Sample records for waste solidification building

  1. WASTE SOLIDIFICATION BUILDING BENCH SCALE HIGH ACTIVITY WASTE SIMULANT VARIABILITY STUDY FY2008

    SciTech Connect (OSTI)

    Hansen, E; Timothy Jones, T; Tommy Edwards, T; Alex Cozzi, A

    2009-03-20T23:59:59.000Z

    The primary objective of this task was to perform a variability study of the high activity waste (HAW) acidic feed to determine the impact of feed variability on the quality of the final grout and on the mixability of the salt solution into the dry powders. The HAW acidic feeds were processed through the neutralization/pH process, targeting a final pH of 12. These fluids were then blended with the dry materials to make the final waste forms. A secondary objective was to determine if elemental substitution for cost prohibitive or toxic elements in the simulant affects the mixing response, thus providing a more economical simulant for use in full scale tests. Though not an objective, the HAW simulant used in the full scale tests was also tested and compared to the results from this task. A statistically designed test matrix was developed based on the maximum molarity inputs used to make the acidic solutions. The maximum molarity inputs were: 7.39 HNO{sub 3}, 0.11618 gallium, 0.5423 silver, and 1.1032 'other' metals based on their NO{sub 3}{sup -} contribution. Substitution of the elements aluminum for gallium and copper for silver was also considered in this test matrix, resulting in a total of 40 tests. During the NaOH addition, the neutralization/pH adjustment process was controlled to a maximum temperature of 60 C. The neutralized/pH adjusted simulants were blended with Portland cement and zircon flour at a water to cement mass ratio of 0.30. The mass ratio of zircon flour to Portland cement was 1/12. The grout was made using a Hobart N-50 mixer running at low speed for two minutes to incorporate and properly wet the dry solids with liquid and at medium speed for five minutes for mixing. The resulting fresh grout was measured for three consecutive yield stress measurements. The cured grout was measured for set, bleed, and density. Given the conditions of preparing the grout in this task, all of the grouts were visually well mixed prior to preparing the grouts for measurements. All of the cured grouts were measured for bleed and set. All of the cured grouts satisfied the bleed and set requirements, where no bleed water was observed on any of the grout samples after one day and all had set within 3 days of curing. This data indicates, for a well mixed product, bleed and set requirement are satisfied for the range of acidic feeds tested in this task. The yield stress measurements provide both an indication on the mixability of the salt solution with dry materials and an indication of how quickly the grout is starting to form structure. The inability to properly mix these two streams into a well mixed grout product will lead to a non-homogeneous mixture that will impact product quality. Product quality issues could be unmixed regions of dry material and hot spots having high concentrations of americium 241. Mixes that were more difficult to incorporate typically resulted in grouts with higher yield stresses. The mixability from these tests will provide Waste Solidification Building (WSB) an indication of which grouts will be more challenging to mix. The first yield stress measurements were statistically compared to a list of variables, specifically the batched chemicals used to make the acidic solutions. The first yield stress was also compared to the physical properties of the acidic solutions, physical and pH properties of the neutralized/pH adjusted solutions, and chemical and physical properties of the grout.

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

    SciTech Connect (OSTI)

    COZZI, ALEX

    2004-02-18T23:59:59.000Z

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

  3. HEAT TRANSFER ANALYSIS FOR NUCLEAR WASTE SOLIDIFICATION CONTAINER

    SciTech Connect (OSTI)

    Lee, S.

    2009-06-01T23:59:59.000Z

    The Nuclear Nonproliferation Programs Design Authority is in the design stage of the Waste Solidification Building (WSB) for the treatment and solidification of the radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility (PDCF) and Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The waste streams will be mixed with a cementitious dry mix in a 55-gallon waste container. Savannah River National Laboratory (SRNL) has been performing the testing and evaluations to support technical decisions for the WSB. Engineering Modeling & Simulation Group was requested to evaluate the thermal performance of the 55-gallon drum containing hydration heat source associated with the current baseline cement waste form. A transient axi-symmetric heat transfer model for the drum partially filled with waste form cement has been developed and heat transfer calculations performed for the baseline design configurations. For this case, 65 percent of the drum volume was assumed to be filled with the waste form, which has transient hydration heat source, as one of the baseline conditions. A series of modeling calculations has been performed using a computational heat transfer approach. The baseline modeling results show that the time to reach the maximum temperature of the 65 percent filled drum is about 32 hours when a 43 C initial cement temperature is assumed to be cooled by natural convection with 27 C external air. In addition, the results computed by the present model were compared with analytical solutions. The modeling results will be benchmarked against the prototypic test results. The verified model will be used for the evaluation of the thermal performance for the WSB drum. Detailed results and the cases considered in the calculations will be discussed here.

  4. The use of glass matrices for solidification of radioactive wastes

    SciTech Connect (OSTI)

    Gromov, V.V.; Minaev, A.A. [Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Physical Chemistry

    1993-12-31T23:59:59.000Z

    The physico-chemical aspects of the solidification of nuclear wastes have been studied at the Institute of Physical Chemistry of the Russian Academy of Sciences for a number of years. This method is viewed as the most reliable method of storage of nuclear wastes. Various glass systems have been studied, including phosphate, borosilicate glasses etc. The data obtained allow optimal glass compositions to be chosen for solidification of various nuclear wastes.

  5. Method for solidification of radioactive and other hazardous waste

    DOE Patents [OSTI]

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

    2002-01-01T23:59:59.000Z

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

  6. MODELING SOLIDIFICATION-INDUCED STRESSES IN CERAMIC WASTE FORMS CONTAINING NUCLEAR WASTES

    SciTech Connect (OSTI)

    Charles W. Solbrig; Kenneth J. Bateman

    2010-11-01T23:59:59.000Z

    The goal of this work is to produce a ceramic waste form (CWF) that permanently occludes radioactive waste. This is accomplished by absorbing radioactive salts into zeolite, mixing with glass frit, heating to a molten state 915 C to form a sodalite glass matrix, and solidifying for long-term storage. Less long term leaching is expected if the solidifying cooling rate doesn’t cause cracking. In addition to thermal stress, this paper proposes that a stress is formed during solidification which is very large for fast cooling rates during solidification and can cause severe cracking. A solidifying glass or ceramic cylinder forms a dome on the cylinder top end. The temperature distribution at the time of solidification causes the stress and the dome. The dome height, “the length deficit,” produces an axial stress when the solid returns to room temperature with the inherent outer region in compression, the inner in tension. Large tensions will cause cracking of the specimen. The temperature deficit, derived by dividing the length deficit by the coefficient of thermal expansion, allows solidification stress theory to be extended to the circumferential stress. This paper derives the solidification stress theory, gives examples, explains how to induce beneficial stresses, and compares theory to experimental data.

  7. Modified phosphate ceramics for stabilization and solidification of salt mixed wastes.

    SciTech Connect (OSTI)

    Singh, D.

    1998-06-26T23:59:59.000Z

    Novel chemically bonded phosphate ceramics have been investigated for stabilization and solidification of chloride and nitrate salt wastes. Using low-temperature processing, we stabilized and solidified chloride and nitrate surrogate salts (with hazardous metals) in magnesium potassium phosphate ceramics up to waste loadings of 70-80 wt.%. A variety of characterizations, including strength, microstructure, and leaching, were then conducted on the waste forms. Leaching tests show that all heavy metals in the leachant are well below the EPAs universal treatment standard limits. Long-term leaching tests, per ANS 16. 1 procedure, yields leachability index for nitrate ions > 12. Chloride ions are expected to have an even higher (i.e., better) leachability index. Structural performance of these final waste forms, as indicated by compression strength and durability in aqueous environments, satisfies the regulatory criteria. Thus, based on the results of this study, it seems that phosphate ceramics are viable option for containment of salt wastes.

  8. Preliminary evaluation of alternative waste form solidification processes. Volume I. Identification of the processes.

    SciTech Connect (OSTI)

    Treat, R.L.; Nesbitt, J.F.; Blair, H.T.; Carter, J.G.; Gorton, P.S.; Partain, W.L.; Timmerman, C.L.

    1980-04-01T23:59:59.000Z

    This document contains preconceptual design data on 11 processes for the solidification and isolation of nuclear high-level liquid wastes (HLLW). The processes are: in-can glass melting (ICGM) process, joule-heated glass melting (JHGM) process, glass-ceramic (GC) process, marbles-in-lead (MIL) matrix process, supercalcine pellets-in-metal (SCPIM) matrix process, pyrolytic-carbon coated pellets-in-metal (PCCPIM) matrix process, supercalcine hot-isostatic-pressing (SCHIP) process, SYNROC hot-isostatic-pressing (SYNROC HIP) process, titanate process, concrete process, and cermet process. For the purposes of this study, it was assumed that each of the solidification processes is capable of handling similar amounts of HLLW generated in a production-sized fuel reprocessing plant. It was also assumed that each of the processes would be enclosed in a shielded canyon or cells within a waste facility located at the fuel reprocessing plant. Finally, it was assumed that all of the processes would be subject to the same set of regulations, codes and standards. Each of the solidification processes converts waste into forms that may be acceptable for geological disposal. Each process begins with the receipt of HLLW from the fuel reprocessing plant. In this study, it was assumed that the original composition of the HLLW would be the same for each process. The process ends when the different waste forms are enclosed in canisters or containers that are acceptable for interim storage. Overviews of each of the 11 processes and the bases used for their identification are presented in the first part of this report. Each process, including its equipment and its requirements, is covered in more detail in Appendices A through K. Pertinent information on the current state of the art and the research and development required for the implementation of each process are also noted in the appendices.

  9. Waste Handeling Building Conceptual Study

    SciTech Connect (OSTI)

    G.W. Rowe

    2000-11-06T23:59:59.000Z

    The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', which will address the overall program objectives and direction, including options and issues associated with transportation, the subsurface facility, and Total System Life Cycle Cost. This study (herein) is limited to the Waste Handling System and associated fuel staging system.

  10. An examination of interference in waste solidification through measurement of heat signature

    SciTech Connect (OSTI)

    Shi, C.; Stegemann, J.; Caldwell, R. [Water Technology International Corp., Burlington, Ontario (Canada)] [Water Technology International Corp., Burlington, Ontario (Canada)

    1998-07-01T23:59:59.000Z

    The hydration of cementing materials is accompanied by heat evolution which is closely related to their structure development. The presence of wastes usually interferes with the hydration of cementing materials. This study examined their interference in waste stabilization/solidification processes through the measurement of adiabatic heat evolution using a computerized Quadrel{trademark} system. Two cementitious materials, an alkali-activated blast furnace slag binder and an ASTM Type 1 Portland cement were used to solidify an electric arc furnace (EAF) dust, which has high concentrations of B, Cr, Hg, Pb, Ni and Zn. The EAF dust contents were 0, 30 and 60% by mass. Different mixing conditions were also examined. The interference of EAF dust with the hydration of cementing materials was described using several parameters derived from the heat evolution curves: equivalent initial time of setting (equivalent time at 20 C); total heat evolution at initial time of setting; equivalent final time of setting, total heat evolution at final time of setting and total heat evolution at equivalent time of 28 and 90 days. Experimental results indicated that the Quadrel{trademark} system was a useful tool to examine the interference in waste stabilization/solidification and to assist with the selection of cementing materials.

  11. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE.

    SciTech Connect (OSTI)

    ADAMA, J.W.; BOWERMAN, B.S.; KALB, P.D.

    2002-10-01T23:59:59.000Z

    The Environmental Protection Agency (EPA) is currently seeking to validate technologies that can directly treat radioactively contaminated high mercury (Hg) subcategory wastes without removing the mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needs additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 30 wt% dry sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  12. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE

    SciTech Connect (OSTI)

    Adams, J. W.; Bowerman, B. S.; Kalb, P. D.

    2002-02-25T23:59:59.000Z

    The Environmental Protection Agency (EPA) is currently evaluating alternative treatment standards for radioactively contaminated high mercury (Hg) subcategory wastes, which do not require the removal of mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needed additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 46 wt% (30 wt% dry) sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide the EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  13. Sorbent Testing for Solidification of Organic Plutonium/Uranium Extraction Waste - Phase IV

    SciTech Connect (OSTI)

    Bickford, J.L.; Joyce, H.O. [MSE Technology Applications, Inc., P.O. Box 4078, Butte, MT 59701 (United States); Holmes-Burns, H. [Westinghouse Savannah River Company, Building 705-3C, P.O. Box A, Aiken SC 29802 (United States)

    2006-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) is evaluating various sorbents to solidify and immobilize hazardous constituents of the organic fraction of plutonium/uranium extraction (PUREX) process waste at the Savannah River Site (SRS).[5] The purpose of the solidification is to provide a cost-effective alternative to incineration of the waste. Incineration at the Consolidated Incinerator Facility (CIF) at SRS is currently identified as the treatment technology for PUREX waste. However, the CIF is not in operation at this time, so SRS is interested in pursuing alternatives to incineration for treatment of this waste. The DOE Western Environmental Technology Office in Butte, MT was designated as the facility for conducting the sorbent testing and evaluation for the organic PUREX waste surrogate. MSE Technology Applications, Inc. tested and evaluated two clay and two polymer sorbents with the capability of solidifying organic PUREX waste. A surrogate organic PUREX waste recipe was utilized, and sorbents were tested and evaluated at bench-scale, 22-liter (5-gallon) scale, and 242-liter (55-gallon) scale. This paper presents experimental results evaluating four sorbent materials including: Imbiber Beads{sup TM} IMB230301-R, Nochar A610 Petrobond{sup TM}, Petroset II{sup TM}, and Petroset II Granular{sup TM}. Previous work at SRS indicated that these products could solidify organic PUREX waste on a bench scale [1]. The sorbents were evaluated using operational criteria and final wasteform properties. Operational criteria included: sorbent capacity; sorption rate; sorbent handling; and mixing requirements. Final wasteform evaluation properties included: ignitability; thermal stability; offgas generation, leachability tests and volumetric expansion. Bench-scale tests, 22-liter (5-gallon) tests, and initial 242-liter (55-gallon) tests are complete. This paper summarizes the results of the bench-scale, 22-liter (5-gallon) scale, and 242-liter (55-gallon) scale tests performed during FY05 with an aqueous/PUREX surrogate. (authors)

  14. Technology and apparatus for solidification of radioactive wastes from nuclear fuel cycle by high temperature adsorption of metals on inorganic matrices

    SciTech Connect (OSTI)

    Nardova, A.K.; Philipov, E.A.; Kudriavtsev, Y.G.; Dzekun, E.G.; Parfanovitch, B.N. [Russian Research Inst. of Chemical Technology, Moscow (Russian Federation)

    1993-12-31T23:59:59.000Z

    This study deals with the investigation of high-level waste (HLW) solidification by high-temperature adsorption of radionuclides on porous inorganic matrices. An appropriate drum-type apparatus using magnetic gear drive was designed and tested. The report contains the test results of the solidification process of high-level radioactive raffinate from the first regeneration extraction cycle of irradiated fuel elements from nuclear power plants. Industrial-scale tests of the HLW solidification process (technology and equipment) are planned.

  15. Solidification/stabilization of toxic metal wastes using coke and coal combustion by-products

    SciTech Connect (OSTI)

    Vempati, R.K.; Mollah, M.Y.A.; Chinthala, A.K.; Cocke, D.L. [Lamar Univ., Beaumont, TX (United States)] [Lamar Univ., Beaumont, TX (United States); Beeghly, J.H. [Dravo Lime, Pittsburgh, PA (United States)] [Dravo Lime, Pittsburgh, PA (United States)

    1995-12-31T23:59:59.000Z

    A study has been conducted to evaluate the potential of a special rubber waste, NISCO Cyclone Ash (NCA), which contains substantial calcium oxide and calcium sulfites/sulfates for solidification/stabilization (S/S) of toxic metal wastes. The mineralogical compositions of the NCA and a class ``C`` fly ash have been characterized by X-ray diffraction (XRD). Hydrated mixtures of these wastes have been examined by XRD and found to form ettringite. Low concentrations of As (15 {micro}g ml{sup {minus}1}), Ba (500 {micro}g ml{sup {minus}1}), Pb (15 {micro}g ml{sup {minus}1}), and Zn (1,000 {micro}g ml{sup {minus}1}) were added to these hydrated mixtures and found to be successfully immobilized and solidified, as determined by the Toxicity Characteristic Leaching Procedure (TCLP). In addition, the mineralogy, chemistry and leaching characteristics of these combined waste products and their interactions with toxic metals are discussed.

  16. A literature review of mixed waste components: Sensitivities and effects upon solidification/stabilization in cement-based matrices

    SciTech Connect (OSTI)

    Mattus, C.H.; Gilliam, T.M.

    1994-03-01T23:59:59.000Z

    The US DOE Oak Ridge Field Office has signed a Federal Facility Compliance Agreement (FFCA) regarding Oak Ridge Reservation (ORR) mixed wastes subject to the land disposal restriction (LDR) provisions of the Resource conservation and Recovery Act. The LDR FFCA establishes an aggressive schedule for conducting treatability studies and developing treatment methods for those ORR mixed (radioactive and hazardous) wastes listed in Appendix B to the Agreement. A development, demonstration, testing, and evaluation program has been initiated to provide those efforts necessary to identify treatment methods for all of the wastes that meet Appendix B criteria. The program has assembled project teams to address treatment development needs in a variety of areas, including that of final waste forms (i.e., stabilization/solidification processes). A literature research has been performed, with the objective of determining waste characterization needs to support cement-based waste-form development. The goal was to determine which waste species are problematic in terms of consistent production of an acceptable cement-based waste form and at what concentrations these species become intolerable. The report discusses the following: hydration mechanisms of Portland cement; mechanisms of retardation and acceleration of cement set-factors affecting the durability of waste forms; regulatory limits as they apply to mixed wastes; review of inorganic species that interfere with the development of cement-based waste forms; review of radioactive species that can be immobilized in cement-based waste forms; and review of organic species that may interfere with various waste-form properties.

  17. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L.

    1995-05-01T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  18. 2401-W Waste storage building closure plan

    SciTech Connect (OSTI)

    LUKE, S.M.

    1999-07-15T23:59:59.000Z

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

  19. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro`s Bruce nuclear generating station {open_quotes}A{close_quotes}

    SciTech Connect (OSTI)

    Day, J.E.; Baker, R.L. [ADTECHS Corporation, Herndon, VA (United States)

    1994-12-31T23:59:59.000Z

    Ontario Hydro at the Bruce Nuclear Generating Station {open_quotes}A{close_quotes} has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

  20. Spray Calciner/In-Can Melter high-level waste solidification technical manual

    SciTech Connect (OSTI)

    Larson, D.E. (ed.)

    1980-09-01T23:59:59.000Z

    This technical manual summarizes process and equipment technology developed at Pacific Northwest Laboratory over the last 20 years for vitrification of high-level liquid waste by the Spray Calciner/In-Can Melter process. Pacific Northwest Laboratory experience includes process development and demonstration in laboratory-, pilot-, and full-scale equipment using nonradioactive synthetic wastes. Also, laboratory- and pilot-scale process demonstrations have been conducted using actual high-level radioactive wastes. In the course of process development, more than 26 tonnes of borosilicate glass have been produced in 75 canisters. Four of these canisters contained radioactive waste glass. The associated process and glass chemistry is discussed. Technology areas described include calciner feed treatment and techniques, calcination, vitrification, off-gas treatment, glass containment (the canister), and waste glass chemistry. Areas of optimization and site-specific development that would be needed to adapt this base technology for specific plant application are indicated. A conceptual Spray Calciner/In-Can Melter system design and analyses are provided in the manual to assist prospective users in evaluating the process for plant application, to provide equipment design information, and to supply information for safety analyses and environmental reports. The base (generic) technology for the Spray Calciner/In-Can Melter process has been developed to a point at which it is ready for plant application.

  1. Iron-phosphate ceramics for solidification of mixed low-level waste

    DOE Patents [OSTI]

    Aloy, Albert S. (St. Petersburg, RU); Kovarskaya, Elena N. (St. Petersburg, RU); Koltsova, Tatiana I. (St. Petersburg, RU); Macheret, Yevgeny (Idaho Falls, ID); Medvedev, Pavel G. (Ozersk, RU); Todd, Terry (Aberdeen, ID)

    2000-01-01T23:59:59.000Z

    A method of immobilizing mixed low-level waste is provided which uses low cost materials and has a relatively long hardening period. The method includes: forming a mixture of iron oxide powders having ratios, in mass %, of FeO:Fe.sub.2 O.sub.3 :Fe.sub.3 O.sub.4 equal to 25-40:40-10:35-50, or weighing a definite amount of magnetite powder. Metallurgical cinder can also be used as the source of iron oxides. A solution of the orthophosphoric acid, or a solution of the orthophosphoric acid and ferric oxide, is formed and a powder phase of low-level waste and the mixture of iron oxide powders or cinder (or magnetite powder) is also formed. The acid solution is mixed with the powder phase to form a slurry with the ratio of components (mass %) of waste:iron oxide powders or magnetite:acid solution=30-60:15-10:55-30. The slurry is blended to form a homogeneous mixture which is cured at room temperature to form the final product.

