from the Advanced Test Reactor Complex (ATR-C) to an onsite landfill two miles away. Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell More Documents & Publications 2011 ARRA Newsletters CX-001627: Categorical Exclusion Determination Occupational Safety Performance Trends

400

News Release: 2010 UMTRCA Title I and Title II Disposal Sites Reports  

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

2010 UMTRCA Title I and Title II Disposal Sites 2010 UMTRCA Title I and Title II Disposal Sites Reports Available News Release: 2010 UMTRCA Title I and Title II Disposal Sites Reports Available February 23, 2011 - 9:51am Addthis News Contact: DOE, Rich Bush, UMTRCA Program Lead (970) 248-6073 Contractor, Bob Darr, S.M. Stoller Corporation Public Affairs (720) 377-9672 Grand Junction, Colo. - The U.S. Department of Energy announces the availability of the 2010 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites and the 2010 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites reports. In 2010, DOE's Office of Legacy Management was responsible for providing long-term surveillance and maintenance services at 25 uranium mill tailings

Note: This page contains sample records for the topic "wds llw disposal" 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

U.S. Department of Energy Announces the Availability of Disposal Contracts  

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

U.S. Department of Energy Announces the Availability of Disposal U.S. Department of Energy Announces the Availability of Disposal Contracts for New Nuclear Reactors U.S. Department of Energy Announces the Availability of Disposal Contracts for New Nuclear Reactors October 31, 2008 - 4:47pm Addthis Washington D.C. -- The U.S Department of Energy (DOE) announced today that the Department is prepared to execute the Standard Contract for the Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (Standard Contract) set forth in 10 C.F.R. 961, together with a new reactor amendment, with those companies desiring to construct new nuclear power reactors. The Department is making the Standard Contract and the new reactor amendment (collectively "disposal contract") available to those companies that have notified the Nuclear Regulatory Commission (NRC) of

402

Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell  

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

Crews Overcome Challenges to Safely Dispose 1-Million-Pound Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell American Recovery and Reinvestment Act cleanup crews at the Idaho site recently disposed of a hot cell as heavy as nine fully loaded Boeing 737s. Unlike the aircrafts, the 1-million-pound concrete structure moved about two miles per hour on a trailer with 224 tires towed by a semi-truck. Workers safely transported the cell from the Advanced Test Reactor Complex (ATR-C) to an onsite landfill two miles away. Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell More Documents & Publications 2011 ARRA Newsletters CX-002327: Categorical Exclusion Determination CX-001627: Categorical Exclusion Determination

403

DOE - Office of Legacy Management -- Shallow Land Disposal Area - PA 45  

Office of Legacy Management (LM)

Shallow Land Disposal Area - PA 45 Shallow Land Disposal Area - PA 45 FUSRAP Considered Sites Shallow Land Disposal Area, PA Alternate Name(s): Parks Township Shallow Land Disposal Area Nuclear Materials and Equipment Corporation (NUMEC) Babcox and Wilcox Parks Facilities PA.45-1 PA.45-5 PA.45-6 Location: PA Route 66 and Kissimere Road, Parks Township, Apollo, Pennsylvania PA.45-1 Historical Operations: Fabricated nulcear fuel under an NRC license as an extension of NUMEC Apollo production facilities. PA.45-1 PA.45-5 Eligibility Determination: Eligible PA.45-6 Radiological Survey(s): None Site Status: Cleanup in progress by U.S. Army Corps of Engineers. PA.45-6 USACE Website Long-term Care Requirements: To be determined upon completion. Also see Documents Related to Shallow Land Disposal Area, PA

404

GRR/Section 18-NV-c - Waste Disposal Permit | Open Energy Information  

Open Energy Info (EERE)

NV-c - Waste Disposal Permit NV-c - Waste Disposal Permit < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-NV-c - Waste Disposal Permit 18NVCWasteDisposalPermit.pdf Click to View Fullscreen Contact Agencies Nevada Division of Environmental Protection Regulations & Policies Nevada Revised Statutes (NRS) Nevada Administrative Code (NAC) Triggers None specified Click "Edit With Form" above to add content 18NVCWasteDisposalPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Within the Nevada Division of Environmental Protection in Nevada, the Bureau of Waste Management (BWM) operates a permitting and compliance

405

EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and  

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

5: Disposal of Greater-than-Class-C Low-Level Radioactive 5: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste Summary This EIS evaluates the reasonably foreseeable environmental impacts associated with the proposed development, operation, and long-term management of a disposal facility or facilities for Greater-Than-Class C (GTCC) low-level radioactive waste and GTCC-like waste. The Environmental Protection Agency is a cooperating agency in the preparation of this EIS. The EIS evaluates potential impacts from the construction and operation of

