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1

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

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

2

Storage and disposal of radioactive waste as glass in canisters  

SciTech Connect

A review of the use of waste glass for the immobilization of high-level radioactive waste glass is presented. Typical properties of the canisters used to contain the glass, and the waste glass, are described. Those properties are used to project the stability of canisterized waste glass through interim storage, transportation, and geologic disposal.

Mendel, J.E.

1978-12-01T23:59:59.000Z

3

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

Science Conference Proceedings (OSTI)

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

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

2008-01-15T23:59:59.000Z

4

Hanford Site waste treatment/storage/disposal integration  

SciTech Connect

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

MCDONALD, K.M.

1999-02-24T23:59:59.000Z

5

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

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

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

6

Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities  

SciTech Connect

A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

Jardine, L J; Borisov, G B

2004-07-21T23:59:59.000Z

7

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

SciTech Connect

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

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

1961-08-22T23:59:59.000Z

8

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

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

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

9

Review of private sector treatment, storage, and disposal capacity for radioactive waste. Revision 1  

SciTech Connect

This report is an update of a report that summarized the current and near-term commercial and disposal of radioactive and mixed waste. This report was capacity for the treatment, storage, dating and written for the Idaho National Engineering Laboratory (INEL) with the objective of updating and expanding the report entitled ``Review of Private Sector Treatment, Storage, and Disposal Capacity for Radioactive Waste``, (INEL-95/0020, January 1995). The capacity to process radioactively-contaminated protective clothing and/or respirators was added to the list of private sector capabilities to be assessed. Of the 20 companies surveyed in the previous report, 14 responded to the request for additional information, five did not respond, and one asked to be deleted from the survey. One additional company was identified as being capable of performing LLMW treatability studies and six were identified as providers of laundering services for radioactively-contaminated protective clothing and/or respirators.

Smith, M.; Harris, J.G.; Moore-Mayne, S.; Mayes, R.; Naretto, C.

1995-04-14T23:59:59.000Z

10

Title: An Advanced Solution for the Storage, Transportation and Disposal of Vitrified High Level Waste  

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

Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 Presented at Global 99, Jackson, Wyoming, August 29 - September 2, 1999 1 AN ADVANCED SOLUTION FOR THE STORAGE, TRANSPORTATION AND DISPOSAL OF SPENT FUEL AND VITRIFIED HIGH LEVEL WASTE William J. Quapp Teton Technologies, Inc. 860 W. Riverview Dr. Idaho Falls, ID 83401 208-535-9001 ABSTRACT For future nuclear power deployment in the US, certain changes in the back end of the fuel cycle, i.e., disposal of high level waste and spent fuel, must become a real options. However, there exists another problem from the front end of the fuel cycle which has until recently, received less attention. Depleted uranium hexafluoride is a by-product of the enrichment process and has accumulated for over 50 years. It now represents a potential environmental problem. This paper describes a

11

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

SciTech Connect

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

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

1996-09-01T23:59:59.000Z

12

Used Oil and Filter Disposal Used Oil: Create a segregated storage area or container. Label the container "Waste Oil Only".  

E-Print Network (OSTI)

Used Oil and Filter Disposal Used Oil: Create a segregated storage area or container. Label the container "Waste Oil Only". Maintain a written log to document all amounts and types of oil added to the container. No solvents, oil contaminated with solvents, PCBs, non-petroleum based oils, or any other

Yener, Aylin

13

Submergible barge retrievable storage and permanent disposal system for radioactive waste  

DOE Patents (OSTI)

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

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

1981-01-01T23:59:59.000Z

14

Sample storage/disposal study  

SciTech Connect

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

Valenzuela, B.D.

1994-09-29T23:59:59.000Z

15

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

16

Pioneering Nuclear Waste Disposal  

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

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

17

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

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

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

18

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

19

HNPF LIQUID WASTE DISPOSAL COST STUDY  

SciTech Connect

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

Piccot, A.R.

1959-11-01T23:59:59.000Z

20

Pioneering Nuclear Waste Disposal  

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

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

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

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

Science Conference Proceedings (OSTI)

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

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

2008-04-15T23:59:59.000Z

22

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

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

23

TWRS Retrieval and Storage Mission and Immobilized Low Activity Waste (ILAW) Disposal Plan  

Science Conference Proceedings (OSTI)

This project plan has a twofold purpose. First, it provides a waste stream project plan specific to the River Protection Project (RPP) (formerly the Tank Waste Remediation System [TWRS] Project) Immobilized Low-Activity Waste (LAW) Disposal Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-90-01 (Ecology et al. 1994) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan (Ecology et al. 1998). Second, it provides an upper tier document that can be used as the basis for future subproject line-item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 [DOE 1992] and 430.1 [DOE 1995a]). The format and content of this project plan are designed to accommodate the requirements mentioned by the Tri-Party Agreement and the DOE orders. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

BURBANK, D.A.

1999-09-01T23:59:59.000Z

24

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

25

Proceedings of the 6th Annual Meeting for Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and WasteTreatment, Storage and Disposal Activities  

SciTech Connect

The sixth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held November 15-17, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, and Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 55 Russian attendees from 16 different Russian organizations and four non-Russian attendees from the US. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C. The 16 different Russian design, industrial sites, and scientific organizations in attendance included staff from Rosatom/Minatom, Federal Nuclear and Radiation Safety Authority of Russia (GOSATOMNADZOR, NIERA/GAN), All Russian Designing & Scientific Research Institute of Complex Power Technology (VNIPIET), Khlopin Radium Institute (KRI), A. A. Bochvar All Russian Scientific Research Institute of Inorganic Materials (VNIINM), All Russian & Design Institute of Production Engineering (VNIPIPT), Ministry of Atomic Energy of Russian Federation Specialized State Designing Institute (GSPI), State Scientific Center Research Institute of Atomic Reactors (RIAR), Siberian Chemical Combine Tomsk (SCC), Mayak PO, Mining Chemical Combine (MCC K-26), Institute of Biophysics (IBPh), Sverdlosk Scientific Research Institute of Chemical Machine Building (SNIIChM), Kurchatov Institute (KI), Institute of Physical Chemistry Russian Academy of Science (IPCh RAS) and Radon PO-Moscow. The four non-Russian attendees included one representative from DOE NNSA, and LLNL, and two from Duratek, The meeting was organized into three major sessions: (1) Waste Treatment, Storage and Disposal; (2) Plutonium Packaging, Storage and Transportation; (3) Spent Fuel Packaging, Storage and Transportation. Twenty presentations were made on the topic of Waste Treatment, Storage and Disposal (Session II), ten presentations on Plutonium Packaging, Storage and Transportation (Session III), and four presentations on Spent Fuel Packaging, Storage and Transportation (Session IV). In addition, DOE/NNSA, Minatom/Rosatom and TVEL summarized the bases for the conference at the beginning of the meeting (Session I). Nine months had passed since the last LLNL contracts review meeting. During that time period, LLNL and TVEL have been able to sign six contracts for a total of $1,700,000 in the areas of: (1) Waste treatment, storage and disposal; and (2) Plutonium packaging, storage and transportation. The scope of several other work projects are now in various stages of development in these areas. It is anticipated that more contracts will be signed before the next meeting of this type. These events have allowed us to start work in our technical activities under new direction from TVEL, which is now the single Russian organization to coordinate and conclude contracts with LLNL. The meeting presentations and discussions have defined where we are and where we are going in the near term in regard to our joint interests in excess weapons plutonium disposition. Each topical section of this Proceedings is introduced by a summary of the presentations in that section.

Jardine, L J

2005-06-30T23:59:59.000Z

26

TWRS retrieval and disposal mission, immobilized high-level waste storage plan  

SciTech Connect

This project plan has a two fold purpose. First, it provides a plan specific to the Hanford Tank Waste Remediation System (TWRS) Immobilized High-Level Waste (EMW) Storage Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestone M-90-01 (Ecology et al. 1996) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan. Second, it provides an upper tier document that can be used as the basis for future subproject line item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 (DOE 1992a) and 430.1 (DOE 1995)). The format and content of this project plan are designed to accommodate the plan`s dual purpose. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

Calmus, R.B.

1998-01-07T23:59:59.000Z

27

Comparative assessment of status and opportunities for carbon Dioxide Capture and storage and Radioactive Waste Disposal In North America  

SciTech Connect

Aside from the target storage regions being underground, geologic carbon sequestration (GCS) and radioactive waste disposal (RWD) share little in common in North America. The large volume of carbon dioxide (CO{sub 2}) needed to be sequestered along with its relatively benign health effects present a sharp contrast to the limited volumes and hazardous nature of high-level radioactive waste (RW). There is well-documented capacity in North America for 100 years or more of sequestration of CO{sub 2} from coal-fired power plants. Aside from economics, the challenges of GCS include lack of fully established legal and regulatory framework for ownership of injected CO{sub 2}, the need for an expanded pipeline infrastructure, and public acceptance of the technology. As for RW, the USA had proposed the unsaturated tuffs of Yucca Mountain, Nevada, as the region's first high-level RWD site before removing it from consideration in early 2009. The Canadian RW program is currently evolving with options that range from geologic disposal to both decentralized and centralized permanent storage in surface facilities. Both the USA and Canada have established legal and regulatory frameworks for RWD. The most challenging technical issue for RWD is the need to predict repository performance on extremely long time scales (10{sup 4}-10{sup 6} years). While attitudes toward nuclear power are rapidly changing as fossil-fuel costs soar and changes in climate occur, public perception remains the most serious challenge to opening RW repositories. Because of the many significant differences between RWD and GCS, there is little that can be shared between them from regulatory, legal, transportation, or economic perspectives. As for public perception, there is currently an opportunity to engage the public on the benefits and risks of both GCS and RWD as they learn more about the urgent energy-climate crisis created by greenhouse gas emissions from current fossil-fuel combustion practices.

Oldenburg, C.; Birkholzer, J.T.

2011-07-22T23:59:59.000Z

28

Pioneering Nuclear Waste Disposal  

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

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

29

Pioneering Nuclear Waste Disposal  

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

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

30

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

31

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

32

Waste Disposal (Illinois) | Department of Energy  

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

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

33

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

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

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

34

Solid Waste Disposal Act (Texas)  

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

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

35

Pioneering Nuclear Waste Disposal  

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

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

36

WASTE DISPOSAL SECTION CORNELL UNIVERSITY  

E-Print Network (OSTI)

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

Manning, Sturt

37

WEB RESOURCE: Nuclear Waste Disposal  

Science Conference Proceedings (OSTI)

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

38

Waste disposal and renewable resources.  

E-Print Network (OSTI)

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

Hai, Qu; PiaoYi, Sun

2013-01-01T23:59:59.000Z

39

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

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

NONE

1996-08-01T23:59:59.000Z

40

Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect

Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

1996-12-01T23:59:59.000Z

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

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

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

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

42

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

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

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

43

LEGACY NONCONFORMANCE ISSUE IN SOLID WASTE DISPOSAL  

Science Conference Proceedings (OSTI)

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

ROGERS, C.A.

2002-12-16T23:59:59.000Z

44

Laboratory Waste Disposal HAZARDOUS GLASS  

E-Print Network (OSTI)

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

Sheridan, Jennifer

45

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

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

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

46

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

SciTech Connect

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

47

Regional geological assessment of the Devonian-Mississippian shale sequence of the Appalachian, Illinois, and Michigan basins relative to potential storage/disposal of radioactive wastes  

SciTech Connect

The thick and regionally extensive sequence of shales and associated clastic sedimentary rocks of Late Devonian and Early Mississippian age has been considered among the nonsalt geologies for deep subsurface containment of high-level radioactive wastes. This report examines some of the regional and basin-specific characteristics of the black and associated nonblack shales of this sequence within the Appalachian, Illinois, and Michigan basins of the north-central and eastern United States. Principal areas where the thickness and depth of this shale sequence are sufficient to warrant further evaluation are identified, but no attempt is made to identify specific storage/disposal sites. Also identified are other areas with less promise for further study because of known potential conflicts such as geologic-hydrologic factors, competing subsurface priorities involving mineral resources and groundwater, or other parameters. Data have been compiled for each basin in an effort to indicate thickness, distribution, and depth relationships for the entire shale sequence as well as individual shale units in the sequence. Included as parts of this geologic assessment are isopach, depth information, structure contour, tectonic elements, and energy-resource maps covering the three basins. Summary evaluations are given for each basin as well as an overall general evaluation of the waste storage/disposal potential of the Devonian-Mississippian shale sequence,including recommendations for future studies to more fully characterize the shale sequence for that purpose. Based on data compiled in this cursory investigation, certain rock units have reasonable promise for radioactive waste storage/disposal and do warrant additional study.

Lomenick, T.F.; Gonzales, S.; Johnson, K.S.; Byerly, D.

1983-01-01T23:59:59.000Z

48

WIPP - Pioneering Nuclear Waste Disposal  

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

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

49

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

Science Conference Proceedings (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

50

Environmental waste disposal contracts awarded  

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

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

51

Tank Waste Disposal Program redefinition  

SciTech Connect

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

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

1991-10-01T23:59:59.000Z

52

Hanford Landfill Reaches 15 Million Tons Disposed - Waste Disposal Mark  

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

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

53

Pioneering Nuclear Waste Disposal  

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

T h e W a s t e I s o l a t i o n P i l o t P l a n t DOE 1980. Final Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1981. Waste Isolation Pilot Plant (WIPP): Record of Decision. Federal Register, Vol. 46, No. 18, p. 9162, (46 Federal Register 9162), January 28, 1981. U.S. Department of Energy. DOE 1990. Final Supplement Environmental Impact Statement, Waste Isolation Pilot Plant. DOE/EIS-0026-FS, Washington, DC, Office of Environmental Management, U.S. Department of Energy. DOE 1990. Record of Decision: Waste Isolation Pilot Plant. Federal Register, Vol. 55, No. 121, 25689-25692, U.S. Department of Energy. DOE 1994. Comparative Study of Waste Isolation Pilot Plant (WIPP) Transportation Alternatives.

54

Waste disposal options report. Volume 1  

SciTech Connect

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

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

1998-02-01T23:59:59.000Z

55

Disposing of nuclear waste in a salt bed  

NLE Websites -- All DOE Office Websites (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

56

Disposal of NORM waste in salt caverns  

Science Conference Proceedings (OSTI)

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

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

1998-07-01T23:59:59.000Z

57

REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE  

SciTech Connect

It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. This indicates that the salt mass is not permeable under conditions of prevailing underground temperature and pressure. Salt specimens tested under atmospheric Pressure and temperature exhibited permeabilities of 0.1 to 0.2 millidarcys. The cost of completing underground storage cavities in salt masses is expected to be approximately 05 per barrel of storage space. (auth)

Brown, K.E.; Jessen, F.W.; Gloyna, E.F.

1959-01-15T23:59:59.000Z

58

Date: ____________ MATERIAL FOR HAZARDOUS WASTE DISPOSAL  

E-Print Network (OSTI)

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

Sinnamon, Gordon J.

59

NDAA Section 3116 Waste Determinations with Related Disposal...  

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

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

60

DISPOSAL OF RADIOACTIVE WASTE ON LAND  

SciTech Connect

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

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

1958-06-01T23:59:59.000Z

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

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

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

62

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

E-Print Network (OSTI)

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

Tsang, C.-F.

2009-01-01T23:59:59.000Z

63

Development of biological and chemical methods for environmental monitoring of DOE waste disposal and storage facilities. Final report  

SciTech Connect

Hazardous chemicals in the environment have received ever increasing attention in recent years. In response to ongoing problems with hazardous waste management, Congress enacted the Resource Conservation and Recovery Act (RCRA) in 1976. In 1980, Congress adopted the Comprehensive Environmental Response Compensation, and Liability Act (CERCLA), commonly called Superfund to provide for emergency spill response and to clean up closed or inactive hazardous waste sites. Scientists and engineers have begun to respond to the hazardous waste challenge with research and development on treatment of waste streams as well as cleanup of polluted areas. The magnitude of the problem is just now beginning to be understood. The U.S. Environmental Protection Agency (USEPA) National Priorities List as of September 13 1985, contained 318 proposed sites and 541 final sites (USEPA, 1985). Estimates of up to 30,000 sites containing hazardous wastes (1,200 to 2,000 of which present a serious threat to public health) have been made (Public Law 96-150). In addition to the large number of sites, the costs of cleanup using available technology are phenomenal. For example, a 10-acre toxic waste site in Ohio is to be cleaned up by removing chemicals from the site and treating the contaminated groundwater. The federal government has already spent more than $7 million to remove the most hazardous wastes and the groundwater decontamination alone is expected to take at least 10 years and cost $12 million. Another example of cleanup costs comes from the State of California Commission for Economic Development which predicts a bright economic future for the state except for the potential outlay of $40 billion for hazardous waste cleanup mandated by federal and state laws.

NONE

1989-04-01T23:59:59.000Z

64

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

E-Print Network (OSTI)

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

Russell, Lynn

65

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

E-Print Network (OSTI)

2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619 (9:1) OR Biohazard symbol (if untreated) and identity of liquid waste Biohazard symbol Address

Firtel, Richard A.

66

Waste disposal options report. Volume 2  

SciTech Connect

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

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

1998-02-01T23:59:59.000Z

67

Evaluation of waste disposal by shale fracturing  

SciTech Connect

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

Weeren, H.O.

1976-02-01T23:59:59.000Z

68

Aerosol can waste disposal device  

DOE Patents (OSTI)

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

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

1993-01-01T23:59:59.000Z

69

Aerosol can waste disposal device  

DOE Patents (OSTI)

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

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

1993-12-21T23:59:59.000Z

70

Preparing Class B and C Waste for Long Term Storage  

SciTech Connect

Commercial Nuclear Generating Stations outside of the Atlantic Compact will lose access to the Barnwell Disposal Facility in July of 2008. Many generators have constructed Interim On-Site Storage Buildings (IOSB) in which to store class B and C waste in the future as other permanent disposal options are developed. Until such time it is important for these generators to ensure class B and C waste generation is minimized and waste generated is packaged to facilitate long term storage. (authors)

Snyder, M.W. [Sacramento Municipal Utility District - Rancho Seco (United States)

2008-07-01T23:59:59.000Z

71

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

Science Conference Proceedings (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

72

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

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

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

73

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

E-Print Network (OSTI)

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

74

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

E-Print Network (OSTI)

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

Zaferatos, Nicholas C.

75

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria  

SciTech Connect

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

76

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

SciTech Connect

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

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

2013-07-29T23:59:59.000Z

77

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

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

78

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

Science Conference Proceedings (OSTI)

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

Beam, T.G.

1996-04-26T23:59:59.000Z

79

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect

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

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

1994-09-01T23:59:59.000Z

80

Disposal of oil field wastes and NORM wastes into salt caverns.  

Science Conference Proceedings (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 nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM), the risk 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 NOW into salt caverns is feasible and, in most cases, would not be prohibited by state agencies (although those agencies may need to revise their wastes management regulations). A risk analysis of several cavern leakage scenarios suggests that the risk from cavern disposal of NOW and NORM wastes is below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

Veil, J. A.

1999-01-27T23:59:59.000Z

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

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

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

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

82

Environmental restoration waste materials co-disposal  

Science Conference Proceedings (OSTI)

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

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

1993-09-01T23:59:59.000Z

83

WASTE TREATMENT AND DISPOSAL PROBLEMS OF THE FUTURE NUCLEAR POWER INDUSTRY  

SciTech Connect

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

Bruce, F.R.

1959-01-28T23:59:59.000Z

84

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect

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

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

1994-07-01T23:59:59.000Z

85

Volume 5: Waste Forms for Interim Storage, Revision 1  

Science Conference Proceedings (OSTI)

In the 1990s, the Electric Power Research Institute (EPRI) published a series of guidance reports on Interim On-Site Storage of Low Level Waste due to concern that loss of access to disposal pathways might one day lead to the need for interim on-site storage of low level waste (LLW). With the closure of the Barnwell Disposal Site to out-of-compact waste in 2008, 85% of the industry has, in fact, been faced with the loss of a disposal pathway for their Class B and C LLW, resulting in the reality of on-sit...

2011-09-14T23:59:59.000Z

86

An Underwater Robotic Network for Monitoring Nuclear Waste Storage Pools  

E-Print Network (OSTI)

An Underwater Robotic Network for Monitoring Nuclear Waste Storage Pools Sarfraz Nawaz1 , Muzammil must be stored for around 60 years in underwater storage pools before permanent disposal. These underwater storage environments must be carefully monitored and controlled to avoid an environmental

Jeavons, Peter

87

Interim Storage of Low and Intermediate Level Wastes: Guidelines for Extended Storage  

Science Conference Proceedings (OSTI)

Domestic utilities are responding to impending changes in low-level waste (LLW) disposal site facility availability by extending their capabilities for interim on-site storage of LLW. International utilities likewise face challenges in implementing complete low and intermediate waste disposal options. Therefore, our members asked EPRI to revise and update our series of documents devoted to on-site interim LLW storage. This report represents the key guidelines document for the series.