  2. Toxicity mitigation and solidification of municipal solid waste incinerator fly ash using alkaline activated coal ash

    SciTech Connect (OSTI)

    Ivan Diaz-Loya, E. [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States); Allouche, Erez N., E-mail: allouche@latech.edu [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States); Eklund, Sven; Joshi, Anupam R. [Department of Chemistry, Louisiana Tech University, Ruston, LA 71272 (United States); Kupwade-Patil, Kunal [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States)

    2012-08-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer Incinerator fly ash (IFA) is added to an alkali activated coal fly ash (CFA) matrix. Black-Right-Pointing-Pointer Means of stabilizing the incinerator ash for use in construction applications. Black-Right-Pointing-Pointer Concrete made from IFA, CFA and IFA-CFA mixes was chemically characterized. Black-Right-Pointing-Pointer Environmentally friendly solution to IFA disposal by reducing its toxicity levels. - Abstract: Municipal solid waste (MSW) incineration is a common and effective practice to reduce the volume of solid waste in urban areas. However, the byproduct of this process is a fly ash (IFA), which contains large quantities of toxic contaminants. The purpose of this research study was to analyze the chemical, physical and mechanical behaviors resulting from the gradual introduction of IFA to an alkaline activated coal fly ash (CFA) matrix, as a mean of stabilizing the incinerator ash for use in industrial construction applications, where human exposure potential is limited. IFA and CFA were analyzed via X-ray fluorescence (XRF), X-ray diffraction (XRD) and Inductive coupled plasma (ICP) to obtain a full chemical analysis of the samples, its crystallographic characteristics and a detailed count of the eight heavy metals contemplated in US Title 40 of the Code of Federal Regulations (40 CFR). The particle size distribution of IFA and CFA was also recorded. EPA's Toxicity Characteristic Leaching Procedure (TCLP) was followed to monitor the leachability of the contaminants before and after the activation. Also images obtained via Scanning Electron Microscopy (SEM), before and after the activation, are presented. Concrete made from IFA, CFA and IFA-CFA mixes was subjected to a full mechanical characterization; tests include compressive strength, flexural strength, elastic modulus, Poisson's ratio and setting time. The leachable heavy metal contents (except for Se) were below the maximum allowable limits and in many cases even below the reporting limit. The leachable Chromium was reduced from 0.153 down to 0.0045 mg/L, Arsenic from 0.256 down to 0.132 mg/L, Selenium from 1.05 down to 0.29 mg/L, Silver from 0.011 down to .001 mg/L, Barium from 2.06 down to 0.314 mg/L and Mercury from 0.007 down to 0.001 mg/L. Although the leachable Cd exhibited an increase from 0.49 up to 0.805 mg/L and Pd from 0.002 up to 0.029 mg/L, these were well below the maximum limits of 1.00 and 5.00 mg/L, respectively.

  3. Sorbent Testing for the Solidification of Organic Process Waste streams from the Radiochemical Engineering Development Center at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Bickford, J.; Foote, M. [MSE Technology Applications, Inc., Montana (United States); Taylor, P. [Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

    2008-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has tasked MSE Technology Applications, Inc. (MSE) with evaluating various sorbents to solidify the radioactive liquid organic waste from the Radiochemical Engineering Development Center (REDC) at Oak Ridge National Laboratory (ORNL). REDC recovers and purifies heavy elements (berkelium, californium, einsteinium, and fermium) from irradiated targets for research and industrial applications. Both aqueous and organic waste streams are discharged from REDC. Organic waste is generated from the plutonium/uranium extraction (PUREX), Cleanex, and Pubex processes.1 The PUREX waste derives from an organic-aqueous isotope separation process for plutonium and uranium fission products, the Cleanex waste derives from the removal of fission products and other impurities from the americium/curium product, and the Pubex waste is derived from the separation process of plutonium from dissolved targets. An aqueous waste stream is also produced from these separation processes. MSE has been tasked to test a grouting formula for the aqueous waste stream that includes specially formulated radioactive shielding materials developed by Science and Technology Applications, LLC. This paper will focus on the sorbent testing work. Based on work performed at Savannah River Site (SRS) (Refs. 1, 2), ORNL tested and evaluated three sorbents capable of solidifying the PUREX, Pubex, and Cleanex waste streams and a composite of the three organic waste streams: Imbiber Beads{sup R} IMB230301 (Imbiber Beads), Nochar A610 Petro Bond, and Petroset II Granular{sup TM} (Petroset II-G). Surrogates of the PUREX, Pubex, Cleanex, and a composite organic waste were used for the bench-scale testing. Recommendations resulting from the ORNL testing included follow-on testing by MSE for two of the three sorbents: Nochar Petro Bond and Petroset II-G. MSE recommended that another clay sorbent, Organoclay BM-QT-199, be added to the test sequence. The sorbent/surrogate combinations were tested at bench scale, 19-liter (L) [5-gallon (gal)] bucket scale, and 208-L (55-gal) drum scale. The testing performed by MSE will help ORNL select the right solidification materials and wasteform generation methods for the design of a new treatment facility. The results could also be used to help demonstrate that ORNL could meet the waste acceptance criteria for the ultimate disposal site for the waste-forms. The organics will be solidified as transuranic waste for disposal at the Waste Isolation Pilot Plant, and the aqueous waste stream will be grouted and disposed of at the Nevada Test Site as low-level waste if real waste testing indicates similar results to the surrogate testing. The objective of this work was to identify a sorbent capable of solidifying PUREX, Pubex, and Cleanex organic wastes individually and a composite of the three organic waste streams. The sorbent and surrogate combinations must also be compatible with processing equipment and maintain stability under a variety of conditions that could occur during storage/shipment of the solidified wastes. (authors)

  4. SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

    SciTech Connect (OSTI)

    CRAWFORD TW

    2008-07-17T23:59:59.000Z

    This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

  5. Waste Technology Engineering Laboratory (324 building)

    SciTech Connect (OSTI)

    Kammenzind, D.E.

    1997-05-27T23:59:59.000Z

    The 324 Facility Standards/Requirements Identification Document (S/RID) is comprised of twenty functional areas. Two of the twenty functional areas (Decontamination and Decommissioning and Environmental Restoration) were determined as nonapplicable functional areas and one functional area (Research and Development and Experimental Activities) was determined applicable, however, requirements are found in other functional areas and will not be duplicated. Each functional area follows as a separate chapter, either containing the S/RID or a justification for nonapplicability. The twenty functional areas listed below follow as chapters: 1. Management Systems; 2. Quality Assurance; 3. Configuration Management; 4. Training and Qualification; 5. Emergency Management; 6. Safeguards and Security; 7. Engineering Program; 8. Construction; 9. Operations; 10. Maintenance; 11. Radiation Protection; 12. Fire Protection; 13. Packaging and Transportation; 14. Environmental Restoration; 15. Decontamination and Decommissioning; 16. Waste Management; 17. Research and Development and Experimental Activities; 18. Nuclear Safety; 19. Occupational Safety and Health; 20. Environmental Protection.

  6. Sorbent Testing For Solidification of Process Waste streams from the Radiochemical Engineering Development Center at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Bickford, J. [MSE Technology Applications, Inc., MT (United States); Taylor, P. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2007-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) tasked MSE Technology Applications, Inc. (MSE) to evaluate sorbents identified by Oak Ridge National Laboratory (ORNL) to solidify the radioactive liquid organic waste from the Radiochemical Engineering Development Center (REDC) at ORNL. REDC recovers and purifies heavy elements (berkelium, californium, einsteinium, and fermium) from irradiated targets for research and industrial applications. Both organic and aqueous waste streams are discharged from REDC. The organic waste is generated from the plutonium/uranium extraction (Purex), Cleanex, and Pubex processes. The Purex waste derives from an organic-aqueous isotope separation process for plutonium and uranium fission products, the Cleanex waste derives from the removal of fission products and other impurities from the americium/curium product, and the Pubex waste is derived from the separation process of plutonium from dissolved targets. MSE had also been tasked to test a grouting formula for the aqueous waste stream that includes radioactive shielding material. The aqueous waste is a mixture of the raffinate streams from the various extraction processes plus the caustic solution that is used to dissolve the aluminum cladding from the irradiated targets. (authors)

  7. Solidification Tests Conducted on Transuranic Mixed Oil Waste (TRUM) at the Rocky Flats Environmental Technology Site (RFETS)

    SciTech Connect (OSTI)

    Brunkow, W. G.; Campbell, D.; Geimer, R.; Gilbreath, C.; Rivera, M.

    2002-02-25T23:59:59.000Z

    Rocky Flats Environmental Technology Site (RFETS) near Golden, Colorado is the first major nuclear weapons site within the DOE complex that has been declared a full closure site. RFETS has been given the challenge of closing the site by 2006. Key to meeting this challenge is the removal of all waste from the site followed by site restoration. Crucial to meeting this challenge is Kaiser-Hill's (RFETS Operating Contractor) ability to dispose of significant quantities of ''orphan'' wastes. Orphan wastes are those with no current disposition for treatment or disposal. Once such waste stream, generically referred to as Transuranic oils, poses a significant threat to meeting the closure schedule. Historically, this waste stream, which consist of a variety of oil contaminated with a range of organic solvents were treated by simply mixing with Environstone. This treatment method rendered a solidified waste form, but unfortunately not a TRUPACT-II transportable waste. So for the last ten years, RFETS has been accumulating these TRU oils while searching for a non-controversial treatment option.

  8. THE NOCHAR{reg_sign} TECHNOLOGY DEPLOYMENT PROGRAM, PROVIDING A PROVEN METHOD WORLDWIDE FOR WASTE SOLIDIFICATION AND STABILIZATION

    SciTech Connect (OSTI)

    Brunkow, W. G.; Govers, R.; Pietsch, C.; Kelley, D.; Krause, D.

    2002-02-25T23:59:59.000Z

    With the recent fall of the Soviet government and the decommissioning of defense plants in the U.S. DOE Complex, and the increasing worldwide emphasis on environmental restoration and controls, a critical need has developed for a proven ''off the shelf'' technology to deal with these enormous hazardous waste issues. While many new technologies are on the horizon and under development to handle complex waste streams, few of these offer immediate solutions. High technology polymers are an answer to present day needs that will allow immediate burial site disposal, above ground depository use for ''safe store'' applications, and stabilization and immobilization plans for safe transport or incineration at a later date.

  9. The Polymers for Liquid Radioactive Waste Solidification: a Lost Chapter in the History of Engineering or a Step Forward? - 13529

    SciTech Connect (OSTI)

    Pokhitonov, Yury [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation)] [V.G. Khlopin Radium Institute, St. Petersburg (Russian Federation); Kelley, Dennis [Pacific Nuclear Solutions, Indianapolis, Indiana (United States)] [Pacific Nuclear Solutions, Indianapolis, Indiana (United States)

    2013-07-01T23:59:59.000Z

    Ideas on the application of polymers for the liquid radioactive waste immobilization go a way back, and the first studies in the area were published 30-40 years ago. One should admit that regardless of the fairly large number of publications appeared in the past years currently the interest in this work came down greatly. It was the successful assimilation and worldwide implementation of the LRW cementation technology caused a slump in the interest in polymers. But today it's safe to say that the situation slowly changes, particularly due to the market appearance of the high-tech polymers manufactured by Nochar Company, and unique properties of these polymers gradually raise the demand in various countries. The results of multiple experiments performed with the simulated solutions have passed the comprehensive tests with actual waste. The economic effect from the implementation of the new technology is defined by the volume reduction of waste coming onto the repository, by the decline in the cost of transportation and of the repository construction on account of cutting down the construction volume. Interesting results have been obtained during the search for the technical decisions that would allow using the polymer materials in the processing technology of the industrial toxic waste. One more promising area of the possible application of polymers should be pointed out. It is the application of polymer materials as the assets for the emergency damage control when the advantages of the polymers become obvious. (authors)

  10. Characterization of past and present waste streams from the 325 Radiochemistry Building

    SciTech Connect (OSTI)

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

    1993-12-01T23:59:59.000Z

    The purpose of this report is to characterize, as far as possible, the solid waste generated by the 325 Radiochemistry Building since its construction in 1953. Solid waste as defined in this document is any containerized or self-contained material that has been declared waste. This characterization is of particular interest in the planning of transuranic (TRU) waste retrieval operations including the Waste Receiving and Processing (WRAP) Facility. Westinghouse Hanford Company (Westinghouse Hanford) and Battelle Pacific Northwest Laboratory (PNL) activities at Building 325 have generated approximately 4.4% and 2.4%, respectively, of the total volume of TRU waste currently stored at the Hanford Site.

  11. Building of multilevel stakeholder consensus in radioactive waste repository siting

    SciTech Connect (OSTI)

    Dreimanis, A. [Radiation Safety Centre, Riga LV (Latvia)

    2007-07-01T23:59:59.000Z

    This report considers the problem of multilevel consensus building for siting and construction of shared multinational/regional repositories for radioactive waste (RW) deep disposal. In the siting of a multinational repository there appears an essential innovative component of stakeholder consensus building, namely: to reach consent - political, social, economic, ecological - among international partners, in addition to solving the whole set of intra-national consensus building items. An entire partnering country is considered as a higher-level stakeholder - the national stakeholder, represented by the national government, being faced to simultaneous seeking an upward (international) and a downward (intra-national) consensus in a psychologically stressed environment, possibly being characterized by diverse political, economic and social interests. The following theses as a possible interdisciplinary approach towards building of shared understanding and stakeholder consensus on the international scale of RW disposal are forwarded and developed: a) building of international stakeholder consensus would be promoted by activating and diversifying on the international scale multilateral interactions between intra- and international stakeholders, including web-based networks of the RW disposal site investigations and decision-making, as well as networks for international cooperation among government authorities in nuclear safety, b) gradual progress in intergovernmental consensus and reaching multilateral agreements on shared deep repositories will be the result of democratic dialogue, via observing the whole set of various interests and common resolving of emerged controversies by using advanced synergetic approaches of conflict resolution, c) cross-cultural thinking and world perception, mental flexibility, creativity and knowledge are considered as basic prerogatives for gaining a higher level of mutual understanding and consensus for seeking further consensus, for advancing the preparedness to act together, and ultimately - for achieving desired shared goals. It is proposed that self-organized social learning will make it possible to promote adequate perception of risk and prevent, by diminishing uncertainties and unknown factors, social amplification of an imagined risk, as well as to increase the trust level and facilitate more adequate equity perception. The proposed approach to the multilevel stakeholder consensus building on international scale is extrapolated to the present-day activities of siting of such near-surface RW disposal facilities which supposedly could have non-negligible trans-boundary impact. A multilevel stakeholder interaction process is considered for the case of resolving of emerged problems in site selection for the planned near-surface RW repository in vicinity of the Lithuanian-Latvian border foreseen for disposal of short lived low- and intermediate level waste arising from the decommissioning of the Ignalina Nuclear Power Plant. (authors)

  12. Press Release Von Roll Inova to build the UK's largest energy-from-waste

    E-Print Network [OSTI]

    Columbia University

    , and regenerative heat recovery is used to boost the plant's overall energy efficiency. The majority of the waste and commercial waste per year in average and generate 72 MW of electrical energy. Riverside Resource Recovery LtdPress Release Von Roll Inova to build the UK's largest energy-from-waste plant Zürich, September, 1

  13. Solidification/stabilization of simulated uranium and nickel contaminated sludges

    E-Print Network [OSTI]

    Ramabhadran, Sanjay

    1996-01-01T23:59:59.000Z

    in this research which focused on better understanding the Solidification/Stabilization (S/S) chemistry, complex waste-binder interactions, and the suitability and effectiveness of additives in the Portland cement based treatment systems. The treatability...

  14. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    SciTech Connect (OSTI)

    NONE

    1997-07-01T23:59:59.000Z

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  15. Special Analysis for the Disposal of the Consolidated Edison Uranium Solidification Project Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Management

    2013-01-31T23:59:59.000Z

    The purpose of this Special Analysis (SA) is to determine if the Oak Ridge (OR) Consolidated Edison Uranium Solidification Project (CEUSP) uranium-233 (233U) waste stream (DRTK000000050, Revision 0) is acceptable for shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The CEUSP 233U waste stream requires a special analysis because the concentrations of thorium-229 (229Th), 230Th, 232U, 233U, and 234U exceeded their NNSS Waste Acceptance Criteria action levels. The acceptability of the waste stream is evaluated by determining if performance assessment (PA) modeling provides a reasonable expectation that SLB disposal is protective of human health and the environment. The CEUSP 233U waste stream is a long-lived waste with unique radiological hazards. The SA evaluates the long-term acceptability of the CEUSP 233U waste stream for near-surface disposal as a two tier process. The first tier, which is the usual SA process, uses the approved probabilistic PA model to determine if there is a reasonable expectation that disposal of the CEUSP 233U waste stream can meet the performance objectives of U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management,” for a period of 1,000 years (y) after closure. The second tier addresses the acceptability of the OR CEUSP 233U waste stream for near-surface disposal by evaluating long-term site stability and security, by performing extended (i.e., 10,000 and 60,000 y) modeling analyses, and by evaluating the effect of containers and the depth of burial on performance. Tier I results indicate that there is a reasonable expectation of compliance with all performance objectives if the OR CEUSP 233U waste stream is disposed in the Area 5 RWMS SLB disposal units. The maximum mean and 95th percentile PA results are all less than the performance objective for 1,000 y. Monte Carlo uncertainty analysis indicates that there is a high likelihood of compliance with all performance objectives. Tier II results indicate that the long-term performance of the OR CEUSP 233U waste stream is protective of human health and the environment. The Area 5 RWMS is located in one of the least populated and most arid regions of the U.S. Site characterization data indicate that infiltration of precipitation below the plant root zone at 2.5 meters (8.2 feet) ceased 10,000 to 15,000 y ago. The site is not expected to have a groundwater pathway as long as the current arid climate persists. The national security mission of the NNSS and the location of the Area 5 RWMS within the Frenchman Flat Corrective Action Unit require that access controls and land use restrictions be maintained indefinitely. PA modeling results for 10,000 to 60,000 y also indicate that the OR CEUSP 233U waste stream is acceptable for near-surface disposal. The mean resident air pathway annual total effective dose (TED), the resident all-pathways annual TED, and the acute drilling TED are less than their performance objectives for 10,000 y after closure. The mean radon-222 (222Rn) flux density exceeds the performance objective at 4,200 y, but this is due to waste already disposed at the Area 5 RWMS and is only slightly affected by disposal of the CEUSP 233U. The peak resident all-pathways annual TED from CEUSP key radionuclides occurs at 48,000 y and is less than the 0.25 millisievert performance objective. Disposal of the OR CEUSP 233U waste stream in a typical SLB trench slightly increases PA results. Increasing the depth was found to eliminate any impacts of the OR CEUSP 233U waste stream. Containers could not be shown to have any significant impact on performance due to the long half-life of the waste stream and a lack of data for pitting corrosion rates of stainless steel in soil. The results of the SA indicate that all performance objectives can be met with disposal of the OR CEUSP 233U waste stream in the SLB units at the Area 5 RWMS. The long-term performance of the OR CEUSP 233U waste stream disposed in the near surface is protective of human health

  16. Solidification of low-volume power plant sludges. Final report

    SciTech Connect (OSTI)

    Bell, N.E.; Halverson, M.A.; Mercer, B.M.

    1981-12-01T23:59:59.000Z

    A literature review was conducted to obtain information on the status of hazardous waste solidification technology and application of this technology to low-volume power plant waste sludges. Because of scarcity of sludge composition data, anticipated major components were identified primarily by chemical reactions that are known to occur during treatment of specific wastewaters. Chemical and physical properties of these sludges were critically analyzed for compatibility with several types of commercially available solidification processes. The study pointed out the need for additional information on the nature of these sludges, especially leaching characteristics and the presence of substances that will interfere with solidification processes. Laboratory studies were recommended for evaluation of solidification process which have the greatest potential for converting hazardous low-volume sludges to non-hazardous waste forms.

  17. EA-0820: Construction of Mixed Waste Storage RCRA Facilities, Buildings 7668 and 7669, Oak Ridge, Tennessee

    Broader source: Energy.gov [DOE]

    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...

  18. 4.0 RISK FROM URANIUM MINING WASTE IN BUILDING In general, building materials contain low levels of radioactivity. For example, the range of

    E-Print Network [OSTI]

    the wastes from uranium mines have been removed from mining sites and used in local and nearby communities4.0 RISK FROM URANIUM MINING WASTE IN BUILDING MATERIALS In general, building materials contain low levels of radioactivity. For example, the range of natural uranium concentrations may average as low

  19. Method for treating materials for solidification

    DOE Patents [OSTI]

    Jantzen, Carol M. (Aiken, SC); Pickett, John B. (Aiken, SC); Martin, Hollis L. (N. Augusta, SC)

    1995-01-01T23:59:59.000Z

    A method for treating materials such as wastes for solidification to form a solid, substantially nonleachable product. Addition of reactive silica rather than ordinary silica to the material when bringing the initial molar ratio of its silica constituent to a desired ratio within a preselected range increases the solubility and retention of the materials in the solidified matrix. Materials include hazardous, radioactive, mixed, and heavy metal species. Amounts of other constituents of the material, in addition to its silica content are also added so that the molar ratio of each of these constituents is within the preselected ranges for the final solidified product. The mixture is then solidified by cement solidification or vitrification. The method can be used to treat a variety of wastes, including but not limited to spent filter aids from waste water treatment, waste sludges, combinations of spent filter aids and waste sludges, combinations of supernate and waste sludges, incinerator ash, incinerator offgas blowdown, combinations of incinerator ash and offgas blowdown, cementitious wastes and contaminated soils.

  20. SOLIDIFICATION OF THE HANFORD LAW WASTE STREAM PRODUCED AS A RESULT OF NEAR-TANK CONTINUOUS SLUDGE LEACHING AND SODIUM HYDROXIDE RECOVERY

    SciTech Connect (OSTI)

    Reigel, M.; Johnson, F.; Crawford, C.; Jantzen, C.