406

Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Recovery  

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

Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Recovery Act Funds Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Recovery Act Funds The Moab Uranium Mill Tailings Remedial Action Project reached its primary American Recovery and Reinvestment Act milestone ahead of schedule on Wednesday with the disposal of 2 million tons of uranium mill tailings. The project had originally planned to ship 2 million tons of tailings with Recovery Act funds. Now, Recovery Act workers are surpassing that goal. Moab Project Disposes 2 Million Tons of Uranium Mill Tailings with Recovery Act Funds More Documents & Publications EIS-0355: Record of Decision EIS-0355: Draft Environmental Impact Statement EIS-0355: Final Environmental Impact Statement

407

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

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

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

408

Criticality safety considerations in the geologic disposal of spent nuclear fuel assemblies  

SciTech Connect (OSTI)

Features of geologic disposal which hamper the demonstration that criticality cannot occur therein include possible changes of shape and form, intrusion of water as a neutron moderator, and selective leaching of spent fuel constituents. If the criticality safety of spent fuel disposal depends on burnup, independent measurements verifying the burnup should be performed prior to disposal. The status of nondestructive analysis method which might provide such verification is discussed. Calculations were performed to assess the potential for increasing the allowed size of a spent fuel disposal canister if potential water intrusion were limited by close-packing the enclosed rods. Several factors were identified which severely limited the potential of this application. The theoretical limit of hexagonal close-packing cannot be achieved due to fuel rod bowing. It is concluded that disposal canisters should be sized on the basis of assumed optimum moderation. Several topics for additional research were identified during this limited study.

Gore, B.F.; McNair, G.W.; Heaberlin, S.W.

1980-05-01T23:59:59.000Z

409

Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility  

SciTech Connect (OSTI)

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2010-10-01T23:59:59.000Z

410

Comparing policy, regulations and institutions for geological disposal of radioactive waste and carbon dioxide  

Science Journals Connector (OSTI)

This paper compares the policy, regulatory and institutional (PRI) settings of Radioactive Waste (RW) and Carbon Dioxide (CO2) disposal for selected countries. This comparison is premised on the following arguments: (a) the policy/political acceptance of nuclear power and coal power with Carbon Capture and Storage (CCS) technology to redress the climate change challenge will be essentially determined by the efficacy of the PRI settings; and (b) the existing discussion on these technologies is largely neglectful of the significance of these settings. The comparison suggests that: (a) while the overall PRI settings for RW and CO2 disposal are generally fuzzy, discordant and fragmented, they are relatively well defined for RW disposal than for CO2 disposal; and (b) PRI settings for RW and CO2 disposal cannot be analysed in isolation from broader settings for nuclear and coal-CCS power, and - more importantly - in isolation from macro-level energy, economic, environmental and socio-political policy settings.

Deepak Sharma; Suchi Misra; Muyi Yang

2014-01-01T23:59:59.000Z

411

Long-term surveillance plan for the Collins Ranch Disposal Site, Lakeview, Oregon. Revision 2  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) for the Lakeview, Oregon, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Lakeview (Collins Ranch) disposal cell, which will be referred to as the Collins Ranch disposal cell throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal cell continues to function as designed. This final LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials. This LTSP documents whether the land and interests are owned by the United States or an Indian tribe, and details how the long-term care of the disposal site will be carried out. It is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992a).

Not Available

1993-12-01T23:59:59.000Z

412

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

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

Current and Planned Current and Planned Low-Level Waste Disposal Capacity Report Revision 2 December 2000 U.S. Department of Energy Office of Environmental Management i TABLE OF CONTENTS EXECUTIVE SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ES-1 1.0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 Summary of Report Sections . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.2 History of Past DOE Low-Level Waste Disposal Operations . . . . . . . . . . . . . . . . . . . . . . 1-2 1.3 Current Status of the Low-Level and Mixed Low-Level Waste Disposal Configuration . . 1-3 1.4 Methodology for Base Case and Alternative Scenarios Analyses . . . . . . . . . . . . . . . . . . . 1-5 1.5 Radiological Assessments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 1.6 Data Sources for Waste Disposal Volumes, Waste Radiological Profiles, and Disposal

413

Establishing the Technical Basis for Disposal of Heat-generating Waste in  

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

Establishing the Technical Basis for Disposal of Heat-generating Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt Establishing the Technical Basis for Disposal of Heat-generating Waste in Salt The report summarizes available historic tests and the developed technical basis for disposal of heat-generating waste in salt, and the means by which a safety case for disposal of heat generating waste at a generic salt site can be initiated from the existing technical basis. Though the basis for a salt safety case is strong and has been made by the German repository program, RD&D programs continue in order to help reduce uncertainty, to improve understanding of certain complex processes, to demonstrate operational concepts, to confirm performance expectations, and to improve modeling capabilities utilizing the latest software platforms.