2002-10-30T23:59:59.000Z

88

Hanford land disposal restrictions plan for mixed wastes  

Science Conference Proceedings (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

89

Interim Storage of Greater Than Class C Low Level Waste  

Science Conference Proceedings (OSTI)

This report serves as a guideline for the safe, interim, on-site storage of low level radioactive waste (LLW) that exceeds the activity limitations for near-surface disposal set forth in 10 CFR 61.55. This waste, referred to as greater than Class C (GTCC) waste, exceeds the Class C limits in the referenced regulation. At the present time, there is no licensed disposal facility for GTCC waste in the United States. This situation forces commercial nuclear reactors to store it on site until a disposal facil...

2001-11-12T23:59:59.000Z

90

Waste Disposal Site and Radioactive Waste Management (Iowa)  

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

91

Treatability study of aqueous, land disposal restricted mixed wastes  

SciTech Connect

Treatment studies have been completed on two aqueous waste streams at the Mixed Waste Storage Facility that are classified as land disposal restricted. Both wastes had mercury and lead as characteristic hazardous constituents. Samples from one of these wastes, composed of mercury and lead sulfide particles along with dissolved mercury and lead, was successfully treated by decanting, filtering, and ion exchanging. The effluent water had an average level of 0.003 and 0.025 mg/L of mercury and lead, respectively. These values are well below the targeted RCRA limits of 0.2 mg/L mercury and 5.0 mg/L lead. An acidic stream, containing the same hazardous metals, was also successfully treated using a treatment process of precipitation, filtering, and then ion exchange. Treatment of another waste was not completely successful, presumably because of the interference of a chelating agent.

Haefner, D.R.

1992-12-01T23:59:59.000Z

92

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

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

93

The Middle Ground for Nuclear Waste Management: Social and Ethical Aspects of Shallow Storage  

Science Conference Proceedings (OSTI)

The 2001 terrorist attacks in the USA and the 2011 seismic events in Japan have brought into sharp relief the vulnerabilities involved in storing nuclear waste on the land's surface. Nuclear engineers and waste managers are deciding that disposing nuclear ... Keywords: Ethics, Inter-Generational Equity, Nuclear Waste, Shallow Storage, Waste Disposal

Alan Marshall

2011-04-01T23:59:59.000Z

94

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

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

95

The Determinants of Hazardous Waste Disposal Choice:  

E-Print Network (OSTI)

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

Anna Alberini; John Bartholomew; Anna Alberini; John Bartholomew

1998-01-01T23:59:59.000Z

96

Microsoft Word - SRSSaltWasteDisposal.doc  

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

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

97

Low level tank waste disposal study  

SciTech Connect

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

Mullally, J.A.

1994-09-29T23:59:59.000Z

98

Low-Level Waste Disposal Facility Federal Review Group Manual  

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

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

99

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS  

SciTech Connect

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

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

2007-06-21T23:59:59.000Z

100

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

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

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

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

Materials for Nuclear Waste Disposal and Environmental Cleanup  

Science Conference Proceedings (OSTI)

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

102

Waste canister for storage of nuclear wastes  

DOE Patents (OSTI)

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

Duffy, James B. (Fullerton, CA)

1977-01-01T23:59:59.000Z

103

Waste Containers for Extended Storage of Class A, B and C Wastes, Rev. 1  

Science Conference Proceedings (OSTI)

In response to the potential loss of low-level waste (LLW) disposal capacity for Class B and C Wastes in 2008, EPRI is updating its guidance documents on the interim storage of LLW wastes. This volume provides a comprehensive review of LLW containers and container technologies to help utilities evaluate their options and make selections for extended on-site storage. This revision updates the listings of commercially available containers, adds international containers, and provides minor technical changes...

2003-08-26T23:59:59.000Z

104

Defense High Level Waste Disposal Container System Description Document  

Science Conference Proceedings (OSTI)

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

N. E. Pettit

2001-07-13T23:59:59.000Z

105

Disposal of Rocky Flats residues as waste  

SciTech Connect

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

106

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

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

107

Innovative Technique Accelerates Waste Disposal at Idaho Site | Department  

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

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

108

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

Hightower, J.R.; Trabalka, J.R.

2000-02-01T23:59:59.000Z

109

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

E-Print Network (OSTI)

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

Machel, Hans

110

International low level waste disposal practices and facilities  

SciTech Connect

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of options for the management of radioactive waste. There is a variety of alternatives for processing waste and for short term or long term storage prior to disposal. Likewise, there are various alternatives currently in use across the globe for the safe disposal of waste, ranging from near surface to geological disposal, depending on the specific classification of the waste. At present, there appears to be a clear and unequivocal understanding that each country is ethically and legally responsible for its own wastes, in accordance with the provisions of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Therefore the default position is that all nuclear wastes will be disposed of in each of the 40 or so countries concerned with nuclear power generation or part of the fuel cycle. To illustrate the global distribution of radioactive waste now and in the near future, Table 1 provides the regional breakdown, based on the UN classification of the world in regions illustrated in Figure 1, of nuclear power reactors in operation and under construction worldwide. In summary, 31 countries operate 433 plants, with a total capacity of more than 365 gigawatts of electrical energy (GW[e]). A further 65 units, totaling nearly 63 GW(e), are under construction across 15 of these nations. In addition, 65 countries are expressing new interest in, considering, or actively planning for nuclear power to help address growing energy demands to fuel economic growth and development, climate change concerns, and volatile fossil fuel prices. Of these 65 new countries, 21 are in Asia and the Pacific region, 21 are from the Africa region, 12 are in Europe (mostly Eastern Europe), and 11 in Central and South America. However, 31 of these 65 are not currently planning to build reactors, and 17 of those 31 have grids of less than 5 GW, which is said to be too small to accommodate most of the reactor designs available. For the remaining 34 countries actively planning reactors, as of September 2010: 14 indicate a strong intention to precede w

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19T23:59:59.000Z

111

REACTOR FUEL WASTE DISPOSAL PROJECT DEVELOPMENT OF DESIGN PRINCIPLE FOR DISPOSAL OF REACTOR FUEL WASTE INTO UNDERGROUND SALT CAVITIES  

SciTech Connect

Waste disposal in underground salt cavities is considered. Theoretical Investigations for spherical and cylindrical cavities included analysis of elastic stress, thermal stress, and stress redistribution due to the development of a plastic zone around the cavity. The problems of temperature distribution and accompanying thermal stress, due to heat emission from the waste, were also studied. The reduction of the cavity volume, the development of the plastic zone, and the resulting stress redistribution around the cavity are presented as functions of cavity depth, internal pressure of cavity, strenzth of salt, and cavity teraperature rise. It is shown that a salt cavity can be designed such that it is structurally stable as a storage container assuming a chemical equilibrium can be established between the liquid waste and salt. (W.D.M.)

Serata, S.; Gloyna, E.F.

1959-01-01T23:59:59.000Z

112

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

SciTech Connect

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

McLaughlin, T.J.

1998-01-06T23:59:59.000Z

113

COMPARATIVE COSTS OF SEA DISPOSAL AND LAND BURIAL FOR THE RADIOACTIVE WASTES OF THE LAWRENCE RADIATION LABORATORY  

SciTech Connect

A study has been made of comparative costs of disposal of radioactive wastes at sea and by burial, taking into account such factors as loading, storage, and transportation by various means. (auth)

Nielsen, E.

1959-01-21T23:59:59.000Z

114

Modelling the upgrade of an urban waste disposal system  

Science Conference Proceedings (OSTI)

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

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

2009-11-01T23:59:59.000Z

115

THE DISPOSAL OF POWER REACTOR WASTE INTO DEEP WELLS  

SciTech Connect

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

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

1957-06-13T23:59:59.000Z

116

Drilling Waste Management Fact Sheet: Offsite Disposal at Commercial  

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

Commercial Disposal Facilities Commercial Disposal Facilities Fact Sheet - Commercial Disposal Facilities Although drilling wastes from many onshore wells are managed at the well site, some wastes cannot be managed onsite. Likewise, some types of offshore drilling wastes cannot be discharged, so they are either injected underground at the platform (not yet common in the United States) or are hauled back to shore for disposal. According to an American Petroleum Institute waste survey, the exploration and production segment of the U.S. oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes in 1985. The report estimates that 28% of drilling wastes are sent to offsite commercial facilities for disposal (Wakim 1987). A similar American Petroleum Institute study conducted ten years later found that the volume of drilling waste had declined substantially to about 150 million bbl.

117

Solid Waste Disposal Facilities (Massachusetts) | Department of Energy  

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

Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) Solid Waste Disposal Facilities (Massachusetts) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Transportation Tribal Government Utility Program Info State Massachusetts Program Type Siting and Permitting Provider Department of Environmental Protection These sections articulate rules for the maintenance and operation of solid waste disposal facilities, as well as site assignment procedures. Applications for site assignment will be reviewed by the Massachusetts Department of Environmental Protection as well as the Department of Public

118

IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS,...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home IDAHO OPERATIONS OFFICE MIXEDLOW-LEVEL WASTE DISPOSAL PLANS, IG-0527 IDAHO OPERATIONS OFFICE...

119

Los Alamos Lab Completes Excavation of Waste Disposal Site Used...  

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

Excavation of Waste Disposal Site Used in the 1940s More Documents & Publications Manhattan Project Truck Unearthed in Recovery Act Cleanup Protecting Recovery Act Cleanup...

120

Household waste disposal in Mekelle city, Northern Ethiopia  

SciTech Connect

In many cities of developing countries, such as Mekelle (Ethiopia), waste management is poor and solid wastes are dumped along roadsides and into open areas, endangering health and attracting vermin. The effects of demographic factors, economic and social status, waste and environmental attributes on household solid waste disposal are investigated using data from household survey. Household level data are then analyzed using multinomial logit estimation to determine the factors that affect household waste disposal decision making. Results show that demographic features such as age, education and household size have an insignificant impact over the choice of alternative waste disposal means, whereas the supply of waste facilities significantly affects waste disposal choice. Inadequate supply of waste containers and longer distance to these containers increase the probability of waste dumping in open areas and roadsides relative to the use of communal containers. Higher household income decreases the probability of using open areas and roadsides as waste destinations relative to communal containers. Measures to make the process of waste disposal less costly and ensuring well functioning institutional waste management would improve proper waste disposal.

Tadesse, Tewodros [Agricultural Economics and Rural Policy Group, Wageningen University, Hollandseweg 1 6706 KN Wageningen (Netherlands)], E-mail: tewodroslog@yahoo.com; Ruijs, Arjan [Environmental Economics and Natural Resources Group, Wageningen University, P.O. Box 8130, 6700 EW Wageningen (Netherlands); Hagos, Fitsum [International Water Management Institute (IWMI), Subregional Office for the Nile Basin and East Africa, P.O. Box 5689, Addis Ababa (Ethiopia)

2008-07-01T23:59:59.000Z

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

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

SciTech Connect

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

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

122

Defense High Level Waste Disposal Container System Description  

Science Conference Proceedings (OSTI)

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

NONE

2000-10-12T23:59:59.000Z

123

Impacts of Secondary Waste on Near-Surface Disposal Facility ...  

Impacts of Secondary Waste on Near-Surface Disposal Facility at Hanford ... DOE low-level and mixed low-level waste. 1E-06 1E-05 1E-04 1E-03 1E-02 ...

124

Minor actinide waste disposal in deep geological boreholes  

E-Print Network (OSTI)

The purpose of this investigation was to evaluate a waste canister design suitable for the disposal of vitrified minor actinide waste in deep geological boreholes using conventional oil/gas/geothermal drilling technology. ...

Sizer, Calvin Gregory

2006-01-01T23:59:59.000Z

125

THE ECONOMICS AND HAZARD POTENTIAL OF WASTE DISPOSAL  

SciTech Connect

The two most important considerations in the disposal of radioactive wastes are safety and economy. All other steps in the waste disposal complex must be tuned to accomplish these two goals. In general, the hazardous waste in the nuclear power complex affect the cost of the nuclear power reactor fuel cycle, the general environment since disposal must exclude radioactivity from the environment for over 500 years, the costs and/or methods of waste treatment including fission product utilization, the methods of shipping, the location of chemical processing plants and waste disposal sites, the methods of disposal best suited for a particular type of waste or site location, and potential public damage and third-party liability.

Arnold, E.D.

1957-07-01T23:59:59.000Z

126

Scenarios of the TWRS low-level waste disposal program  

Science Conference Proceedings (OSTI)

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

NONE

1994-10-01T23:59:59.000Z

127

Environmental Degradation of Nuclear Waste Storage Canister ...  

Science Conference Proceedings (OSTI)

Abstract Scope, The interaction between mild steel nuclear waste storage containers ... Durable and Highly Efficient Energy-harvesting Electrochromic Window ...

128

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

SciTech Connect

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

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

1986-06-01T23:59:59.000Z

129

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

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

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,

130

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

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

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

131

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

2008-03-01T23:59:59.000Z

132

Resource Conservation and Recovery Act (RCRA) General Contingency Plan for Hazardous Waste Treatment, Storage, and Disposal Units at the Oak Ridge Y-12 Plant  

SciTech Connect

This contingency plan provides a description of the Y-12 plant and its waste units and prescribes control procedures and emergency response procedures. It lists emergency and spill response equipment, provides information on coordination agreements with local agencies, and describes the evacuation plan and reporting requirements.

1999-04-01T23:59:59.000Z

133

Low-Level Waste Disposal Alternatives Analysis Report  

SciTech Connect

This report identifies and compares on-site and off-site disposal options for the disposal of contract-handled and remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Potential disposal options are screened for viability by waste type resulting in a short list of options for further consideration. The most crediable option are selected after systematic consideration of cost, schedule constraints, and risk. In order to holistically address the approach for low-level waste disposal, options are compiled into comprehensive disposal schemes, that is, alternative scenarios. Each alternative scenario addresses the disposal path for all low-level waste types over the period of interest. The alternative scenarios are compared and ranked using cost, risk and complexity to arrive at the recommended approach. Schedule alignment with disposal needs is addressed to ensure that all waste types are managed appropriately. The recommended alternative scenario for the disposal of low-level waste based on this analysis is to build a disposal facility at the Idaho National Laboratory Site.

Timothy Carlson; Kay Adler-Flitton; Roy Grant; Joan Connolly; Peggy Hinman; Charles Marcinkiewicz

2006-09-01T23:59:59.000Z

134

1999 Report on Hanford Site land disposal restriction for mixed waste  

SciTech Connect

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-011. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility.

BLACK, D.G.

1999-03-25T23:59:59.000Z

135

1996 Hanford site report on land disposal restrictions for mixed waste  

Science Conference Proceedings (OSTI)

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order milestone M-26-OIF. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal-restricted mixed waste management at the Hanford Site.

Black, D.G.

1996-04-01T23:59:59.000Z

136

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

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

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

137

1998 report on Hanford Site land disposal restrictions for mixed waste  

SciTech Connect

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities stored, generation rates, location and method of storage, an assessment of storage-unit compliance status, storage capacity, and the bases and assumptions used in making the estimates.

Black, D.G.

1998-04-10T23:59:59.000Z

138

Low and medium level radioactive waste disposal in France  

Science Conference Proceedings (OSTI)

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

Potier, J.M.

1994-12-31T23:59:59.000Z

139

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage...  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help...

140

Options and cost for disposal of NORM waste.  

Science Conference Proceedings (OSTI)

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

Veil, J. A.

1998-10-22T23:59:59.000Z

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

B Plant complex treatment, storage, and disposal units inspection plan  

Science Conference Proceedings (OSTI)

Owners or operators of facilities that treat, store, and/or dispose of dangerous waste and/or mixed waste as defined by WAC 173-303, {open_quotes}Dangerous Waste Regulations,{close_quotes} must inspect their facilities to prevent malfunctions and deteriorations, operator errors, and discharges that may cause or lead to the release of hazardous waste constituents to the environment and/or cause a threat to human health. The WAC regulations require a written inspection schedule be developed, implemented, and kept at the facility.

Beam, T.G.

1994-10-01T23:59:59.000Z

142

LANL completes excavation of 1940s waste disposal site  

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

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

143

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

Science Conference Proceedings (OSTI)

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

Potter, R.D.

1998-01-08T23:59:59.000Z

144

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

SciTech Connect

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

1961-10-31T23:59:59.000Z

145

GRR/Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and  

Open Energy Info (EERE)

8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and 8-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-HI-b - RCRA - Hazardous Waste Treatment, Storage, and Disposal Permit (TSD) 18HIB - RCRAHazardousWasteTreatmentStorageAndDisposalPermitTSD.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Health Solid and Hazardous Waste Branch United States Environmental Protection Agency Regulations & Policies Resource Conversation and Recovery Act (42 U.S.C. 6901, et seq.) 40 CFR 270 Hawaii Administrative Rules Title 11, Chapter 261 Hawaii Administrative Rules Title 11, Chapter 265 Triggers None specified Click "Edit With Form" above to add content

146

Immobilized low-level waste disposal options configuration study  

Science Conference Proceedings (OSTI)

This report compiles information that supports the eventual conceptual and definitive design of a disposal facility for immobilized low-level waste. The report includes the results of a joint Westinghouse/Fluor Daniel Inc. evaluation of trade-offs for glass manufacturing and product (waste form) disposal. Though recommendations for the preferred manufacturing and disposal option for low-level waste are outside the scope of this document, relative ranking as applied to facility complexity, safety, remote operation concepts and ease of retrieval are addressed.

Mitchell, D.E.

1995-02-01T23:59:59.000Z

147

Interface control document between PUREX Plant Transition and Solid Waste Disposal Division  

SciTech Connect

The interfacing responsibilities regarding solid waste management are described for the Solid Waste Disposal Division and the PUREX Transition Organization.

Carlson, A.B.

1995-09-01T23:59:59.000Z

148

RADIOACTIVE WASTE DISPOSAL AT KNOLLS ATOMIC POWER LABORATORY  

SciTech Connect

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

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

1958-03-01T23:59:59.000Z

149

Low-Level Waste Disposal Facility Federal Review Group Manual  

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

LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP MANUAL REVISION 3 JUNE 2008 (This page intentionally left blank) Low-Level JVllsfe Disposal Fllcili~l' Federal Review Group il1allUlli Revision 3, June 200S Concurrence The Low-Level Waste Disposal Facility Federal Review Group Manual, Revision 3, is approved for use as of the most recent date below. Date Chair, Low-Level Waste Disposal Federal Review Group Andrew WalJo, 1II Deputy Director, Otlice of Nuclear Safety, Quality Assurance, and Environment Department of Energy OHlce of Health, Safety, and Security e C. WilJiams Associate Administrator for Infrastructure and Environment National Nuclear Security Administration Low-Level 'Vaste Disposal Facility Federal Review Group J1aJll/ai

150

Modeling Coupled Processes in Clay Formations for Radioactive Waste Disposal  

Science Conference Proceedings (OSTI)

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

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

2010-08-31T23:59:59.000Z

151

Guide for Operating an Interim On-Site Low Level Radioactive Waste Storage Facility  

Science Conference Proceedings (OSTI)

As a result of increasing low-level waste (LLW) disposal site uncertainty, the industry expects that utilities will have to rely on their own on-site storage LLW storage programs in the near future. This report captures essential information related to the operation of an on-site LLW storage program. The report is a comprehensive reference to which utilities can routinely refer throughout the development and implementation of the storage program and operation of the storage facility.

2004-11-16T23:59:59.000Z

152

Depleted Uranium Dioxide as SNF Waste Package Fill: A Disposal...  

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

DEPLETED URANIUM DIOXIDE AS SNF WASTE PACKAGE FILL: A DISPOSAL OPTION Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6179 Tel: (865)...

153

Proof of Proper Solid Waste Disposal (West Virginia)  

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

154

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

155

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

Science Conference Proceedings (OSTI)

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

Elcock, D.

1998-03-10T23:59:59.000Z

156

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

Science Conference Proceedings (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

157

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

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

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

2011-01-01T23:59:59.000Z

158

NDAA Section 3116 Waste Determinations with Related Disposal Performance  

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

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

159

Permitting plan for the high-level waste interim storage  

SciTech Connect

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

Deffenbaugh, M.L.

1997-04-23T23:59:59.000Z

160

Simulation of waste processing, transportation, and disposal operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years. 1

Janis Trone

2000-01-01T23:59:59.000Z

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

Simulation Of Waste Processing, Transportation, And Disposal Operations  

E-Print Network (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, in conjunction with Simulation Dynamics, has developed a Supply Chain model of the cradle to grave management of radioactive waste. Sandia has used this model to assist the Department of Energy in developing a cost effective, regulatory compliant and efficient approach to dispose of waste from 25 sites across the country over the next 35 years.

J. A. Joines; R. R. Barton; K. Kang; P. A. Fishwick; Janis Trone; Angela Guerin

2000-01-01T23:59:59.000Z

162

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

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

163

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

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

164

Mixed waste characterization, treatment, and disposal focus area. Technology summary  

Science Conference Proceedings (OSTI)

This paper presents details about the technology development programs of the Department of Energy. In this document, waste characterization, thermal treatment processes, non-thermal treatment processes, effluent monitors and controls, development of on-site innovative technologies, and DOE business opportunities are applied to environmental restoration. The focus areas for research are: contaminant plume containment and remediation; mixed waste characterization, treatment, and disposal; high-level waste tank remediation; landfill stabilization; and decontamination and decommissioning.