    2011-09-20T23:59:59.000Z

    The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge can be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems. The iron phosphate glasses tested using the product consistency test had normalized release rates lower than the waste form requirements although the CCC glasses had higher release rates than the quenched glasses. However, the waste form failed to meet the vapor hydration test criteria listed in the WTP contract. In addition, the waste loading in the phosphate glasses were not as high as other candidate waste forms. Vitrification of HLW waste as borosilicate glass is a proven process; however the HLW and LAW streams at Hanford can vary significantly from waste currently being immobilized. The ccc glasses show lower release rates for B and Na than the quenched glasses and all glasses meet the acceptance criterion of < 4 g/L. Glass samples spiked with Re{sub 2}O{sub 7} also passed the PCT test. However, further vapor hydration testing must be performed since all the samples cracked and the test could not be performed. The waste loading of the iron phosphate and borosilicate glasses are approximately 20 and 25% respectively. The steam reforming process produced the predicted waste form for both the high and low aluminate waste streams. The predicted waste loadings for the monolithic samples is approximately 39%, which is higher than the glass waste forms; however, at the time of this report, no monolithic samples were made and therefore compliance with the PA cannot be determined. The waste loading in the geopolymer is approximately 40% but can vary with the sodium hydroxide content in the waste stream. Initial geopolymer mixes revealed compressive strengths that are greater than 500 psi for the low aluminate mixes and less than 500 psi for the high aluminate mixes. Further work testing needs to be performed to formulate a geopolymer waste form made using a high aluminate salt solution. A cementitious waste form has the advantage that the process is performed at ambient conditions and is a proven process currently in use for LAW disposal. The Saltstone/Cast Stone formulated using low and high aluminate salt solutions retained at least 97% of the Re that was added to the mix as a dopant. While this data is promising, additional leaching testing must be performed to show compliance with the PA. Compressive strength tests must also be performed on the Cast Ston

  1. DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization

    SciTech Connect (OSTI)

    T.A. Lee

    2006-02-06T23:59:59.000Z

    This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.

  2. Expert System for Building TRU Waste Payloads - 13554

    SciTech Connect (OSTI)

    Bruemmer, Heather; Slater, Bryant [Information Systems Laboratories, 2235 East 25th Street, Suite 100, Idaho Falls, ID 83404 (United States)] [Information Systems Laboratories, 2235 East 25th Street, Suite 100, Idaho Falls, ID 83404 (United States)

    2013-07-01T23:59:59.000Z

    The process for grouping TRU waste drums into payloads for shipment to the Waste Isolation Pilot Plant (WIPP) for disposal is a very complex process. Transportation and regulatory requirements must be met, along with striving for the goals of shipment efficiency: maximize the number of waste drums in a shipment and minimize the use of empty drums which take up precious underground storage space. The restrictions on payloads range from weight restrictions, to limitations on flammable gas in the headspace, to minimum TRU alpha activity concentration requirements. The Overpack and Payload Assistant Tool (OPAT) has been developed as a mixed-initiative intelligent system within the WIPP Waste Data System (WDS) to guide the construction of multiple acceptable payloads. OPAT saves the user time while at the same time maximizes the efficiency of shipments for the given drum population. The tool provides the user with the flexibility to tune critical factors that guide OPAT's operation based on real-time feedback concerning the results of the execution. This feedback complements the user's external knowledge of the drum population (such as location of drums, known challenges, internal shipment goals). This work demonstrates how software can be utilized to complement the unique domain knowledge of the users. The mixed-initiative approach combines the insight and intuition of the human expert with the proficiency of automated computational algorithms. The result is the ability to thoroughly and efficiently explore the search space of possible solutions and derive the best waste management decision. (authors)

  3. Alternative configurations for the waste-handling building at the Yucca Mountain Repository

    SciTech Connect (OSTI)

    NONE

    1990-08-01T23:59:59.000Z

    Two alternative configurations of the waste-handling building have been developed for the proposed nuclear waste repository in tuff at Yucca Mountain, Nevada. One configuration is based on criteria and assumptions used in Case 2 (no monitored retrievable storage facility, no consolidation), and the other configuration is based on criteria and assumptions used in Case 5 (consolidation at the monitored retrievable storage facility) of the Monitored Retrievable Storage System Study for the Repository. Desirable waste-handling design concepts have been selected and are included in these configurations. For each configuration, general arrangement drawings, plot plans, block flow diagrams, and timeline diagrams are prepared.

  4. Vitrification and solidification remedial treatment and disposal costs

    SciTech Connect (OSTI)

    Gimpel, R.F.

    1992-03-12T23:59:59.000Z

    Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450,000 m{sup 3} of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarizes a detailed study done to: compare the economics of the solidification and vitrification processes, determine if the stigma assigned to vitrification is warranted and, determine if investing millions of dollars into vitrification development, along with solidification development, at the Fernald is warranted.

  5. Making Green Building Units By Using Some Wastes of Ceramic Industry 

    E-Print Network [OSTI]

    Abd El-Ghafour, N.G.

    2010-01-01T23:59:59.000Z

    clays show that they are highly plastic and very sensitive upon drying. Accordingly, they are continuously in need to some additives for adjusting such properties. The environmental impact of this work is producing a green building unit has a zero waste...

  6. Webinar: Make Your Building Sing!: Building-Retuning to Reduce Energy Waste

    Broader source: Energy.gov [DOE]

    Panelists: Eileen Gohr and Steve Harrison, Parameter Realty Partners; Dennis Bohlayer, Towson University; Benjamin Goldstein, U.S. Department of Energy; Lisa Shulock, Building Owners and Managers...

  7. UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation Into Solid Waste Accounting In the New Student Union Building At the

    E-Print Network [OSTI]

    Into Solid Waste Accounting In the New Student Union Building At the University of British Columbia Lucy Bai of a project/report". #12;An Investigation Into Solid Waste Accounting In the New Student Union Building Strategy, a waste accounting method is needed to measure the amount of solid waste generated in the New

  8. Seismic Vulnerability Assessment Waste Characterization Reduction and Repackaging Building, TA-50-69

    SciTech Connect (OSTI)

    M.W.Sullivan; J.Ruminer; I.Cuesta

    2003-02-02T23:59:59.000Z

    This report presents the results of the seismic structural analyses completed on the Waste Characterization Reduction and Repackaging (WCRR) Building in support of ongoing safety analyses. WCRR is designated as TA-50-69 at Los Alamos National Laboratory, Los Alamos, New Mexico. The facility has been evaluated against Department of Energy (DOE) seismic criteria for Natural Phenomena Hazards (NPH) Performance Category II (PC 2). The seismic capacities of two subsystems within the WCRR building, the material handling glove box and the lift rack immediately adjacent to the Glove Box are also documented, and the results are presented.

  9. Development of solidification technique for dredged sediments

    SciTech Connect (OSTI)

    Yamasaki, Shoichi [Aoki Marine Co., Ltd., Fukushima, Osaka (Japan); Yasui, Hiroshi [San O Co., Ltd., Kyoto (Japan); Fukue, Masaharu [Tokai Univ., Shimizu (Japan). Marine Science and Technology

    1995-12-31T23:59:59.000Z

    The sediments deposited on the bottoms of seas, lakes, and rivers can be contaminated with hazardous and toxic substances as a result of the discharge of human activities. Therefore, since the natural remediation process cannot be expected, contaminated or polluted as well as highly organic sediments must be treated as waste and be properly disposed for human health and environmental protection. One method of disposal may be to remove the sediments by dredging and to treat them with a proper technique. The main problems in the dredging method are as follows: (1) since sediments usually have very high water content, it is necessary to decrease the volume and solidify them for the next procedure, e.g., landfill; (2) the leachates from the sediments should be treated also. It is required that the water to be discharged be kept at a quality satisfying the level of standards. This paper describes an experimental study using a solidification system performed for the cleanup of the bottom of a river. To promote the solidification of the system, several agents, such as lime, cement, polymer, resin, etc., were used. The results show that these agents strongly influence the solidification characteristics of the sediments and the quality of the leachate from the sediments.

  10. Life Cycle cost Analysis of Waste Heat Operated Absorption Cooling Systems for Building HVAC Applications

    E-Print Network [OSTI]

    Saravanan, R.; Murugavel, V.

    2010-01-01T23:59:59.000Z

    effect from CO2 emission resulting from the combustion of fossil fuels in utility power plants and the use of chlorofluorocarbon refrigerants, which is currently thought to affect depletion of the ozone layer. The ban on fluorocarbon fluids has been...LIFE CYCLE COST ANALYSIS OF WASTE HEAT OPERATED ABSORPTION COOLING SYSTEMS FOR BUILDING HVAC APPLICATIONS V. Murugavel and R. Saravanan Refrigeration and Air conditioning Laboratory Department of Mechanical Engineering, Anna University...

  11. Decontamination and decommissioning assessment for the Waste Incineration Facility (Building 232-Z) Hanford Site, [Hanford], WA

    SciTech Connect (OSTI)

    Dean, L.N. [Advanced Sciences, Inc., (United States)

    1994-02-01T23:59:59.000Z

    Building 232-Z is an element of the Plutonium Finishing Plant (PFP) located in the 200 West Area of the Hanford Site. From 1961 until 1972, plutonium-bearing combustible materials were incinerated in the building. Between 1972 and 1983, following shutdown of the incinerator, the facility was used for waste segregation activities. The facility was placed in retired inactive status in 1984 and classified as a Limited Control Facility pursuant to DOE Order 5480.5, Safety of Nuclear Facilities, and 6430.1A, General Design Criteria. The current plutonium inventory within the building is estimated to be approximately 848 grams, the majority of which is retained within the process hood ventilation system. As a contaminated retired facility, Building 232-Z is included in the DOE Surplus Facility Management Program. The objective of this Decontamination and Decommissioning (D&D) assessment is to remove Building 232-Z, thereby elmininating the radiological and environmental hazards associated with the plutonium inventory within the structure. The steps to accomplish the plan objectives are: (1) identifying the locations of the most significant amounts of plutonium, (2) removing residual plutonium, (3) removing and decontaminating remaining building equipment, (4) dismantling the remaining structure, and (5) closing out the project.

  12. Development of Waste Acceptance Criteria at 221-U Building: Initial Flow and Transport Scoping Calculations

    SciTech Connect (OSTI)

    Freedman, Vicky L.; Zhang, Z. F.; Keller, Jason M.; Chen, Yousu

    2007-05-30T23:59:59.000Z

    This report documents numerical flow and transport simulations performed that establish initial waste acceptance criteria for the potential waste streams that may be safely sequestered in the 221-U Building and similar canyon structures. Specifically, simulations were executed to identify the maximum loading of contaminant mass (without respect to volume) that can be emplaced within the 221-U Building with no more than 1 pCi/m2 of contaminant migrating outside the structure within a 1,000 year time period. The initial scoping simulations were executed in one dimension to assess important processes, and then two dimensions to establish waste acceptance criteria. Two monolithic conditions were assessed: (1) a grouted canyon monolith; and (2) a canyon monolith filled with sand, both assuming no cracks or fissures were present to cause preferential transport. A three-staged approach was taken to account for different processes that may impact the amount of contaminant that can be safely sequestered in canyon structure. In the first stage, flow and transport simulations established waste acceptance criteria based on a linear (Kd) isotherm approach. In the second stage, impacts on thermal loading were examined and the differences in waste acceptance criteria quantified. In the third stage of modeling, precipitation/dissolution reactions were considered on the release and transport of the contaminants, and the subsequent impact on the maximum contaminant loading. The reactive transport modeling is considered a demonstration of the reactive transport capability, and shows the importance of its use for future performance predictions once site-specific data have been obtained.

  13. Stabilization/solidification of TSCA incinerator ash

    SciTech Connect (OSTI)

    Spence, R.D.; Trotter, D.R.; Francis, C.L.; Morgan, I.L.

    1994-06-01T23:59:59.000Z

    Stabilization/solidification is a well-known waste treatment technique that utilizes different additives and processes. The Phoenix Ash Technology of the Technical Innovation Development Engineering Company is such a technique that uses Cass C fly ash and mechanical pressure to make brick waste forms out of solid wastes, such as the bottom ash from the Toxic Substances Control Act incinerator at the Oak Ridge K-25 Site. One advantage of this technique is that no volume increase over the bulk volume of the bottom ash occurs. This technique should have the same high pH stabilization for Resource Conservation and Recovery Act metals as similar techniques. Also, consolidation of the bottom ash minimizes the potential problems of material dispersion and container corrosion. The bottom ash was spiked with {sup 99}{Tc} to test the effectiveness of the bricks as a physical barrier. The {sup 99}{Tc} leachability index measured for these bricks was 6.8, typical for the pertechnetate anion in cementitious waste forms, indicating that these bricks have accessible porosity as high as that of other cementitious waste forms, despite the mechanical compression, higher waste form density, and water resistant polymer coating.

  14. Evaluation of existing Hanford buildings for the storage of solid wastes

    SciTech Connect (OSTI)

    Carlson, M.C.; Hodgson, R.D.; Sabin, J.C.

    1993-05-01T23:59:59.000Z

    Existing storage space at the Hanford Site for solid low-level mixed waste (LLMW) will be filled up by 1997. Westinghouse Hanford Company (WHC) has initiated the project funding cycle for additional storage space to assure that new facilities are available when needed. In the course of considering the funding request, the US Department of Energy (DOE) has asked WHC to identify and review any existing Hanford Site facilities that could be modified and used as an alternative to constructing the proposed W-112 Project. This report documents the results of that review. In summary, no buildings exist at the Hanford Site that can be utilized for storage of solid LLMW on a cost-effective basis when compared to new construction. The nearest approach to an economically sensible conversion would involve upgrade of 100,000 ft{sup 2} of space in the 2101-M Building in the 200 East Area. Here, modified storage space is estimated to cost about $106 per ft{sup 2} while new construction will cost about $50 per ft{sup 2}. Construction costs for the waste storage portion of the W-112 Project are comparable with W-016 Project actual costs, with escalation considered. Details of the cost evaluation for this building and for other selected candidate facilities are presented in this report. All comparisons presented address the potential decontamination and decommissioning (D&D) cost avoidances realized by using existing facilities.

  15. Preliminary Dynamic Siol-Structure-Interaction Analysis for the Waste Handling Building

    SciTech Connect (OSTI)

    G. Wagenblast

    2000-05-01T23:59:59.000Z

    The objective of this analysis package is to document a preliminary dynamic seismic evaluation of a simplified design concept of the Wade Handling Building (WHB). Preliminary seismic ground motions and soil data will be used. Loading criteria of the WHB System Design Description will be used. Detail design of structural members will not be performed.. The results of the analysis will be used to determine preliminary sizes of structural concrete and steel members and to determine whether the seismic response of the structure is within an acceptable level for future License Application design of safety related facilities. In order to complete this preliminary dynamic evaluation to meet the Site Recommendation (SR) schedule, the building configuration was ''frozen in time'' as the conceptual design existed in October 1999. Modular design features and dry or wet waste storage features were intentionally excluded from this preliminary dynamic seismic evaluation. The document was prepared in accordance with the Development Plan for the ''Preliminary/Dynamic Soil Structure Interaction Analysis for the Waste Handling Building'' (CRWMS M&O 2000b), which was completed, in accordance with AP-2.13Q, ''Technical Product Development Planning''.

  16. Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report.

    SciTech Connect (OSTI)

    Wiese, E. C.

    1998-11-23T23:59:59.000Z

    The Building 594 D&D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 {micro}Ci (175 kBq). The radionuclides of concern were Co{sup 60}, Cs{sup 137}, and Am{sup 241}. The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr).

  17. Waste properties of a strippable coating used for the TMI-2 reactor building decontamination

    SciTech Connect (OSTI)

    Dougherty, D.R.; Adams, J.W.; Barletta, R.E.

    1982-01-01T23:59:59.000Z

    Strippable coating material considered for use in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing, performed using a modified IAEA procedure, resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation of the coating did not produce any apparent physical changes in the coating to a dose of 1 x 10/sup 8/ rad, however, radiolytic gas generation of H/sub 2/, CO, and CO/sub 2/ was observed. Biodegradation testing was performed in soil samples from the Barnwell, South Carolina, and Hanford, Washington, low-level waste disposal sites. These test results indicate that strippable coating radwaste of itself will not meet the requirements for stabilized Class B waste outlined in 10 CFR 61 (proposed) and the NRC Draft Branch Technical Position on Waste Form.

  18. Influence of construction and demolition waste management on the environmental impact of buildings

    SciTech Connect (OSTI)

    Coelho, Andre [Department of Civil Engineering and Architecture, Instituto Superior Tecnico, Universidade Tecnica de Lisboa, Av. Rovisco Pais, 1049-001 Lisbon (Portugal); Brito, Jorge de, E-mail: jbrito@civil.ist.utl.pt [Department of Civil Engineering and Architecture, Instituto Superior Tecnico, Universidade Tecnica de Lisboa, Av. Rovisco Pais, 1049-001 Lisbon (Portugal)

    2012-03-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer Environmental impacts of different demolition practices. Black-Right-Pointing-Pointer 'Top-down' approach to the Life Cycle Analysis methodology. Black-Right-Pointing-Pointer Results based on real buildings measurements and demolition contractor activities. Black-Right-Pointing-Pointer Not every type of selective demolition brings about environmental benefits. - Abstract: The purpose of this study is to quantify comparable environmental impacts within a Life Cycle Analysis (LCA) perspective, for buildings in which the first (Materials) and last (End of Life) life cycle stages are adjusted to several waste/material management options. Unlike most LCAs, the approach is 'top-down' rather than 'bottom-up', which usually involves large amounts of data and the use of specific software applications. This approach is considered appropriate for a limited but expedient LCA designed to compare the environmental impacts of different life cycle options. Present results, based on real buildings measurements and demolition contractor activities, show that shallow, superficial, selective demolition may not result in reduced environmental impacts. Calculations actually show an increase (generally less than 5%) in most impact categories for the Materials and End of Life stages because of extra transportation needs. However, core material separation in demolition operations and its recycling and/or reuse does bring environmental benefits. A reduction of around 77% has been estimated in the climate change impact category, 57% in acidification potential and 81% in the summer smog impact (for the life cycle stages referred).

  19. UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation Into Composting Food Waste at the New Student Union Building

    E-Print Network [OSTI]

    Into Composting Food Waste at the New Student Union Building Peter Hua, Jordan Smith, Kelsey Zhu University Investigation Into Composting Food Waste at the New Student Union Building Peter Hua Jordan Smith Kelsey Zhu LIST OF ILLUSTRATIONS GLOSSARY LIST OF ABBREVIATIONS 1.0 INTRODUCTION 2.0 ROOFTOP COMPOSTING

  20. Scenario development for the Waste Isolation Pilot Plant: Building confidence in the assessment

    SciTech Connect (OSTI)

    Galson, D.A. [Galson Sciences Limited, (United Kingdom); Swift, P.N. [Sandia National Labs., Albuquerque, NM (United States)

    1994-03-01T23:59:59.000Z

    Scenario developments is part of the iterative performance assessment (PA) process for the Waste Isolation Pilot Plant (WIPP). Scenario development for the WIPP has been the subject of intense external review, and is certain to be the subject of continued scrutiny as the project proceeds toward regulatory compliance. The principal means of increasing confidence is this aspect of the PA will be through the use of a systematic and thorough procedure toward developing the scenarios and conceptual models on which the assessment is to be based. Early and ongoing interaction with project reviewers can assist with confidence building. Quality of argument and clarity of presentation in PA will be of key concern. Appropriate tools are required for documenting and tracking assumptions, through a single assessment phase, and between iterative assessment phases. Risks associated with future human actions are of particular concern to the WIPP project, and international consensus on the principles for incorporation of future human actions in assessments would be valuable.

  1. APPLICATION OF HIGH TECHNOLOGY POLYMERS FOR THE IMMOBILIZATION AND SOLIDIFICATION OF COMPLEX LIQUID RADWASTE TYPES

    SciTech Connect (OSTI)

    Kelley, Dennis; Brunkow, Ward; Pokhitonov, Yuri; Starchenko, Vadim

    2003-02-27T23:59:59.000Z

    The Cold War era created a massive build-up of nuclear weapon stockpiles in the former Soviet Union and the United States. The primary objective during this period was the development of nuclear technologies for weapons, space and power with lack of attention to the impact of radioactive and hazardous waste products on the environment. Effective technologies for radioactive and hazardous waste treatment and disposal were not well investigated or promoted during the arms build-up; and consequently, environmental contamination has become a major problem. These problems in Russia and the United States are well documented. Significant amounts of liquid radwaste have existed since the 1950's. The current government of the Russian Federation is addressing the issues of land remediation and permanent storage of radwaste resulting from internal and external pressures for safe cleanup and storage. The Russian government seeks new technologies from internal sources and from the West that will provide high performance, long term stability, safe for transport and for long-term storage of liquid radwaste at a reasonable economic cost. With the great diversity of liquid chemical compositions and activity levels, it is important to note that these waste products cannot be processed with commonly used methods. Different techniques and materials can be used for this problem resolution including the use of polymer materials that are capable of forming chemically stable, solidified waste products. In 2001, the V.G. Khlopin Radium Institute (St. Petersburg, Russia) and Pacific World Trade (Indianapolis, Indiana) began an extensive research and test program to determine the effectiveness and performance of high technology polymers for the immobilization and solidification of complex liquid radwaste types generated by the Ministry of Atomic Energy (Minatom), Russia, organization. The high tech polymers used in the tests were provided by Nochar, Inc. (Indianapolis, Indiana).