414

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

E-Print Network [OSTI]

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

Hunt, Andrew Robert

2007-01-01T23:59:59.000Z

415

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

SciTech Connect (OSTI)

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

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

1989-11-01T23:59:59.000Z

416

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect (OSTI)

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

417

Long-term surveillance plan for the Maybell, Colorado Disposal Site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-12-01T23:59:59.000Z

418

Long-term surveillance plan for the Maybell, Colorado Disposal Site  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Maybell disposal site in Moffat County, Colorado. The U.S. Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CFR Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites are cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the Maybell disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination that remedial action is complete for the Maybell site and the NRC formally accepts this LTSP. This document describes the long-term surveillance program the DOE will implement to ensure the Maybell disposal site performs as designed. The program is based on site inspections to identify threats to disposal cell integrity. The LTSP is based on the UMTRA Project long-term surveillance program guidance document and meets the requirements of 10 CFR {section}40.27(b) and 40 CFR {section}192.03.

NONE

1997-09-01T23:59:59.000Z

419

Long-term surveillance plan for the South Clive Disposal Site, Clive, Utah  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the US Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project South Clive disposal site in Clive, Utah. The US Nuclear Regulatory Commission (NRC) has developed regulations for the issuance of a general license for the custody and long-term care of UMTRA Project disposal sites in 10 CRF Part 40. The purpose of this general license is to ensure that the UMTRA Project disposal sites will be cared for in a manner that protects the public health and safety and the environment. For each disposal site to be licensed, the NRC requires the DOE to submit a site-specific LTSP. The DOE prepared this LTSP to meet this requirement for the South Clive disposal site. The general license becomes effective when the NRC concurs with the DOE`s determination of completion of remedial action for the South Clive site and the NRC formally accepts this LTSP. This LTSP describes the long-term surveillance program the DOE will implement to ensure that the South Clive disposal site performs as designed. The program`s primary activity is site inspections to identify threats to disposal cell integrity.

NONE

1996-03-01T23:59:59.000Z

420

Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site  

SciTech Connect (OSTI)

This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd{sup 3} (4,580 m{sup 3}) of glass gems prior to disposal. This report documents Sandia National Laboratories` preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment.

Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Price, L.L. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Beta Inc. (United States)

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "wds llw disposal" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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421

Used oil disposal and recycling in the United States  

SciTech Connect (OSTI)

Used oil represents an important energy resource, which, if properly managed and reused, could lessen US dependence on imported fuels. About 1.4 million gallons of used oil is generated annually in the United States. Of that total, about 70% is recycled: 57% is used as fuel and 12% is refined. In August 1992, the US Environmental Protection Agency adopted standards for recycling of used oil, and many states also regulate used oil (six states list used oil as hazardous waste). This report reviews the sources of used oil and methods of disposition, focusing on reprocessing and re-refining. About 83% of the recycled used oil is reprocessed for use as fuel. However, concern about the level of lead in such fuel is increasing. Re-refining used oil is an environmentally friendly process that yields higher energy savings than reprocessing; however, it is more capital-intensive. Reprocessing used oil for use as fuel yields an energy savings (over disposal) of 131,130 Btu/gal, while re-refining the oil for reuse as lube oil saves 180,000 Btu/gal, an advantage of 48,870 Btu/gal. However, further research is needed to enhance re- refining and to demonstrate the quality and competitiveness of its products.

Karvelas, D.E.; Daniels, E.J.

1993-07-01T23:59:59.000Z

422

Stabilization of a mixed waste sludge for land disposal  

SciTech Connect (OSTI)

A solidification and stabilization technique was developed for a chemically complex mixed waste sludge containing nitrate processing wastes, sewage sludge and electroplating wastewaters, among other wastes. The sludge is originally from a solar evaporation pond and has high concentrations of nitrate salts; cadmium, chromium, and nickel concentrations of concern; and low levels of organic constituents and alpha and beta emitters. Sulfide reduction of nitrate and precipitation of metallic species, followed by evaporation to dryness and solidification of the dry sludge in recycled high density polyethylene with added lime was determined to be a satisfactory preparation for land disposal in a mixed waste repository. The application of post-consumer polyethylene has the added benefit of utilizing another problem-causing waste product. A modified Toxicity Characteristic Leaching Procedure was used to determine required treatment chemical dosages and treatment effectiveness. The waste complexity prohibited use of standard chemical equilibrium methods for prediction of reaction products during treatment. Waste characterization followed by determination of thermodynamic feasibility of oxidation and reduction products. These calculations were shown to be accurate in laboratory testing. 13 refs., 3 figs., 2 tabs.