NONE

1995-06-01T23:59:59.000Z

165

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

SciTech Connect

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; large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

166

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

Science Conference Proceedings (OSTI)

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

167

1997 Hanford site report on land disposal restrictions for mixed waste  

Science Conference Proceedings (OSTI)

The baseline land disposal restrictions (LDR) plan was prepared in 1990 in accordance with the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tn-Party Agreement) Milestone M-26-00 (Ecology et al, 1989). The text of this milestone is below. ''LDR requirements include limitations on storage of specified hazardous wastes (including mixed wastes). In accordance with approved plans and schedules, the U.S. Department of Energy (DOE) shall develop and implement technologies necessary to achieve full compliance with LDR requirements for mixed wastes at the Hanford Site. LDR plans and schedules shall be developed with consideration of other action plan milestones and will not become effective until approved by the U.S. Environmental Protection Agency (EPA) (or Washington State Department of Ecology [Ecology]) upon authorization to administer LDRs pursuant to Section 3006 of the Resource Conservation and Recovery Act of 1976 (RCRA). Disposal of LDR wastes at any time is prohibited except in accordance with applicable LDR requirements for nonradioactive wastes at all times. The plan will include, but not be limited to, the following: Waste characterization plan; Storage report; Treatment report; Treatment plan; Waste minimization plan; A schedule depicting the events necessary to achieve full compliance with LDR requirements; and A process for establishing interim milestones.

Black, D.G.

1997-04-07T23:59:59.000Z

168

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental...  

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

46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site,...

169

Disposal criticality analysis methodology for fissile waste forms  

SciTech Connect

A general methodology has been developed to evaluate the criticality potential of the wide range of waste forms planned for geologic disposal. The range of waste forms include commercial spent fuel, high level waste, DOE spent fuel (including highly enriched), MOX using weapons grade plutonium, and immobilized plutonium. The disposal of these waste forms will be in a container with sufficiently thick corrosion resistant barriers to prevent water penetration for up to 10,000 years. The criticality control for DOE spent fuel is primarily provided by neutron absorber material incorporated into the basket holding the individual assemblies. For the immobilized plutonium, the neutron absorber material is incorporated into the waste form itself. The disposal criticality analysis methodology includes the analysis of geochemical and physical processes that can breach the waste package and affect the waste forms within. The basic purpose of the methodology is to guide the criticality control features of the waste package design, and to demonstrate that the final design meets the criticality control licensing requirements. The methodology can also be extended to the analysis of criticality consequences (primarily increased radionuclide inventory), which will support the total performance assessment for the respository.

Davis, J.W. [Framatome Cogema Fuels, Las Vegas, NV (United States); Gottlieb, P. [TRW Environmental Safety Systems, Las Vegas, NV (United States)

1998-03-01T23:59:59.000Z

170

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

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

171

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk  

Science Conference Proceedings (OSTI)

Volume three contains appendices for the following: Public comments do DOE`s proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates.

NONE

1995-08-01T23:59:59.000Z

172

Update on cavern disposal of NORM-contaminated oil field wastes.  

Science Conference Proceedings (OSTI)

Some types of oil and gas production and processing wastes contain naturally occurring radioactive material (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. Argonne National Laboratory has previously evaluated the feasibility, legality, risk and economics of disposing of nonhazardous oil field wastes, other than NORM waste, in salt caverns. Cavern disposal of nonhazardous oil field waste, other than NORM waste, is occurring at four Texas facilities, in several Canadian facilities, and reportedly in Europe. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns as well. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, a review of federal regulations and regulations from several states indicated that there are no outright prohibitions against NORM disposal in salt caverns or other Class II wells, except for Louisiana which prohibits disposal of radioactive wastes or other radioactive materials in salt domes. Currently, however, only Texas and New Mexico are working on disposal cavern regulations, and no states have issued permits to allow cavern disposal of NORM waste. On the basis of the costs currently charged for cavern disposal of nonhazardous oil field waste (NOW), NORM waste disposal in caverns is likely to be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

Veil, J. A.

1998-09-22T23:59:59.000Z

173

PUREX storage tunnels waste analysis plan  

SciTech Connect

Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX Plant, as well as waste received from other on-site sources.

Haas, C.R., Westinghouse Hanford

1996-07-10T23:59:59.000Z

174

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

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

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 . . . . . . . . . . . . . . . . . . . . . . . . .

175

National waste terminal storage program  

SciTech Connect

An overview is provided of the national geologic disposal program. The portions of the program concerning South Dakota are discussed in detail. (LK)

Zerby, C.D.

1976-10-07T23:59:59.000Z

176

Hanford facility dangerous waste permit application, PUREX storage tunnels  

SciTech Connect

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997.

Price, S.M.

1997-09-08T23:59:59.000Z

177

Interim Storage of Greater than Class C Low Level Waste, Rev. 1  

Science Conference Proceedings (OSTI)

This report serves as a guideline for the safe, interim on-site storage of low-level radioactive waste (LLW) that exceeds the activity limitations for near-surface disposal set forth in 10 CFR 61.55. The nuclear industry refers to this waste as "greater than Class C (GTTC) waste" as it exceeds the Class C limits in the referenced regulation. At the present time, there is no licensed disposal facility for GTCC waste in the United States . This situation forces commercial nuclear reactors to store it on si...

2003-07-23T23:59:59.000Z

178

Anaerobic digestion as a waste disposal option for American Samoa  

DOE Green Energy (OSTI)

Tuna sludge and municipal solid waste (MSW) generated on Tutuila Island, American Samoa, represent an ongoing disposal problem as well as an emerging opportunity for use in renewable fuel production. This research project focuses on the biological conversion of the organic fraction of these wastes to useful products including methane and fertilizer-grade residue through anaerobic high solids digestion. In this preliminary study, the anaerobic bioconversion of tuna sludge with MSW appears promising.

Rivard, C

1993-01-01T23:59:59.000Z

179

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect

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

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

2002-02-25T23:59:59.000Z

180

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect

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

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

2002-01-01T23:59:59.000Z

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

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

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

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

182

Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control  

SciTech Connect

The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for defining when {sup 233}U-containing materials can be managed as waste and when they must be managed as concentrated fissile materials has been developed. The requirements for storage, transport, and disposal of radioactive wastes are significantly different than those for fissile materials. Because of these differences, it is important to classify material in its appropriate category. The establishment of a definition of what is waste and what is fissile material will provide the guidance for appropriate management of these materials. Wastes are defined in this report as materials containing sufficiently small masses or low concentrations of fissile materials such that they can be managed as typical radioactive waste. Concentrated fissile materials are defined herein as materials containing sufficient fissile content such as to warrant special handling to address nuclear criticality, safeguards, and arms control concerns.

Forsberg, C.W.; Storch, S.N. [Oak Ridge National Lab., TN (United States); Lewis, L.C. [Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-07-07T23:59:59.000Z

183

An Overview of Waste Classification for Disposal Summary  

E-Print Network (OSTI)

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

Anthony Andrews

2006-01-01T23:59:59.000Z

184

Crystalline ceramics: Waste forms for the disposal of weapons plutonium  

Science Conference Proceedings (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

185

Ultimate Disposal of Wastes by Pyrolysis and Incineration  

E-Print Network (OSTI)

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

Columbia University

186

DISPOSAL OF LOW-LEVEL AND LOW-LEVEL MIXED WASTES, IG-0426  

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

The Department of Energy (Department) is faced with the legacy of thousands of contaminated areas and buildings and large volumes of "backlog" waste requiring disposal. Waste management and...

187

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

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

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

188

Disposal of EOR and waste fluids. Final report  

SciTech Connect

When enhanced oil recovery (EOR) chemicals and/or waste fluids are injected into deep wells for recovery of oil or for disposal, they may pose environmental problems. This report, based only on a study of the literature, discusses injection waters, water compatibilities, and formation rocks with emphasis on clay minerals, corrosion, bacterial problems, EOR operations, waste fluid injection operations, injection well design, radioactive wastes, transport and fate processes, and mathematical models. Environmental problems can result from petroleum production operations such as: (1) primary recovery, (2) secondary recovery, (3) tertiary and/or EOR, and (4) waste disposal. Present environmental laws and probable future amendments are such that the petroleum production industry and government should implement research in specific areas. For example, characterization of a waste disposal site with respect to a contaminant such as an EOR chemical involves not only characterization of the site (injection well and reservoir), but also the contaminant (the EOR chemical). The major environmental impacts associated with EOR are: (1) possible contamination of surface and ground water, (2) possible contamination of agricultural land, (3) use of potable water in EOR operations, and (4) possible contamination of air quality (primarily related to steamflooding). This report addresses items 1 and 2 above. 12 refs., 1 fig.

Collins, A.G.; Madden, M.P.

1986-06-01T23:59:59.000Z

189

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis  

Science Conference Proceedings (OSTI)

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-10-01T23:59:59.000Z

190

Low-level radioactive waste disposal facility closure  

Science Conference Proceedings (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

191

Oil-tanker waste-disposal practices: A review  

SciTech Connect

In the spring of 1991, the Environmental Protection Agency, Region 10 (EPA), launched an investigation into tanker waste disposal practices for vessels discharging ballast water at the Alyeska Pipeline Services Company's Ballast Water Treatment (BWT) facility and marine terminal in Valdez, Alaska. It had been alleged that the Exxon Shipping Company was transferring 'toxic wastes originating in California' to Valdez. In response, EPA decided to examine all waste streams generated on board and determine what the fate of these wastes were in addition to investigating the Exxon specific charges. An extensive Information Request was generated and sent to the shipping companies that operate vessels transporting Alaska North Slope Crude. Findings included information on cargo and fuel tank washings, cleaning agents, and engine room waste.

1992-01-01T23:59:59.000Z

192

Advanced Volume Reduction and Waste Segregation Strategies for Low-Level Waste Disposal  

Science Conference Proceedings (OSTI)

EPRI has initiated a series of studies to mitigate the impact of limited disposal site access on continued operations. This report investigates two Class BC low level radioactive waste minimization techniques. The first is an advanced volume reduction (VR) technique for non-metal filter waste, while the second is a compilation of advanced waste segregation strategies aimed at minimizing the generation of BC wastes.

2003-11-07T23:59:59.000Z

193

Decision analysis for INEL hazardous waste storage  

Science Conference Proceedings (OSTI)

In mid-November 1993, the Idaho National Engineering Laboratory (INEL) Waste Reduction Operations Complex (WROC) Manager requested that the INEL Hazardous Waste Type Manager perform a decision analysis to determine whether or not a new Hazardous Waste Storage Facility (HWSF) was needed to store INEL hazardous waste (HW). In response to this request, a team was formed to perform a decision analysis for recommending the best configuration for storage of INEL HW. Personnel who participated in the decision analysis are listed in Appendix B. The results of the analysis indicate that the existing HWSF is not the best configuration for storage of INEL HW. The analysis detailed in Appendix C concludes that the best HW storage configuration would be to modify and use a portion of the Waste Experimental Reduction Facility (WERF) Waste Storage Building (WWSB), PBF-623 (Alternative 3). This facility was constructed in 1991 to serve as a waste staging facility for WERF incineration. The modifications include an extension of the current Room 105 across the south end of the WWSB and installing heating, ventilation, and bay curbing, which would provide approximately 1,600 ft{sup 2} of isolated HW storage area. Negotiations with the State to discuss aisle space requirements along with modifications to WWSB operating procedures are also necessary. The process to begin utilizing the WWSB for HW storage includes planned closure of the HWSF, modification to the WWSB, and relocation of the HW inventory. The cost to modify the WWSB can be funded by a reallocation of funding currently identified to correct HWSF deficiencies.

Page, L.A.; Roach, J.A.

1994-01-01T23:59:59.000Z

194

Degradation of transuranic waste drums in underground storage  

Science Conference Proceedings (OSTI)

The Hanford site is one of several U.S. Department of Energy locations that has transuranic radioactive Waste in storage, resulting from nuclear weapons material production. Transuranic waste has extremely long-lived radionuclides requiring great care in management; such waste is slated for eventual disposal in the Waste Isolation Pilot Plant in New Mexico. Most of this waste is stored in 208-{ell} (55-gal) drums below ground. At the Hanford site 37 641 drums are stored in several trenches. The drums were stacked up to five high with plywood sheeting between the layers and on top of the stacks. Plastic tarps were used to cover the drums and the plywood, with several feet of earth backfilled on top of the plastic. A fraction of the drums ({approximately}20%) were covered only with earth, not with plywood and plastic. The drums are either painted low-carbon steel or galvanized low-carbon steel. They have been placed in storage from 1970 to 1988, resulting in between 7 and 25 yr of storage. The environment is either soil or air atmosphere. The air atmosphere environment also includes, for some drum surfaces, contact with the underside of the tarp. The temperature of the air atmosphere is relatively uniform. Year-round measurements have not been taken, but available data suggest that the temperature span should be from {approximately} 10 to 30{degrees}C (50 to 86{degrees}F). Humidity in underground storage module mock-ups has been measured at nearly 90% during testing in the summer months. Subsequent tests have shown that the humidity probably drops to 50 to 60% during other seasons. This report describes results of a project to inspect the condition of the waste drums.

Duncan, D.; DeRosa, D.C.; Demiter, J.A. [Westinghouse Hanford Company, Richland, WA (United States)

1995-12-31T23:59:59.000Z

195

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

SciTech Connect

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

Swita, W.R.

1998-01-09T23:59:59.000Z

196

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

SciTech Connect

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

Jordan, J.; Flach, G.

2012-03-29T23:59:59.000Z

197

Sources, classification, and disposal of radioactive wastes: History and legal and regulatory requirements  

Science Conference Proceedings (OSTI)

This report discusses the following topics: (1) early definitions of different types (classes) of radioactive waste developed prior to definitions in laws and regulations; (2) sources of different classes of radioactive waste; (3) current laws and regulations addressing classification of radioactive wastes; and requirements for disposal of different waste classes. Relationship between waste classification and requirements for permanent disposal is emphasized; (4) federal and state responsibilities for radioactive wastes; and (5) distinctions between radioactive wastes produced in civilian and defense sectors.

Kocher, D.C.

1991-01-01T23:59:59.000Z

198

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

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

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.

199

Combination gas producing and waste-water disposal well  

DOE Patents (OSTI)

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

Malinchak, Raymond M. (McKeesport, PA)

1984-01-01T23:59:59.000Z

200

Waste Encapsulation and Storage Facility mission analysis report  

Science Conference Proceedings (OSTI)

This report defines the mission for the Waste Encapsulation and Storage Facility (WESF). It contains summary information regarding the mission analysis which was performed by holding workshops attended by relevant persons involved in the WESF operations. The scope of the WESF mission is to provide storage of Cesium (Cs) and Strontium (Sr) capsules, previously produced at WESF, until every capsule has been removed from the facility either to another storage location, for disposal or for beneficial use by public or private enterprises. Since the disposition of the capsules has not yet been determined, they may be stored at WESF for many years, even decades. The current condition of the WESF facility must be upgraded and maintained to provide for storage which is safe, cost effective, and fully compliant with DOE direction as well as federal, state, and local laws and regulations. The Cs capsules produced at WESF were originally released to private enterprises for uses such as the sterilization of medical equipment; but because of the leakage of one capsule, all are being returned. The systems, subsystems, and equipment not required for the storage mission will be available for use by other projects or private enterprises. Beyond the storage of the Cs and Sr capsules, no future mission for the WESF has been identified.

Lund, D.P.

1995-05-24T23:59:59.000Z

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

DISPOSAL OF TRU WASTE FROM THE PLUTONIUM FINISHING PLANT IN PIPE OVERPACK CONTAINERS TO WIPP INCLUDING NEW SECURITY REQUIREMENTS  

Science Conference Proceedings (OSTI)

The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site or, a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, Hanford incinerator ash and Sand, Slag and Crucible (SS&C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

Hopkins, A.M.; Sutter, C.; Hulse, G.; Teal, J.

2003-02-27T23:59:59.000Z

202

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

SciTech Connect

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

203

Development of Improved Oil Field Waste Injection Disposal Techniques  

Science Conference Proceedings (OSTI)

The goals of this DOE sponsored project are to: (1) assemble and analyze a comprehensive database of past waste injection operations; (2) develop improved diagnostic techniques for monitoring fracture growth and formation changes; (3) develop operating guidelines to optimize daily operations and ultimate storage capacity of the target formation; and (4) to test these improved models and guidelines in the field.

Terralog Technologies USA Inc.

2001-12-17T23:59:59.000Z

204

Development of Improved Oil Field Waste Injection Disposal Techniques  

Science Conference Proceedings (OSTI)

The goals of this project have was to: (1) assemble and analyze a comprehensive database of past waste injection operations; (2) develop improved diagnostic techniques for monitoring fracture growth and formation changes; (3) develop operating guidelines to optimize daily operations and ultimate storage capacity of the target formation; and (4) to apply these improved models and guidelines in the field.

Terralog Technologies

2002-11-25T23:59:59.000Z

205

Should high-level nuclear waste be disposed of at geographically dispersed sites?  

SciTech Connect

Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear waste repository has led to an intense debate regarding the economic, social, and political impacts of the repository. Impediments to the siting process mean that the nuclear waste problem is being resolved by adhering to the status quo, in which nuclear waste is stored at scattered sites near major population centers. To assess the merits of alternative siting strategies--including both the permanent repository and the status quo- we consider the variables that would be included in a model designed to select (1) the optimal number of disposal facilities, (2) the types of facilities (e.g., permanent repository or monitored retrievable facility), and (3) the geographic location of storage sites. The objective function in the model is an all-inclusive measure of social cost. The intent of the exercise is not to demonstrate the superiority of any single disposal strategy; uncertainties preclude a conclusive proof of optimality for any of the disposal options. Instead, we want to assess the sensitivity of a variety of proposed solutions to variations in the physical, economic, political, and social variables that influence a siting strategy.

Bassett, G.W. Jr. [Chicago Univ., IL (United States). Dept. of Economics; Hemphill, R.; Kohout, E. [Argonne National Lab., IL (United States)

1992-07-01T23:59:59.000Z

206

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

207

U.S. Department of Energy Awards Contracts for Waste Storage Canisters for  

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

U.S. Department of Energy Awards Contracts for Waste Storage U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain U.S. Department of Energy Awards Contracts for Waste Storage Canisters for Yucca Mountain May 21, 2008 - 12:00pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Areva Federal Services and NAC International have been awarded contracts for the design, licensing, and demonstration of the Transportation, Aging, and Disposal (TAD) canister system. The two contracts have a total value of up to $13.8 million if all options are exercised by DOE and are each for a term of up to five years. The TAD canister will be the primary means for packaging spent nuclear fuel for transportation to and disposal in the proposed repository at Yucca Mountain, about 90 miles northwest of Las

208

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

NLE Websites -- All DOE Office Websites (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

209

1993 report on Hanford Site land disposal restrictions for mixed wastes  

SciTech Connect

Since the early 1940s, the contractors at the Hanford Site have 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 (RMW). This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976{sup 2}(RCRA) and Atomic Energy Act{sup 3}. This report covers mixed waste only. Hazardous waste that is not contaminated with radionuclides is not addressed in this report. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order{sup 1} (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for RMW. This report is the third update of the plan first issued in 1990. The Tri-Party Agreement requires, and the baseline plan and annual update reports provide, the information that follows: Waste characterization information; storage data; treatment information; waste reduction information; schedule; and progress.

Black, D.

1993-04-01T23:59:59.000Z

210

Extended storage of low-level radioactive waste: potential problem areas  

DOE Green Energy (OSTI)

If a state or state compact does not have adequate disposal capacity for low-level radioactive waste (LLRW) by 1986 as required by the Low-Level Waste Policy Act, then extended storage of certain LLRW may be necessary. The issue of extended storage of LLRW is addressed in order to determine for the Nuclear Regulatory Commission the areas of concern and the actions recommended to resolve these concerns. The focus is on the properties and behavior of the waste form and waste container. Storage alternatives are considered in order to characterize the likely storage environments for these wastes. The areas of concern about extended storage of LLRW are grouped into two categories: 1. Behavior of the waste form and/or container during storage, e.g., radiolytic gas generation, radiation-enhanced degradation of polymeric materials, and corrosion. 2. Effects of extended storage on the properties of the waste form and/or container that are important after storage (e.g., radiation-induced oxidative embrittlement of high-density polyethylene and the weakening of steel containers resulting from corrosion by the waste). The additional information and actions required to address these concerns are discussed and, in particular, it is concluded that further information is needed on the rates of corrosion of container material by Class A wastes and on the apparent dose-rate dependence of radiolytic processes in Class B and C waste packages. Modifications to the guidance for solidified wastes and high-integrity containers in NRC's Technical Position on Waste Form are recommended. 27 references.

Siskind, B.; Dougherty, D.R.; MacKenzie, D.R.