  2. NOCHAR Polymers: An Aqueous and Organic Liquid Solidification Process for Cadarache LOR (Liquides Organiques Radioactifs) - 13195

    SciTech Connect (OSTI)

    Vaudey, Claire-Emilie; Renou, Sebastien; Porco, Julien [AREVA CL BU, STMI ZAC de Courcelle 1 route de la Noue 91196 Gif-sur-Yvette (France)] [AREVA CL BU, STMI ZAC de Courcelle 1 route de la Noue 91196 Gif-sur-Yvette (France); Kelley, Dennis [Pacific World Trade, Inc. Hillsdale Technical Center 6970 Hillsdale Court Indianapolis, Indiana 46250 (United States)] [Pacific World Trade, Inc. Hillsdale Technical Center 6970 Hillsdale Court Indianapolis, Indiana 46250 (United States); Cochaud, Chantal [CEA Cadarache, DSN/SGTD, 13108 St Paul Lez Durance Cedex (France)] [CEA Cadarache, DSN/SGTD, 13108 St Paul Lez Durance Cedex (France); Serrano, Roger [CEA Marcoule, DPAD, BP 17171, 30207 Bagnols sur Ceze Cedex (France)] [CEA Marcoule, DPAD, BP 17171, 30207 Bagnols sur Ceze Cedex (France)

    2013-07-01T23:59:59.000Z

    To handle the Very Low Level Waste (VLLW) and the Low Level Waste (LLW) in France, two options can be considered: the incineration at CENTRACO facility and the disposal facility on ANDRA sites. The waste acceptance in these radwaste routes is dependent upon the adequacy between the waste characteristics (physical chemistry and radiological) and the radwaste route specifications. If the waste characteristics are incompatible with the radwaste route specifications (presence of significant quantities of chlorine, fluorine, organic component etc or/and high activity limits), it is necessary to find an alternative solution that consists of a waste pre-treatment process. In the context of the problematic Cadarache LOR (Liquides Organiques Radioactifs) waste streams, two radioactive scintillation cocktails have to be treated. The first one is composed of organic liquids at 13.1 % (diphenyloxazol, mesitylene, TBP, xylene) and water at 86.9 %. The second one is composed of TBP at 8.6 % and water at 91.4 %. They contain chlorine, fluorine and sulphate and have got alpha/beta/gamma spectra with mass activities equal to some kBq.g{sup -1}. Therefore, tritium is present and creates the second problematic waste stream. As a consequence, in order for disposal acceptance at the ANDRA site, it is necessary to pre-treat the waste. The NOCHAR polymers as an aqueous and organic liquid solidification process seem to be an adequate solution. Indeed, these polymers constitute an important variety of products applied to the treatment of radioactive aqueous and organic liquids (solvent, oil, solvent/oil mixing etc) and sludge through a mechanical and chemical solidification process. For Cadarache LOR, N910 and N960 respectively dedicated to the organic and aqueous liquids solidification are considered. With the N910, the organic waste solidification occurs in two steps. As the organic liquid travels moves through the polymer strands, the strands swell and immobilise the liquid. Then as the polymer-organic cure, over time, the polymer continues to collapse on the organic to create a permanent bond. The N960 has the ability to absorb aqueous waste up to 100 times its own weight. It creates a strong mechanical bond which permanently traps the contamination imbedded in the aqueous liquids. As a consequence, these two polymers seem to be able to constitute a suitable solidification matrix for a final acceptance in storage on ANDRA sites. In order to validate the polymers as an acceptable aqueous and organic solidification process for Cadarache LOR, some solidification tests realized with N910 and N960, have been carried out for different Waste/Polymer ratios. The determination of the best Waste/Polymer ratio and of the optimal experimental parameters has been made through an exudation test. Indeed, the process prevents leaching and it results in the absence of residual free organic or aqueous liquid which is forbidden in storage by ANDRA specifications. With these test results, we generated scientific data which are fundamental to obtain an ANDRA agreement. As a conclusion, the aim of this study is to demonstrate that the solidification by polymers can constitute a pre-treatment solution for Cadarache LOR and more generally, for various organic and mixed organic/aqueous waste which can not be directly acceptable at CENTRACO facility or at ANDRA storage sites. This work is, therefore, a solid background to demonstrate the feasibility of the waste pre-treatment by solidification with polymers and to encourage the development of this process. (authors)

  3. Incorporation of pollution prevention and waste minimization practices during the decommissioning of Building 310 at Argonne National Laboratory-East

    SciTech Connect (OSTI)

    Mezaraups, J. [Argonne National Lab., IL (United States); Krstich, M.A. [Environmental Management Solutions, Cincinnati, OH (United States); Yerace, P.J. [Dept. of Energy, Cincinnati, OH (United States). Fernald Field Office; Gresalfi, M.J. [Lockheed Martin, Germantown, MD (United States)

    1997-10-01T23:59:59.000Z

    The decommissioning of radiologically contaminated buildings at Department of Energy (DOE) sites provides a major opportunity to include pollution prevention and waste minimization (P2/WMin) practices to minimize waste using authorized release opportunities, and recycle and reuse (R2) activities on a complex-wide basis. The ``P2/WMin Users Guide for Decommissioning Projects`` (a.k.a. Users Guide or Guide) will be used to incorporate P2/WMin practices into the decommissioning and dismantlement (D and D) of Building 310 retention tanks at Argonne National Laboratory-East (ANL-E). The Building 310 service floor retention-tank facility contains ten isolated retention tanks that served to store excess radioactive liquids generated during process operations. The building consists of three rooms containing three tanks each and a larger room containing one tank. Due to a concern that the deteriorating facility could expose personnel working in the vicinity to radioactive contamination, a decision was made to decommission the building. The Users Guide, a document prepared under the auspices of the Office of Pollution Prevention (EM-77), details a step-by-step approach for incorporating P2/WMin options into a project`s documentation and subsequent decommissioning activities. It is a compilation of lessons learned and strategic P2/WMin initiatives from across the DOE complex. The benefits derived from using P2/WMin initiatives for the D and D of Building 310 include an accelerated decommissioning schedule, reduction in health risk, and the elimination of six release sites from the DOE EM-40 list. The benefits derived from implementation of P2/WMin initiatives into this project include cost savings, reduction in long-term liability, and deployment of technologies without impacting scope or schedule for the project.

  4. Literature review of stabilization/solidification of volatile organic compounds and the implications for Hanford grouts

    SciTech Connect (OSTI)

    Spence, R.D.; Osborne, S.C.

    1993-09-01T23:59:59.000Z

    A literature review was conducted on the stabilization/solidification of volatile organic compounds (VOCs). Based on this literature, it is likely that the limestone-containing grout will not permanently immobilize VOCs and that no presently available additives can guarantee permanent immobilization. The Westinghouse hanford company grout may be fairly effective at retarding aqueous leaching of VOCs, and commercial additives can improve this performance. Significant VOC losses do occur during stabilization/solidification, and the high temperatures of the Westinghouse Hanford Company waste and grout should exacerbate this problem. In fact, these high temperatures raise doubts about the presence of VOCs in the double-shell tanks supernates.

  5. Environmental Management Waste Management Facility Proxy Waste Lot Profile 6.999 for Building K-25 West Wing, East Tennessee Technology Park, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Rigsby V.P.

    2009-02-12T23:59:59.000Z

    In 1989, the Oak Ridge Reservation (ORR), which includes the East Tennessee Technology Park (ETTP), was placed on the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) National Priorities List. The Federal Facility Agreement (FFA) (DOE 1992), effective January 1, 1992, now governs environmental restoration activities conducted under CERCLA at the ORR. Following signing of the FFA, U.S. Department of Energy (DOE), U.S. Environmental Protection Agency (EPA), and the state of Tennessee signed the Oak Ridge Accelerated Cleanup Plan Agreement on June 18, 2002. The purpose of this agreement is to define a streamlined decision-making process to facilitate the accelerated implementation of cleanup, resolve ORR milestone issues, and establish future actions necessary to complete the accelerated cleanup plan by the end of fiscal year 2008. While the FFA continues to serve as the overall regulatory framework for remediation, the Accelerated Cleanup Plan Agreement supplements existing requirements to streamline the decision-making process. Decontamination and decommissioning (D&D) activities of Bldg. K-25, the original gaseous diffusion facility, is being conducted by Bechtel Jacobs Company LLC (BJC) on behalf of the DOE. The planned CERCLA action covering disposal of building structure and remaining components from the K-25 building is scheduled as a non-time-critical CERCLA action as part of DOE's continuous risk reduction strategy for ETTP. The K-25 building is proposed for D&D because of its poor physical condition and the expense of surveillance and maintenance activities. The K-25/K-27 D&D Project proposes to dispose of the commingled waste listed below from the K-25 west side building structure and remaining components and process gas equipment and piping at the Environmental Management Waste Management Facility (EMWMF) under waste disposal proxy lot (WPXL) 6.999: (1) Building structure (e.g. concrete floors [excluding basement slab], roofing, structural steel supports, interior walls, and exterior walls) and support system components including the recirculation cooling water (RCW); electrical; communication; fire protection; ventilation; process coolant; process lube oil; utilities such as steam, water and drain lines; (2) Process Piping; (3) Seal Exhaust Headers; (4) Seal Exhaust Traps; (5) Process Valves; (6) Differential Blind Multipliers (DBM)/Partial Blind Multipliers (PBM); and (7) Aftercoolers (also known as Intercell coolers). Converters and compressors while components of the process gas system, are not included in this commingled waste lot. On January 6, 2009, a meeting was held with EPA, TDEC, DOE and the team for the sole purpose of finalizing the objectives, format, and content of WPXL 6.999. The objective of WPXL 6.999 was to provide a crosswalk to the building structure and the PGE components profiles. This was accomplished by providing tables with references to the specific section of the individual profiles for each of the WLs. There are two building profiles and eight PGE profiles. All of the waste identified in the individual profiles will be commingled, shipped, and disposed exclusively under WPXL 6.999. The individual profiles were provided to the EPA and Tennessee Department of Environment and Conservation (TDEC) for information purposes only. This summary WPXL 6.999 will be submitted to EPA, TDEC, and DOE for review and approval. The format agreed upon by the regulators and DOE form the basis for WPXL 6.999. The agreed format is found on pages v and vi of the CONTENTS section of this profile. The disposal of this waste will be executed in accordance with the Action Memorandum for the Decontamination and Decommissioning of the K-25 and K-27 Buildings, East Tennessee Technology Park, Oak Ridge, Tennessee (DOE 2002), Removal Action Work Plan for the K-25 and K-27 Buildings, Process Equipment Removal and Demolition, K-25/K-27 Project, East Tennessee Technology Park, Oak Ridge, Tennessee (DOE 2008a); Waste Handling Plan for Demolition of the K-25 and K-27 Bui

  6. Nuclear waste management. Quarterly progress report, January-March 1980

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-06-01T23:59:59.000Z

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  7. Sulfur Polymer Stabilization/Solidification Treatability Study of Mercury Contaminated Soil from the Y-12 Site

    SciTech Connect (OSTI)

    Kalb P.; Milian, L.; Yim, S. P.

    2012-11-30T23:59:59.000Z

    As a result of past operations, the Department of Energy’s (DOE) Oak Ridge Y-12 National Security Complex (Y-12 Plant) has extensive mercury-contamination in building structures, soils, storm sewer sediments, and stream sediments, which are a source of pollution to the local ecosystem. Because of mercury’s toxicity and potential impacts on human health and the environment, DOE continues to investigate and implement projects to support the remediation of the Y-12 site.URS and #9122;CH2M Oak Ridge LLC (UCOR) under its prime contract with DOE has cleanup responsibilities on the DOE Oak Ridge Reservation and is investigating potential mercury-contaminated soil treatment technologies through an agreement with Babcock and Wilcox (B and W) Y-12, the Y-12 operating contractor to DOE. As part of its investigations, UCOR has subcontracted with Brookhaven National Laboratory (BNL) to conduct laboratory-scale studies evaluating the applicability of the Sulfur Polymer Stabilization/Solidification (SPSS) process using surrogate and actual mixed waste Y-12 soils containing mercury (Hg) at 135, 2,000, and 10,000 ppm.SPSS uses a thermoplastic sulfur binder to convert Hg to stable mercury sulfide (HgS) and solidifies the chemically stable product in a monolithic solid final waste form to reduce dispersion and permeability. Formulations containing 40 – 60 dry wt% Y-12 soil were fabricated and samples were prepared in triplicate for Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP) testing by an independent laboratory. Those containing 50 and 60 wt% soil easily met the study criteria for maximum allowable Hg concentrations (47 and 1 ppb, respectively compared with the TCLP limit of 200 ppb Hg). The lowest waste loading of 40 wt% yielded TCLP Hg concentrations slightly higher (240 ppb) than the allowable limit. Since the Y-12 soil tended to form clumps, the improved leaching at higher waste loadings was probably due to reduction in particle size from friction of the soil mixing, which creates more surface area for chemical conversion. This was corroborated by the fact that the same waste loading pre-treated by ball milling to reduce particle size prior to SPSS processing yielded TCLP concentrations almost 30 times lower, and at 8.5 ppb Hg was well below EPA limits. Pre-treatment by ball milling also allowed a reduction in the time required for stabilization, thus potentially reducing total process times by 30%.Additional performance testing was conducted including measurement of compressive strength to confirm mechanical integrity and immersion testing to determine the potential impacts of storage or disposal under saturated conditions. For both surrogate and actual Y-12 treated soils, waste form compressive strengths ranged between 2,300 and 6,500 psi, indicating very strong mechanical integrity (a minimum of greater than 40 times greater than the NRC guidance for low-level radioactive waste). In general, compressive strength increases with waste loading as the soil acts as an aggregate in the sulfur concrete waste forms. No statistically significant loss in strength was recorded for the 30 and 40 wt% surrogate waste samples and only a minor reduction in strength was measured for the 43 wt% waste forms. The 30 wt% Y-12 soil did not show a significant loss in strength but the 50 wt% samples were severely degraded in immersion due to swelling of the clay soil. The impact on Hg leaching, if any, was not determined.

  8. Development of Stable Solidification Method for Insoluble Ferrocyanides-13170

    SciTech Connect (OSTI)

    Ikarashi, Yuki; Masud, Rana Syed; Mimura, Hitoshi [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aramaki-Aza-Aoba6-6-01-2, Sendai, 980-8579 (Japan)] [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aramaki-Aza-Aoba6-6-01-2, Sendai, 980-8579 (Japan); Ishizaki, Eiji; Matsukura, Minoru [UNION SHOWA K.K. 17-20, Mita 2-chome, Minato-ku, Tokyo 108-0073 (Japan)] [UNION SHOWA K.K. 17-20, Mita 2-chome, Minato-ku, Tokyo 108-0073 (Japan)

    2013-07-01T23:59:59.000Z

    The development of stable solidification method of insoluble ferrocyanides sludge is an important subject for the safety decontamination in Fukushima NPP-1. By using the excellent immobilizing properties of zeolites such as gas trapping ability and self-sintering properties, the stable solidification of insoluble ferrocyanides was accomplished. The immobilization ratio of Cs for K{sub 2}[CoFe(CN){sub 6}].nH{sub 2}O saturated with Cs{sup +} ions (Cs{sub 2}[CoFe(CN){sub 6}].nH{sub 2}O) was estimated to be less than 0.1% above 1,000 deg. C; the adsorbed Cs{sup +} ions are completely volatilized. In contrast, the novel stable solid form was produced by the press-sintering of the mixture of Cs{sub 2}[CoFe(CN){sub 6}].nH{sub 2}O and zeolites at higher temperature of 1,000 deg. C and 1,100 deg. C; Cs volatilization and cyanide release were completely depressed. The immobilization ratio of Cs, under the mixing conditions of Cs{sub 2}[CoFe(CN){sub 6}].nH{sub 2}O:CP= 1:1 and calcining temperature: 1,000 deg. C, was estimated to be nearly 100%. As for the kinds of zeolites, natural mordenite (NM), clinoptilolite (CP) and Chabazite tended to have higher immobilization ratio compared to zeolite A. This may be due to the difference in the phase transformation between natural zeolites and synthetic zeolite A. In the case of the composites (K{sub 2-X}Ni{sub X/2}[NiFe(CN){sub 6}].nH{sub 2}O loaded natural mordenite), relatively high immobilization ratio of Cs was also obtained. This method using zeolite matrices can be applied to the stable solidification of the solid wastes of insoluble ferrocyanides sludge. (authors)

  9. Waste Treatment Plant Overview

    Office of Environmental Management (EM)

    contracted Bechtel National, Inc., to design and build the world's largest radioactive waste treatment plant. The Waste Treatment and Immobilization Plant (WTP), also known as the...

  10. CHANGES IN SOLIDIFICATION MODE, AND THE MEASUREMENT OF COOLING RATES FOLLOWING SOLIDIFICATION DURING ARC WELDING

    E-Print Network [OSTI]

    Cambridge, University of

    SOLIDIFICATION DURING ARC WELDING 2.1 INTRODUCTION The solidification process in a weld pool has been shown to have a considerable in- fluence upon the properties of the resultant weld. It influences elements, and hence the homogeneity of the weld. Previous work on the cooling behaviour of welds (Garland

  11. Recent technologies and processes for enhanced safety in bitumen or cement solidification of Li/ml radwaste

    SciTech Connect (OSTI)

    Tchemitcheff, F.

    1993-12-31T23:59:59.000Z

    SGN has more than 20 years of experience in the treatment of low and medium level radioactive wastes. SGN industrialized two major types of radwaste processes: bituminization and cement solidification. The R&D work on these two processes is discussed.

  12. MULTISCALE MODELING OF SOLIDIFICATION OF MULTI-COMPONENT ALLOYS

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    MULTISCALE MODELING OF SOLIDIFICATION OF MULTI-COMPONENT ALLOYS A Dissertation Presented;MULTISCALE MODELING OF SOLIDIFICATION OF MULTI-COMPONENT ALLOYS Lijian Tan, Ph.D. Cornell University 2007-dimensional dendrite growth of pure material and alloys, eutectic and peritectic solidification, convection effects

  13. Book Reviews Solidification and Crystallization. Dieter M.

    E-Print Network [OSTI]

    Regel, Liya L.

    , grain refine- ment by inoculation, ultrasound Doppler velocimetry, laser welding, arc melting, laser of 32 papers selected from 96 abstracts submitted for a symposium on solidification at the 2003 EUROMAT phase diagrams, dendrite deforma- tion caused by shear stress of the convecting melt, grain

  14. Remaining Sites Verification Package for the 1607-F7, 141-M Building Septic Tank, Waste Site Reclassification Form 2006-040

    SciTech Connect (OSTI)

    L. M. Dittmer

    2006-10-19T23:59:59.000Z

    The 1607-F7, 141-M Building Septic Tank waste site was a septic tank and drain field that received sanitary sewage from the former 141-M Building. Remedial action was performed in August and November 2005. The results of verification sampling demonstrate that residual contaminant concentrations support future unrestricted land uses that can be represented by a rural-residential scenario. These results also show that residual concentrations support unrestricted future use of shallow zone soil and that contaminant levels remaining in the soil are protective of groundwater and the Columbia River.

  15. Waste Description Pounds Reduced,

    E-Print Network [OSTI]

    -labeled oligonucleotides Waste minimization 3,144 Radiological waste (396 ft3 ); Mixed waste (35 gallons); Hazardous Waste of radioactivity, thus avoiding radiological waste generation. This process won a 2008 DOE P2 Star Award environmentally friendly manor. BNL pays shipping fees to the recycling facility. Building demolition recycling

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

    SciTech Connect (OSTI)

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

    1994-02-01T23:59:59.000Z

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

  17. Building condition monitoring

    E-Print Network [OSTI]

    Samouhos, Stephen V. (Stephen Vincent), 1982-

    2010-01-01T23:59:59.000Z

    The building sector of the United States currently consumes over 40% of the United States primary energy supply. Estimates suggest that between 5 and 30% of any building's annual energy consumption is unknowingly wasted ...

  18. Microstructural Development during Solidification of Stainless Steel Alloys

    E-Print Network [OSTI]

    Eagar, Thomas W.

    for each process and an even wider range of cooling rates for different pro- cessing techniques solidification processing techniques, resulting in microstructures that are far from equilib- rium. The cooling solidification, and by parametric variations within each of these techniques. One variable that has been used

  19. Secondary Waste Cast Stone Waste Form Qualification Testing Plan

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Serne, R. Jeffrey

    2012-09-26T23:59:59.000Z

    The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

  20. Determining the leaching characteristics of solidified/stabilized wastes using constant pH leaching tests

    E-Print Network [OSTI]

    Sofjan, Indratjahja

    1995-01-01T23:59:59.000Z

    Solidification/Stabilization treatment using Portland cement is an established procedure in the management of hazardous wastes. The technology is relatively simple, cheap, and highly reliable in prohibiting the migration of hazardous contaminants...

  1. Utilizing New Binder Materials for Green Building has Zero Waste by Recycling Slag and Sewage Sludge Ash 

    E-Print Network [OSTI]

    Zeedan, S. R.

    2010-01-01T23:59:59.000Z

    binding material to save energy and to produce new innovative zero materials waste . The current research aims to investigate new binder materials as alternative of Portland cement. Alkali activated slag (AAS) blended with sewage sludge ash (SSA...

  2. Stabilization of high and low solids Consolidated Incinerator Facility (CIF) waste with super cement

    SciTech Connect (OSTI)

    Walker, B.W.