Powers, S.E.; Zander, A.K. [Clarkson Univ., Potsdam, NY (United States)

1996-12-31T23:59:59.000Z

423

Automated Monitoring System for Waste Disposal Sites and Groundwater  

SciTech Connect (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

424

Conditioning of spent nuclear fuel for permanent disposal  

SciTech Connect (OSTI)

A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or pyroprocessing, provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the US Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (> 99.9%) separation of transuranics. The resultant waste forms from the pyroprocess are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and that avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

Laidler, J.J. [Argonne National Lab., IL (United States). Chemical Technology Div.

1994-12-31T23:59:59.000Z

425

Conditioning of spent nuclear fuel for permanent disposal  

SciTech Connect (OSTI)

A compact, efficient method for conditioning spent nuclear fuel is under development This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (99.9%) separation of transuranics. The resultant waste forms from the pyroprocess are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and preclude the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

Laidler, J.J.

1994-10-01T23:59:59.000Z

426

Generic Disposal System Modeling--Fiscal Year 2011 Progress Report  

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

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

427

Operating limit evaluation for disposal of uranium enrichment plant wastes  

SciTech Connect (OSTI)

A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) will accept wastes generated during normal plant operations that are considered to be non-radioactive. However, nearly all solid waste from any source or facility contains small amounts of radioactive material, due to the presence in most materials of trace quantities of such naturally occurring radionuclides as uranium and thorium. This paper describes an evaluation of operating limits, which are protective of public health and the environment, that would allow waste materials containing small amounts of radioactive material to be sent to a new solid waste landfill at PGDP. The operating limits are expressed as limits on concentrations of radionuclides in waste materials that could be sent to the landfill based on a site-specific analysis of the performance of the facility. These limits are advantageous to PGDP and DOE for several reasons. Most importantly, substantial cost savings in the management of waste is achieved. In addition, certain liabilities that could result from shipment of wastes to a commercial off-site solid waste landfill are avoided. Finally, assurance that disposal operations at the PGDP landfill are protective of public health and the environment is provided by establishing verifiable operating limits for small amounts of radioactive material; rather than relying solely on administrative controls. The operating limit determined in this study has been presented to the Commonwealth of Kentucky and accepted as a condition to be attached to the operating permit for the solid waste landfill.

Lee, D.W.; Kocher, D.C.; Wang, J.C.

1996-02-01T23:59:59.000Z

428

Idaho CERCLA Disposal Facility Complex Compliance Demonstration for DOE Order 435.1  

SciTech Connect (OSTI)

This compliance demonstration document provides an analysis of the Idaho CERCLA Disposal Facility (ICDF) Complex compliance with DOE Order 435.1. The ICDF Complex includes the disposal facility (landfill), evaporation pond, administration facility, weigh scale, and various staging/storage areas. These facilities were designed and constructed to be compliant with DOE Order 435.1, Resource Conservation and Recovery act Subtitle C, and Toxic Substances Control Act polychlorinated biphenyl design and construction standards. The ICDF Complex is designated as the Idaho National Laboratory (INL) facility for the receipt, staging/storage, treatment, and disposal of INL Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) waste streams.

Simonds, J.

2007-11-06T23:59:59.000Z

429

Z-Area saltstone disposal facility groundwater monitoring report. First and second quarters 1997  

SciTech Connect (OSTI)

This report presents the results of groundwater sampling during the first and second quarters of 1997 in the Z-Area Saltstone Disposal Facility. This report presents only the data for sampling during the first half of 1997 as required by industrial Solid Waste Permit No. 025500-1603. For a detailed discussion of groundwater monitoring in the Z-Area Saltstone Disposal Facility, consult the 1996 Z-Area Saltstone Disposal Annual Report. Appendix A presents the proposed South Carolina Department of Health and Environmental Control Proposed Groundwater Monitoring Standards. Flagging criteria are described in Appendix B. In May 1997 SCDHEC granted approval for seven hydrocone sampling.