1985-01-01T23:59:59.000Z

211

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

DOE Green Energy (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

212

Revision of the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase  

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

56 56 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices 1 In addition to more significant quantities of PCB-contaminated waste already at the Hanford site, DOE transferred a small amount of TRU waste with PCBs (4 cubic meters) from the Energy Technology Engineering Site in California to Hanford in December 2002 for characterization, repackaging, and storage pending shipment to WIPP. 67 FR 56989 (Sept. 6, 2002). At that time, DOE designated that particular waste for disposal at WIPP in accordance with the WIPP Land Withdrawal Act. DEPARTMENT OF ENERGY Revision to the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase AGENCY: Department of Energy. ACTION: Revision to record of decision. SUMMARY: The Department of Energy

213

NWTS program criteria for mined geologic disposal of nuclear waste: repository performance and development criteria. Public draft  

Science Conference Proceedings (OSTI)

This document, DOE/NWTS-33(3) is one of a series of documents to establish the National Waste Terminal Storage (NWTS) program criteria for mined geologic disposal of high-level radioactive waste. For both repository performance and repository development it delineates the criteria for design performance, radiological safety, mining safety, long-term containment and isolation, operations, and decommissioning. The US Department of Energy will use these criteria to guide the development of repositories to assist in achieving performance and will reevaluate their use when the US Nuclear Regulatory Commission issues radioactive waste repository rules.

none,

1982-07-01T23:59:59.000Z

214

SCFA lead lab technical assistance at Oak Ridge Y-12 national security complex: Evaluation of treatment and characterization alternatives of mixed waste soil and debris at disposal area remedial action DARA solids storage facility (SSF)  

E-Print Network (OSTI)

Ploymerization flyer TRU and Mixed Waste Focus Area, U.S.DC Arc Melters flyer TRU and Mixed Waste Focus Area, U.S.team. Maio, Vincent, 1998, Mixed Waste Area Approach for

Hazen, Terry

2002-01-01T23:59:59.000Z

215

Drilling Waste Management Fact Sheet: Disposal in Salt Caverns  

NLE Websites -- All DOE Office Websites (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

216

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

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

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

217

1995 Report on Hanford site land disposal restrictions for mixed waste  

Science Conference Proceedings (OSTI)

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated 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 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report.

Black, D.G.

1995-04-01T23:59:59.000Z

218

Stabilization and disposal of Argonne-West low-level mixed wastes in ceramicrete waste forms.  

SciTech Connect

The technology of room-temperature-setting phosphate ceramics or Ceramicrete{trademark} technology, developed at Argonne National Laboratory (ANL)-East is being used to treat and dispose of low-level mixed wastes through the Department of Energy complex. During the past year, Ceramicrete{trademark} technology was implemented for field application at ANL-West. Debris wastes were treated and stabilized: (a) Hg-contaminated low-level radioactive crushed light bulbs and (b) low-level radioactive Pb-lined gloves (part of the MWIR {number_sign} AW-W002 waste stream). In addition to hazardous metals, these wastes are contaminated with low-level fission products. Initially, bench-scale waste forms with simulated and actual waste streams were fabricated by acid-base reactions between mixtures of magnesium oxide powders and an acid phosphate solution, and the wastes. Size reduction of Pb-lined plastic glove waste was accomplished by cryofractionation. The Ceramicrete{trademark} process produces dense, hard ceramic waste forms. Toxicity Characteristic Leaching Procedure (TCLP) results showed excellent stabilization of both Hg and Pb in the waste forms. The principal advantage of this technology is that immobilization of contaminants is the result of both chemical stabilization and subsequent microencapsulation of the reaction products. Based on bench-scale studies, Ceramicrete{trademark} technology has been implemented in the fabrication of 5-gal waste forms at ANL-West. Approximately 35 kg of real waste has been treated. The TCLP is being conducted on the samples from the 5-gal waste forms. It is expected that because the waste forms pass the limits set by the EPAs Universal Treatment Standard, they will be sent to a radioactive-waste disposal facility.

Barber, D. B.; Singh, D.; Strain, R. V.; Tlustochowicz, M.; Wagh, A. S.

1998-02-17T23:59:59.000Z

219

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

SciTech Connect

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

220

GNEP Material Transportation, Storage and Disposal Analysis FY-08 Summary Report  

Science Conference Proceedings (OSTI)

This report provides a summary for FY-2008 of activities, analyses and products from the Material Transportation, Storage and Disposal (M-TSD) sub-task of Systems Analysis within the Advanced Fuel Cycle Research & Development area of the Global Nuclear Energy Partnership. The objective of this work is to evaluate near-term material management requirements for initial GNEP facilities and activities, long-term requirements for large-scale GNEP technology deployment, and alternatives and paths forward to meet these needs. For FY-08, the work expanded to include the Integrated Waste Management Strategy as well as integration with the newly formed Waste Forms Campaign. The M-TSD team was expanded with the addition of support from Savannah River National Lab (SRNL) to the existing team of Lawrence Livermore National Lab (LLNL), Argonne National Lab (ANL), Idaho National Lab (INL), Sandia National Lab (SNL) and University of Nevada - Reno (UN-R). During the first half of the year, analysis was focused on providing supporting technical analysis and documentation to support anticipated high-level decisions on program direction. A number of analyses were conducted and reports prepared as program deliverables. This work is briefly summarized in this report. Analyses provided informally to other program efforts are included in this report to provide documentation. This year-end summary was planned primarily as a compilation of activities following the anticipated programmatic decisions. These decisions were deferred beyond the end of the year, and funds were reallocated in a number of areas, thus reducing the M-TSD activities. This report summarizes the miscellaneous 'ad-hoc' work conducted during the later part of the year, such as support to the draft Programmatic Environmental Impact Statement (PEIS), and support to other program studies. Major programmatic contributions from the M-TSD team during the year included: (1) Completion of the IWMS in March 2008 as the baseline for waste management calculations for the GNEP Programmatic Environmental Impact Statement (PEIS). The IWMS represents a collaborative effort between the Systems Analysis, Waste Forms, and Separations Campaigns with contributing authors from multiple laboratories. The IWMS reference is: 'Global Nuclear Energy Partnership Integrated Waste Management Strategy, D. Gombert, INL, et al, GNEP-WAST-WAST-AI-RT-2008-000214, March 2008'. (2) As input to the IWMS and support for program decisions, an evaluation of the current regulatory framework in the U.S. pertaining to the disposal of radioactive wastes under an advanced nuclear fuel cycle was completed by ANL. This evaluation also investigated potential disposal pathways for these wastes. The entire evaluation is provided in Appendix A of this report. (3) Support was provided to the development of the GNEP Programmatic Environmental Impact Statement from INL, SNL and ANL M-TSD staff. (4) M-TSD staff prepared input for DSARR (Dynamic Systems Analysis Report for Nuclear Fuel Recycle) report. The DSARR is an INL led report to examine the time-dependent dynamics for a transition from the current open fuel cycle to either a 1-tier or 2-tier closed fuel cycle. Section 5.3 Waste Management Impacts was provided to INL for incorporation into the DSARR. (5) SNL M-TSD staff prepared a M2 milestone report 'Material Transportation, Storage and Disposal Contribution for Secretarial Decision Package'. The report purpose was to comprehensively evaluate and discuss packaging, storage, and transportation for all potential nuclear and radioactive materials in the process and waste streams being considered by the GNEP program. In particular, a systems view was used to capture all packaging, storage, and transport operations needed to link the various functional aspects of the fuel cycle. (6) SRNL M-TSD staff developed a deliverable report 'Management of Decay Heat from Spent Nuclear Fuel'. This report evaluated a range of options for managing the near-term decay heat associated with Cs and Sr in spent nuclear fuel (SNF) reprocessing waste

Halsey, W

2009-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage 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.


221

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology  

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

46: Radioactive Waste Storage at Rocky Flats Environmental 46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste storage facilities in order to increase storage capacity for low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 9, 1996 EA-1146: Finding of No Significant Impact Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

222

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

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

223

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

224

Basis for Section 3116 Determination for Salt Waste Disposal at the  

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

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

225

Thermodynamic data management system for nuclear waste disposal performance assessment  

Science Conference Proceedings (OSTI)

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

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

1988-04-01T23:59:59.000Z

226

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR AUGUST AND SEPTEMBER 1961  

SciTech Connect

Work is being carried out to develop and demonstrate on pilot plant scale integrated processes for treatment and disposal of radmoactive wastes. High-level waste calcination, low-level waste treatment, economic and hazards evaluation, engineering evaluation, disposal in deep wells, disposal in natural salt formations, Clinch River studies, fundamental studies of minerals, and White Oak Creek basin study are discussed. (M.C.G.)

Blanco, R.E.; Struxness, E.G.

1961-11-29T23:59:59.000Z

227

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR DECEMBER 1961 AND JANUARY 1962  

SciTech Connect

Progress in the development and demonstration on a pilot plant scale integrated processes for treatment and ultimate disposal of radioactive wastes is reported. Topics covered include: high-level waste calcination; lowlevel waste treatment; engineering, economics, and hazards evaluation; disposal ln deep wells; disposal in natural salt formations; Clinch River study; fundamental study of minerals; and White Oak Creek basin study. (M.C.G.)

Blanco, R.E.; Struxness, E.G.

1962-10-31T23:59:59.000Z

228

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

229

Radioactive waste disposal characteristics of candidate tokamak demonstration reactors  

SciTech Connect

Results from the current physics, materials and blanket R and D programs are combined with physics and engineering design constraints to characterize candidate tokamak demonstration plant (DEMO) designs. Blanket designs based on the principal structural materials, breeding materials and coolants being developed for the DEMO were adapted from the literature. Neutron flux and activation calculations were performed, and several radioactive waste disposal indices were evaluated, for each design. Of the primary low-activation structural materials under development in the US, it appears that vanadium and ferritic steel alloys, and possibly silicon carbide, could lead to DEMO designs which could satisfy realistic low-level waste (LLW) criteria, provided that impurities can be controlled within plausible limits. Allowable LLW concentrations are established for the limiting alloying and impurity elements. All breeding materials and neutron multipliers considered meet the LLW criterion.

Hoffman, E.A.; Stacey, W.M.; Hertel, N.E.

1998-08-01T23:59:59.000Z

230

Salt Waste Disposal at the Savannah River Site | Department of Energy  

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

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,

231

Method for storage of solid waste  

DOE Patents (OSTI)

Metal canisters for long-term storage of calcined highlevel radioactive wastes can be made self-sealing against a breach in the canister wall by the addition of powdered cement to the canister with the calcine before it is sealed for storage. Any breach in the canister wall will permit entry of water which will mix with the cement and harden to form a concrete patch, thus sealing the opening in the wall of the canister and preventing the release of radioactive material to the cooling water or atmosphere.

Mecham, William J. (La Grange, IL)

1976-01-01T23:59:59.000Z

232

Plutonium Finishing Plan (PFP) Treatment and Storage Unit Waste Analysis Plan  

Science Conference Proceedings (OSTI)

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

PRIGNANO, A.L.

2000-07-01T23:59:59.000Z

233

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

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

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

234

Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...  

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

2008 ETR-12 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF)...

235

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators.

D. Wieland, V. Yucel, L. Desotell, G. Shott, J. Wrapp

2008-04-01T23:59:59.000Z

236

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

237

Waste Encapsulation Storage Facility, January 2011  

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

February 11, 2011 February 11, 2011 Site Visit Report Waste Encapsulation Storage Facility, January 2011 INTRODUCTION This report documents the results of a review conducted by the Office of Health, Safety and Security (HSS) of the Waste Encapsulation Storage Facility (WESF) documented safety analysis (DSA) at the Hanford Site. During discussions with the U.S. Department of Energy Richland Operations Office (DOE- RL), the review of WESF was jointly selected by HSS and DOE-RL based on the high hazards of the facility and the need to periodically evaluate the facility and DSA by independent reviewers. SCOPE The scope of the review was to evaluate the WESF safety and support systems in detecting, preventing and mitigating analyzed events as described in the facility's DSA, PRC-EDC-10-45190, 2010, Executive

238

Existing nuclear sites can be used for new powerplants and nuclear waste storage  

SciTech Connect

Locating future nuclear powerplants at existing sites offers important advantages which warrant consideration by the Nuclear Regulatory Commission. The number of locations committed to long-term restricted use and periodic surveillance and maintenance could be limited. The burden of long-term care and final disposition of retired nuclear powerplants could be eased. Overall environmental impacts from the construction and operation of the powerplants could be reduced. Time and money in completing licensing proceedings could be saved. GAO also found that low-level wastes can be stored at nuclear powerplant sites, but such storage only postpones the inevitable need for disposal. Finally, permanent waste disposal at powerplant sites should only be permitted when sites conform to the national low-level waste disposal plan being prepared by the Department of Energy.

Staats, E.B.

1980-04-01T23:59:59.000Z

239

Evaluating off-site disposal of low-level waste at LANL-9498  

SciTech Connect

Los Alamos National Laboratory generates a wide range of waste types, including solid low-level radioactive waste (LL W), in conducting its national security mission and other science and technology activities. Although most ofLANL's LLW has been disposed on-site, limitations on expansion, stakeholder concerns, and the potential for significant volumes from environmental remediation and decontamination and demolition (D&D) have led LANL to evaluate the feasibility of increasing off-site disposal. It appears that most of the LL W generated at LANL would meet the Waste Acceptance Criteria at the Nevada Test Site or the available commercial LL W disposal site. Some waste is considered to be problematic to transport to off-site disposal even though it could meet the off-site Waste Acceptance Criteria. Cost estimates for off-site disposal are being evaluated for comparison to estimated costs under the current plans for continued on-site disposal.

Hargis, Kenneth M [Los Alamos National Laboratory; French, Sean B [Los Alamos National Laboratory; Boyance, Julien A [NORTH WIND, INC.

2009-01-01T23:59:59.000Z

240

Technical framework to facilitate foreign spent fuel storage and geologic disposal in Russia  

SciTech Connect

The option of storage and eventual geologic disposal in Russia of spent fuel of US origin used in Taiwan provides a unique opportunity that can benefit many parties. Taiwan has a near term need for a spent fuel storage and geologic disposal solution, available financial resources, but limited prospect for a timely domestic solution. Russia has significant spent fuel storage and transportation management experience, candidate storage and repository sites, but limited financial resources available for their development. The US has interest in Taiwan energy security, national security and nonproliferation interests in Russian spent fuel storage and disposal and interest in the US origin fuel. While it is understood that such a project includes complex policy and international political issues as well as technical issues, the goal of this paper is to begin the discussion by presenting a technical path forward to establish the feasibility of this concept for Russia.

Jardine, L J; Halsey, W G; Cmith, C F

2000-01-31T23:59:59.000Z

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

DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at  

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

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

242

RADIOACTIVE WASTE DISPOSAL PRACTICES IN THE ATOMIC ENERGY INDUSTRY. A Survey of the Costs  

SciTech Connect

A survey was made on methcds and related costs of disposing of radioactive wastes as practiced in 1955 by twelve atomic industry installations. Wherever possible, estimated unit costs of differentiated stages of waste handling are shown- these are integrated to show the over-all scope of waste dispesal practices at each site. Tabular data summarize costs and operation magnitades at the installations. A pattern is established for standardizing the reporting of fixed costs and equipment unsage costs. The economy of solid waste volume reduction is analyzed. Material costs are listed. An outline for recording monthly waste disposal costs is presented. Obvious conclusions drawn from the factual data are: that it is more expensive per cubic foot to handle high-level wastes than low-level wastes. and that land disposal is less expenaive than sea disposal. A reexamination of baling economics shows that high compression of solid wastes is more expensive than simpler forms of compaction. (auth)

Joseph, A.B.

1955-12-31T23:59:59.000Z

243

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

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

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

244

Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect

A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

Timothy Solack; Carol Mason

2012-03-01T23:59:59.000Z

245

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

Science Conference Proceedings (OSTI)

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

NONE

1995-01-01T23:59:59.000Z

246

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report  

SciTech Connect

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

Pickett, W.W.

1997-12-30T23:59:59.000Z

247

A STUDY OF CORROSION AND STRESS CORROSION CRACKING OF CARBON STEEL NUCLEAR WASTE STORAGE TANKS  

SciTech Connect

The Hanford reservation Tank Farms in Washington State has 177 underground storage tanks that contain approximately 50 million gallons of liquid legacy radioactive waste from cold war plutonium production. These tanks will continue to store waste until it is treated and disposed. These nuclear wastes were converted to highly alkaline pH wastes to protect the carbon steel storage tanks from corrosion. However, the carbon steel is still susceptible to localized corrosion and stress corrosion cracking. The waste chemistry varies from tank to tank, and contains various combinations of hydroxide, nitrate, nitrite, chloride, carbonate, aluminate and other species. The effect of each of these species and any synergistic effects on localized corrosion and stress corrosion cracking of carbon steel have been investigated with electrochemical polarization, slow strain rate, and crack growth rate testing. The effect of solution chemistry, pH, temperature and applied potential are all considered and their role in the corrosion behavior will be discussed.

BOOMER, K.D.

2007-08-21T23:59:59.000Z

248

DESIGN ANALYSIS FOR THE DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER  

SciTech Connect

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

G. Radulesscu; J.S. Tang

2000-06-07T23:59:59.000Z

249

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

Vejvoda, E.J.; Pottmeyer, J.A.; DeLorenzo, D.S.; Weyns-Rollosson, M.I. [Los Alamos Technical Associates, Inc., NM (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

250

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

SciTech Connect

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

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

2011-07-15T23:59:59.000Z

251

Disposal of NORM-contaminated oil field wastes in salt caverns -- Legality, technical feasibility, economics, and risk  

Science Conference Proceedings (OSTI)

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

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

1998-07-01T23:59:59.000Z

252

Disposal of NORM-Contaminated Oil Field Wastes in Salt Caverns  

Science Conference Proceedings (OSTI)

In 1995, the U.S. Department of Energy (DOE), Office of Fossil Energy, asked Argonne National Laboratory (Argonne) to conduct a preliminary technical and legal evaluation of disposing of nonhazardous oil field waste (NOW) into salt caverns. That study concluded that disposal of NOW into salt caverns is feasible and legal. If caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they can be a suitable means of disposing of NOW (Veil et al. 1996). Considering these findings and the increased U.S. interest in using salt caverns for NOW disposal, the Office of Fossil Energy asked Argonne to conduct further research on the cost of cavern disposal compared with the cost of more traditional NOW disposal methods and on preliminary identification and investigation of the risks associated with such disposal. The cost study (Veil 1997) found that disposal costs at the four permitted disposal caverns in the United States were comparable to or lower than the costs of other disposal facilities in the same geographic area. The risk study (Tomasko et al. 1997) estimated that both cancer and noncancer human health risks from drinking water that had been contaminated by releases of cavern contents were significantly lower than the accepted risk thresholds. Since 1992, DOE has funded Argonne to conduct a series of studies evaluating issues related to management and disposal of oil field wastes contaminated with naturally occurring radioactive material (NORM). Included among these studies were radiological dose assessments of several different NORM disposal options (Smith et al. 1996). In 1997, DOE asked Argonne to conduct additional analyses on waste disposal in salt caverns, except that this time the wastes to be evaluated would be those types of oil field wastes that are contaminated by NORM. This report describes these analyses. Throughout the remainder of this report, the term ''NORM waste'' is used to mean ''oil field waste contaminated by NORM''.

Blunt, D.L.; Elcock, D.; Smith, K.P.; Tomasko, D.; Viel, J.A.; and Williams, G.P.

1999-01-21T23:59:59.000Z

253

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

SciTech Connect

This report presents a history of commercial low-level radioactive waste management 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 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab.

Not Available

1990-10-01T23:59:59.000Z

254

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

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

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

255

Thermal impact of waste emplacement and surface cooling associated with geologic disposal of nuclear waste  

Science Conference Proceedings (OSTI)

The thermal effects associated with the emplacement of aged radioactive wastes in a geologic repository were studied, with emphasis on the following subjects: the waste characteristics, repository structure, and rock properties controlling the thermally induced effects; the current knowledge of the thermal, thermomechanical, and thermohydrologic impacts, determined mainly on the basis of previous studies that assume 10-year-old wastes; the thermal criteria used to determine the repository waste loading densities; and the technical advantages and disadvantages of surface cooling of the wastes prior to disposal as a means of mitigating the thermal impacts. The waste loading densities determined by repository designs for 10-year-old wastes are extended to older wastes using the near-field thermomechanical criteria based on room stability considerations. Also discussed are the effects of long surface cooling periods determined on the basis of far-field thermomechanical and thermohydrologic considerations. The extension of the surface cooling period from 10 years to longer periods can lower the near-field thermal impact but have only modest long-term effects for spent fuel. More significant long-term effects can be achieved by surface cooling of reprocessed high-level waste.

Wang, J.S.Y.; Mangold, D.C.; Spencer, R.K.; Tsang, C.F.