    2000-01-11T23:59:59.000Z

    This report details solidification activities using selected Mixed Waste Focus Area technologies with the High and Low Solid waste streams. Ceramicrete and Super Cement technologies were chosen as the best possible replacement solidification candidates for the waste streams generated by the SRS incinerator from a list of several suggested Mixed Waste Focus Area technologies. These technologies were tested, evaluated, and compared to the current Portland cement technology being employed. Recommendation of a technology for replacement depends on waste form performance, process flexibility, process complexity, and cost of equipment and/or raw materials.

  3. Independent Oversight Review, Savannah River Site- August 2011

    Broader source: Energy.gov [DOE]

    Review of Commercial Grade Dedication Plans for the Safety Instrumented System at the Savannah River Site Waste Solidification Building Project

  4. Independent Oversight Review, Savannah River Site- July 2011

    Broader source: Energy.gov [DOE]

    Review of Electrical System Configuration Management and Design Change Control at the Savannah River Site, Waste Solidification Building Project

  5. Characterization of Transport and Solidification in the Metal Recycling Processes

    SciTech Connect (OSTI)

    M. A. Ebadian; R. C. Xin; Z. F. Dong

    1997-08-06T23:59:59.000Z

    The characterization of the transport and solidification of metal in the melting and casting processes is significant for the optimization of the radioactively contaminated metal recycling and refining processes. . In this research project, the transport process in the melting and solidification of metal was numerically predicted, and the microstructure and radionuclide distribution have been characterized by scanning electron microscope/electron diffractive X-ray (SEWEDX) analysis using cesium chloride (CSC1) as the radionuclide surrogate. In the melting and solidification process, a resistance furnace whose heating and cooling rates are program- controlled in the helium atmosphere was used. The characterization procedures included weighing, melting and solidification, weighing after solidification, sample preparation, and SEM/EDX analysis. This analytical methodology can be used to characterize metal recycling and refining products in order to evaluate the performance of the recycling process. The data obtained provide much valuable information that is necessary for the enhancement of radioactive contaminated metal decontamination and recycling technologies. The numerical method for the prediction of the melting and solidification process can be implemented in the control and monitoring system-of the melting and casting process in radioactive contaminated metal recycling. The use of radionuclide surrogates instead of real radionuclides enables the research to be performed without causing harmfid effects on people or the community. This characterization process has been conducted at the Hemispheric Center for Environmental Technology (HCET) at Florida International University since October 1995. Tests have been conducted on aluminum (Al) and copper (Cu) using cesium chloride (CSCI) as a radionuclide surrogate, and information regarding the radionuclide transfer and distribution in melting and solidification process has been obtained. The numerical simulation of the solidification of molten metal has been very successful for aluminium; however, a stability problem in the simulation of iron/steel solidification poses a challenge. Thus, additional development is needed to simulate the radionuclide transfer and distribution behaviors in the melting and casting processes. This project was initially based on a two-year plan. However, due to technical and financial difficulties, the project ended in FY96. The work which has been accomplished in the first year includes the characterization of radionuclide transfer and distribution in the melting-solidification process and the numerical simulation of metal solidification. The Argon-arc melting method was tested for the melting of copper and steel materials. Five tests were performed to characterize the transfer and distribution of radionuclides in the aluminiurn and copper melting/solidification process using CSC1 as radionuclide surrogates. The numerical simulation of molten aluminium and steel solidification process was performed. Different boundary conditions were applied in the simulations.

  6. Nochar Petrobond{reg_sign} Absorbent Polymer Tritiated Oil Solidification. Innovative Technology Summary Report

    SciTech Connect (OSTI)

    None

    2001-09-01T23:59:59.000Z

    NOCHAR is a high technology polymer solidifying agent that can provide a simple and effective disposal method for tritiated oil. The NOCHAR agent will absorb oil with no mixing or required mixing equipment, and with a combination or 'formula' of high tech polymers can be specifically designed to address the characteristics of waste oil as it exists at a given site. The NOCHAR Petro Bond product can be effectively used for free liquid control in storage, transport, and disposal of radioactive and RCRA defined waste oils. Petro Bond Polymer Crystals are non-toxic, non-biodegradable and incinerable to less than 0.02% ash with an absorbent capacity of up to 15:1 (oil to solidification agent ratio by weight).

  7. Grout and glass performance in support of stabilization/solidification of ORNL tank sludges

    SciTech Connect (OSTI)

    Spence, R.D.; Mattus, C.H.; Mattus, A.J.

    1998-09-01T23:59:59.000Z

    Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) and Bethel Valley Evaporator Storage Tanks (BVEST) pending treatment for disposal. In addition, some sludges and supernatants also requiring treatment remain in two inactive tank systems: the gunite and associated tanks (GAAT) and the old hydrofracture (OHF) tank. The waste consists of two phases: sludge and supernatant. The sludges contain a high amount of radioactivity, and some are classified as TRU sludges. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough to be defined as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste. Grouting and vitrification are currently two likely stabilization/solidification alternatives for mixed wastes. Grouting has been used to stabilize/solidify hazardous and low-level radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and has been under development recently as an alternative disposal technology for mixed waste. The objective of this project is to define an envelope, or operating window, for grout and glass formulations for ORNL tank sludges. Formulations will be defined for the average composition of each of the major tank farms (BVEST/MVST, GAAT, and OHF) and for an overall average composition of all tank farms. This objective is to be accomplished using surrogates of the tank sludges with hot testing of actual tank sludges to check the efficacy of the surrogates.

  8. SOLIDIFICATION FRONTS AND SOLUTE TRAPPING IN A BINARY ALLOY

    E-Print Network [OSTI]

    Fife, Paul

    , Israel and PAUL C. FIFE , Mathematics Department, University of Utah, Salt Lake City, Utah 84112, USA­9703483. 1 #12;1 Introduction During the process of solidification of molten binary alloys

  9. HAZARDOUS WASTE LABEL DEPAUL UNIVERSITY

    E-Print Network [OSTI]

    Schaefer, Marcus

    - Hazardous Ignitable Reactive Toxic Oxidizer Other ( explain ) Generator Building Dept. HAZARDOUS WASTE LABEL: Generator Building Dept. Please fill out the hazardous waste label on line and download labels on to a plainHAZARDOUS WASTE LABEL DEPAUL UNIVERSITY ENVIRONMENTAL HEALTH & SAFETY 5-4170 Corrosive Non

  10. Weld solidification cracking in 304 to 204L stainless steel

    SciTech Connect (OSTI)

    Hochanadel, Patrick W [Los Alamos National Laboratory; Lienert, Thomas J [Los Alamos National Laboratory; Martinez, Jesse N [Los Alamos National Laboratory; Johnson, Matthew Q [Los Alamos National Laboratory

    2010-09-15T23:59:59.000Z

    A series of annulus welds were made between 304 and 304L stainless steel coaxial tubes using both pulsed laser beam welding (LBW) and pulsed gas tungsten arc welding (GTAW). In this application, a change in process from pulsed LBW to pulsed gas tungsten arc welding was proposed to limit the possibility of weld solidification cracking since weldability diagrams developed for GTAW display a greater range of compositions that are not crack susceptible relative to those developed for pulsed LBW. Contrary to the predictions of the GTAW weldability diagram, cracking was found.This result was rationalized in terms of the more rapid solidification rate of the pulsed gas tungsten arc welds. In addition, for the pulsed LBW conditions, the material compositions were predicted to be, by themselves, 'weldable' according to the pulsed LBW weldability diagram. However, the composition range along the tie line connecting the two compositions passed through the crack susceptible range. Microstructurally, the primary solidification mode (PSM) of the material processed with higher power LBW was determined to be austenite (A), while solidification mode of the materials processed with lower power LBW apparently exhibited a dual PSM of both austenite (A) and ferrite-austenite (FA) within the same weld. The materials processed by pulsed GTAW showed mostly primary austenite solidification, with some regions of either primary austenite-second phase ferrite (AF) solidification or primary ferrite-second phase austenite (FA) solidification. This work demonstrates that variations in crack susceptibility may be realized when welding different heats of 'weldable' materials together, and that slight variations in processing can also contribute to crack susceptibility.

  11. Weld solidification cracking in 304 to 304L stainless steel

    SciTech Connect (OSTI)

    Hochanadel, Patrick W [Los Alamos National Laboratory; Lienert, Thomas J [Los Alamos National Laboratory; Martinez, Jesse N [Los Alamos National Laboratory; Martinez, Raymond J [Los Alamos National Laboratory; Johnson, Matthew Q [Los Alamos National Laboratory

    2010-01-01T23:59:59.000Z

    A series of annulus welds were made between 304 and 304L stainless steel coaxial tubes using both pulsed laser beam welding (LBW) and pulsed gas tungsten arc welding (GTAW). In this application, a change in process from pulsed LBW to pulsed gas tungsten arc welding was proposed to limit the possibility of weld solidification cracking since weldability diagrams developed for GTAW display a greater range of compositions that are not crack susceptible relative to those developed for pulsed LBW. Contrary to the predictions of the GTAW weldability diagram, cracking was found. This result was rationalized in terms of the more rapid solidification rate of the pulsed gas tungsten arc welds. In addition, for the pulsed LBW conditions, the material compositions were predicted to be, by themselves, 'weldable' according to the pulsed LBW weldability diagram. However, the composition range along the tie line connecting the two compositions passed through the crack susceptible range. Microstructurally, the primary solidification mode (PSM) of the material processed with higher power LBW was determined to be austenite (A), while solidification mode of the materials processed with lower power LBW apparently exhibited a dual PSM of both austenite (A) and ferrite-austenite (FA) within the same weld. The materials processed by pulsed GT A W showed mostly primary austenite solidification, with some regions of either primary austenite-second phase ferrite (AF) solidification or primary ferrite-second phase austenite (FA) solidification. This work demonstrates that variations in crack susceptibility may be realized when welding different heats of 'weldable' materials together, and that slight variations in processing can also contribute to crack susceptibility.

  12. Waste Management Facilities Cost Information Report

    SciTech Connect (OSTI)

    Feizollahi, F.; Shropshire, D.

    1992-10-01T23:59:59.000Z

    The Waste Management Facility Cost Information (WMFCI) Report, commissioned by the US Department of Energy (DOE), develops planning life-cycle cost (PLCC) estimates for treatment, storage, and disposal facilities. This report contains PLCC estimates versus capacity for 26 different facility cost modules. A procedure to guide DOE and its contractor personnel in the use of estimating data is also provided. Estimates in the report apply to five distinctive waste streams: low-level waste, low-level mixed waste, alpha contaminated low-level waste, alpha contaminated low-level mixed waste, and transuranic waste. The report addresses five different treatment types: incineration, metal/melting and recovery, shredder/compaction, solidification, and vitrification. Data in this report allows the user to develop PLCC estimates for various waste management options.

  13. Building a World of Difference

    Broader source: Energy.gov [DOE]

    Waste?to?Energy Roadmapping Workshop Building a World of Difference Presentation by Patricia Scanlan, Director of Residuals Treatment Technologies, Black & Veatch

  14. Feasibility of using reject fly ash in cement-based stabilization/solidification processes

    SciTech Connect (OSTI)

    Poon, C.S.; Qiao, X.C.; Cheeseman, C.R.; Lin, Z.S. [Hong Kong Polytechnic University, Kowloon (China). Dept. of Civil & Structural Engineering

    2006-01-15T23:59:59.000Z

    Stabilization/solidification (s/s) has been routinely used for the final treatment of hazardous wastes prior to land disposal. These processes involve adding one or more solidifying reagents into the waste to transform it into a monolithic solid with improved structural integrity. Cement-based systems with partial replacement by pulverized fuel ash (PFA) have been widely used to minimize leaching of contaminants from hazardous wastes. The finer fraction of PFA ({lt}45 {mu} m, fine fly ash, MA), produced by passing the raw ash through a classifying process is commonly used in s/s processes. Low-grade fly ash is rejected (rFA) from the ash classifying process, and is largely unused due to high carbon content and large particle size but represents a significant proportion of PFA. This paper presents experimental results of a study that has assessed the feasibility of using rFA in the cement-based s/s of a synthetic heavy metal waste. Results were compared to mixes containing fFA. The strength results show that cement-based waste forms with rFA replacement are suitable for disposal at landfill and that the addition of heavy metal sludge can increase the degree of hydration of fly ash and decrease the porosity of samples. Adding Ca(OH){sub 2} and flue gas desulphurization sludge reduces the retarding effect of heavy metals on strength development. The results of the Toxicity Characteristic Leaching Procedure and Dynamic Leach Test show that rFA can be used in cement-based s/s wastes without compromising performance of the product.

  15. Relationship of Surplus Plutonium Disposition Alternatives and...

    National Nuclear Security Administration (NNSA)

    Valley Authority WIPP Waste Isolation Pilot Plant WSB Waste Solidification Building Note: Appendices C and D provide details about the analyses of human health effects...

  16. Statement of work for conceptual design of solidified high-level waste interim storage system project (phase I)

    SciTech Connect (OSTI)

    Calmus, R.B., Westinghouse Hanford

    1996-12-17T23:59:59.000Z

    The U.S. Department of Energy (DOE) has embarked upon a course to acquire Hanford Site tank waste treatment and immobilization services using privatized facilities. This plan contains a two phased approach. Phase I is a ``proof-of-principle/commercial demonstration- scale`` effort and Phase II is a full-scale production effort. In accordance with the planned approach, interim storage (IS) and disposal of various products from privatized facilities are to be DOE furnished. The path forward adopted for Phase I solidification HLW IS entails use of Vaults 2 and 3 in the Spent Nuclear Fuel Canister Storage Building, to be located in the Hanford Site 200 East Area. This Statement of Work describes the work scope to be performed by the Architect-Engineer to prepare a conceptual design for the solidified HLW IS System.

  17. Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

    SciTech Connect (OSTI)

    Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States)] [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)] [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

    2013-07-01T23:59:59.000Z

    The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

  18. Hanford Site Secondary Waste Roadmap

    SciTech Connect (OSTI)

    Westsik, Joseph H.

    2009-01-29T23:59:59.000Z

    Summary The U.S. Department of Energy (DOE) is making plans to dispose of 54 million gallons of radioactive tank wastes at the Hanford Site near Richland, Washington. The high-level wastes and low-activity wastes will be vitrified and placed in permanent disposal sites. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents, and these need to be processed and disposed of also. The Department of Energy Office of Waste Processing sponsored a meeting to develop a roadmap to outline the steps necessary to design the secondary waste forms. Representatives from DOE, the U.S. Environmental Protection Agency, the Washington State Department of Ecology, the Oregon Department of Energy, Nuclear Regulatory Commission, technical experts from the DOE national laboratories, academia, and private consultants convened in Richland, Washington, during the week of July 21-23, 2008, to participate in a workshop to identify the risks and uncertainties associated with the treatment and disposal of the secondary wastes and to develop a roadmap for addressing those risks and uncertainties. This report describes the results of the roadmap meeting in Richland. Processing of the tank wastes will generate secondary wastes, including routine solid wastes and liquid process effluents. The secondary waste roadmap workshop focused on the waste streams that contained the largest fractions of the 129I and 99Tc that the Integrated Disposal Facility risk assessment analyses were showing to have the largest contribution to the estimated IDF disposal impacts to groundwater. Thus, the roadmapping effort was to focus on the scrubber/off-gas treatment liquids with 99Tc to be sent to the Effluent Treatment Facility for treatment and solidification and the silver mordenite and carbon beds with the captured 129I to be packaged and sent to the IDF. At the highest level, the secondary waste roadmap includes elements addressing regulatory and performance requirements, waste composition, preliminary waste form screening, waste form development, process design and support, and validation. The regulatory and performance requirements activity will provide the secondary waste-form performance requirements. The waste-composition activity will provide workable ranges of secondary waste compositions and formulations for simulants and surrogates. Preliminary waste form screening will identify candidate waste forms for immobilizing the secondary wastes. The waste form development activity will mature the waste forms, leading to a selected waste form(s) with a defensible understanding of the long-term release rate and input into the critical decision process for a secondary waste treatment process/facility. The process and design support activity will provide a reliable process flowsheet and input to support a robust facility design. The validation effort will confirm that the selected waste form meets regulatory requirements. The final outcome of the implementation of the secondary waste roadmap is the compliant, effective, timely, and cost-effective disposal of the secondary wastes. The work necessary to address the programmatic, regulatory, and technical risks and uncertainties identified through the Secondary Waste Roadmap Workshop are assembled into several program needs elements. Programmatic/Regulatory needs include: • Select and deploy Hanford tank waste supplemental treatment technology • Provide treatment capability for secondary waste streams from tank waste treatment • Develop consensus on secondary waste form acceptance. Technology needs include: • Define secondary waste composition ranges and uncertainties • Identify and develop waste forms for secondary waste immobilization and disposal • Develop test methods to characterize secondary waste form performance. Details for each of these program elements are provided.

  19. Solidification at the High and Low Rate Extreme

    SciTech Connect (OSTI)

    Halim Meco

    2004-12-19T23:59:59.000Z

    The microstructures formed upon solidification are strongly influenced by the imposed growth rates on an alloy system. Depending on the characteristics of the solidification process, a wide range of growth rates is accessible. The prevailing solidification mechanisms, and thus the final microstructure of the alloy, are governed by these imposed growth rates. At the high rate extreme, for instance, one can have access to novel microstructures that are unattainable at low growth rates. While the low growth rates can be utilized for the study of the intrinsic growth behavior of a certain phase growing from the melt. Although the length scales associated with certain processes, such as capillarity, and the diffusion of heat and solute, are different at low and high rate extremes, the phenomena that govern the selection of a certain microstructural length scale or a growth mode are the same. Consequently, one can analyze the solidification phenomena at both high and low rates by using the same governing principles. In this study, we examined the microstructural control at both low and high extremes. For the high rate extreme, the formation of crystalline products and factors that control the microstructure during rapid solidification by free-jet melt spinning are examined in Fe-Si-B system. Particular attention was given to the behavior of the melt pool at different quench-wheel speeds. Since the solidification process takes place within the melt-pool that forms on the rotating quench-wheel, we examined the influence of melt-pool dynamics on nucleation and growth of crystalline solidification products and glass formation. High-speed imaging of the melt-pool, analysis of ribbon microstructure, and measurement of ribbon geometry and surface character all indicate upper and lower limits for melt-spinning rates for which nucleation can be avoided, and fully amorphous ribbons can be achieved. Comparison of the relevant time scales reveals that surface-controlled melt-pool oscillation may be the dominant factor governing the onset of unsteady thermal conditions accompanied by varying amounts of crystalline nucleation observed near the lower limit. At high quench-wheel velocities, the influence of these oscillations is minimal due to very short melt-pool residence times. However, microstructural evidence suggests that the entrapment of gas pockets at the wheel-metal interface plays a critical role in establishing the upper rate limit. An observed transition in wheel-side surface character with increasing melt-spinning rate supports this conclusion.

  20. Y-12 Plant decontamination and decommissioning Technology Logic Diagram for Building 9201-4: Volume 3, Technology evaluation data sheets: Part B, Decontamination; robotics/automation; waste management

    SciTech Connect (OSTI)

    NONE

    1994-09-01T23:59:59.000Z

    This volume consists of the Technology Logic Diagrams (TLDs) for the decontamination, robotics/automation, and waste management areas.

  1. Engineering Building a better

    E-Print Network [OSTI]

    Barthelat, Francois

    and modern buildings laid out around an oasis of green space. Much like the multicultural population restoration, waste reduction, climate change impact mitigation and air pollution abatement. + 5 COURSESCivil Engineering future Building a better #12;McGill University Montreal, with a population

  2. Analysis of weld solidification cracking in cast nickel aluminide alloys

    SciTech Connect (OSTI)

    Santella, M.L.; Feng, Z. [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.

    1995-09-01T23:59:59.000Z

    A study of the response of several nickel aluminide alloys to SigmaJig testing was done to examine their weld solidification cracking behavior and the effect of Zr concentration. The alloys were based on the Ni-8Al-7.7Cr-1.5Mo-0.003B wt% composition and contained Zr concentrations of 3, 4.5, and 6 wt%. Vacuum induction melted ingots with a diameter of 2.7 in and weight about 18 lb were made of each alloy, and were used to make 2 x 2 x 0.030 in specimens for the Sigmajig test. The gas tungsten arc welds were made at travel speeds of 10, 20, and 30 ipm with heat inputs of 2--2.5 kJ/in. When an arc was established before traveling onto the test specimen centerline cracking was always observed. This problem was overcome by initiating the arc directly on the specimens. Using this approach, the 3 wt% Zr alloy withstood an applied stress of 24 ksi without cracking at a welding speed of 10 ipm. This alloy cracked at 4 ksi applied at 20 ipm, and with no applied load at 30 ipm. Only limited testing was done on the remaining alloys, but the results indicate that resistance to solidification cracking increases with Zr concentration. Zirconium has limited solid solubility and segregates strongly to interdendritic regions during solidification where it forms a Ni solid solution-Ni{sub 5}Zr eutectic. The volume fraction of the eutectic increases with Zr concentration. The solidification cracking behavior of these alloys is consistent with phenomenological theory, and is discussed in this context. The results from SigmaJig testing are analyzed using finite element modeling of the development of mechanical strains during solidification of welds. Experimental data from the test substantially agree with recent analysis results.

  3. Performance Metrics for Commercial Buildings

    SciTech Connect (OSTI)

    Fowler, Kimberly M.; Wang, Na; Romero, Rachel L.; Deru, Michael P.

    2010-09-30T23:59:59.000Z

    Commercial building owners and operators have requested a standard set of key performance metrics to provide a systematic way to evaluate the performance of their buildings. The performance metrics included in this document provide standard metrics for the energy, water, operations and maintenance, indoor environmental quality, purchasing, waste and recycling and transportation impact of their building. The metrics can be used for comparative performance analysis between existing buildings and industry standards to clarify the impact of sustainably designed and operated buildings.