NONE

1997-07-01T23:59:59.000Z

430

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect (OSTI)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. [Bechtel National, Inc., San Francisco, CA (United States); Schafer, J.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-05-01T23:59:59.000Z

431

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect (OSTI)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. (Bechtel National, Inc., San Francisco, CA (United States)); Schafer, J.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-05-01T23:59:59.000Z

432

Long-term surveillance plan for the Mexican Hat disposal site, Mexican Hat, Utah  

SciTech Connect (OSTI)

This plan describes the long-term surveillance activities for the Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site at Mexican Hat, Utah. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This long-term surveillance plan (LTSP) was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive material (RRM). This LTSPC documents the land ownership interests and details how the long-term care of the disposal site will be accomplished.

NONE

1996-01-01T23:59:59.000Z

433

Long-term surveillance plan for the South Clive disposal site Clive, Utah  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) describes the U.S. Department of Energy`s (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project South Clive disposal site in Clive, Utah. This LSTP describes the long-term surveillance program the DOE will implement to ensure the South Clive disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP.

NONE

1997-09-01T23:59:59.000Z

434

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect (OSTI)

This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders.

Not Available

1994-08-01T23:59:59.000Z

435

CHARACTERIZATION OF CORE SAMPLE COLLECTED FROM THE SALTSTONE DISPOSAL FACILITY  

SciTech Connect (OSTI)

During the month of September 2008, grout core samples were collected from the Saltstone Disposal Facility, Vault 4, cell E. This grout was placed during processing campaigns in December 2007 from Deliquification, Dissolution and Adjustment Batch 2 salt solution. The 4QCY07 Waste Acceptance Criteria sample collected on 11/16/07 represents the salt solution in the core samples. Core samples were retrieved to initiate the historical database of properties of emplaced Saltstone and to demonstrate the correlation between field collected and laboratory prepared samples. Three samples were collected from three different locations. Samples were collected using a two-inch diameter concrete coring bit. In April 2009, the core samples were removed from the evacuated sample container, inspected, transferred to PVC containers, and backfilled with nitrogen. Samples furthest from the wall were the most intact cylindrically shaped cored samples. The shade of the core samples darkened as the depth of coring increased. Based on the visual inspection, sample 3-3 was selected for all subsequent analysis. The density and porosity of the Vault 4 core sample, 1.90 g/cm{sup 3} and 59.90% respectively, were comparable to values achieved for laboratory prepared samples. X-ray diffraction analysis identified phases consistent with the expectations for hydrated Saltstone. Microscopic analysis revealed morphology features characteristic of cementitious materials with fly ash and calcium silicate hydrate gel. When taken together, the results of the density, porosity, x-ray diffraction analysis and microscopic analysis support the conclusion that the Vault 4, Cell E core sample is representative of the expected waste form.

Cozzi, A.; Duncan, A.

2010-01-28T23:59:59.000Z

436

Gasification combined cycle: Carbon dioxide recovery, transport, and disposal  

SciTech Connect (OSTI)

The objective of the project is to develop engineering evaluations of technologies for the capture, use, and disposal of carbon dioxide (CO{sub 2}). This project emphasizes CO{sub 2}-capture technologies combined with integrated gasification combined-cycle (IGCC) power systems. Complementary evaluations address CO{sub 2} transportation, CO{sub 2} use, and options for the long-term sequestering of unused CO{sub 2}. Commercially available CO{sub 2}-capture technology is providing a performance and economic baseline against which to compare innovative technologies. The intent is to provide the CO{sub 2} budget, or an {open_quotes}equivalent CO{sub 2}{close_quotes} budget, associated with each of the individual energy-cycle steps, in addition to process design capital and operating costs. The value used for the {open_quotes}equivalent CO{sub 2}{close_quotes} budget is 1 kg of CO{sub 2} per kilowatt-hour (electric). The base case is a 458-MW IGCC system that uses an air-blown Kellogg-Rust-Westinghouse agglomerating fluidized-bed gasifier, Illinois No. 6 bituminous coal feed, and in-bed sulfur removal. Mining, feed preparation, and conversion result in a net electric power production of 454 MW, with a CO{sub 2} release rate of 0.835 kg/kWhe. Two additional life-cycle energy balances for emerging technologies were considered: (1) high-temperature CO{sub 2} separation with calcium- or magnesium-based sorbents, and (2) ambient-temperature facilitated-transport polymer membranes for acid-gas removal.

Doctor, R.D.; Molburg, J.C.; Thimmapuram, P.R.; Berry, G.F.; Livengood, C.D.