1982-08-01T23:59:59.000Z

256

Preliminary technical and legal evaluation of disposing of nonhazardous oil field waste into salt caverns  

Science Conference Proceedings (OSTI)

Caverns can be readily formed in salt formations through solution mining. The caverns may be formed incidentally, as a result of salt recovery, or intentionally to create an underground chamber that can be used for storing hydrocarbon products or compressed air or disposing of wastes. The purpose of this report is to evaluate the feasibility, suitability, and legality of disposing of nonhazardous oil and gas exploration, development, and production wastes (hereafter referred to as oil field wastes, unless otherwise noted) in salt caverns. Chapter 2 provides background information on: types and locations of US subsurface salt deposits; basic solution mining techniques used to create caverns; and ways in which salt caverns are used. Later chapters provide discussion of: federal and state regulatory requirements concerning disposal of oil field waste, including which wastes are considered eligible for cavern disposal; waste streams that are considered to be oil field waste; and an evaluation of technical issues concerning the suitability of using salt caverns for disposing of oil field waste. Separate chapters present: types of oil field wastes suitable for cavern disposal; cavern design and location; disposal operations; and closure and remediation. This report does not suggest specific numerical limits for such factors or variables as distance to neighboring activities, depths for casings, pressure testing, or size and shape of cavern. The intent is to raise issues and general approaches that will contribute to the growing body of information on this subject.

Veil, J.; Elcock, D.; Raivel, M.; Caudle, D.; Ayers, R.C. Jr.; Grunewald, B.

1996-06-01T23:59:59.000Z

257

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

SciTech Connect

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

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

1989-11-01T23:59:59.000Z

258

A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL  

SciTech Connect

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs.

Arrenholz, D.A.; Knight, J.L.

1991-08-01T23:59:59.000Z

259

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

Science Conference Proceedings (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

260

Radionuclide concentrations in vegetation at radioactive-waste disposal Area G during the 1994 growing season  

Science Conference Proceedings (OSTI)

Overstory (pinon pine) and understory (grass and forb) vegetation samples were collected within and around selected points at Area G-a low-level radioactive solid-waste disposal facility at Los Alamos National Laboratory-for the analysis of tritium ({sup 3}H), strontium ({sup 90}Sr), plutonium ({sup 238} Pu and {sup 239}Pu), cesium ({sup 137}Cs), americium ({sup 241}Am), and total uranium. In general, most vegetation samples collected within and around Area G contained radionuclide levels in higher concentrations than vegetation collected from background areas. Tritium, in particular, was detected as high as 5,800 pCi/mL in overstory vegetation collected outside the fence just west of the tritium shafts; this suggests that tritium is migrating from this waste repository through subsurface pathways. Also, understory vegetation collected north of the transuranic (TRU) pads (outside the fence of Area G) contained the highest values of {sup 90}Sr, {sup 238}Pu, {sup 239}Pu, {sup 137}Cs, and {sup 241}Am, and may be a result of surface holding, storage, or disposal activities.

Fresquez, P.R.; Biggs, J.B.; Bennett, K.D.

1995-07-01T23:59:59.000Z

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

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6. This Introduction to the WASTE STORAGE FACILITIES TSRs is not part of the TSR limits or conditions and contains no requirements related to WASTE STORAGE FACILITIES operations or to the safety analyses of the DSA.

Larson, H L

2007-09-07T23:59:59.000Z

262

Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste 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 2015). Development of a new onsite disposal facility, the highest ranked alternative, 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.

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

2010-10-01T23:59:59.000Z

263

Disposal of low-level and low-level mixed waste: audit report  

Science Conference Proceedings (OSTI)

The Department of Energy (Department) is faced with the legacy of thousands of contaminated areas and buildings and large volumes of `backlog` waste requiring disposal. Waste management and environmental restoration activities have become central to the Department`s mission. One of the Department`s priorities is to clean up former nuclear weapons sites and find more effective and timely methods for disposing of nuclear waste. This audit focused on determining if the Department was disposing of low-level and low-level mixed waste in the most cost-effective manner.

NONE

1998-09-03T23:59:59.000Z

264

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

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

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...

265

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

266

DC Hazardous Waste Management (District of Columbia)  

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

This regulation regulates the generation, storage, transportation, treatment, and disposal of hazardous waste, and wherever feasible, reduces or eliminates waste at the source. It is the policy of...

267

Documented Safety Analysis for the Waste Storage Facilities March 2010  

SciTech Connect

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D T

2010-03-05T23:59:59.000Z

268

Documented Safety Analysis for the Waste Storage Facilities  

Science Conference Proceedings (OSTI)

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D

2008-06-16T23:59:59.000Z

269

Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization (40 CFR {section} 761.75[c])  

Science Conference Proceedings (OSTI)

This initial report is being submitted pursuant to Title 40 Code of Federal Regulations (CFR) {section} 761.75(c) to request authorization to allow the disposal of transuranic (TRU) wastes containing polychlorinated biphenyls (PCBs) which are duly regulated under the Toxic Substances Control Act (TSCA). Approval of this initial report will not affect the disposal of TRU or TRU mixed wastes that do not contain PCBs. This initial report also demonstrates how the Waste Isolation Pilot Plant (WIPP) meets or exceeds the technical standards for a Chemical Waste Landfill. Approval of this request will allow the U.S. Department of Energy (DOE) to dispose of approximately 88,000 cubic feet (ft3) (2,500 cubic meters [m3]) of TRU wastes containing PCBs subject to regulation under the TSCA. This approval will include only those PCB/TRU wastes, which the TSCA regulations allow for disposal of the PCB component in municipal solid waste facilities or chemical waste landfills (e.g., PCB remediation waste, PC B articles, and bulk PCB product waste). Disposal of TRU waste by the DOE is congressionally mandated in Public Law 102-579 (as amended by the National Defense Authorization Act for Fiscal Year 1997, Pub. L. 104-201, referred to as the WIPP Land Withdrawal Act [LWA]). Portions of the TRU waste inventory contain hazardous waste constituents regulated under 40 CFR Parts 260 through 279, and/or PCBs and PCB Items regulated under 40 CFR Part 761. Therefore, the DOE TRU waste program must address the disposal requirements for these hazardous waste constituents and PCBs. To facilitate the disposal of TRU wastes containing hazardous waste constituents, the owner/operators received a Hazardous Waste Facility Permit (HWFP) from the New Mexico Environment Department (NMED) on October 27, 1999. The permit allows the disposal of TRU wastes subject to hazardous waste disposal requirements (TRU mixed waste). Informational copies of this permit and other referenced documents are available from the WIPP website. To facilitate the disposal of TRU wastes containing PCBs, the owner/operators are hereby submitting this initial report containing information required pursuant to the Chemical Waste Landfill Approval requirements in 40 CFR {section} 761.75(c). Although WIPP is defined as a miscellaneous unit and not a landfill by the New Mexico Hazardous Waste Act, WIPP meets or exceeds all applicable technical standards for chemical waste landfills by virtue of its design and programs as indicated in the Engineering Report (Attachment B). The layout of this initial report is consistent with requirements (i.e., Sections 2.0 through 12.0 following the sequence of 40 CFR {section} 761.75[c][i] -[ix] with sections added to discuss the Contingency and Training Plans; and Attachment B of this initial report addresses the requirements of 40 CFR {section} 761.75[b][1] through [9] in this order). This initial report includes a description of three proposed changes that will be subject to ''conditional approval.'' The first will allow the disposal of remote-handled (RH) PCB/TRU waste at WIPP. The second will allow the establishment of a central confirmation facility at WIPP. The third will allow for an increase in contact-handled Working Copy Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization DOE/WIPP 02-3196 (CH) waste storage capacities. These proposed changes are discussed further in Section 3.3 of this initial report. ''Conditional approval'' of these requests would allow these activities at WIPP contingent upon: - Approval of the HWFP modification (NMED) and Compliance Certification Application (CCA) change request (Environmental Protection Agency [EPA]) - Inspection of facility prior to implementing the change (if deemed necessary by the EPA) - Written approval from the EPA This initial report also includes the following three requests for waivers to the technical requirements for Chemical Waste Landfills pursuant to 40 CFR {section} 761.75(c)(4): - Hydrologic Conditions (40 CFR {section} 761.75[b][3]) - Monitoring Systems (40 CFR {sect

Westinghouse TRU Solutions

2002-03-19T23:59:59.000Z

270

Municipal solid waste management in India: From waste disposal to recovery of resources?  

SciTech Connect

Unlike that of western countries, the solid waste of Asian cities is often comprised of 70-80% organic matter, dirt and dust. Composting is considered to be the best option to deal with the waste generated. Composting helps reduce the waste transported to and disposed of in landfills. During the course of the research, the author learned that several developing countries established large-scale composting plants that eventually failed for various reasons. The main flaw that led to the unsuccessful establishment of the plants was the lack of application of simple scientific methods to select the material to be composted. Landfills have also been widely unsuccessful in countries like India because the landfill sites have a very limited time frame of usage. The population of the developing countries is another factor that detrimentally impacts the function of landfill sites. As the population keeps increasing, the garbage quantity also increases, which, in turn, exhausts the landfill sites. Landfills are also becoming increasingly expensive because of the rising costs of construction and operation. Incineration, which can greatly reduce the amount of incoming municipal solid waste, is the second most common method for disposal in developed countries. However, incinerator ash may contain hazardous materials including heavy metals and organic compounds such as dioxins, etc. Recycling plays a large role in solid waste management, especially in cities in developing countries. None of the three methods mentioned here are free from problems. The aim of this study is thus to compare the three methods, keeping in mind the costs that would be incurred by the respective governments, and identify the most economical and best option possible to combat the waste disposal problem.

Narayana, Tapan [Hidayatullah National Law University, HNLU Bhawan, Civil Lines, Raipur 492001, Chhattisgarh (India)], E-mail: tapan.narayana@gmail.com

2009-03-15T23:59:59.000Z

271

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network (OSTI)

The United States Department of Energy is proposing to build a nuclear waste storage facility in southern Nevada. This facility will be designed to last 10,000 years. It must prevent the waste from contaminating the ...

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

272

EA-0820: Construction of Mixed Waste Storage RCRA Facilities...  

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

waste storage facilities (Buildings 7668 and 7669) in accordance with Resource Conservation and Recovery Act requirements. Site preparation and construction activities would...

273

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations  

SciTech Connect

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

274

DOE Awards Task Order for Disposal of Los Alamos National Lab Waste |  

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

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

275

Selection of infectious medical waste disposal firms by using the analytic hierarchy process and sensitivity analysis  

SciTech Connect

While Taiwanese hospitals dispose of large amounts of medical waste to ensure sanitation and personal hygiene, doing so inefficiently creates potential environmental hazards and increases operational expenses. However, hospitals lack objective criteria to select the most appropriate waste disposal firm and evaluate its performance, instead relying on their own subjective judgment and previous experiences. Therefore, this work presents an analytic hierarchy process (AHP) method to objectively select medical waste disposal firms based on the results of interviews with experts in the field, thus reducing overhead costs and enhancing medical waste management. An appropriate weight criterion based on AHP is derived to assess the effectiveness of medical waste disposal firms. The proposed AHP-based method offers a more efficient and precise means of selecting medical waste firms than subjective assessment methods do, thus reducing the potential risks for hospitals. Analysis results indicate that the medical sector selects the most appropriate infectious medical waste disposal firm based on the following rank: matching degree, contractor's qualifications, contractor's service capability, contractor's equipment and economic factors. By providing hospitals with an effective means of evaluating medical waste disposal firms, the proposed AHP method can reduce overhead costs and enable medical waste management to understand the market demand in the health sector. Moreover, performed through use of Expert Choice software, sensitivity analysis can survey the criterion weight of the degree of influence with an alternative hierarchy.

Hsu, P.-F. [Department of Communications Management, Shih Hsin University, No.1, Lane 17, Mu-Cha Road, Sec.1, Taipei 11604, Taiwan (China)], E-mail: celina9@ms26.hinet.net; Wu, C.-R. [Graduate Institute of Business and Management, Yuanpei University, 306 Yuanpei Street, Hsin Chu 300, Taiwan (China)], E-mail: alexru00@ms41.hinet.net; Li, Y.-T. [Graduate Institute of Business and Management, Yuanpei University, 306 Yuanpei Street, Hsin Chu 300, Taiwan (China)], E-mail: ting.ding@msa.hinet.net

2008-07-01T23:59:59.000Z

276

A New Approach for the Permanent Disposal of Long Lived Fission Waste  

DOE Green Energy (OSTI)

Nuclear fission can meet humanity's disparate requirements for carbon-free energy throughout this century and for millennia to come - not only for electricity but also as a source of hydrogen for transportation fuels and a heat source for desalination. However, most countries are not pursuing fission as an option for future energy and global climate needs. One paramount reason is diminished public acceptance over concerns of waste disposal. We would also add 'fuel resources' as a major future concern, because fission is not sustainable in the long term with the present 'once-through' fuel that utilizes less than 1% of the mined uranium and consigns its fertile potential to a permanent waste repository. Accordingly, global scale fission will become attainable (i.e., doable) if and when an integrated solution to this overall 'fuel-cycle' problem is realized. It is the back-end of the fuel cycle - i.e., the need for permanent storage of spent fuel and high-level waste - that has become the focus of much of the criticism. In particular, the construction and implementation of permanent waste repositories such as Yucca Mountain is becoming increasingly problematic from a financial and political perspective. The major shortcoming of these conventional repositories is that they must accommodate the whole spent fuel output from once-through fuel cycles. They are thus burdened with very large masses of material but where less than 1% is long-term, hazardous waste and where only a small fraction of the potential nuclear energy has been extracted. Second, such facilities must ensure integrity of waste containment for tens of thousands of years. Given that anything more than a few hundred years hence is unknowable and wholly unpredictable as far as future civilizations are concerned, public perception is that such facilities cannot be guaranteed to be absolutely secure for their envisaged lifetimes of tens of millennia.

Perkins, L J

2007-03-27T23:59:59.000Z

277

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

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

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.

278

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

279

Mixed waste removal from a hazardous waste storage tank  

Science Conference Proceedings (OSTI)

The spent fuel transfer canal at the Oak Ridge Graphite Reactor was found to be leaking 400 gallons of water per day into the surrounding soil. Sampling of the sediment layer on the floor of the canal to determine the environmental impact of the leak identified significant radiological contamination and elevated levels of cadmium and lead which are hazardous under the Resource Conservation and Recovery Act (RCRA). Under RCRA regulations and Rules of Tennessee Department of Environment and Conservation, the canal was considered a hazardous waste storage tank. This paper describes elements of the radiological control program established in support of a fast-track RCRA closure plan that involved underwater mapping of the radiation fields, vacuuming, and ultra-filtration techniques that were successfully used to remove the mixed waste sediments and close the canal in a method compliant with state and federal regulations.

Geber, K.R.

1993-06-01T23:59:59.000Z

280

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.4.

Laycak, D T

2010-03-05T23:59:59.000Z

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

Technical Safety Requirements for the Waste Storage Facilities  

SciTech Connect

This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting of buildings, tents, other structures, and open areas as described in Chapter 2 of the DSA. Section 2.4 of the DSA provides an overview of the buildings, structures, and areas in the WASTE STORAGE FACILITIES, including construction details such as basic floor plans, equipment layout, construction materials, controlling dimensions, and dimensions significant to the hazard and accident analysis. Chapter 5 of the DSA documents the derivation of the TSRs and develops the operational limits that protect the safety envelope defined for the WASTE STORAGE FACILITIES. This TSR document is applicable to the handling, storage, and treatment of hazardous waste, TRU WASTE, LLW, mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste received or generated in the WASTE STORAGE FACILITIES. Section 5, Administrative Controls, contains those Administrative Controls necessary to ensure safe operation of the WASTE STORAGE FACILITIES. Programmatic Administrative Controls are in Section 5.6.

Laycak, D T

2008-06-16T23:59:59.000Z

282

Summary of treatment, storage, and disposal facility usage data collected from U.S. Department of Energy sites  

SciTech Connect

This report presents an analysis for the US Department of Energy (DOE) to determine the level and extent of treatment, storage, and disposal facility (TSDF) assessment duplication. Commercial TSDFs are used as an integral part of the hazardous waste management process for those DOE sites that generate hazardous waste. Data regarding the DOE sites` usage have been extracted from three sets of data and analyzed in this report. The data are presented both qualitatively and quantitatively, as appropriate. This information provides the basis for further analysis of assessment duplication to be documented in issue papers as appropriate. Once the issues have been identified and adequately defined, corrective measures will be proposed and subsequently implemented.

Jacobs, A.; Oswald, K. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Trump, C. [EG and G Rocky Flats, Golden, CO (United States)

1995-04-01T23:59:59.000Z

283

Groundwater quality assessment report for Solid Waste Storage Area 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

Solid Waste Storage Area (SWSA) 6, located at the US Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) facility, is a shallow land burial site for low-level radioactive waste (LLW) and other waste types. Wastes were disposed of in unlined trenches and auger holes from 1969 until May 1986, when it was determined that Resource Conservation and Recovery Act (RCRA) regulated wastes were being disposed of there. DOE closed SWSA 6 until changes in operating procedures prevented the disposal of RCRA wastes at SWSA 6. The site, which reopened for waste disposal activities in July 1986, is the only currently operated disposal area for low-level radioactive waste at ORNL. This report provides the results of the 1998 RCRA groundwater assessment monitoring. The monitoring was performed in accordance with the proposed routine monitoring plan recommended in the 1996 EMP. Section 2 provides pertinent background on SWSA 6. Section 3 presents the 1998 monitoring results and discusses the results in terms of any significant changes from previous monitoring efforts. Section 4 provides recommendations for changes in monitoring based on the 1998 results. References are provided in Section 5. Appendix A provides the 1998 RCRA Sampling Data and Appendix B provides a summary of 1998 Quality Assurance results.

NONE

1998-12-31T23:59:59.000Z

284

Project report for the commercial disposal of mixed low-level waste debris  

SciTech Connect

This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.

Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

1994-05-01T23:59:59.000Z

285

Unresolved issues for the disposal of remote-handled transuranic waste in the Waste Isolation Pilot Plant  

SciTech Connect

The purpose of the Waste Isolation Pilot Plant (WIPP) is to dispose of 176,000 cubic meters of transuranic (TRU) waste generated by the defense activities of the US Government. The envisioned inventory contains approximately 6 million cubic feet of contact-handled transuranic (CH TRU) waste and 250,000 cubic feet of remote handled transuranic (RH TRU) waste. CH TRU emits less than 0.2 rem/hr at the container surface. Of the 250,000 cubic feet of RH TRU waste, 5% by volume can emit up to 1,000 rem/hr at the container surface. The remainder of RH TRU waste must emit less than 100 rem/hr. These are major unresolved problems with the intended disposal of RH TRU waste in the WIPP. (1) The WIPP design requires the canisters of RH TRU waste to be emplaced in the walls (ribs) of each repository room. Each room will then be filled with drums of CH TRU waste. However, the RH TRU waste will not be available for shipment and disposal until after several rooms have already been filled with drums of CH TRU waste. RH TRU disposal capacity will be loss for each room that is first filled with CH TRU waste. (2) Complete RH TRU waste characterization data will not be available for performance assessment because the facilities needed for waste handling, waste treatment, waste packaging, and waste characterization do not yet exist. (3) The DOE does not have a transportation cask for RH TRU waste certified by the US Nuclear Regulatory Commission (NRC). These issues are discussed along with possible solutions and consequences from these solutions. 46 refs.

Silva, M.K.; Neill, R.H.

1994-09-01T23:59:59.000Z

286

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

SciTech Connect

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

287

DOE Awards Task Order for Disposal of Los Alamos National Laboratory Waste  

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

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.