  4. Nuclear waste management. Quarterly progress report, April-June 1980

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-09-01T23:59:59.000Z

    The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

  5. Nuclear waste management. Quarterly progress report, October through December 1980

    SciTech Connect (OSTI)

    Chikalla, T.D.; Powell, J.A. (comps.)

    1981-03-01T23:59:59.000Z

    Progress reports and summaries are presented under the following headings: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of radionuclides in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; high level waste form preparation; development of backfill material; development of structural engineered barriers; ONWI disposal charge analysis; spent fuel and fuel component integrity program; analysis of spent fuel policy implementation; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; revegetation of inactive uranium tailing sites; verification instrument development.

  6. West Valley demonstration project: alternative processes for solidifying the high-level wastes

    SciTech Connect (OSTI)

    Holton, L.K.; Larson, D.E.; Partain, W.L.; Treat, R.L.

    1981-10-01T23:59:59.000Z

    In 1980, the US Department of Energy (DOE) established the West Valley Solidification Project as the result of legislation passed by the US Congress. The purpose of this project was to carry out a high level nuclear waste management demonstration project at the Western New York Nuclear Service Center in West Valley, New York. The DOE authorized the Pacific Northwest Laboratory (PNL), which is operated by Battelle Memorial Institute, to assess alternative processes for treatment and solidification of the WNYNSC high-level wastes. The Process Alternatives Study is the suject of this report. Two pretreatment approaches and several waste form processes were selected for evaluation in this study. The two waste treatment approaches were the salt/sludge separation process and the combined waste process. Both terminal and interim waste form processes were studied.

  7. Secondary Waste Form Development and Optimization—Cast Stone

    SciTech Connect (OSTI)

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

    2011-07-14T23:59:59.000Z

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

  8. Ecologically friendly buildings The new de Picciotto building for scientific and technical research which will be

    E-Print Network [OSTI]

    Shapiro, Ehud

    with vegetation which offers the pro's to isolate the roof from heat, they absorb moisture and reduce temperatures for the separation of waste at source in the kitchens and other central areas in the building. Electric hand dryers in the building. #12;Separation of Biodegradable Waste The separation of biodegradable waste started in January

  9. Chemical Waste in Satellite Campuses or Buildings and Non-Laboratories on Campus -This checklist is for managing Chemical Waste in all satellite campuses such as but not limited

    E-Print Network [OSTI]

    Subramanian, Venkat

    . This checklist is also for off campus clinics and physician offices. The checklist should also be used for non a yellow Hazardous Waste label to the waste container at time of first filling and complete the label. o Ensure full chemical name is printed on the label (no acronyms). o Ensure location and Manager Name

  10. Waste products in highway construction. Final report

    SciTech Connect (OSTI)

    Han, C.

    1993-04-01T23:59:59.000Z

    The report presents waste materials and products for highway construction. The general legislation, local liability, and research projects related to waste materials are outlined. The waste materials and products presented include waste paving materials, industrial ash materials, taconite tailing materials, waste tire rubber materials and products, building rubble materials, incinerator ash products and materials, waste glass materials, waste shingle materials and products, waste plastics products, and slag materials. For each waste category, the legislation and restrictions, material properties, construction and application, field performance, and recycling at the end of service life if available are discussed.

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

    SciTech Connect (OSTI)

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

    2011-09-12T23:59:59.000Z

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

  12. Operating data to In-Tank Solidification (ITS)-2 for January 1 to October 10, 1974

    SciTech Connect (OSTI)

    Reich, F.R., Westinghouse Hanford

    1996-08-02T23:59:59.000Z

    Data sheets containing date, time, feet above bottom,temperature, comments. Operating data to In-Tank Solidification (ITS)-2 for January 1 to October 10, 1974.

  13. Radioactive Waste Radioactive Waste

    E-Print Network [OSTI]

    Slatton, Clint

    form · Separate liquid from solid · Radionuclide · Separate all but H3/C14 #12;#12;Radioactive Waste;Radioactive Waste H3/C14 solids Type B (non-incinerable) metal glass hazardous materials #12;#12;Radioactive#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to

  14. Building stability through decentralization : the environmental, economic, and ethical argument for informal sector collection and decentralized waste processing in urban India

    E-Print Network [OSTI]

    Howe, Caroline Louise

    2014-01-01T23:59:59.000Z

    Rapid population growth, urbanization and increasing affluence have led to increases in consumption and waste generation in all Indian cities. The current system, a mix of informal recyclables collection and centralized ...

  15. Porous Alumina Silicate Matrix Gubka for Solidification of {sup 137}Cs Strip Product

    SciTech Connect (OSTI)

    Aloy, Albert; Strelnikov, Alexander; Essimantovskiy, Vyacheslav ['V.G. Khlopin Radium Institute', 2nd Murinskiy str., 28, Saint Petersburg, 194021 (Russian Federation)

    2007-07-01T23:59:59.000Z

    Separated liquid high-level radioactive waste (HLW) fractions, in particular, about 100 liters of a {sup 137}Cs strip product with activity up to {approx} 100 Ci/l (3.7 TBq/l) have been produced during the development and testing of partitioning technology and temporarily stored at V.G. Khlopin Radium Institute (KRI) (Saint-Petersburg, Russia). The bench-scale experimental unit designed for operation in the hot cell was developed for {sup 137}Cs strip product solidification using an alumina silicate porous inorganic material (PIM) called Gubka. Conditions of saturation, drying, and calcinations of the salts into Gubka pores were optimized, and the operations under a remote control regime were executed during tests using a simulated strip product doped with {sup 137}Cs. The volume reduction coefficients were equal by a factor of 3.2-3.9 and a {sup 137}Cs discharge into an off-gas system was not detected. {sup 137}Cs leach rates from Gubka blocks after calcination at 800 deg. C were 1.0-1.5.10{sup -3} g/m{sup 2}.per day. (authors)

  16. Control of macrosegregation during the solidification of alloys using magnetic fields

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    Control of macrosegregation during the solidification of alloys using magnetic fields Deep Samanta and Aerospace Engineering, 188 Frank H.T. Rhodes Hall, Cornell University, Ithaca, NY 14853-3801, USA Abstract Numerical modeling of convection damping and macrosegregation suppression during solidification of alloys

  17. MCWASP, Modeling of Casting, Welding and Advanced Solidification Processes XI TMS (The Minerals, Metals & Materials Society),

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    OF THE SOLIDIFICATION OF ALUMINUM ALLOYS ON MOLDS OF UNEVEN TOPOGRAPHIES. Nicholas Zabaras1 , Deep Samanta1 , Lijian Tan of Mechanical and Aerospace Engineering, Cornell University; Ithaca, NY 14853-3801, USA Keywords: Solidification, Aluminum alloys, Cast surfaces, Mold topography, Inverse segregation, Imperfect contact, Air-gaps, Solid

  18. A level set simulation of dendritic solidification of multi-component alloys

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    A level set simulation of dendritic solidification of multi-component alloys Lijian Tan, Nicholas Zabaras 1 Materials Process Design and Control Laboratory, Sibley School of Mechanical and Aerospace microstructure evolution in the solidification of multi-component alloys. Phase boundaries are tracked by solving

  19. A thermomechanical study of the effects of mold topography on the solidification of Aluminum alloys

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    mold surfaces for the control of cast surface morphologies. Keywords: Solidification; Aluminum alloys1 A thermomechanical study of the effects of mold topography on the solidification of Aluminum alloys Lijian Tana and Nicholas Zabarasa a Materials Process Design and Control Laboratory, Sibley School

  20. Solidification of Aluminum Alloys Edited by TMS (The Minerals, Metals & Materials Society), 2004

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    Solidification of Aluminum Alloys Edited by TMS (The Minerals, Metals & Materials Society), 2004 Modeling the Effects of Mold Topography on Aluminum Cast Surfaces Lijian Tan1 , Nicholas Zabaras1 1 14853, USA Keywords: Aluminum Solidification; Mold topography; Cast Surfaces Abstract The air

  1. An integrated model for the post-solidification shape and grain morphology of fusion welds

    E-Print Network [OSTI]

    Kidess, Anton; Duggan, Gregory; Browne, David J; Kenjereš, Saša; Richardson, Ian; Kleijn, Chris R

    2015-01-01T23:59:59.000Z

    Through an integrated macroscale/mesoscale computational model, we investigate the developing shape and grain morphology during the melting and solidification of a weld. In addition to macroscale surface tension driven fluid flow and heat transfer, we predict the solidification progression using a mesoscale model accounting for realistic solidification kinetics, rather than quasi-equilibrium thermodynamics. The tight coupling between the macroscale and the mesoscale distinguishes our results from previously published studies. The inclusion of Marangoni driven fluid flow and heat transfer, both during heating and cooling, was found to be crucial for accurately predicting both weld pool shape and grain morphology. However, if only the shape of the weld pool is of interest, a thermodynamic quasi-equilibrium solidification model, neglecting solidification kinetics, was found to suffice when including fluid flow and heat transfer. We demonstrate that the addition of a sufficient concentration of approximately 1 $\\...

  2. High-Level Waste Melter Study Report

    SciTech Connect (OSTI)

    Perez, Joseph M.; Bickford, Dennis F.; Day, Delbert E.; Kim, Dong-Sang; Lambert, Steven L.; Marra, Sharon L.; Peeler, David K.; Strachan, Denis M.; Triplett, Mark B.; Vienna, John D.; Wittman, Richard S.

    2001-07-13T23:59:59.000Z

    At the Hanford Site in Richland, Washington, the path to site cleanup involves vitrification of the majority of the wastes that currently reside in large underground tanks. A Joule-heated glass melter is the equipment of choice for vitrifying the high-level fraction of these wastes. Even though this technology has general national and international acceptance, opportunities may exist to improve or change the technology to reduce the enormous cost of accomplishing the mission of site cleanup. Consequently, the U.S. Department of Energy requested the staff of the Tanks Focus Area to review immobilization technologies, waste forms, and modifications to requirements for solidification of the high-level waste fraction at Hanford to determine what aspects could affect cost reductions with reasonable long-term risk. The results of this study are summarized in this report.

  3. EA-0874: Low-level Waste Drum Staging Building at Weapons Engineering Tritium Facility, TA-16 Los Alamos National Laboratory, Los Alamos, New Mexico

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of a proposal to place a 3 meter (m) by 4.5 m prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium...

  4. Review of Electrical System Configuration Management and Design...

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

    Office of Health, Safety and Security (HSS), conducted an independent review of selected engineering processes for the Waste Solidification Building (WSB) safety significant...

  5. SPD SEIS References for Appendix H | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Analysis for Construction and Operation of a Waste Solidification Building at the Savannah River Site, DOEEIS-0283-SA-2, Savannah River Operations Office, Aiken, South...

  6. BETTER BUILDINGS ALLIANCE

    Office of Energy Efficiency and Renewable Energy (EERE)

    Commercial buildings—our offices, schools, hospitals, restaurants, hotels and stores—consume nearly 20% of all energy used in the United States. We spend more than $200 billion each year to power our country's commercial buildings. Unfortunately, much of this energy and money is wasted; a typical commercial building could save 20% on its energy bills simply by commissioning existing systems so they operate as intended. Energy efficiency is a cost-effective way to save money, support job growth, reduce pollution, and improve competitiveness.

  7. WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION

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

    Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1...

  8. Building Stones

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    3). Photographs by the author. Building Stones, Harrell, UEEOxford Short Citation: Harrell, 2012, Building Stones. UEE.Harrell, James A. , 2012, Building Stones. In Willeke

  9. Directional solidification of the alumina-zirconia ceramic eutectic system

    SciTech Connect (OSTI)

    Boldt, C.

    1994-07-27T23:59:59.000Z

    It is possible to produce alumina-zirconia ceramic samples through existing solidification techniques. The resulting microstructures typically consist of rods of zirconia in an alumina matrix, although a lamellar structure has been noted in some cases. In nearly all cases, colony growth was present which may possibly result from grain size, repeated nucleation events, and lamellar oscillations. In the same vein, it appears that the amount of impurities within the system might be the underlying cause for the colony growth. Colony growth was diminished through impurity control as the higher purity samples exhibited colony free behavior. In addition to colony formations, faceted alumina dendrites or nonfaceted zirconia dendrites may result in the ceramic if the sample is solidified out of the coupled zone. In all cases, for larger-sized Bridgman samples, a lower limit in the eutectic spacing was noted. The solidification model which includes the kinetic effect has been developed, although the effect appears to be negligible under present experimental conditions. A spacing limit might also occur due to the result of heat flow problems. Heat flow out of the ceramic is difficult to control, often causing radial and not axial growth. This behavior is exaggerated in the presence of impurities. Thus, higher purity powders should always be used. Higher purity samples, in addition to yielding a more microstructurally uniform ceramic, also showed increased directionality. In the future, the kinetic model needs to be examined in more detail, and further research needs to be accomplished in the area of molten ceramics. Once better system constants are in place, the kinetic model will give a better indication of the behavior in the alumina-zirconia system.

  10. DNAPL source control by reductive dechlorination with iron-based degradative solidification/stabilization 

    E-Print Network [OSTI]

    Do, Si Hyun

    2009-05-15T23:59:59.000Z

    Iron-based degradative solidification/stabilization (Fe(II)-DS/S) is a treatment method that could be economically applied to smaller DNAPL-contaminated sites and to those sites with impermeable soils. Reductive dechlorination is achieved...

  11. A thermodynamical framework for the solidification of molten polymers and its application to fiber extrusion

    E-Print Network [OSTI]

    Kannan, Krishna

    2006-04-12T23:59:59.000Z

    A thermodynamical framework is presented that describes the solidification of molten polymers to an amorphous as well as to a semicrystalline solid-like state. This framework fits into a general structure developed for materials undergoing a large...

  12. FORESTRY BUILDING: BUILDING EMERGENCY PLAN

    E-Print Network [OSTI]

    FORESTRY BUILDING: BUILDING EMERGENCY PLAN Date Adopted: August 18, 2009 Date Revised June 17, 2013 Prepared By: Diana Evans and Jennifer Meyer #12;PURDUE UNIVERSITY BUILDING EMERGENCY PLAN VERSION 3 2 Table Suspension or Campus Closure SECTION 3: BUILDING INFORMATION 3.1 Building Deputy/Alternate Building Deputy

  13. BUILDING NAME HEYDON-LAURENCE BUILDING

    E-Print Network [OSTI]

    Viglas, Anastasios

    BUILDING NAME HEYDON-LAURENCE BUILDING PHARMACY AND BANK BUILDING JOHN WOOLEY BUILDING OLD TEARCHER'S BUILDING PHYSICS BUILDING BAXTER'S LODGE INSTITUTE BUILDING CONSERVATION WORKS R.D.WATT BUILDING MACLEAY BUILDING THE QUARANGLE BADHAM BUILDING J.D. STEWART BUILDING BLACKBURN BUILDING MADSEN BUILDING STORE

  14. A study of immobilization of four heavy metals by solidification/stabilization with portland cement

    E-Print Network [OSTI]

    Trussell, Susan A

    1994-01-01T23:59:59.000Z

    A STUDY OF IMMOBILIZATION OF FOUR HEAUY METALS BY SOLIDIFICATION/STABILIZATION WITH PORTLAND CEMEhK A Thesis by SUSAN ANN TRUSSELL Submitted to Texas AdcM University in partial fulfillment of the requirements for the degree of MASTER... of Immobilization of Four Heavy Metals By Solidification/Stabilization with Portland Cement. (May 1994) Susan Trussell, B. S. , Baylor University; M. A. , Texas ARM University Chair of Advisory Committee: Dr. Bill Batchelor Immobilization of four heavy metals...

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

    SciTech Connect (OSTI)

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

    2010-01-30T23:59:59.000Z

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

  16. 4 Questions for a Better Buildings Case Competition Judge: Marc...

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

    CHALLENGE Register for Better Buildings Challenge webinars on multifamily housing, the public sector, and K-12 and higher education Infographic: Leaders Cutting Energy Waste in...

  17. Building America Expert Meeting: Multifamily Hydronic and Steam...

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

    controls and distribution retrofit options for hot water and steam space heating systems in multi-family buildings with the goals of reducing energy waste and...

  18. Software for fault detection in HVAC systems in commercial buildings

    E-Print Network [OSTI]

    Deshmukh, Suhrid Avinash

    2014-01-01T23:59:59.000Z

    The building sector of the United States currently consumes over 41% of the United States primary energy supply. Estimates suggest that between 5 and 30% of any building's annual energy consumption is unknowingly wasted ...

  19. The necessity for permanence : making a nuclear waste storage facility

    E-Print Network [OSTI]

    Stupay, Robert Irving

    1991-01-01T23:59:59.000Z

    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 ...

  20. Solidification/stabilization of simulated uranium and nickel contaminated sludges 

    E-Print Network [OSTI]

    Ramabhadran, Sanjay

    1996-01-01T23:59:59.000Z

    Research missions in nuclear energy conducted by the U.S. Department of Energy facilities have generated large volumes of mixed wastes with hazardous and radioactive components. Uranium and nickel are the primary contaminants of concern...

  1. Berkeley Lab to Help Build Straw Bale Building

    SciTech Connect (OSTI)

    Worsham, S.A.; Van Mechelen, G.

    1998-12-01T23:59:59.000Z

    The Shorebird Environmental Learning Center (SELC) is a new straw bale building that will showcase current and future technologies and techniques that will reduce the environmental impacts of building construction and operations. The building will also serve as a living laboratory to test systems and monitor their performance. The project will be the model for a building process that stops using our precious resources and reduces waste pollution. The rice straw that will be used for the bale construction is generally waste material that is typically burned--millions of tons of it a year--especially in California's San Joaquin Valley. Buildings have significant impacts on the overall environment. Building operations, including lighting, heating, and cooling, consume about 30% of the energy used in the United States. Building construction and the processes into making building materials consume an additional 8% of total energy. Construction also accounts for 39% of wood consumed in the U S, while 25% of solid waste volume is construction and demolition (C &D) debris. The SELC will incorporate a variety of materials and techniques that will address these and other issues, while providing a model of environmentally considered design for Bay Area residents and builders. Environmental considerations include energy use in construction and operations, selection of materials, waste minimization, and indoor air quality. We have developed five major environmental goals for this project: (1) Minimize energy use in construction and operations; (2) Employ material sources that are renewable, salvaged, recycled, and/or recyclable; (3) Increase building lifespan with durable materials and designs that permit flexibility and modification with minimal demolition; (4) Reduce and strive to eliminate construction debris; and (5) Avoid products that create toxic pollutants and make a healthy indoor environment.

  2. Remaining Sites Verification Package for the 100-F-44:2, Discovery Pipeline Near 108-F Building, Waste Site Reclassification Form 2007-006

    SciTech Connect (OSTI)

    J. M. Capron

    2008-05-30T23:59:59.000Z

    The 100-F-44:2 waste site is a steel pipeline that was discovered in a junction box during confirmatory sampling of the 100-F-26:4 pipeline from December 2004 through January 2005. The 100-F-44:2 pipeline feeds into the 100-F-26:4 subsite vitrified clay pipe (VCP) process sewer pipeline from the 108-F Biology Laboratory at the junction box. In accordance with this evaluation, the confirmatory sampling results support a reclassification of this site to No Action. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. The results of confirmatory sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

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

    SciTech Connect (OSTI)

    Serne, R. Jeffrey; Westsik, Joseph H.

    2011-09-05T23:59:59.000Z

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

  4. Around Buildings

    E-Print Network [OSTI]

    Treib, Marc

    1987-01-01T23:59:59.000Z

    Around Buildings W h y startw i t h buildings and w o r k o u t wa r d ? For one, buildings are difficult t o a v o i d these

  5. BUILDING INSPECTION Building, Infrastructure, Transportation

    E-Print Network [OSTI]

    BUILDING INSPECTION Building, Infrastructure, Transportation City of Redwood City 1017 Middlefield Sacramento, Ca 95814-5514 Re: Green Building Ordinance and the Building Energy Efficiency Standards Per of Redwood City enforce the current Title 24 Building Energy Efficiency Standards as part

  6. Effect of turbulent heat transfer on continuous ingot solidification

    SciTech Connect (OSTI)

    Shyy, W.; Chen, M.H. (Univ. of Florida, Gainesville, FL (United States). Dept. of Aerospace Engineering); Pang, Y.; Wei, D.Y. (GE Aircraft Engines, Engineering Materials Technology Labs., Lynn, MA (United States)); Hunter, G.B. (GE Aircraft Engines, Engineering Materials Technology Labs., Cincinnati, OH (United States))

    1993-01-01T23:59:59.000Z

    For many continuous ingot casting processes, turbulent heat transfer in the molten pool plays a critical role which, along with buoyancy and surface tension, is responsible for the quality of the end products. Based on a modified low Reynolds number K-[epsilon] two-equation closure, accounting for the phase change and mushy zone formation, the effect of turbulent heat transfer on the solidification characteristics during titanium alloy ingot casting in an electron beam melting process is investigated. The overall heat transfer rate is enhanced by turbulent transport via two sources, one through the correlated velocity and temperature fluctuations present for both single- and multi-phase flows, and the other through the correlated velocity and release of latent heat fluctuations which are unique to the flows with phase change. The roles played by both mechanisms are identified and assessed. The present turbulence model predicts that although the mushy zone defined by the mean temperature field is generally of substantial thickness as a result of the convection effect, the actual instantaneous zone thickness varies substantially due to turbulence effect. This finding is in contrast to the traditionally held viewpoint, based on the conduction analysis, of a generally thin mushy zone. The impact of turbulent heat transfer on local dendrite formation and remelting is illustrated and the issues involved in model development highlighted.