1994-09-01T23:59:59.000Z

437

U.S. and Russia Reaffirm Commitment to Disposing of Weapon-Grade Plutonium  

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

Reaffirm Commitment to Disposing of Weapon-Grade Reaffirm Commitment to Disposing of Weapon-Grade Plutonium U.S. and Russia Reaffirm Commitment to Disposing of Weapon-Grade Plutonium July 13, 2006 - 3:05pm Addthis WASHINGTON, DC - U.S. Energy Secretary Samuel W. Bodman and Sergey Kiriyenko, the director of Russia's Federal Atomic Energy Agency, have signed a joint statement reaffirming their commitment to dispose of 34 metric tons of excess weapon-grade plutonium by irradiation in nuclear reactors. "This statement is a clear sign of our mutual commitment to keeping dangerous nuclear material out of the hands of terrorists. We look forward to working together with the Russians to ensure that this important nonproliferation project moves forward in both Russia and the United States," Secretary Bodman said.

438

Summary - Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant  

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

Paducah, KY Paducah, KY EM Project: On-Site Disposal Facility ETR Report Date: August 2008 ETR-16 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Disposal Facility(OSDF) at the Paducah Gaseous Diffusion Plant Why DOE-EM Did This Review The Paducah Gaseous Diffusion Plant (PGDP) is an active uranium enrichment facility that was placed on the National Priorities List. DOE is required to remediate the PGDP in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). DOE is evaluating alternatives to dispose of waste generated from the remedial activities at the PGDP. One option is to construct an on-site disposal facility (OSDF) meeting the CERCLA requirements.

439

Salt Waste Disposal at the Savannah River Site | Department of Energy  

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

Salt Waste Disposal at the Savannah River Site Salt Waste Disposal at the Savannah River Site Salt Waste Disposal at the Savannah River Site Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Currently, DOE SRS has prepared one final (salt waste) and is working on two additional waste determinations: F Tank Farm and H Tank Farm. The Salt Waste Determination has been finalized and the Secretary of Energy issued that determination on January 17, 2006. In 2007, it was decided that due to a new Saltstone disposal vault design,

440

DOE Awards Task Order for Disposal of Los Alamos National Lab Waste |  

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

DOE Awards Task Order for Disposal of Los Alamos National Lab Waste DOE Awards Task Order for Disposal of Los Alamos National Lab Waste DOE Awards Task Order for Disposal of Los Alamos National Lab Waste November 13, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 bill.taylor@srs.gov Cincinnati - The Department of Energy (DOE) today awarded a task order in support of the Los Alamos National Laboratory Legacy Waste Project to Waste Control Specialists (WCS) of Andrews, Texas under the Environmental Management (EM) Low-Level and Mixed Low-Level Waste Disposal Indefinite Delivery/Indefinite Quantity (ID/IQ) Master Contract. This is a fixed-price task order based on pre-established rates with a $2,225,140 value and has a one-year performance period. The work to be performed under this task order includes the receipt and

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441

EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS  

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

89: Disposal of Decommissioned, Defueled Naval Reactor Plants 89: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington EA-1889: Disposal of Decommissioned, Defueled Naval Reactor Plants from USS Enterprise (CVN 65) at the Hanford Site, Richland, Washington Summary This EA, prepared by the Department of the Navy, evaluates the environmental impacts of the disposal of decommissioned, defueled, naval reactor plants from the USS Enterprise at DOE's Hanford Site, Richland, Washington. DOE participated as a cooperating agency in the preparation of this EA. The Department of the Navy issued its FONSI on August 23, 2012. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download August 23, 2012

442

Grand Junction, Colorado, Disposal Site Long-Term Surveillance and Maintenance Program Fact Sheet, July 2001  

Office of Legacy Management (LM)

Grand Junction Disposal Site Grand Junction Disposal Site Uranium ore was processed at the Climax millsite at Grand Junction, Colorado, between 1951 and 1970. The milling operations created process-related waste and tailings, a sandlike material containing radioactive materials and other contaminants. The tailings were an ideal and inexpensive construction material suitable for concrete, mortar, and fill. Accordingly, the tailings were widely used in the Grand Junction area for these purposes. The U.S. Department of Energy (DOE) encapsulated the tailings and other contaminated materials from the millsite and more than 4,000 vicinity properties in the Grand Junction area in an engineered disposal cell. Part of the disposal cell was completed in 1994; the remainder of the cell remains open until it is

443

DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at  

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

Announces Preference for Disposal of Hanford Transuranic Tank Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP March 6, 2013 - 12:00pm Addthis WASHINGTON, D.C. - Today the U.S. Department of Energy (DOE) announced its preferred alternative to retrieve, treat, package, characterize and certify certain Hanford tank waste for disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, if such waste is properly classified in the future as defense-related mixed transuranic tank waste (mixed TRU waste). This preferred alternative, which may cover up to approximately 3.1 million gallons of tank waste contained in up to 20 tanks, will provide DOE with an option to deal with recent information about possible tank leaks and to