288

Nuclear Waste Disposal: An Independent View of the Big Picture and a Proposal for CARD  

E-Print Network (OSTI)

1 Nuclear Waste Disposal: An Independent View of the Big Picture and a Proposal for CARD Presented to isolate nuclear waste successfully from the biosphere for the long term can be developed if our society to this impasse? In the 1940's at the beginning of the nuclear age, nuclear waste was seen as a "problem" only

California at Santa Cruz, University of

289

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada Test Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

SciTech Connect

The NTS solid waste disposal sites must be permitted by the state of Nevada Solid Waste Management Authority (SWMA). The SWMA for the NTS is the Nevada Division of Environmental Protection, Bureau of Federal Facilities (NDEP/BFF). The U.S. Department of Energy's National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as land manager (owner), and National Security Technologies (NSTec), as operator, will store, collect, process, and dispose all solid waste by means that do not create a health hazard, a public nuisance, or cause impairment of the environment. NTS disposal sites will not be included in the Nye County Solid Waste Management Plan. The NTS is located approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1). The U.S. Department of Energy (DOE) is the federal lands management authority for the NTS, and NSTec is the Management and Operations contractor. Access on and off the NTS is tightly controlled, restricted, and guarded on a 24-hour basis. The NTS has signs posted along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NTS. The Area 5 RWMS is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NTS (Figure 2), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. A Notice of Intent to operate the disposal site as a Class III site was submitted to the state of Nevada on January 28, 1994, and was acknowledged as being received in a letter to the NNSA/NSO on August 30, 1994. Interim approval to operate a Class III SWDS for regulated asbestiform low-level waste (ALLW) was authorized on August 12, 1996 (in letter from Paul Liebendorfer to Runore Wycoff), with operations to be conducted in accordance with the ''Management Plan for the Disposal of Low-Level Waste with Regulated Asbestos Waste.'' A requirement of the authorization was that on or before October 9, 1999, a permit was required to be issued. Because of NDEP and NNSA/NSO review cycles, the final permit was issued on April 5, 2000, for the operation of the Area 5 Low-Level Waste Disposal Site, utilizing Pit 7 (P07) as the designated disposal cell. The original permit applied only to Pit 7, with a total design capacity of 5,831 cubic yards (yd{sup 3}) (157,437 cubic feet [ft{sup 3}]). NNSA/NSO is expanding the SWDS to include the adjacent Upper Cell of Pit 6 (P06), with an additional capacity of 28,037 yd{sup 3} (756,999 ft{sup 3}) (Figure 3). The proposed total capacity of ALLW in Pit 7 and P06 will be approximately 33,870 yd{sup 3} (0.9 million ft{sup 3}). The site will be used for the disposal of regulated ALLW, small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. The only waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM). The term asbestiform is used throughout this document to describe this waste. Other TSCA waste (i.e., polychlorinated biphenyls [PCBs]) will not be accepted for disposal at the SWDS. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the U.S. Department of Energy, Nevada Operations Office (DOE/NV) 325

NSTec Environmental Programs

2010-09-14T23:59:59.000Z

290

APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil  

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

APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil APS Protocols for Handling, Storage, and Disposal of Untreated Foreign Soil and Regulated Domestic Soil Arrival of New Samples: Unpack shipping containers. Treat any ice/melted water immediately. Decontaminate any "blue ice" packets with 70% ethyl alcohol. Collect any loose soil from container and heat-treat immediately. Immediately decontaminate shipping containers. Heat-treat wooden, metal, or cardboard shipping containers (using lowest heat). Treat plastic containers and coolers with 70% ethyl alcohol. Storage of Samples: Store dry samples in the locked storage cabinet in Room 431Z021 until they can be delivered to the appropriate beamline for analysis. Label containers with origin and arrival date. Log samples into the APS Soil Inventory book maintained in 431Z021.

291

Mixed Waste Storage and Treatment: Regulatory Compliance Manual  

Science Conference Proceedings (OSTI)

The management and storage of mixed wastes represents one of the most challenging regulatory issues currently facing NRC licensees. This report provides instructions and guidance regarding the on-site storage and treatment of mixed waste in compliance with Resource Conservation and Recovery Act (RCRA) requirements.

1994-12-31T23:59:59.000Z

292

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-10-01T23:59:59.000Z

293

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-05-01T23:59:59.000Z

294

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-02-01T23:59:59.000Z

295

Accepting Mixed Waste as Alternate Feed Material for Processing and Disposal at a Licensed Uranium Mill  

SciTech Connect

Certain categories of mixed wastes that contain recoverable amounts of natural uranium can be processed for the recovery of valuable uranium, alone or together with other metals, at licensed uranium mills, and the resulting tailings permanently disposed of as 11e.(2) byproduct material in the mill's tailings impoundment, as an alternative to treatment and/or direct disposal at a mixed waste disposal facility. This paper discusses the regulatory background applicable to hazardous wastes, mixed wastes and uranium mills and, in particular, NRC's Alternate Feed Guidance under which alternate feed materials that contain certain types of mixed wastes may be processed and disposed of at uranium mills. The paper discusses the way in which the Alternate Feed Guidance has been interpreted in the past with respect to processing mixed wastes and the significance of recent changes in NRC's interpretation of the Alternate Feed Guidance that sets the stage for a broader range of mixed waste materials to be processed as alternate feed materials. The paper also reviews the le gal rationale and policy reasons why materials that would otherwise have to be treated and/or disposed of as mixed waste, at a mixed waste disposal facility, are exempt from RCRA when reprocessed as alternate feed material at a uranium mill and become subject to the sole jurisdiction of NRC, and some of the reasons why processing mixed wastes as alternate feed materials at uranium mills is preferable to direct disposal. Finally, the paper concludes with a discussion of the specific acceptance, characterization and certification requirements applicable to alternate feed materials and mixed wastes at International Uranium (USA) Corporation's White Mesa Mill, which has been the most active uranium mill in the processing of alternate feed materials under the Alternate Feed Guidance.

Frydenland, D. C.; Hochstein, R. F.; Thompson, A. J.

2002-02-26T23:59:59.000Z

296

Automated Monitoring System for Waste Disposal Sites and Groundwater  

Science Conference Proceedings (OSTI)

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

S. E. Rawlinson

2003-03-01T23:59:59.000Z

297

Hardened, environmentally disposable composite granules of coal cleaning refuse, coal combustion waste, and other wastes, and method preparing the same  

DOE Patents (OSTI)

A hardened, environmentally inert and disposable composite granule of coal cleaning refuse and coal combustion waste, and method for producing the same, wherein the coal combustion waste is first granulated. The coal cleaning refuse is pulverized into fine particles and is then bound, as an outer layer, to the granulated coal combustion waste granules. This combination is then combusted and sintered. After cooling, the combination results in hardened, environmentally inert and disposable composite granules having cores of coal combustion waste, and outer shells of coal cleaning refuse. The composite particles are durable and extremely resistant to environmental and chemical forces.

Burnet, George (Ames, IA); Gokhale, Ashok J. (College Station, TX)

1990-07-10T23:59:59.000Z

298

Hardened, environmentally disposable composite granules of coal cleaning refuse, coal combustion waste, and other wastes, and method preparing the same  

DOE Patents (OSTI)

A hardened, environmentally inert and disposable composite granule of coal cleaning refuse and coal combustion waste and method for producing the same are disclosed, wherein the coal combustion waste is first granulated. The coal cleaning refuse is pulverized into fine particles and is then bound, as an outer layer, to the granulated coal combustion waste granules. This combination is then combusted and sintered. After cooling, the combination results in hardened, environmentally inert and disposable composite granules having cores of coal combustion waste, and outer shells of coal cleaning refuse. The composite particles are durable and extremely resistant to environmental and chemical forces. 3 figs.

Burnet, G.; Gokhale, A.J.

1990-07-10T23:59:59.000Z

299

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (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

2011-03-01T23:59:59.000Z

300

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project  

SciTech Connect

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.

David Duncan

2011-05-01T23:59:59.000Z

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

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

SciTech Connect

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

302

Offsite commercial disposal of oil and gas exploration and production waste :availability, options, and cost.  

Science Conference Proceedings (OSTI)

A survey conducted in 1995 by the American Petroleum Institute (API) found that the U.S. exploration and production (E&P) segment of the oil and gas industry generated more than 149 million bbl of drilling wastes, almost 18 billion bbl of produced water, and 21 million bbl of associated wastes. The results of that survey, published in 2000, suggested that 3% of drilling wastes, less than 0.5% of produced water, and 15% of associated wastes are sent to offsite commercial facilities for disposal. Argonne National Laboratory (Argonne) collected information on commercial E&P waste disposal companies in different states in 1997. While the information is nearly a decade old, the report has proved useful. In 2005, Argonne began collecting current information to update and expand the data. This report describes the new 2005-2006 database and focuses on the availability of offsite commercial disposal companies, the prevailing disposal methods, and estimated disposal costs. The data were collected in two phases. In the first phase, state oil and gas regulatory officials in 31 states were contacted to determine whether their agency maintained a list of permitted commercial disposal companies dedicated to oil. In the second stage, individual commercial disposal companies were interviewed to determine disposal methods and costs. The availability of offsite commercial disposal companies and facilities falls into three categories. The states with high oil and gas production typically have a dedicated network of offsite commercial disposal companies and facilities in place. In other states, such an infrastructure does not exist and very often, commercial disposal companies focus on produced water services. About half of the states do not have any industry-specific offsite commercial disposal infrastructure. In those states, operators take their wastes to local municipal landfills if permitted or haul the wastes to other states. This report provides state-by-state summaries of the types of offsite commercial disposal facilities that are found in each state. In later sections, data are presented by waste type and then by disposal method.

Puder, M. G.; Veil, J. A.

2006-09-05T23:59:59.000Z

303

Safety analysis report for the Waste Storage Facility. Revision 2  

SciTech Connect

This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

Bengston, S.J.

1994-05-01T23:59:59.000Z

304

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

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

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

305

Simulation of large supply chains: simulation of waste processing, transportation, and disposal operations  

Science Conference Proceedings (OSTI)

In response to the accelerated cleanup goals of the Department of Energy, Sandia National Laboratory (Sandia) has developed and utilized a number of simulation models to represent the processing, transportation, and disposal of radioactive waste. Sandia, ...

Janis Trone; Angela Guerin; Amber D. Clay

2000-12-01T23:59:59.000Z

306

Effective thermal conductivity measurements relevant to deep borehole nuclear waste disposal  

E-Print Network (OSTI)

The objective of this work was to measure the effective thermal conductivity of a number of materials (particle beds, and fluids) proposed for use in and around canisters for disposal of high level nuclear waste in deep ...

Shaikh, Samina

2007-01-01T23:59:59.000Z

307

Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal  

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

308

An evaluation of the feasibility of disposal of nuclear waste in very deep boreholes  

E-Print Network (OSTI)

Deep boreholes, 3 to 5 km into igneous rock, such as granite, are evaluated for next- generation repository use in the disposal of spent nuclear fuel and other high level waste. The primary focus is on the stability and ...

Anderson, Victoria Katherine, 1980-

2004-01-01T23:59:59.000Z

309

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

SciTech Connect

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

Ashworth, S.C.

1998-08-06T23:59:59.000Z

310

Management Strategies for Treatment and Disposal of Utility-Generated Low-Level Radioactive Waste  

Science Conference Proceedings (OSTI)

Some states or regional compacts may be unable to establish LLRW disposal facilities by the January 1, 1993, deadline. The possible strategies described in this report should help nuclear utilities prepare for this possibility by identifying safe and cost-effective waste disposal options.

1989-04-11T23:59:59.000Z

311

Revegetation of a Comanaged Utility Waste Disposal Area: A Southwestern Site  

Science Conference Proceedings (OSTI)

Comanagement of low-volume coal combustion by-products with high-volume wastes produces a saline material, which presents unique challenges to revegetation after disposal area closure. This report describes studies evaluating plants, amendments, and techniques for revegetating one of these sites in the southwestern United States. These studies have produced guidelines for successful revegetation of comanaged disposal sites.

1999-11-29T23:59:59.000Z

312

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

Science Conference Proceedings (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

313

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

SciTech Connect

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

None

1981-04-01T23:59:59.000Z

314

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

E-Print Network (OSTI)

Environmental Protection Agency (US EPA) regulations, it produces energy and does not emit fossil carbonCCA-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

Florida, University of

315

Risk perception on management of nuclear high-level and transuranic waste storage  

SciTech Connect

The Department of Energy`s program for disposing of nuclear High-Level Waste (HLW) and transuranic (TRU) waste has been impeded by overwhelming political opposition fueled by public perceptions of actual risk. Analysis of these perceptions shows them to be deeply rooted in images of fear and dread that have been present since the discovery of radioactivity. The development and use of nuclear weapons linked these images to reality and the mishandling of radioactive waste from the nations military weapons facilities has contributed toward creating a state of distrust that cannot be erased quickly or easily. In addition, the analysis indicates that even the highly educated technical community is not well informed on the latest technology involved with nuclear HLW and TRU waste disposal. It is not surprising then, that the general public feels uncomfortable with DOE`s management plans for with nuclear HLW and TRU waste disposal. Postponing the permanent geologic repository and use of Monitored Retrievable Storage (MRS) would provide the time necessary for difficult social and political issues to be resolved. It would also allow time for the public to become better educated if DOE chooses to become proactive.

Dees, L.A.

1994-08-15T23:59:59.000Z

316

The role of acceptable knowledge in transuranic waste disposal operations - 11117  

SciTech Connect

The Acceptable Knowledge (AK) process plays a key role in the delineation of waste streams destined for the Waste Isolation Pilot Plant (WIPP). General Electric's Vallecitos Nuclear Center (GEVNC) provides for an ideal case study of the application of AK in a multiple steward environment. In this review we will elucidate the pivotal role Acceptable Knowledge played in segregating Department of Energy (DOE) responsibilities from a commercial facility. The Acceptable Knowledge process is a necessary component of waste characterization that determines whether or not a waste stream may be considered for disposal at the WIPP site. This process may be thought of as an effort to gain a thorough understanding of the waste origin, chemical content, and physical form gleaned by the collection of documentation that concerns generator/storage site history, mission, and operations; in addition to waste stream specific information which includes the waste generation process, the waste matrix, the quantity of waste concerned, and the radiological and chemical make up of the waste. The collection and dissemination of relevant documentation is the fundamental requirement for the AK process to work. Acceptable Knowledge is the predominant process of characterization and, therefore, a crucial part of WIPP's transuranic waste characterization program. This characterization process, when conducted to the standards set forth in WIPP's operating permit, requires confirmation/verification by physical techniques such as Non-Destructive Examination (NDE), Visual Examination (VE), and Non-Destructive Assay (NDA). These physical characterization techniques may vary in their appropriateness for a given waste stream; however, nothing will allow the substitution or exclusion of AK. Beyond the normal scope of operations, AK may be considered, when appropriate, a surrogate for the physical characterization techniques in a procedure that appeals to concepts such As Low As Reasonably Achievable (ALARA) and budgetary savings. This substitution is referred to as an Acceptable Knowledge Sufficiency Determination. With a Sufficiency Determination Request, AK may supplant the need for one or all of the physical analysis methods. This powerful procedure may be used on a scale as small as a single container to that of a vast waste stream. Only under the most stringent requirements will an AK Sufficiency Determination be approved by the regulators and, to date, only six such Sufficiency Determinations have been approved. Although Acceptable Knowledge is legislated into the operational procedures of the WIPP facility there is more to it than compliance. AK is not merely one of a long list of requirements in the characterization and verification of transuranic (TRU) waste destined for the WIPP. Acceptable Knowledge goes beyond the regulatory threshold by offering a way to reduce risk, cost, time, and uncertainty on its own laurels. Therefore, AK alone can be argued superior to any other waste characterization technique.

Chancellor, Christopher John [Los Alamos National Laboratory; Nelson, Roger [DOE-CARLSBAD

2010-11-08T23:59:59.000Z

317

Microsoft Word - SRSSaltWasteDisposal.doc | Department of Energy  

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

Savannah River Site - Tank 48 SRS Review Report 2009 Performance Assessment for the Saltstone Disposal Facility DOE Order 435.1 Performance Assessment Savannah River Site...

318

Low-Level Waste Disposal Facility Federal Review Group (LFRG) | Department  

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

Program Management » Compliance » Low-Level Waste Program Management » Compliance » Low-Level Waste Disposal Facility Federal Review Group (LFRG) Low-Level Waste Disposal Facility Federal Review Group (LFRG) The Office of Environmental Management (EM) Low-Level Waste Disposal Facility Federal Review Group (LFRG) was established to fulfill the requirements contained in Section I.2.E(1)(a) of the Department of Energy (DOE) Order 435.1, Radioactive Waste Management, and exercised by the senior managers of EM. The LFRG assists EM senior managers in the review of documentation that supports the approval of performance assessments and composite analyses or appropriate Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)documents as described in Section II of the LFRG Charter. Through its efforts, the LFRG supports the issuance

319

Ground disposal of oil shale wastes: a review with an indexed annotated bibliography through 1976  

SciTech Connect

This review covers the available literature concerning ground-disposed wastes and effluents of a potential oil shale industry. Ground disposal has been proposed for essentially all of the solid and liquid wastes produced (Pfeffer, 1974). Since an oil shale industry is not actually in operation, the review is anticipatory in nature. The section, Oil Shale Technology, provides essential background for interpreting the literature on potential shale oil wastes and the topics are treated more completely in the section entitled Environmental Aspects of the Potential Disposal of Oil Shale Wastes to Ground. The first section of the annotated bibliography cites literature concerning potential oil shale wastes and the second section cites literature concerning oil shale technology. Each section contains references arranged historically by year. An index is provided.

Routson, R.C.; Bean, R.M.

1977-12-01T23:59:59.000Z

320

Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

Science Conference Proceedings (OSTI)

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

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

2012-04-17T23:59:59.000Z

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

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

322

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

323

Method of preparing nuclear wastes for tansportation and interim storage  

SciTech Connect

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

324

Consideration of nuclear criticality when disposing of transuranic waste at the Waste Isolation Pilot Plant  

Science Conference Proceedings (OSTI)

Based on general arguments presented in this report, nuclear criticality was eliminated from performance assessment calculations for the Waste Isolation Pilot Plant (WIPP), a repository for waste contaminated with transuranic (TRU) radioisotopes, located in southeastern New Mexico. At the WIPP, the probability of criticality within the repository is low because mechanisms to concentrate the fissile radioisotopes dispersed throughout the waste are absent. In addition, following an inadvertent human intrusion into the repository (an event that must be considered because of safety regulations), the probability of nuclear criticality away from the repository is low because (1) the amount of fissile mass transported over 10,000 yr is predicted to be small, (2) often there are insufficient spaces in the advective pore space (e.g., macroscopic fractures) to provide sufficient thickness for precipitation of fissile material, and (3) there is no credible mechanism to counteract the natural tendency of the material to disperse during transport and instead concentrate fissile material in a small enough volume for it to form a critical concentration. Furthermore, before a criticality would have the potential to affect human health after closure of the repository--assuming that a criticality could occur--it would have to either (1) degrade the ability of the disposal system to contain nuclear waste or (2) produce significantly more radioisotopes than originally present. Neither of these situations can occur at the WIPP; thus, the consequences of a criticality are also low.

RECHARD,ROBERT P.; SANCHEZ,LAWRENCE C.; STOCKMAN,CHRISTINE T.; TRELLUE,HOLLY R.

2000-04-01T23:59:59.000Z

325

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

SciTech Connect

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-05-01T23:59:59.000Z

326

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

Science Conference Proceedings (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility 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). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-02-01T23:59:59.000Z

327

Report on waste burial charges. Escalation of decommissioning waste disposal costs at low-level waste burial facilities, Revision 4  

SciTech Connect

One of the requirements placed upon nuclear power reactor licensees by the U.S. Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fourth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991 and 1993, superseding the values given in the May 1993 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1994 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

Not Available

1994-06-01T23:59:59.000Z

328

Report on waste burial charges: Escalation of decommissioning waste disposal costs at Low-Level Waste Burial facilities. Revision 5  

SciTech Connect

One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plants, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised periodically, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC. The sources of information to be used in the escalation formula are identified, and the values developed for the escalation of radioactive waste burial costs, by site and by year, are given. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analyses, or they may use an escalation rate at least equal to the escalation approach presented herein. This fifth revision of NUREG-1307 contains revised spreadsheet results for the disposal costs for the reference PWR and the reference BWR and the ratios of disposal costs at the Washington, Nevada, and South Carolina sites for the years 1986, 1988, 1991, 1993, and 1994, superseding the values given in the June 1994 issue of this report. Burial cost surcharges mandated by the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) have been incorporated into the revised ratio tables for those years. In addition, spreadsheet results for the disposal costs for the reference reactors and ratios of disposal costs at the two remaining burial sites in Washington and South Carolina for the year 1995 are provided. These latter results do not include any LLRWPAA surcharges, since those provisions of the Act expired at the end of 1992. An example calculation for escalated disposal cost is presented, demonstrating the use of the data contained in this report.

NONE

1995-08-01T23:59:59.000Z

329

Performance assessment for a hypothetical low-level waste disposal facility  

Science Conference Proceedings (OSTI)

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

Smith, C.S.; Rohe, M.J.; Ritter, P.D. [and others

1997-01-01T23:59:59.000Z

330

Disposal concepts and characteristics of existing and potential low-waste repositories - 9076  

Science Conference Proceedings (OSTI)

The closure of the Barnwell low-level waste (LLW) disposal facility to non-Atlantic Compact users poses significant problems for organizations seeking to remove waste material from public circulation. Beta-gamma sources such as {sup 137}Cs and {sup 90}Sr in particular create problems because in 36 states no path forward exists for disposal. Furthermore, several other countries are considering disposition of sealed sources in a variety of facilities. Like much of the United States, many of these countries currently have no means of disposal. Consequently, there is a greater tendency for sources to be misplaced or stored in insufficient facilities, resulting in an increased likelihood of unwitting exposure of nearby people to radioactive materials. This paper provides an overview of the various disposal concepts that have been employed or attempted in the United States. From these concepts, a general overview of characteristics necessary for long-term disposal is synthesized.

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

2009-01-01T23:59:59.000Z

331

A Generic Technical Basis for Implementing a Very Low Level Waste Category for Disposal of Low Activity Radioactive Wastes  

Science Conference Proceedings (OSTI)

The International Atomic Energy Agency (IAEA) has recognized Very Low Level Waste (VLLW) as a category that provides both practical and economic benefits. Implementation of VLLW in the international community has been successfully demonstrated in France and Spain, as described in EPRI report 1024844, Basis for National and International Low Activity and Very Low Level Waste (VLLW) Disposal Classifications. This report presents the technical basis for a waste category of Very Low Level ...