  7. Solidification microstructures in single-crystal stainless steel melt pools

    SciTech Connect (OSTI)

    Sipf, J.B.; Boatner, L.A.; David, S.A.

    1994-03-01T23:59:59.000Z

    Development of microstructure of stationary melt pools of oriented stainless steel single crystals (70%Fe-15%Ni-15%Cr was analyzed. Stationary melt pools were formed by electron-beam and gas-tungsten-arc heating on (001), (011), and (111) oriented planes of the austenitic, fcc-alloy crystals. Characterization and analysis of resulting microstructure was carried out for each crystallographic plane and welding method. Results showed that crystallography which favors ``easy growth`` along the <100> family of directions is a controlling factor in the microstructural formation along with the melt-pool shape. The microstructure was found to depend on the melting method, since each method forms a unique melt-pool shape. These results are used in making a three-dimensional reconstruction of the microstructure for each plane and melting method employed. This investigation also suggests avenues for future research into the microstructural properties of electron-beam welds as well as providing an experimental basis for mathematical models for the prediction of solidification microstructures.

  8. NEW MEXICO ENVIRONMENT DEPARTMENT Hazardous Waste Burealt SUSANA...

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

    MEXICO ENVIRONMENT DEPARTMENT Hazardous Waste Burealt SUSANA MARTINEZ Governor 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 875056303 Phone (50S) 476-6000 Fax...

  9. Lab obtains approval to begin design on new radioactive waste...

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

    complex will include multiple staging buildings plus an operations center and a concrete pad for mobile waste characterization equipment. September 1, 2010 Los Alamos...

  10. Tank Closure and Waste Management Environmental Impact Statement...

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

    CWC's main buildings are shown in Figure 2-23, including Building 2403-WD, which has a radioactive waste storage capacity of 17,500 drums. Other structures include the...

  11. Solidification characterization of a new rapidly solidified Ni-Cr-Co based superalloy

    SciTech Connect (OSTI)

    Wu, Kai, E-mail: wk-ustb@163.com [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China)] [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China); Liu, Guoquan [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China) [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China); State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083 (China); Hu, Benfu [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China)] [School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083 (China); Li, Feng [Department of Materials Science and Metallurgy, University of Cambridge, Cambridge CB2 3QZ (United Kingdom)] [Department of Materials Science and Metallurgy, University of Cambridge, Cambridge CB2 3QZ (United Kingdom); Zhang, Yiwen [School of Metallurgical and Ecological Engineering, University of Science and Technology Beijing, Beijing 100083 (China) [School of Metallurgical and Ecological Engineering, University of Science and Technology Beijing, Beijing 100083 (China); High Temperature Materials Research Institution, CISRI, Beijing 100081 (China); Tao, Yu; Liu, Jiantao [High Temperature Materials Research Institution, CISRI, Beijing 100081 (China)] [High Temperature Materials Research Institution, CISRI, Beijing 100081 (China)

    2012-11-15T23:59:59.000Z

    The solidification characterization of a new rapidly solidified Ni-Cr-Co based superalloy prepared by plasma rotating electrode process was investigated by means of optical microscope, scanning electron microscope, and transmission electron microscope. The results show that the solidification microstructure changes from dendrites to cellular and microcrystal structures with decreasing powder size. The elements of Co, Cr, W and Ni are enriched in the dendrites, while Mo, Nb and Ti are higher in the interdendritic regions. The relationships between powder size with the average solid-liquid interface moving rate, the average interface temperature gradient and the average cooling rate are established. Microsegregation is increased with larger powder size. The geometric integrity of MC Prime type carbides in the powders changes from regular to diverse with decreasing powder size. The morphology and quantity of carbides depend on the thermal parameters and non-equilibrium solute partition coefficients during rapid solidification. - Highlights: Black-Right-Pointing-Pointer The relations of solidification thermal parameters with powder size are established. Black-Right-Pointing-Pointer The relation of non-equilibrium solute partition with powder size is investigated. Black-Right-Pointing-Pointer The solidification microstructure is related to thermal parameters. Black-Right-Pointing-Pointer The segregation behavior is linked to non-equilibrium partition coefficients. Black-Right-Pointing-Pointer The morphology and quantity of carbides depend on the above combined factors.

  12. Design/installation and structural integrity assessment of Bethel Valley low-level waste collection and transfer system upgrade for Building 3092 (Central Off-Gas Scrubber Facility) at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    This document describes and assesses planned modifications to be made to the Building 3092 Central Off-Gas Scrubber Facility of the Oak Ridge National Laboratory, Oak Ridge, Tennessee. The modifications are made in responsible to the requirements of 40CFR264 Subpart J, relating to environmental protection requirements for buried tank systems. The modifications include the provision of a new scrubber recirculation tank in a new, below ground, lines concrete vault, replacing and existing recirculation sump that does not provide double containment. A new buried, double contained pipeline is provided to permit discharge of spent scrubber recirculation fluid to the Central Waste Collection Header. The new vault, tank, and discharge line are provided with leak detection and provisions to remove accumulated liquid. New scrubber recirculation pumps, piping, and accessories are also provided. This assessment concludes that the planned modifications comply with applicable requirements of 40CFR264 Subpart J, as set forth in Appendix F to the Federal Facility Agreement, Docket No. 89-04-FF, covering the Oak Ridge Reservation.

  13. Examination of the solidification macrostructure of spheroidal and flake graphite cast irons using DAAS and ESBD

    SciTech Connect (OSTI)

    Rivera, G. [Metallurgy Division INTEMA, National University of Mar del Plata, CONICET, J. B. Justo 4302 (B7608FDQ) Mar del Plata (Argentina); Calvillo, P.R. [Department of Metallurgy and Materials Science, Ghent University (Belgium); Boeri, R. [Metallurgy Division INTEMA, National University of Mar del Plata, CONICET, J. B. Justo 4302 (B7608FDQ) Mar del Plata (Argentina)], E-mail: boeri@fi.mdp.edu.ar; Houbaert, Y. [Department of Metallurgy and Materials Science, Ghent University (Belgium); Sikora, J. [Metallurgy Division INTEMA, National University of Mar del Plata, CONICET, J. B. Justo 4302 (B7608FDQ) Mar del Plata (Argentina)], E-mail: jsikora@fi.mdp.edu.ar

    2008-09-15T23:59:59.000Z

    This investigation focuses on the study of the solidification macrostructure of sand cast flake and spheroidal graphite cast irons. The macrostructure is revealed by using a special technique developed earlier by the authors, called Direct Austempering After Solidification. The observations make use of conventional metallography and Electron Back Scattering Diffraction. The latter technique allows a more detailed observation of the morphology of the austenite grains and the microstructure of the matrix. The results of Electron Back Scattering Diffraction validate the observations made using the macrographic technique. It is verified that the solidification of both flake and spheroidal graphite cast irons is dominated by the growth of large austenite dendrites that form a grain pattern similar to that usually found in most metallic alloys.

  14. Secondary waste form testing : ceramicrete phosphate bonded ceramics.

    SciTech Connect (OSTI)

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

    2011-06-21T23:59:59.000Z

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

  15. Nuclear waste management. Quarterly progress report, January-March, 1981

    SciTech Connect (OSTI)

    Chikalla, T.D.; Powell, J.A. (comp.)

    1981-06-01T23:59:59.000Z

    Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

  16. Westinghouse Cementation Facility of Solid Waste Treatment System - 13503

    SciTech Connect (OSTI)

    Jacobs, Torsten; Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D- 22419 Hamburg (Germany)

    2013-07-01T23:59:59.000Z

    During NPP operation, several waste streams are generated, caused by different technical and physical processes. Besides others, liquid waste represents one of the major types of waste. Depending on national regulation for storage and disposal of radioactive waste, solidification can be one specific requirement. To accommodate the global request for waste treatment systems Westinghouse developed several specific treatment processes for the different types of waste. In the period of 2006 to 2008 Westinghouse awarded several contracts for the design and delivery of waste treatment systems related to the latest CPR-1000 nuclear power plants. One of these contracts contains the delivery of four Cementation Facilities for waste treatment, s.c. 'Follow on Cementations' dedicated to three locations, HongYanHe, NingDe and YangJiang, of new CPR-1000 nuclear power stations in the People's Republic of China. Previously, Westinghouse delivered a similar cementation facility to the CPR-1000 plant LingAo II, in Daya Bay, PR China. This plant already passed the hot functioning tests successfully in June 2012 and is now ready and released for regular operation. The 'Follow on plants' are designed to package three 'typical' kind of radioactive waste: evaporator concentrates, spent resins and filter cartridges. The purpose of this paper is to provide an overview on the Westinghouse experience to design and execution of cementation facilities. (authors)

  17. Building America Expert Meeting Report: Hydronic Heating in Multifamily Buildings

    SciTech Connect (OSTI)

    Dentz, J.

    2011-10-01T23:59:59.000Z

    The topic of this expert meeting was cost-effective controls and distribution retrofit options for hot water and steam space heating systems in multi-family buildings with the goals of reducing energy waste and improving occupant comfort. The U.S. Department of Energy's Building America program develops technologies with the goal of reducing energy use by 30% to 50% in residential buildings. Toward this goal, the program sponsors 'Expert Meetings' focused on specific building technology topics. The meetings are intended to sharpen Building America research priorities, create a forum for sharing information among industry leaders and build partnerships with professionals and others that can help support the program's research needs and objectives. The topic of this expert meeting was cost-effective controls and distribution retrofit options for hot water and steam space heating systems in multifamily buildings with the goals of reducing energy waste and improving occupant comfort. The objectives of the meeting were to: (1) Share knowledge and experience on new and existing solutions: what works, what doesn't and why, and what's new; (2) Understand the market barriers to currently offered solutions: what disconnects exist in the market and what is needed to overcome or bridge these gaps; and (3) Identify research needs.

  18. Beauty in Architecture: Simply a Waste

    E-Print Network [OSTI]

    McDonald, Orla

    2007-01-01T23:59:59.000Z

    This study was an exploratory investigation of beauty in architecture, through which a theory of waste predicting beauty in buildings was developed. In a series of four experiments, it was shown firstly, through an ...

  19. Modeling Building Thermal Response to HVAC Zoning Virginia Smith

    E-Print Network [OSTI]

    Whitehouse, Kamin

    . Much of this wasted energy is used to heat or cool unoccupied spaces during long periods when people HVAC systems account for 38% of building energy usage. Studies have indicated at least 5-15% waste due to unoccu- pied spaces being conditioned. Our goal is to minimize this waste by retrofitting HVAC systems

  20. INL Green Building Strategy

    SciTech Connect (OSTI)

    Jennifer Dalton

    2005-05-01T23:59:59.000Z

    Green buildings, also known as sustainable buildings, resource efficient buildings, and high performance buildings, are structures that minimize the impact on the environment by using less energy and water, reducing solid waste and pollutants, and limiting the depletion of natural resources. As Idaho National Laboratory (INL) becomes the nation’s premier nuclear energy research laboratory, the physical infrastructure will be established to help accomplish the mission. This infrastructure, particularly the buildings, should incorporate green design features in order to be environmentally responsible and reflect an image of progressiveness and innovation to the public and prospective employees. With this in mind, the recommendations described in this strategy are intended to form the INL foundation for green building standards. The recommendations in this strategy are broken down into three levels: Baseline Minimum, Leadership in Energy and Environmental Design (LEED)Certification, and Innovative. Baseline Minimum features should be included in all new occupied buildings no matter what the purpose or size. These features do not require significant research, design, or capital costs and yet they can reduce Operation and Maintenance (O&M) costs and produce more environmentally friendly buildings. LEED Certification features are more aggressive than the Baseline Minimums in that they require documentation, studies, and/or additional funding. Combined with the Baseline Minimums, many of the features in this level will need to be implemented to achieve the goal of LEED certification. LEED Silver certification should be the minimum goal for all new buildings (including office buildings, laboratories, cafeterias, and visitor centers) greater than 25,000 square feet or a total cost of $10 million. Innovative features can also contribute to LEED certification, but are less mainstream than those listed in the previous two levels. These features are identified as areas where INL can demonstrate leadership but they could require significant upfront cost, additional studies, and/or development. Appendix A includes a checklist summary of the INL Green Building Strategy that can be used as a tool during the design process when considering which green building features to include. It provides a quick reference for determining which strategies have lower or no increased capital cost, yield lower O&M costs, increase employee productivity, and contribute to LEED certification.

  1. Frederick Albert Sutton Building Quick Green Facts

    E-Print Network [OSTI]

    Feschotte, Cedric

    of the project. · Site lighting planning and carefully selected fixtures reduce light pollution. WATER EFFICIENCY. ENERGY & ATMOSPHERE · The building energy usage is reduced by 30.6% annually from efficient heating, plastic and metal will be collected for recycling from the building. · 81.9% of construction waste

  2. Tank waste remediation system dangerous waste training plan

    SciTech Connect (OSTI)

    POHTO, R.E.

    1999-05-13T23:59:59.000Z

    This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench.

  3. Building America

    SciTech Connect (OSTI)

    Brad Oberg

    2010-12-31T23:59:59.000Z

    IBACOS researched the constructability and viability issues of using high performance windows as one component of a larger approach to building houses that achieve the Building America 70% energy savings target.

  4. Building technologies

    SciTech Connect (OSTI)

    Jackson, Roderick

    2014-07-14T23:59:59.000Z

    After growing up on construction sites, Roderick Jackson is now helping to make buildings nationwide far more energy efficient.

  5. Building technologies

    ScienceCinema (OSTI)

    Jackson, Roderick

    2014-07-15T23:59:59.000Z

    After growing up on construction sites, Roderick Jackson is now helping to make buildings nationwide far more energy efficient.

  6. Beardmore Building

    High Performance Buildings Database

    Priest River, ID Originally built in 1922 by Charles Beardmore, the building housed offices, mercantile shops, a ballroom and a theater. After decades of neglect under outside ownership, Brian Runberg, an architect and great-grandson of Charles Beardmore, purchased the building in 2006 and began an extensive whole building historic restoration.

  7. Building America Residential Buildings Energy Efficiency Meeting...

    Energy Savers [EERE]

    Building America Residential Buildings Energy Efficiency Meeting: July 2010 Building America Residential Buildings Energy Efficiency Meeting: July 2010 On this page, you may link...

  8. Polyethylene encapsulatin of nitrate salt wastes: Waste form stability, process scale-up, and economics

    SciTech Connect (OSTI)

    Kalb, P.D.; Heiser, J.H. III; Colombo, P.

    1991-07-01T23:59:59.000Z

    A polyethylene encapsulation system for treatment of low-level radioactive, hazardous, and mixed wastes has been developed at Brookhaven National Laboratory. Polyethylene has several advantages compared with conventional solidification/stabilization materials such as hydraulic cements. Waste can be encapsulated with greater efficiency and with better waste form performance than is possible with hydraulic cement. The properties of polyethylene relevant to its long-term durability in storage and disposal environments are reviewed. Response to specific potential failure mechanisms including biodegradation, radiation, chemical attack, flammability, environmental stress cracking, and photodegradation are examined. These data are supported by results from extensive waste form performance testing including compressive yield strength, water immersion, thermal cycling, leachability of radioactive and hazardous species, irradiation, biodegradation, and flammability. The bench-scale process has been successfully tested for application with a number of specific problem'' waste streams. Quality assurance and performance testing of the resulting waste form confirmed scale-up feasibility. Use of this system at Rocky Flats Plant can result in over 70% fewer drums processed and shipped for disposal, compared with optimal cement formulations. Based on the current Rocky Flats production of nitrate salt per year, polyethylene encapsulation can yield an estimated annual savings between $1.5 million and $2.7 million, compared with conventional hydraulic cement systems. 72 refs., 23 figs., 16 tabs.

  9. Solidification using smoothed particle hydrodynamics Joseph J. Monaghan a,*, Herbert E. Huppert b

    E-Print Network [OSTI]

    Worster, M. Grae

    behind a relatively light residual liquid, or cooled from below leaving behind a relatively heavy liquid in geology and industry. In the former it plays a major part in the formation of mineral deposits of silica for the semi-conductor industry. The simplest of the solidification problems is the Stefan problem

  10. Modelling of Casting, Welding, and Advanced Solidification Processing XI NON-MONOTONE TEMPERATURE BOUNDARY CONDITIONS

    E-Print Network [OSTI]

    Lowengrub, John

    Modelling of Casting, Welding, and Advanced Solidification Processing XI NON-MONOTONE TEMPERATURE anisotropy, such as a needle crystal or dendrite, the interface can develop periodic non-monotone temperature in the equilibrium temperature close to the highly curved tip. This minimum results in the tip temperature itself

  11. Non-equilibrium solidification and ferrite in d-TRIP steel

    E-Print Network [OSTI]

    Cambridge, University of

    Non-equilibrium solidification and ferrite in d-TRIP steel H. L. Yi1 , S. K. Ghosh1 , W. J. Liu1, designed on the basis of equilibrium to contain substantial amounts of d-ferrite, reveal zero or much transformation of d-ferrite into austenite occurs without the required partitioning of solutes

  12. Interface Stability During Rapid Solidification of Silicon-Tin A thesis presented

    E-Print Network [OSTI]

    Interface Stability During Rapid Solidification of Silicon-Tin A thesis presented by David Eric for the experiment were silicon and silicon-on-sapphire (SOS) wafers implanted with tin. The SOS samples were also/s, the interface might undergo breakdown at 0.3 atomic percent tin, resulting in a cellular structure with a cell

  13. Reductive dechlorination of chlorinated aliphatic hydrocarbons by Fe(ii) in degradative solidification/stabilization

    E-Print Network [OSTI]

    Jung, Bahng Mi

    2007-04-25T23:59:59.000Z

    ............................................................................................7 2.1 Degradative Solidification/Stabilization...................................................7 2.2 Cement Chemistry.....................................................................................8 2.2.1 Portland Cement... of typical cements . .........................9 Table 2.2 Portland cement compound transformation................................................15 Table 2.3 The oxides, hydroxides, and oxyhydroxides of Fe.....................................16 Table 2...

  14. Immobilization of sodium nitrate waste with polymers: Topical report

    SciTech Connect (OSTI)

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

    1987-04-01T23:59:59.000Z

    This report describes the development of solidification systems for sodium nitrate waste. Sodium nitrate waste was solidified in the polymers polyethylene, polyester-styrene (PES), and water-extendible polyester-styrene (WEP). Evaluations were made of the properties of waste forms containing various amounts of sodium nitrate by leaching immersion in water, measuring compressive strengths and by the EPA Extraction Procedure. Results of the leaching test are presented as cumulative fraction leached (CFL), incremental leaching rate, and average leaching indices (LI). For waste forms containing 30 to 70 wt% sodium nitrate, the CFL ranged from 9.0 x 10/sup -3/ to 7.3 x 10/sup -1/ and the LI from 11 to 7.8. After ninety days immersion in water, the compressive strengths ranged from 720 psi to 2550 psi. The nitrate releases from these samples using the EPA Extraction Procedure were below 500 ppM. The nitrate releases from PES waste forms were similar to those from polyethylene waste forms at the same waste loadings. The compressive yield strengths, measured after ninety-day immersion in water, ranged between 2070 and 7710 psi. In the case of WEP waste forms, only 30 wt% loaded samples passed the immersion test. 23 refs., 24 figs., 12 tabs.

  15. RCRA/UST, superfund, and EPCRA hotline training module. Introduction to: Containment buildings (40 CFR parts 264/265, subpart DD) updated as of July 1995

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

    In 1992, EPA developed standards for a new hazardous waste management unit called a containment building. Containment buildings, which are essentially waste piles enclosed in a building, facilitate management of bulky materials without triggering land disposal and land disposal restrictions (LDR). This module outlines the regulatory history and purpose of containment buildings. It discusses the relationship between LDR and containment buildings, summarizes the design and operating standards applicable to containment buildings, and describes the relationship between generator accumulation standards and containment buildings.

  16. Waste incinerator to be built on campus By GAVIN WILSON

    E-Print Network [OSTI]

    Farrell, Anthony P.

    I::---- - - . . Waste incinerator to be built on campus ~~~ By GAVIN WILSON UBC hasapplied streaming of other waste products." The incinerators will be used to dispose of waste solvents and bio. "It is the sensible thing to bring these materials to UBC rather than building three incinerators

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

    E-Print Network [OSTI]

    Tsien, Roger Y.

    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

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

    E-Print Network [OSTI]

    Tsien, Roger Y.

    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

  19. System to control contamination during retrieval of buried TRU waste

    DOE Patents [OSTI]

    Menkhaus, Daniel E. (Idaho Falls, ID); Loomis, Guy G. (Idaho Falls, ID); Mullen, Carlan K. (Idaho Falls, ID); Scott, Donald W. (Idaho Falls, ID); Feldman, Edgar M. (Idaho Falls, ID); Meyer, Leroy C. (Idaho Falls, ID)

    1993-01-01T23:59:59.000Z

    A system to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

  20. System to control contamination during retrieval of buried TRU waste

    DOE Patents [OSTI]

    Menkhaus, D.E.; Loomis, G.G.; Mullen, C.K.; Scott, D.W.; Feldman, E.M.; Meyer, L.C.

    1993-04-20T23:59:59.000Z

    A system is described to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

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

    SciTech Connect (OSTI)

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

    2011-08-12T23:59:59.000Z

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

  2. Social and Economic Challenges of Implementing Sustainable Materials on Buildings in Kuwait

    E-Print Network [OSTI]

    Al-Foraih, R.; Al-Fahad, F.