444

DOE Completes Disposal Operations In Panel 5 of the WIPP Underground |  

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

Disposal Operations In Panel 5 of the WIPP Disposal Operations In Panel 5 of the WIPP Underground DOE Completes Disposal Operations In Panel 5 of the WIPP Underground August 15, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy (DOE) announced that disposal operations in Panel 5 of the Waste Isolation Pilot Plant (WIPP) underground repository are complete. Last month, the final contact-handled transuranic (CH-TRU) waste shipment was emplaced in the panel, which took just over two years to fill. "All TRU waste management employees at WIPP and at the generator sites deserve the credit for this accomplishment," National TRU Program Director J.R. Stroble said. "It is through their dedication to performing their jobs safely, compliantly and timely that WIPP and the TRU Waste

445

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and  

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

EIS-0250: Geologic Repository for the Disposal of Spent Nuclear EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada EIS-0250: Geologic Repository for the Disposal of Spent Nuclear Fuel and High-Level Radioactive Waste at Yucca Mountain, Nye County, Nevada Summary This EIS analyzes DOE's proposed action to construct, operate, monitor, and eventually close a geologic repository at Yucca Mountain for the disposal of spent nuclear fuel and high-level radioactive waste. The EIS evaluates not only impacts from constructing, operating, monitoring, and closing a repository, but also from transporting the materials from 72 commercial and 4 DOE sites to the Yucca Mountain repository site in Nye County, Nevada. Public Comment Opportunities

446

DOE Completes Disposal Operations In Panel 5 of the WIPP Underground |  

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

DOE Completes Disposal Operations In Panel 5 of the WIPP DOE Completes Disposal Operations In Panel 5 of the WIPP Underground DOE Completes Disposal Operations In Panel 5 of the WIPP Underground August 15, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy (DOE) announced that disposal operations in Panel 5 of the Waste Isolation Pilot Plant (WIPP) underground repository are complete. Last month, the final contact-handled transuranic (CH-TRU) waste shipment was emplaced in the panel, which took just over two years to fill. "All TRU waste management employees at WIPP and at the generator sites deserve the credit for this accomplishment," National TRU Program Director J.R. Stroble said. "It is through their dedication to performing

447

Moab Mill Tailings Pile 25 Percent Disposed: DOE Moab Project Reaches  

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

Mill Tailings Pile 25 Percent Disposed: DOE Moab Project Mill Tailings Pile 25 Percent Disposed: DOE Moab Project Reaches Significant Milestone Moab Mill Tailings Pile 25 Percent Disposed: DOE Moab Project Reaches Significant Milestone June 3, 2011 - 12:00pm Addthis Media Contacts Donald Metzler Moab Federal Project Director (970) 257-2115 Wendee Ryan S&K Aerospace Public Affairs Manager (970) 257-2145 Grand Junction, CO - One quarter of the uranium mill tailings pile located in Moab, Utah, has been relocated to the Crescent Junction, Utah, site for permanent disposal. Four million tons of the 16 million tons total has been relocated under the Uranium Mill Tailings Remedial Action Project managed by the U.S. Department of Energy (DOE). A little over 2 years ago, Remedial Action Contractor EnergySolutions began

448

FAQ 27-Are there any currently-operating disposal facilities that can  

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

currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? Are there any currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? With respect to available capacity, three sites could accept the entire inventory of depleted uranium oxide: the Department of Energy's (DOE's) Hanford site in Washington State, DOE's Nevada Test Site, or EnergySolution Clive, Utah Facility, a commercial site. Each of these sites would have sufficient capacity for either the grouted or ungrouted oxide forms of depleted uranium (for the two DOE sites, this also takes into account other projected disposal volumes through the year 2070).

449

Moab Mill Tailings Removal Project Reaches 5 Million Tons Disposed: Project  

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

Moab Mill Tailings Removal Project Reaches 5 Million Tons Disposed: Moab Mill Tailings Removal Project Reaches 5 Million Tons Disposed: Project Accomplishes Milestone While Doing it Safely Moab Mill Tailings Removal Project Reaches 5 Million Tons Disposed: Project Accomplishes Milestone While Doing it Safely February 27, 2012 - 12:00pm Addthis Media Contacts Donald Metzler, Moab Federal Project Director, (970) 257-2115 Wendee Ryan, S&K Aerospace Public Affairs Manager, (970) 257-2145 Grand Junction, CO- The U.S. Department of Energy (DOE) reached another milestone today for the Uranium Mill Tailings Remedial Action Project, having shipped 5 million tons of tailings from the massive pile located in Moab, Utah, to the engineered disposal cell near Crescent Junction, Utah. The pile comprised an estimated 16 million tons total when DOE's Remedial

450

Dynamics of particle clouds in ambient currents with application to open-water sediment disposal  

E-Print Network [OSTI]

Open-water sediment disposal is used in many applications around the world, including land reclamation, dredging, and contaminated sediment isolation. Timely examples include the land reclamation campaign currently underway ...