2013-12-23T23:59:59.000Z

332

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

Science Conference Proceedings (OSTI)

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

Swita, W.R.

1998-01-05T23:59:59.000Z

333

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

Science Conference Proceedings (OSTI)

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

Diana H. Bacon; B. Peter McGrail

2003-04-01T23:59:59.000Z

334

THE BURNING ISSUES OF MUNICIPAL SOLID WASTE DISPOSAL WHAT WORKS AND WHAT DOESN'T  

E-Print Network (OSTI)

1 THE BURNING ISSUES OF MUNICIPAL SOLID WASTE DISPOSAL ­ WHAT WORKS AND WHAT DOESN'T By: Jack D devil burns and the Lord recycles." Perhaps these negative references to waste burning come from, the Valley of Hinnom south of ancient Jerusalem. This was the site of a foul, smoking, open burning garbage

Columbia University

335

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

SciTech Connect

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

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

1996-06-01T23:59:59.000Z

336

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

Science Conference Proceedings (OSTI)

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

Hall, C.E.

1998-01-06T23:59:59.000Z

337

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

Science Conference Proceedings (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

338

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

Science Conference Proceedings (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, the highest ranked alternative, 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.

2011-04-01T23:59:59.000Z

339

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

Science Conference Proceedings (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

340

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

Science Conference Proceedings (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, the highest ranked alternative, 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.

2011-01-01T23:59:59.000Z

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

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

Science Conference Proceedings (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

342

EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings  

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

0: Construction of Mixed Waste Storage RCRA Facilities, 0: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee SUMMARY This EA evaluates the environmental impacts of a proposal to construct and operate two mixed (both radioactive and hazardous) waste storage facilities (Buildings 7668 and 7669) in accordance with Resource Conservation and Recovery Act requirements. Site preparation and construction activities would take place at the U.S. Department of Energy's Oak Ridge National Laboratory in Oak Ridge, Tennessee. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 16, 1994 EA-0820: Finding of No Significant Impact

343

The performance assessment process for DOE low-level waste disposal facilities  

Science Conference Proceedings (OSTI)

Safety of the low-level waste disposal facilities, as well as al US DOE facilities, is a primary criterion in their design and operation. Safety of low-level waste disposal facilities is evaluated from two perspectives. Operational safety is evaluated based on the perceived level of hazard of the operation. The safety evaluations vary from simple safety assessments to very complex safety analysis reports, depending on the degree of hazard associated with the facility operation. Operational requirements for the Department's low-level waste disposal facilities, including long-term safety are contained in DOE Order 5820.2A, Radioactive Waste Management (1). This paper will focus on the process of conducting long-term performance analyses rather than on operational safety analysis.

Wilhite, E.L.

1992-01-01T23:59:59.000Z

344

The performance assessment process for DOE low-level waste disposal facilities  

Science Conference Proceedings (OSTI)

Safety of the low-level waste disposal facilities, as well as al US DOE facilities, is a primary criterion in their design and operation. Safety of low-level waste disposal facilities is evaluated from two perspectives. Operational safety is evaluated based on the perceived level of hazard of the operation. The safety evaluations vary from simple safety assessments to very complex safety analysis reports, depending on the degree of hazard associated with the facility operation. Operational requirements for the Department`s low-level waste disposal facilities, including long-term safety are contained in DOE Order 5820.2A, Radioactive Waste Management (1). This paper will focus on the process of conducting long-term performance analyses rather than on operational safety analysis.

Wilhite, E.L.

1992-11-01T23:59:59.000Z

345

Method of encapsulating solid radioactive waste material for storage  

DOE Patents (OSTI)

High-level radioactive wastes are encapsulated in vitreous carbon for long-term storage by mixing the wastes as finely divided solids with a suitable resin, formed into an appropriate shape and cured. The cured resin is carbonized by heating under a vacuum to form vitreous carbon. The vitreous carbon shapes may be further protected for storage by encasement in a canister containing a low melting temperature matrix material such as aluminum to increase impact resistance and improve heat dissipation.

Bunnell, Lee Roy (Kennewick, WA); Bates, J. Lambert (Richland, WA)

1976-01-01T23:59:59.000Z

346

LANL completes excavation of 1940s waste disposal site  

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

Environment Feature Stories Public Reading Room: Environmental Documents, Reports LANL Home Phonebook Calendar Video Business Business Stories Excavation of waste...

347

Solid Waste Management Act (Pennsylvania)  

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

This Act provides for the planning and regulation of solid waste storage, collection, transportation, processing, treatment, and disposal. It requires that municipalities submit plans for municipal...

348

Federal fees and contracts for storage and disposal of spent LWR fuel  

SciTech Connect

The methodology for establishing a fee for federal spent fuel storage and disposal services is explained along with a presentation of the cost centers and cost data used to calculate the fee. Results of the initial fee calculation and the attendant sensitivity studies are also reviewed. The current status of the fee update is presented. The content of the proposed contract for federal services is briefly reviewed.

Clark, H.J.

1979-01-01T23:59:59.000Z

349

Radioactive waste shipments to Hanford retrievable storage from Westinghouse Advanced Reactors and Nuclear Fuels Divisions, Cheswick, Pennsylvania  

Science Conference Proceedings (OSTI)

During the next two decades the transuranic (TRU) waste now stored in the burial trenches and storage facilities at the Hanford Sits in southeastern Washington State is to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico for final disposal. Approximately 5.7 percent of the TRU waste to be retrieved for shipment to WIPP was generated by the decontamination and decommissioning (D&D) of the Westinghouse Advanced Reactors Division (WARD) and the Westinghouse Nuclear Fuels Division (WNFD) in Cheswick, Pennsylvania and shipped to the Hanford Sits for storage. This report characterizes these radioactive solid wastes using process knowledge, existing records, and oral history interviews.

Duncan, D. [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Weyns, M.I.; Dicenso, K.D.; DeLorenzo, D.S. [Los Alamos Technical Associates, Inc., NM (United States)

1994-04-01T23:59:59.000Z

350

Impact of Construction Waste Disposal Charging Scheme on work practices at construction sites in Hong Kong  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer A significant reduction of construction waste was achieved at the first 3 years of CWDCS implementation. Black-Right-Pointing-Pointer However, the reduction cannot be sustained. Black-Right-Pointing-Pointer Implementation of the CWDCS has generated positive effects in waste reduction by all main trades. - Abstract: Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C and D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C and D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C and D waste.

Yu, Ann T.W., E-mail: bsannyu@polyu.edu.hk [Department of Building and Real Estate, The Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong); Poon, C.S.; Wong, Agnes; Yip, Robin; Jaillon, Lara [Department of Civil and Structural Engineering, Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong)

2013-01-15T23:59:59.000Z

351

Nuclear energy and radioactive waste disposal in the age of recycling  

Science Conference Proceedings (OSTI)

The magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. For a variety of reasons, nuclear energy must be a major portion of the distribution, at least one third. The often-cited strategic hurdle to this approach is nuclear waste disposal. Present strategies concerning disposal of nuclear waste need to be changed if the world is to achieve both a sustainable energy distribution by 2040 and solve the largest environmental issue of the 21. century - global warming. It is hoped that ambitious proposals to replace fossil fuel power generation by alternatives will drop the percentage of fossil fuel use substantially, but the absolute amount of fossil fuel produced electricity must be kept at or below its present 10 trillion kW-hrs/year. Unfortunately, the rapid growth in consumption to over 30 trillion kW-hrs/year by 2040, means that 20 trillion kW-hrs/yr of non-fossil fuel generated power has to come from other sources. If half of that comes from alternative non-nuclear, non-hydroelectric sources (an increase of 3000%), then nuclear still needs to increase by a factor of four worldwide to compensate. Many of the reasons nuclear energy did not expand after 1970 in North America (proliferation, capital costs, operational risks, waste disposal, and public fear) are no longer a problem. The WIPP site in New Mexico, an example of a solution to the nuclear waste disposal issue, and also to public fear, is an operating deep geologic nuclear waste repository in the massive bedded salt of the Salado Formation. WIPP has been operating for eight years, and as of this writing, has disposed of over 50,000 m{sup 3} of transuranic waste (>100 nCi/g but <23 Curie/liter) including high activity waste. The Salado Formation is an ideal host for any type of nuclear waste, especially waste from recycled spent fuel. (authors)

Conca, James L. [New Mexico State University, CEMRC IEE, 1400 University Drive, Carlsbad New Mexico 88220 (United States); Apted, Michael [Monitor Scientific, 3900 S. Wadsworth, Denver, CO 80235 (United States)

2007-07-01T23:59:59.000Z

352

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

Science Conference Proceedings (OSTI)

This comprehensive report provides definitive volume, mass, and composition (chemical and radioactivity) of calcined waste stored at the Idaho Nuclear Technology and Engineering Center. Calcine composition data are required for regulatory compliance (such as permitting and waste disposal), future treatment of the caline, and shipping the calcine to an off-Site-facility (such as a geologic repository). This report also contains a description of the calcine storage bins. The Calcined Solids Storage Facilities (CSSFs) were designed by different architectural engineering firms and built at different times. Each CSSF has a unique design, reflecting varying design criteria and lessons learned from historical CSSF operation. The varying CSSF design will affect future calcine retrieval processes and equipment. Revision 4 of this report presents refinements and enhancements of calculations concerning the composition, volume, mass, chemical content, and radioactivity of calcined waste produced and stored within the CSSFs. The historical calcine samples are insufficient in number and scope of analysis to fully characterize the entire inventory of calcine in the CSSFs. Sample data exist for all the liquid wastes that were calcined. This report provides calcine composition data based on liquid waste sample analyses, volume of liquid waste calcined, calciner operating data, and CSSF operating data using several large Microsoft Excel (Microsoft 2003) databases and spreadsheets that are collectively called the Historical Processing Model. The calcine composition determined by this method compares favorably with historical calcine sample data.

Staiger, M. Daniel, Swenson, Michael C.

2011-09-01T23:59:59.000Z

353

DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE  

SciTech Connect

Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

2011-01-13T23:59:59.000Z

354

Geological challenges in radioactive waste isolation: Third worldwide review  

E-Print Network (OSTI)

Waste Disposal, Science and Technology in Hungary, Safety of Nuclear Energy,Disposal of Radioactive Waste and Spent Nuclear Fuel Po vilas Poskas Lithuanian EnergyNuclear Energy. ” Article 48, entitled “Storage or Disposal of Radioactive Wastes,” states that the disposal

Witherspoon editor, P.A.; Bodvarsson editor, G.S.

2001-01-01T23:59:59.000Z

355

WASTE TREATMENT AND DISPOSAL PROGRESS REPORT FOR JUNE AND JULY 1961  

DOE Green Energy (OSTI)

7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scavenging-ion exchange pilot plant on ORNL low-activity waste. Decontamination factors were satisfactory after 1500 resin bed voluumes of waste had been treated, i. e, Sr> 1000, TRE 100, Cs> 100, and sufficiently high for other activities that the waste activity was reduced to <10% of MPC. The physical properties of vermiculite, clinoptilolite, and rock phosphate were found to be suitable for second-stage treatment of process waste. Engineering, Econommc, and Hazards Evaluation. A cost study of the conversion of high-level solutions to solids by pot calcimation was completed. Aging had a negligible effect on costs for processing in a given vessel size. The lowest cost was 0.87 x 10/sup-2/ mill/kwh/sub 3/ for processing acidic Purex and Thorex wastes in 24-in.-dia. vessels, and the highest was 5.0 x 10/sup -2/ mill/kwh/sub e/ for processing reacidifled Purex and Thorex wastes im 6-in.-dia. vessels. Disposal ion Deep Wells. Test drilling at the site of the second fracturing experiment is nearly completed. The upper grout sheet extends out from the injection well some 500 ft to the east and northeast, but only- short distances out in other directions. The lower grout sheet extends largely to the north and northwest, but its outer limits are still undefimed. Disposal in Natural Salt Formations. Stress measurements in the pillars of the Hutchimson mine have shown the absence of horizontal stresses and the presence of vertical stress varyimg from 1300 to 1600 psi. Comparison of the data from the field cavities and theoretical calculations of temperature rises aroumd spheres indicates that the thermal conductivity of the salt surrounding the experimental cavities is 2.6 Btu hr/sup -1/ ft/sup 10/ F/sup -1/ and the diffusivity is 0.099 ft/sup 2/hr. A computer code was designed for the solution of temperature rise in a heat-generating layer of infinite horizontal dimensions and in the salt surrounding the layer, as a function of time for wastes of variable age. The use of this code showed that the storage of waste decayed less than one year is wasteful of mine space and that the thickness of the slab from 1 to 10 ft has little effect on the temperature rise in the slab. Studies on radiolytic gas production of wastes in salt showed that gas production can be eliminated by pressurizing the cavity or by maintaining an atmosphere of hydrogen over the waste. Clinch River Studies. A continuous water-sampling system was imstalled at Centers Ferry on the Clinch River. The imstruments were so designed that the rate of sampling is proportional to the velocity of flow in the river. Results of sorption tests on membrane filters indicate that essentially no strontium, cobalt, or ruthenium is sorbed as river water samples are filtered. A small percentage of cesium, 4%, is sorbed by the filters. Various types of bottom sediment core samplers were tested and evaluated for compaction and retention characteristics. Results of a recent silt range survey showed that additional cross section sampling sections, intermediate to the standard silt ranges, do not significantiy change estimates of sediment volume. Fundamental Studies of Minerals. Sodium-vermiculite showed three distinct sorption-of-strontium responses in the pH ramge 2 to 11. Up to pH 4.5 the response depends on the displacement of aluminuna from octahedral layers of the mineral. Thus, sorption was <10% at pH 2 and only 59% at pH 4.0; in both

Blanco, R.E.; Struxness, E.G.

1961-10-24T23:59:59.000Z

356

Tank Farm Contractor Phase 1 Feed Delivery and Storage and Disposal Mission Summary for 2006 Hot Start Extended Order  

SciTech Connect

This is the level one logic diagram for the River Protection Project (RPP), Tank Farm Contractor, Phase 1, Feed Delivery Storage and Disposal Mission Summary for 2006 Hot Start.

DAVIS, T.J.

2000-04-24T23:59:59.000Z

357

Chapter 37 Hazardous Waste Land Disposal Restrictions (Kentucky...  

Open Energy Info (EERE)

Policy Contact Contact Name Anthony Hatton (Director) Department Department for Environmental Protection Division Division of Waste Management Address 200 Fair Oaks Ln.,...

358

Solid Waste Disposal Resource Recovery Facilities Act (South Carolina)  

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

This legislation authorizes local governing bodies to form joint agencies to advance the collection, transfer, processing of solid waste, recovery of resources, and sales of recovered resources in...

359

Managing commercial low-level radioactive waste beyond 1992: Transportation planning for a LLW disposal facility  

Science Conference Proceedings (OSTI)

This technical bulletin presents information on the many activities and issues related to transportation of low-level radioactive waste (LLW) to allow interested States to investigate further those subjects for which proactive preparation will facilitate the development and operation of a LLW disposal facility. The activities related to transportation for a LLW disposal facility are discussed under the following headings: safety; legislation, regulations, and implementation guidance; operations-related transport (LLW and non-LLW traffic); construction traffic; economics; and public involvement.

Quinn, G.J. [Wastren, Inc. (United States)

1992-01-01T23:59:59.000Z

360

Polysiloxane Encapsulation of High Level Calcine Waste for Transportation or Disposal  

SciTech Connect

This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: 1) a characterization of the pilot calcine waste; 2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, 3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test.

Loomis, Guy George

2000-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage 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.


361

Silicon-Polymer Encapsulation of High-Level Calcine Waste for Transportation or Disposal  

SciTech Connect

This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: (1) a characterization of the pilot calcine waste; (2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, (3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test.

G. G. Loomis; C. M. Miller; J. A. Giansiracusa; R. Kimmel; S. V. Prewett

2000-01-01T23:59:59.000Z

362

Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant  

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

OH OH EM Project: On-Site Disposal Facility ETR Report Date: February 2008 ETR-12 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did This Review The On-Site Waste Disposal Facility (OSWDF) is proposed for long-term containment of contaminated materials from the planned Decontamination and Decommissioning (D&D) activities at the Portsmouth Gaseous Diffusion Plant. Acceptable performance of the proposed OSWDF will depend on interactions between engineered landfill features and operations methods that recognize the unique characteristics of the waste stream and site-

363

Potential for Subsidence at the Low-Level Radioactive Waste Disposal Area  

Science Conference Proceedings (OSTI)

U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management requires that DOE low-level radioactive waste (LLW) disposal facilities receive a Disposal Authorization Statement (DAS) from DOE-Headquarters. The DAS for the LLW disposal facility at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL) was granted in April 2000 and included a number of conditions that must be addressed. A maintenance plan (Schuman 2000) was prepared that identifies the tasks to be completed to address the conditions in the DAS as well as a schedule for their completion. The need for a subsidence analysis was one of the conditions identified for the DAS, and thus, a task to prepare a subsidence analysis was included in the maintenance plan. This document provides the information necessary to satisfy that requirement.

Keck, K.A.; Seitz, R.R.

2002-09-26T23:59:59.000Z

364

Potential for Subsidence at the Low-level Waste Disposal Area  

Science Conference Proceedings (OSTI)

U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management requires that DOE low-level radioactive waste (LLW) disposal facilities receive a Disposal Authorization Statement (DAS) from DOE-Headquarters. The DAS for the LLW disposal facility at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL) was granted in April 2000 and included a number of conditions that must be addressed. A maintenance plan (Schuman 2000) was prepared that identifies the tasks to be completed to address the conditions in the DAS as well as a schedule for their completion. The need for a subsidence analysis was one of the conditions identified for the DAS, and thus, a task to prepare a subsidence analysis was included in the maintenance plan. This document provides the information necessary to satisfy that requirement.

Keck, Karen Nina; Seitz, Roger Ray

2002-09-01T23:59:59.000Z

365

Framework for DOE mixed low-level waste disposal: Site fact sheets  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) is required to prepare and submit Site Treatment Plans (STPS) pursuant to the Federal Facility Compliance Act (FFCAct). Although the FFCAct does not require that disposal be addressed in the STPS, the DOE and the States recognize that treatment of mixed low-level waste will result in residues that will require disposal in either low-level waste or mixed low-level waste disposal facilities. As a result, the DOE is working with the States to define and develop a process for evaluating disposal-site suitability in concert with the FFCAct and development of the STPS. Forty-nine potential disposal sites were screened; preliminary screening criteria reduced the number of sites for consideration to twenty-six. The DOE then prepared fact sheets for the remaining sites. These fact sheets provided additional site-specific information for understanding the strengths and weaknesses of the twenty-six sites as potential disposal sites. The information also provided the basis for discussion among affected States and the DOE in recommending sites for more detailed evaluation.

Gruebel, M.M.; Waters, R.D.; Hospelhorn, M.B.; Chu, M.S.Y. [eds.

1994-11-01T23:59:59.000Z

366

Immobilization of Nuclear Wastes  

Science Conference Proceedings (OSTI)

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

367

DOE/WIPP 02-3196 - Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization, March 19, 2002  

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

2-3196 2-3196 Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization (40 CFR § 761.75[c]) March 19, 2002 Waste Isolation Pilot Plant Initial Report for PCB Disposal Authorization DOE/WIPP 02-3196 TABLE OF CONTENTS 1.0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 LOCATION OF THE DISPOSAL FACILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3.0 DETAILED DESCRIPTION OF THE DISPOSAL FACILITY . . . . . . . . . . . . . . . . . . . 4 4.0 ENGINEERING REPORT ON TECHNICAL STANDARDS FOR CHEMICAL WASTE LANDFILLS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5.0 SAMPLING AND MONITORING EQUIPMENT AND FACILITIES AVAILABLE 6 6.0 EXPECTED WASTE VOLUMES OF PCB/TRU WASTE . . . . . . . . . . . . . . . . . . . . 7 7.0 GENERAL DESCRIPTION OF WASTE MATERIALS OTHER THAN PCBS . . . . 8 8.0 DISPOSAL FACILITY OPERATIONS PLAN

368

Some aspects of low-level radioactive-waste disposal in the US  

Science Conference Proceedings (OSTI)

This report summarizes the NRC supported Shallow Land Burial research program at Brookhaven National Laboraotry and its relationship to the proposed revised ruling on disposal of low level radioactive waste, 10 CFR Part 61. Section of the proposed regulation, which establish the new low level waste classification system and the performance objective placed on waste form, are described briefly. The report also summarizes the preliminary results obtained from the EPA program in which low level waste drums were retrieved from the Atlantic and Pacific Oceans.

Schweitzer, D.G.; Davis, R.E.