Gensheimer, Robert James, III

2010-01-01T23:59:59.000Z

451

Long-term surveillance plan for the Bodo Canyon Disposal Site, Durango, Colorado  

SciTech Connect (OSTI)

This long-term surveillance plan (LTSP) for the Durango, Colorado, Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site describes the surveillance activities for the Durango (Bodo Canyon) disposal site, which will be referred to as the disposal site throughout this document. The US Department of Energy (DOE) will carry out these activities to ensure that the disposal site continues to function as designed. This LTSP was prepared as a requirement for acceptance under the US Nuclear Regulatory Commission (NRC) general license for custody and long-term care of residual radioactive materials (RRM). RRMs include tailings and other uranium ore processing wastes still at the site, which the DOE determines to be radioactive. This LTSP is based on the DOE`s Guidance for Implementing the UMTRA Project Long-term Surveillance Program (DOE, 1992).

Not Available

1994-03-01T23:59:59.000Z

452

Regulatory standards for permanent disposal of spent nuclear fuel and high-level radioactive waste.  

SciTech Connect (OSTI)

This paper provides a summary of observations drawn from twenty years of personal experience in working with regulatory criteria for the permanent disposal of radioactive waste for both the Waste Isolation Pilot Plant repository for transuranic defense waste and the proposed Yucca Mountain repository for spent nuclear fuel and high-level wastes. Rather than providing specific recommendations for regulatory criteria, my goal here is to provide a perspective on topics that are fundamental to how high-level radioactive waste disposal regulations have been implemented in the past. What are the main questions raised relevant to long-term disposal regulations? What has proven effective in the past? Where have regulatory requirements perhaps had unintended consequences? New regulations for radioactive waste disposal may prove necessary, but the drafting of these regulations may be premature until a broad range of policy issues are better addressed. In the interim, the perspective offered here may be helpful for framing policy discussions.

Swift, Peter N.

2010-08-01T23:59:59.000Z

453

Thermoplastic Microfluidic Device for On-Chip Purification of Nucleic Acids for Disposable  

E-Print Network [OSTI]

Thermoplastic Microfluidic Device for On-Chip Purification of Nucleic Acids for Disposable, Brookline, Massachusetts 02446 A polymeric microfluidic device for solid-phase extraction (SPE applications. Microfluidic approaches to nucleic acid isolation have therefore received great attention

454

Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal  

Broader source: Energy.gov [DOE]

The Department of Energy (DOE) published in the Federal Register (January 24, 2006), a Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site.

455

Citizen-State Interaction and Technical Controversy: The U.S. Army Chemical Stockpile Disposal Program  

E-Print Network [OSTI]

This paper explores the development and transformation of a local collective campaign opposing the U.S. Army's ChemicaL Weapons Stockpile Disposal Program into a social movement with national and international dimensions. ...

Futrell, Robert

1997-04-01T23:59:59.000Z

456

Standard Contract for Disposal of SNF and/or HRW | Department...  

Energy Savers [EERE]

under the laws of a given state to dispose of Spent Nuclear Fuel (SNF) andor High-Level Radioactive Waste (HRW). NewStandardContract.pdf More Documents & Publications...

457

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal  

SciTech Connect (OSTI)

The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs.

Klett, R.D.

1997-06-01T23:59:59.000Z

458

E-Print Network 3.0 - assess waste disposal Sample Search Results  

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

the University is implementing a charge to fund the costs of handling and disposal of "E-Waste." As previously... : Tuesday, December 23, 2008 Re: Notice of E-Waste Charge,...

459

Ecotoxicological Implications of Aquatic Disposal of Coal Combustion Residues In the United States: A Review  

Science Journals Connector (OSTI)

We provide an overview of research related to environmental effects of disposal of coal combustion residues (CCR) in sites in the United States. Our focus is on aspects of CCR that have the potential to negati...

Christopher L. Rowe; William A. Hopkins…

2002-12-01T23:59:59.000Z

460

Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site  

Broader source: Energy.gov [DOE]

The Department of Energy (DOE) announces the availability of a section 3116 determination for the disposal of separated, solidified, low-activity salt waste at the Savannah River Site (SRS) near...