1982-01-01T23:59:59.000Z

369

Household disposables as breeding habitats of dengue vectors: Linking wastes and public health  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer An assessment of different household wastes as larval habitats of dengue vectors Aedes aegypti and Aedes albopictus was made using Kolkata, India as a model geographical area. Black-Right-Pointing-Pointer Household wastes of four major categories namely earthen, porcelain, plastic and coconut shells varied significantly for Aedes immature depending on species, month and location. Black-Right-Pointing-Pointer Based on the relative density of Aedes immature, cluster analyses allowed segregation and classification of the waste containers and relative importance as mosquito larval habitats. Black-Right-Pointing-Pointer Conversion of disposed wastes into larval habitats cautions for continuance of Aedes population in Kolkata and similar cities of tropics lacking suitable waste management practices. - Abstract: An assessment of the household wastes as larval habitats of the dengue vectors was made considering Kolkata, India, as geographical area. Wastes of four major categories, namely, earthen, porcelain, plastic and coconut shells were monitored for positive with immature of either Aedes aegypti or Aedes albopictus. Twenty six types of wastes with varying size and shape, resembling containers, were identified that hosted mosquito immature. The number of waste containers positive for Aedes immature varied significantly (P < 0.05) with respect to location, type and month. The relative density of Aedes immature in the waste containers varied significantly (P < 0.05) with the types and months. The significant interaction between the month, waste container types and density of Aedes immature suggest that the household wastes are important contributors to the maintenance of the population of Aedes mosquito in the city. Based on the relative density of mosquito immature in the wastes, cluster analysis allowed segregation and classification of the wastes and their importance as mosquito larval habitats. Apparently, the containers that are most frequently disposed off contributed largely to the sustenance of Aedes mosquito population in the city. This calls for a strict legislation towards disposal as well as enhanced management of the household wastes. A link between the wastes disposed and subsequent conversion to the mosquito larval habitats cautions for continuance of Aedes population and possibility of dengue epidemics if the existing management practices are not improved.

Banerjee, Soumyajit, E-mail: soumyajitb@gmail.com [Department of Zoology, University of Calcutta, 35 Ballygunge Circular Road, Kolkata 700 019 (India); Aditya, Gautam, E-mail: gautamaditya2001@gmail.com [Department of Zoology, University of Calcutta, 35 Ballygunge Circular Road, Kolkata 700 019 (India); Department of Zoology, The University of Burdwan, Golapbag, Burdwan 713 104 (India); Saha, Goutam K, E-mail: gkszoo@rediffmail.com [Department of Zoology, University of Calcutta, 35 Ballygunge Circular Road, Kolkata 700 019 (India)

2013-01-15T23:59:59.000Z

370

Feasibility study on the management of the disposal of Bangkok municipal waste. Final report  

SciTech Connect

In January, 1985, the Government of Thailand sought assistance from the United States Trade and Development Program (USTDP) to undertake a feasibility study to review and update the solid waste management master plan, with particular emphasis to be placed on waste disposal methods. In April, 1985, the USTDP engaged the firm of Engineering and Economic Research, Inc. to carry out a definitional/prefeasibility study to assess the potential of a project for solid waste management and energy production using municipal solid waste as fuel.

1989-09-01T23:59:59.000Z

371

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

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

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 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

372

Independent review of inappropriate identification, storage and treatment methods of polychlorinated biphenyl waste streams  

SciTech Connect

The purpose of the review was to evaluate incidents involving the inappropriate identification, storage, and treatment methods associated with polychlorinated biphenyl (PCB) waste streams originating from the V-tank system at the Test Area North (TAN). The team was instructed to perform a comprehensive review of Lockheed Martin Idaho Technologies Company (LMITCO`s) compliance programs related to these incidents to assess the adequacy and effectiveness of the management program in all respects including: adequacy of the waste management program in meeting all LMITCO requirements and regulations; adequacy of policies, plans, and procedures in addressing and implementing all federal and state requirements and regulations; and compliance status of LMITCO, LMITCO contract team members, and LMITCO contract/team member subcontractor personnel with established PCB management policies, plans, and procedures. The V-Tanks are part of an intermediate waste disposal system and are located at the Technical Support Facility (TSF) at TAN at the Idaho National Engineering and Environmental Laboratory (INEEL). The IRT evaluated how a waste was characterized, managed, and information was documented; however, they did not take control of wastes or ensure followup was performed on all waste streams that may have been generated from the V-Tanks. The team has also subsequently learned that the Environmental Restoration (ER) program is revising the plans for the decontamination and decommissioning of the intermediate waste disposal system based on new information listed and PCB wastes. The team has not reviewed those in-process changes. The source of PCB in the V-Tank is suspected to be a spill of hydraulic fluid in 1968.

1997-07-01T23:59:59.000Z

373

New information on disposal of oil field wastes in salt caverns  

Science Conference Proceedings (OSTI)

Solution-mined salt caverns have been used for many years for storing hydrocarbon products. This paper summarizes an Argonne National Laboratory report that reviews the legality, technical suitability, and feasibility of disposing of nonhazardous oil and gas exploration and production wastes in salt caverns. An analysis of regulations indicated that there are no outright regulatory prohibitions on cavern disposal of oil field wastes at either the federal level or in the 11 oil-producing states that were studied. There is no actual field experience on the long-term impacts that might arise following closure of waste disposal caverns. Although research has found that pressures will build-up in a closed cavern, none has specifically addressed caverns filled with oil field wastes. More field research on pressure build-up in closed caverns is needed. On the basis of preliminary investigations, we believe that disposal of oil field wastes in salt caverns is legal and feasible. The technical suitability of the practice depends on whether the caverns are well-sited and well-designed, carefully operated, properly closed, and routinely monitored.

Veil, J.A.

1996-10-01T23:59:59.000Z

374

Can nonhazardous oil field wastes be disposed of in salt caverns?  

Science Conference Proceedings (OSTI)

Solution-mined salt caverns have been used for many years for storing hydrocarbon products. This paper summarizes an Argonne National Laboratory report that reviews the legality, technical suitability, and feasibility of disposing of nonhazardous oil and gas exploration and production wastes in salt caverns. An analysis of regulations indicated that there are no outright regulatory prohibitions on cavern disposal -of oil field wastes at either the federal level or in the 11 oil-producing states that were studied. There is no actual field experience on the long-term impacts that might arise following closure of waste disposal caverns. Although research has found that pressures will build up in a closed cavern, none has specifically addressed caverns filled with oil field wastes. More field research on pressure build up in closed caverns is needed. On the basis of preliminary investigations, we believe that disposal of oil field wastes in salt caverns is legal and feasible. The technical suitability of the practice depends on whether the caverns are well-sited and well-designed, carefully operated, properly closed, and routinely monitored.

Veil, J.A.

1996-10-01T23:59:59.000Z

375

Alternative design concept for the second Glass Waste Storage Building  

SciTech Connect

This document presents an alternative design concept for storing canisters filled with vitrified waste produced at the Defense Waste Processing Facility (DWPF). The existing Glass Waste Storage Building (GWSB1) has the capacity to store 2,262 canisters and is projected to be completely filled by the year 2000. Current plans for glass waste storage are based on constructing a second Glass Waste Storage Building (GWSB2) once the existing Glass Waste Storage Building (GWSB1) is filled to capacity. The GWSB2 project (Project S-2045) is to provide additional storage capacity for 2,262 canisters. This project was initiated with the issue of a basic data report on March 6, 1989. In response to the basic data report Bechtel National, Inc. (BNI) prepared a draft conceptual design report (CDR) for the GWSB2 project in April 1991. In May 1991 WSRC Systems Engineering issued a revised Functional Design Criteria (FDC), the Rev. I document has not yet been approved by DOE. This document proposes an alternative design for the conceptual design (CDR) completed in April 1991. In June 1992 Project Management Department authorized Systems Engineering to further develop the proposed alternative design. The proposed facility will have a storage capacity for 2,268 canisters and will meet DWPF interim storage requirements for a five-year period. This document contains: a description of the proposed facility; a cost estimate of the proposed design; a cost comparison between the proposed facility and the design outlined in the FDC/CDR; and an overall assessment of the alternative design as compared with the reference FDC/CDR design.

Rainisch, R.

1992-10-01T23:59:59.000Z

376

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

Science Conference Proceedings (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

377

Nuclear waste disposal in New Mexico and Nevada  

Science Conference Proceedings (OSTI)

The author describes the Waste Isolation Pilot Project (WIPP) for safely discarded nuclear wates is discussed. WIPP, now essentially complete, near Carlsbad, NM, and Yucca Mountain, in the early stages of construction northwest of Las Vegas, Nev. The ...

J. Beard

1997-11-01T23:59:59.000Z

378

Basis for Section 3116 Determination for Salt Waste Disposal...  

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

concentrate the insoluble solids and the MST solids loaded with Sr and actinides, if MST treatment of the waste was performed. The cross-flow filtration process will yield a...

379

The Properties of Spent Nuclear Fuel under Waste Disposal ...  

Science Conference Proceedings (OSTI)

Symposium, Materials Issues in Nuclear Waste Management in the 21st Century ... UO2 in the form of a ceramic pellet with a density close to theoretical. ... On discharge fro reactor the pellets have undergone a number of physical and ...

380

Perspectives on integrating the US radioactive waste disposal system  

SciTech Connect

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

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

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waste storage 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.


381

Performance Assessment for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

This performance assessment for the Remote-Handled Low-Level Radioactive Waste Disposal Facility at the Idaho National Laboratory documents the projected radiological dose impacts associated with the disposal of low-level radioactive waste at the facility. This assessment evaluates compliance with the applicable radiological criteria of the U.S. Department of Energy and the U.S. Environmental Protection Agency for protection of the public and the environment. The calculations involve modeling transport of radionuclides from buried waste to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses are calculated for both offsite receptors and individuals who inadvertently intrude into the waste after site closure. The results of the calculations are used to evaluate the future performance of the low-level radioactive waste disposal facility and to provide input for establishment of waste acceptance criteria. In addition, one-factor-at-a-time, Monte Carlo, and rank correlation analyses are included for sensitivity and uncertainty analysis. The comparison of the performance assessment results to the applicable performance objectives provides reasonable expectation that the performance objectives will be met

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

2012-05-01T23:59:59.000Z

382

Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation,OAS-RA-L-12-01  

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

Waste Disposal and Recovery Act Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation INS-RA-L-12-01 December 2011 Department of Energy Washington, DC 20585 December 16, 2011 MEMORANDUM FOR THE MANAGER, OAK RIDGE OFFICE FROM: Sandra D. Bruce Assistant Inspector General for Inspections Office of Inspector General SUBJECT: INFORMATION: Inspection Report on "Waste Disposal and Recovery Act Efforts at the Oak Ridge Reservation" BACKGROUND The Department of Energy's (Department) expends billions of dollars to clean up contaminated sites and dispose of hazardous waste. The Department's Oak Ridge Office (ORO) is responsible for processing and disposing of the Transuranic (TRU) waste on the Oak Ridge Reservation (ORR), including approximately 3,500 cubic meters of legacy remote-handled (RH) and contact-

383

Field study of disposed wastes from advanced coal processes. Quarterly technical progress report, April--June 1992  

Science Conference Proceedings (OSTI)

The Department of Energy/Morgantown Energy Technology Center (DOE/METC) has initiated research on the disposal of solid wastes from advanced coal processes. The objective of this research is to develop information to be used by private industry and government agencies for planning waste disposal practices associated with advanced coal processes. To accomplish this objective, DOE has contracted Radian Corporation and the North Dakota Energy & Environmental Research Center (EERC) to design, construct, and monitor a limited number of field disposal tests with advanced coal process wastes. These field tests will be monitored over a three year period with the emphasis on collecting data on the field disposal of these wastes. There has been considerable research on the characteristics and laboratory leaching behavior of coal wastes -- a lesser amount on wastes from advanced coal processes. However, very little information exists on the field disposal behavior of these wastes. Information on field disposal behavior is needed (a) as input to predictive models being developed, (b) as input to the development of rule of thumb design guidelines for the disposal of these wastes, and (c) as evidence of the behavior of these wastes in the natural environment.

Not Available

1992-12-31T23:59:59.000Z

384

Los Alamos Lab Completes Excavation of Waste Disposal Site Used in the 1940s  

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

September 29, 2011 September 29, 2011 LOS ALAMOS, N.M. - Los Alamos National Laboratory recently completed excava- tion of its oldest waste disposal site, Material Disposal Area B (MDA-B), thanks to American Recovery and Reinvestment Act funding. The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. MDA-B was used from 1944 to 1948 as a waste disposal site for Manhat- tan Project and Cold War-era research and production. "The completion of the excavation of MDA-B is a landmark for our Recov- ery Act projects and environmental cleanup efforts," said George Rael, assistant manager for Environmental Operations at the National Nuclear Security Administration's Los Alamos Site Office. Completion of the excavation ends EM

385

Disposal of NORM-Contaminated Oil Field Wastes in Salt Caverns  

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

Prepared for: U.S. Department of Energy U.S. Department of Energy Office of Fossil Energy Office of Fossil Energy National Petroleum Technology Office National Petroleum Technology Office under Contract W -31-109- under Contract W -31-109- Eng Eng -38 -38 Prepared by: Prepared by: John A. Veil, Karen P. Smith, David John A. Veil, Karen P. Smith, David Tomasko Tomasko , , Deborah Deborah Elcock Elcock , Deborah L. Blunt, and , Deborah L. Blunt, and Gustavious Gustavious P. W illiams P. W illiams Argonne National Laboratory August 1998 August 1998 Disposal of NORM - Disposal of NORM - Contam inated O il Contam inated O il Field Wastes in Salt Field Wastes in Salt Caverns Caverns Disposal of NORM in Salt Caverns Page i Table of Contents Acronyms and Abbreviations . . . . . . . . . . . . . . . . . . . . . . . . . .

386

A data base for low-level radioactive waste disposal sites  

SciTech Connect

A computerized database was developed to assist the US Environmental Protection Agency (EPA) in evaluating methods and data for characterizing health hazards associated with land and ocean disposal options for low-level radioactive wastes. The data cover 1984 to 1987. The types of sites considered include Nuclear Regulatory Commission (NRC) licensed commercial disposal sites, EPA National Priority List (NPL) sites, US Department of Energy (DOE) Formerly Utilized Sites Remedial Action Project (FUSRAP) and DOE Surplus Facilities Management Program (SFMP) sites, inactive US ocean disposal sites, and DOE/Department of Defense facilities. Sources of information include reports from EPA, the US Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC), as well as direct communication with individuals associated with specific programs. The data include site descriptions, waste volumes and activity levels, and physical and radiological characterization of low-level wastes. Additional information on mixed waste, packaging forms, and disposal methods were compiled, but are not yet included in the database. 55 refs., 4 figs., 2 tabs.

Daum, M.L.; Moskowitz, P.D.

1989-07-01T23:59:59.000Z

387

U Itimate Disposal of Industrial Wastes C. A. HESCHELES, P. E.  

E-Print Network (OSTI)

sophisticated control equip ment can later be installed. The stack and I.D. Fan design should anticipate this financed, designed and operated re gional industrial waste disposal facility that has reached an actual. There appears to be a number of unusual design features which I would like to see clarified and the rationale

Columbia University

388

RADIOACTIVE WASTE PROCESSING AND DISPOSAL: A BIBLIOGRAPHY OF SELECTED REPORT LITERATURE  

SciTech Connect

An annotated bibliography is presented containing 698 references to unclassifled reports on currert and proposed ranioactive waste processing and disposal practices for solutions from radiochemical processing plants and laboratories, decontamination of surfaces, air cleaning, and other related subjects. Author, corporate author, subject, and report nuunber indexes are included. (auth)

Voress, H.E.; Davis, T.F.; Hubbard, T.N. Jr.

1958-06-01T23:59:59.000Z

389

Preliminary Technical and Legal Evaluation of Disposing of Nonhazardous Oil Field Waste into Salt Caverns  

Science Conference Proceedings (OSTI)

This report presents an initial evaluation of the suitability, feasibility, and legality of using salt caverns for disposal of nonhazardous oil field wastes. Given the preliminary and general nature of this report, we recognize that some of our findings and conclusions maybe speculative and subject to change upon further research on this topic.

Ayers, Robert C.; Caudle, Dan; Elcock, Deborah; Raivel, Mary; Veil, John; and Grunewald, Ben

1999-01-21T23:59:59.000Z

390

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

Science Conference Proceedings (OSTI)

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

Seitz, R.

2011-03-02T23:59:59.000Z

391

The impact of NRC guidance on concentration averaging on low level waste sealed source disposal - 11424  

SciTech Connect

As part of its ongoing efforts to revise the Nuclear Regulatory Commission's (NRC) current position on blending to be risk-informed and performance based and its current review of the low-level waste classification codified in 10 CFR 61.55, the Nuclear Regulatory Commission (NRC) has stated that it may review the 1995 'Branch Technical Position on Concentration Averaging and Encapsulation' (BTP), which is still commonly used today. Such a review will have timely advantages, given the lack of commercial disposal availability within the United States for radioactive sealed sources that are in wide beneficial use across the country. The current application of the BTP guidance has resulted in an effective cap on commercial disposal for sources larger than 1.1 TBq (30 Ci). This paper will analyze how the BTP has been implemented with respect to sealed sources, what the implications have been for commercial disposal availability, and whether alternative packaging configurations could be considered for disposal.

Whitworth, Julia [Los Alamos National Laboratory; Stewart, Bill [Los Alamos National Laboratory; Cuthbertson, Abigail [DOE

2011-01-20T23:59:59.000Z

392

Effects of actinide burning on waste disposal at Yucca Mountain  

SciTech Connect

Release rates of 15 radionuclides from waste packages expected to result from partitioning and transmutation of Light-Water Reactor (LWR) and Actinide-Burning Liquid-Metal Reactor (ALMR) spent fuel are calculated and compared to release rates from standard LWR spent fuel packages. The release rates are input to a model for radionuclide transport from the proposed geologic repository at Yucca Mountain to the water table. Discharge rates at the water table are calculated and used in a model for transport to the accessible environment, defined to be five kilometers from the repository edge. Concentrations and dose rates at the accessible environment from spent fuel and wastes from reprocessing, with partitioning and transmutation, are calculated. Partitioning and transmutation of LWR and ALMR spent fuel reduces the inventories of uranium, neptunium, plutonium, americium and curium in the high-level waste by factors of 40 to 500. However, because release rates of all of the actinides except curium are limited by solubility and are independent of package inventory, they are not reduced correspondingly. Only for curium is the repository release rate much lower for reprocessing wastes.

Hirschfelder, J. [California Univ., Berkeley, CA (United States)

1992-07-01T23:59:59.000Z

393

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01T23:59:59.000Z

394

DOE Awards Task Order for Disposal of Los Alamos National Laboratory Waste  

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

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. The award is a firm, fixed-price task order, based on pre-established rates with a $1.29 million value and has a one-year performance period.

395

Pre-title I safety evaluation for the retrieval operations of transuranic waste drums in the Solid Waste Disposal Facility. Revision 2  

SciTech Connect

Phase I of the Transuranic (TRU) Waste Facility Line Item Project includes the retrieval and safe storage of the pad drums that are stored on TRU pads 2-6 in the Solid Waste Disposal Facility (SWDF). Drums containing TRU waste were placed on these pads as early as 1974. The pads, once filled, were mounded with soil. The retrieval activities will include the excavation of the soil, retrieval of the pad drums, placing the drums in overpacks (if necessary) and venting and purging the retrieved drums. Once the drums have been vented and purged, they will be transported to other pads within the SWDF or in a designated area until they are eventually treated as necessary for ultimate shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico. This safety evaluation provides a bounding assessment of the radiological risk involved with the drum retrieval activities to the maximally exposed offsite individual and the co-located worker. The results of the analysis indicate that the risk to the maximally exposed offsite individual and the co-located worker using maximum frequencies and maximum consequences are within the acceptance criteria defined in WSRC Procedural Manual 9Q. The purpose of this evaluation is to demonstrate the incremental risk from the SWDF due to the retrieval activities for use as design input only. As design information becomes available, this evaluation can be revised to satisfy the safety analysis requirements of DOE Orders 4700 and 5480.23.

Rabin, M.S.

1992-08-01T23:59:59.000Z

396

DEPARTMENT OF ENERGY Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford  

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

Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Site, Richland, Washington; Record of Decision (ROO). This Record of Decision has been prepared pursuant to the Council on Environme~tal Quality ~egulations for Implementing the Procedural Provisions of the National Environmental Pol icy Act (NEPAl (40 CFR Parts 1500-1508) and the Department of Energy NEPA Guidelines (52 FR 47662, December 15, 1987). It is based on DOE's "Environmental Impact Statement for the Oi sposal of Hanford Defense High-Level, Transuranic, and Tank Wastes'' (OOE/EIS-0113) and consideration of ~11 public and agency comments received on the Environmental Impact Statement (EIS). fJECISION The decision is to implement the ''Preferred Alternative'' as discussed in

397

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2009-10-01T23:59:59.000Z

398

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-03-01T23:59:59.000Z

399

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2011-04-01T23:59:59.000Z

400

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis  

SciTech Connect

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

David Duncan

2010-06-01T23:59:59.0