    2012-01-01T23:59:59.000Z

    management and occupant cooperation. This raises challenges when requiring cooperation from building occupants and cleaning staff for the solid waste management credits which require dedication to reduce the amount of waste going to landfills and incinerating...

  3. Documentation on currently operating low-level radioactive waste treatment systems: National Low-Level Waste Management Program

    SciTech Connect (OSTI)

    Not Available

    1987-11-01T23:59:59.000Z

    In May 1985, the US Department of Energy issued a Program Research and Development Announcement requesting documentation on currently operating low-level radioactive waste treatment systems. Six grants were awarded to support that documentation. Final reports for the following grants and grantees are compiled in this document: Shredder/Compactor Report by Impell Corp., Volume Reduction and Solidification System for Low-Level Radwaste Treatment by Waste Chem Corp., Low-Level Radioactive Waste Treatment Systems in Northern Europe by Pacific Nuclear Services/Nuclear Packaging Inc., The University of Missouri Research Reactor Facility Can Melter System by the University of Missouri, Drying of Ion-Exchange Resin and Filter Media by Nuclear Packaging Inc., and Operational Experience with Selective Ion-Exchange Media in Sluiceable Pressurized Demineralizers at Nuclear Power Plants by Analytical Resources Inc. 65 refs., 4 figs., 7 tabs.

  4. Secondary Waste Form Down Selection Data Package – Ceramicrete

    SciTech Connect (OSTI)

    Cantrell, Kirk J.; Westsik, Joseph H.

    2011-08-31T23:59:59.000Z

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

  5. The Waste Isolation Pilot Plant Hazardous Waste Facility Permit...

    Office of Environmental Management (EM)

    The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan The Waste Isolation Pilot Plant Hazardous Waste Facility Permit, Waste Analysis Plan This...

  6. Building Stones

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    was no good source of local building stone, rock was usuallyrock-cut shrines and especially tombs, and these are the sources

  7. Radioactive waste management in the USSR: A review of unclassified sources. Volume 2

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01T23:59:59.000Z

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  8. Radioactive waste management in the USSR: A review of unclassified sources

    SciTech Connect (OSTI)

    Bradley, D.J.

    1991-03-01T23:59:59.000Z

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

  9. Hazardous Waste Program (Alabama)

    Broader source: Energy.gov [DOE]

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

  10. Smart Buildings for Occupiers and Facilities Suppliers Buildings and facilities are the second largest cost of an organisation after human resources, and have a large

    E-Print Network [OSTI]

    costs and improve operational efficiency o Open integration of building and resource data (energySmart Buildings for Occupiers and Facilities Suppliers Buildings and facilities are the second-system, operating environment involving all aspects of energy, waste and service systems, optimised at building

  11. Hanford Waste Transfer Planning and Control - 13465

    SciTech Connect (OSTI)

    Kirch, N.W.; Uytioco, E.M.; Jo, J. [Washington River Protection Solutions, LLC, Richland, Washington (United States)] [Washington River Protection Solutions, LLC, Richland, Washington (United States)

    2013-07-01T23:59:59.000Z

    Hanford tank waste cleanup requires efficient use of double-shell tank space to support single-shell tank retrievals and future waste feed delivery to the Waste Treatment and Immobilization Plant (WTP). Every waste transfer, including single-shell tank retrievals and evaporator campaign, is evaluated via the Waste Transfer Compatibility Program for compliance with safety basis, environmental compliance, operational limits and controls to enhance future waste treatment. Mixed radioactive and hazardous wastes are stored at the Hanford Site on an interim basis until they can be treated, as necessary, for final disposal. Implementation of the Tank Farms Waste Transfer Compatibility Program helps to ensure continued safe and prudent storage and handling of these wastes within the Tank Farms Facility. The Tank Farms Waste Transfer Compatibility Program is a Safety Management Program that is a formal process for evaluating waste transfers and chemical additions through the preparation of documented Waste Compatibility Assessments (WCA). The primary purpose of the program is to ensure that sufficient controls are in place to prevent the formation of incompatible mixtures as the result of waste transfer operations. The program defines a consistent means of evaluating compliance with certain administrative controls, safety, operational, regulatory, and programmatic criteria and specifies considerations necessary to assess waste transfers and chemical additions. Current operations are most limited by staying within compliance with the safety basis controls to prevent flammable gas build up in the tank headspace. The depth of solids, the depth of supernatant, the total waste depth and the waste temperature are monitored and controlled to stay within the Compatibility Program rules. Also, transfer planning includes a preliminary evaluation against the Compatibility Program to assure that operating plans will comply with the Waste Transfer Compatibility Program. (authors)

  12. Resource recovery potential from secondary components of segregated municipal solid wastes

    E-Print Network [OSTI]

    Columbia University

    Resource recovery potential from secondary components of segregated municipal solid wastes H. N solid wastes (MSW) . Fermentation wastes . Solid-state stratified bed (SSB) . BMP Introduction India is building up its city level solid waste management in an extensive manner. It has framed necessary rules

  13. Better Buildings

    E-Print Network [OSTI]

    Neukomm, M.

    2012-01-01T23:59:59.000Z

    efficiency as top priority energy resource Revolutionary change in market Robust energy efficiency industry Prime the market for new technology Better Buildings Challenge Goals Make commercial & industrial buildings 20% more efficient by 2020... opportunities for energy efficiency 2 Great opportunities in the residential, commercial and industrial sectors 20% + savings is average Other benefits: Jobs, Environment, Competitiveness But persistent barriers exist?? ?Energy efficiency...

  14. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    Bioelectrochemical Integration of Waste Heat Recovery, Waste-to-Energy Conversion, and Waste-to-Chemical Conversion with Industrial Gas and Chemical Manufacturing Processes...

  15. Bioelectrochemical Integration of Waste Heat Recovery, Waste...

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

    MHRC System Concept ADVANCED MANUFACTURING OFFICE Bioelectrochemical Integration of Waste Heat Recovery, Waste-to-Energy Conversion, and Waste-to-Chemical Conversion with...

  16. INL High Performance Building Strategy

    SciTech Connect (OSTI)

    Jennifer D. Morton

    2010-02-01T23:59:59.000Z

    High performance buildings, also known as sustainable buildings and green buildings, are resource efficient structures that minimize the impact on the environment by using less energy and water, reduce solid waste and pollutants, and limit the depletion of natural resources while also providing a thermally and visually comfortable working environment that increases productivity for building occupants. As Idaho National Laboratory (INL) becomes the nation’s premier nuclear energy research laboratory, the physical infrastructure will be established to help accomplish this mission. This infrastructure, particularly the buildings, should incorporate high performance sustainable design features in order to be environmentally responsible and reflect an image of progressiveness and innovation to the public and prospective employees. Additionally, INL is a large consumer of energy that contributes to both carbon emissions and resource inefficiency. In the current climate of rising energy prices and political pressure for carbon reduction, this guide will help new construction project teams to design facilities that are sustainable and reduce energy costs, thereby reducing carbon emissions. With these concerns in mind, the recommendations described in the INL High Performance Building Strategy (previously called the INL Green Building Strategy) are intended to form the INL foundation for high performance building standards. This revised strategy incorporates the latest federal and DOE orders (Executive Order [EO] 13514, “Federal Leadership in Environmental, Energy, and Economic Performance” [2009], EO 13423, “Strengthening Federal Environmental, Energy, and Transportation Management” [2007], and DOE Order 430.2B, “Departmental Energy, Renewable Energy, and Transportation Management” [2008]), the latest guidelines, trends, and observations in high performance building construction, and the latest changes to the Leadership in Energy and Environmental Design (LEED®) Green Building Rating System (LEED 2009). The document employs a two-level approach for high performance building at INL. The first level identifies the requirements of the Guiding Principles for Sustainable New Construction and Major Renovations, and the second level recommends which credits should be met when LEED Gold certification is required.

  17. In-situ Monitoring of Dynamic Phenomena during Solidification and Phase Transformation Processing

    SciTech Connect (OSTI)

    Clarke, Amy J. [Los Alamos National Laboratory; Cooley, Jason C. [Los Alamos National Laboratory; Morris, Christopher [Los Alamos National Laboratory; Merrill, Frank E. [Los Alamos National Laboratory; Hollander, Brian J. [Los Alamos National Laboratory; Mariam, Fesseha G. [Los Alamos National Laboratory; Patterson, Brian M. [Los Alamos National Laboratory; Imhoff, Seth D. [Los Alamos National Laboratory; Lee, Wah Keat [Brookhaven National Lab; Fezzaa, Kamel [Argonne National Lab; Deriy, Alex [Argonne NationalLbaoratory; Tucker, Tim J. [Los Alamos National Laboratory; Clarke, Kester D. [Los Alamos National Laboratory; Field, Robert D. [Los Alamos National Laboratory; Thoma, Dan J. [Los Alamos National Laboratory; Teter, David F. [Los Alamos National Laboratory; Beard, Timothy V. [Los Alamos National Laboratory; Hudson, Richard W. [Los Alamos National Laboratory; Freibert, Franz J. [Los Alamos National Laboratory; Korzekwa, Deniece R. [Los Alamos National Laboratory; Farrow, Adam M. [Los Alamos National Laboratory; Cross, Carl E. [Los Alamos National Laboratory; Mihaila, Bogdan [Los Alamos National Laboratory; Lookman, Turab [Los Alamos National Laboratory; Hunter, Abigail [Los Alamos National Laboratory; Choudhury, Samrat [Los Alamos National Laboratory; Karma, Alain [Northeastern University; Ott, Thomas J. Jr. [Los Alamos National Laboratory; Barker, Martha R. [Los Alamos National Laboratory; O'Neill, Finian [Former MST-6 Summer Student; Hill, Joshua [Former MST-6 Summer Student; Emigh, Megan G. [Los Alamos National Laboratory

    2012-07-30T23:59:59.000Z

    The purpose of this project is to: (1) Directly observe phase transformations and microstructure evolution using proton (and synchrotron x-ray) radiography and tomography; (2) Constrain phase-field models for microstructure evolution; (3) Experimentally control microstructure evolution during processing to enable co-design; and (4) Advance toward the MaRIE vision. Understand microstructure evolution and chemical segregation during solidification {yields} solid-state transformations in Pu-Ga.

  18. Building America Webinar: Ventilation in Multifamily Buildings...

    Energy Savers [EERE]

    Ventilation in Multifamily Buildings Building America Webinar: Ventilation in Multifamily Buildings This webinar was presented by research team Consortium for Advanced Residential...

  19. Building America Expert Meeting: Transforming Existing Buildings...

    Energy Savers [EERE]

    Transforming Existing Buildings through New Media--An Idea Exchange Building America Expert Meeting: Transforming Existing Buildings through New Media--An Idea Exchange This report...

  20. MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT

    E-Print Network [OSTI]

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

  1. Deactivation of Building 7602

    SciTech Connect (OSTI)

    Yook, H.R.; Barnett, J.R.; Collins, T.L. [and others

    1995-10-01T23:59:59.000Z

    The Department of Energy (DOE) has sponsored research and development programs in Building 7602 at Oak Ridge National Laboratory (ORNL) since 1984. This work focused on development of advanced technology for processing nuclear fuels. Building 7602 was used for engineering-scale tests using depleted and natural uranium to simulate the nuclear fuel. In April 1994 the DOE Office of Nuclear Energy (NE) sent supplemental FY 1994 guidance to ORNL stating that in FY 1995 and beyond, Building 7602 is considered surplus to NE programs and missions and shall be shut down (deactivated) and maintained in a radiologically and industrially safe condition with minimal surveillance and maintenance (S&M). DOE-NE subsequently provided FY 1995 funding to support the deactivation activities. Deactivation of Building 7602 was initiated on October 1, 1994. The principal activity during the first quarter of FY 1995 was removal of process materials (chemicals and uranium) from the systems. The process systems were operated to achieve chemical solution concentrations needed for reuse or disposal of the solutions prior to removal of the materials from the systems. During this phase of deactivation the process materials processed and removed were: (1) Uranyl nitrate solution 30,178 L containing 4490 kg of uranium; (2) Nitric acid (neutralized) 9850 L containing less than 0.013 kg of uranium; (3) Organic solution 3346 L containing 265 kg of uranium; (4) Uranium oxide powder 95 kg; and (5) Miscellaneous chemicals. At the end of December 1994, the process systems and control systems were shut down and deactivated. Disposition of the process materials removed from the process systems in Building 7602 proved to be the most difficult part of the deactivation. An operational stand down and funding reductions at Y-12 prevented planned conversion of the uranyl nitrate solution to depleted uranium oxide powder. This led to disposal of the uranyl nitrate solution as waste.

  2. Sorting and Characterizing Oversized Boxes of Transuranic Waste at the Nevada Test Site

    ScienceCinema (OSTI)

    None

    2014-10-28T23:59:59.000Z

    Characterization activities conducted inside the Visual Examination and Repackaging Building at the Area 5 Radioactive Waste Management Complex on the Nevada Test Site.

  3. Building Science

    Broader source: Energy.gov [DOE]

    This presentation was given at the Summer 2012 DOE Building America meeting on July 25, 2012, and addressed the question ŤHow do we first do no harm with high-r enclosures??

  4. Building debris

    E-Print Network [OSTI]

    Dahmen, Joseph (Joseph F. D.)

    2006-01-01T23:59:59.000Z

    This thesis relates architectural practices to intelligent use of resources and the reuse of derelict spaces. The initial investigation of rammed earth as a building material is followed by site-specific operations at the ...

  5. Building Stones

    E-Print Network [OSTI]

    2012-01-01T23:59:59.000Z

    1992 Are the pyramids of Egypt built of poured concreteel-Anba’ut, Red Sea coast, Egypt. Marmora 6, pp. 45 - 56.building stones of ancient Egypt are those relatively soft,

  6. Healthy buildings

    SciTech Connect (OSTI)

    Not Available

    1991-01-01T23:59:59.000Z

    This book is covered under the following headings: Healthy building strategies/productivity, Energy and design issues, Ventilation, Contaminants, Thermal, airflow, and humidity issues, School-related issues, Sources and sinks, Filtering, Operation and maintenance.

  7. Healthy buildings

    SciTech Connect (OSTI)

    Geshwiler, M.; Montgomery, L.; Moran, M. (eds.)

    1991-01-01T23:59:59.000Z

    This proceedings is of the Indoor Air Quality (IAQ) Conference held September 4--8, 1991 in Washington, D.C. Entitled the IAQ 91, Healthy Buildings,'' the major topics of discussion included: healthy building strategies/productivity; energy and design issues; ventilation; contaminants; thermal, airflow, and humidity issues; school-related issues; sources and sinks; filtering; and operation and maintenance. For these conference proceedings, individual papers are processed separately for input into the Energy Data Base. (BN)

  8. Archive Reference Buildings by Building Type: Supermarket

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  9. Archive Reference Buildings by Building Type: Warehouse

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  10. NREL's Building-Integrated Supercomputer Provides Heating and...

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

    allowing it to help meet building heating loads. At least 90 percent of the computer's waste heat is captured and reused as the primary heat source for the ESIF offices and...

  11. Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste

    SciTech Connect (OSTI)

    Morrell, D.K.; Fischer, D.K.

    1995-01-01T23:59:59.000Z

    This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW.

  12. Building Interoperability

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof Energy FutureDepartment of Energy Building Energy-EfficientBuilding

  13. Building Interoperability

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny: Theof Energy FutureDepartment of Energy Building Energy-EfficientBuilding

  14. Low Level Radioactive Wastes Conditioning during Decommissioning of Salaspils Research Reactor

    SciTech Connect (OSTI)

    Abramenkova, G.; Klavins, M. [Faculty of Geographical and Earth Sciences, University of Latvia, 19 Rainis Boulevard, Riga, LV-1586 (Latvia); Abramenkovs, A. [Ministry of Environment, Hazardous Wastes Management State Agency, 31 Miera Street, Salaspils, LV-2169 (Latvia)

    2008-01-15T23:59:59.000Z

    The decommissioning of Salaspils research reactor is connected with the treatment of 2200 tons different materials. The largest part of all materials ({approx}60 % of all dismantled materials) is connected with low level radioactive wastes conditioning activities. Dismantled radioactive materials were cemented in concrete containers using water-cement mortar. According to elaborated technology, the tritiated water (150 tons of liquid wastes from special canalization tanks) was used for preparation of water-cement mortar. Such approach excludes the emissions of tritiated water into environment and increases the efficiency of radioactive wastes management system for decommissioning of Salaspils research reactor. The Environmental Impact Assessment studies for Salaspils research reactor decommissioning (2004) and for upgrade of repository 'Radons' for decommissioning purposes (2005) induced the investigations of radionuclides release parameters from cemented radioactive waste packages. These data were necessary for implementation of quality assurance demands during conditioning of radioactive wastes and for safety assessment modeling for institutional control period during 300 years. Experimental studies indicated, that during solidification of water- cement samples proceeds the increase of temperature up to 81 deg. C. It is unpleasant phenomena since it can result in damage of concrete container due to expansion differences for mortar and concrete walls. Another unpleasant factor is connected with the formation of bubbles and cavities in the mortar structure which can reduce the mechanical stability of samples and increase the release of radionuclides from solidified cement matrix. The several additives, fly ash and PENETRON were used for decrease of solidification temperature. It was found, that addition of fly ash to the cement-water mortar can reduce the solidification temperature up to 62 deg. C. Addition of PENETRON results in increasing of solidification temperature up to 83 deg. C. Experimental data shows, that water/cement ratio significantly influences on water-cement mortar's viscosity and solidified samples mechanical stability. Increasing of water ratio from 0.45 up to 0.65 decreases water-cement mortar's viscosity from 1100 mPas up to 90 mPas. Significant reduction of viscosity is an important factor, which facilitates the fulfillment all gaps and cavities with the mortar during conditioning of solid radioactive wastes in containers. On the other hand, increase water ratio from 0.45 up to 0.65 decreases mechanical stability of water-cement samples from 23 N/mm{sup 2} to the 12 N/mm{sup 2}. It means that water-cement bulk stability significantly decreases with increasing of water content. Technologically is important to increase the tritiated water content in container with cemented radioactive wastes. It gives a possibility to increase the fulfillment of container with radioactive materials. On the other hand, additional water significantly reduces bulk stability of containers with cemented radioactive wastes, which can result in disintegration of radioactive wastes packages in repository during 300 years. Taking into account the experimental results, it is not recommended to exceed the water/cement ratio more than 0.60. Tritium and Cs{sup 137} leakage tests show, that radionuclides release curves has a complicate structure. Experimental results indicated that addition of fly ash result in facilitation of tritium and cesium release in water phase. This is unpleasant factor, which significantly decreases the safety of disposed radioactive wastes. Despite the positive impact on solidification temperature drop, the addition of fly ash to the cement-water mortar is not recommended in case of cementation of radionuclides in concrete containers. In conclusion: The cementation processes of solid radioactive wastes in concrete containers were investigated. The influence of additives on cementation processes was studied. It was shown, that the increasing of water ratio from 0.45 up to 0.65 decreases water-cement mortar

  15. Environmental assessment, finding of no significant impact, and response to comments. Radioactive waste storage

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    The Department of Energy`s (DOE) Rocky Flats Environmental Technology Site (the Site), formerly known as the Rocky Flats Plant, has generated radioactive, hazardous, and mixed waste (waste with both radioactive and hazardous constituents) since it began operations in 1952. Such wastes were the byproducts of the Site`s original mission to produce nuclear weapons components. Since 1989, when weapons component production ceased, waste has been generated as a result of the Site`s new mission of environmental restoration and deactivation, decontamination and decommissioning (D&D) of buildings. It is anticipated that the existing onsite waste storage capacity, which meets the criteria for low-level waste (LL), low-level mixed waste (LLM), transuranic (TRU) waste, and TRU mixed waste (TRUM) would be completely filled in early 1997. At that time, either waste generating activities must cease, waste must be shipped offsite, or new waste storage capacity must be developed.

  16. Immobilization of fission products in low-temperature ceramic waste forms

    SciTech Connect (OSTI)

    Singh, D.; Wagh, A.S.; Tlustochowicz, M.; Mandalika, V.

    1997-01-01T23:59:59.000Z

    Over the last few years, Argonne National Laboratory has been developing room-temperature-setting chemically bonded phosphate ceramics (CBPCs) for use in solidifying and stabilizing low-level mixed wastes. The focus of this work is development of CBPCs for use with fission-product wastes generated from high-level waste (HLW) tank cleaning or other decontamination and decommissioning activities. The volatile fission products such as Tc, Cs, and Sr removed from HLW need to be disposed of in a low-temperature immobilization system. Specifically, this paper reports on the solidification and stabilization of separated {sup 99}Tc from Los Alamos National Laboratory`s complexation-elution process. Using rhenium as a surrogate form technetium, we fabricated CBPC waste forms by acid-base reactions. Dense and hard ceramic waste forms are produced in this process. The principal advantage of this technology is that the contaminants are immobilized by both chemical stabilization and subsequent microencapsulation of the reaction products. This paper reports the results of durability studies conducted on waste forms made with 35 wt.% waste loading. Standard leaching tests such as ANS 16.1 and PCT were conducted on the final waste forms. In addition, stability of the waste forms in aqueous environments was evaluated by long-term water-immersion tests.

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

    SciTech Connect (OSTI)

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

    1996-05-01T23:59:59.000Z

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

  18. Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)

    SciTech Connect (OSTI)

    TOMASZEWSKI, T.A.

    2000-04-25T23:59:59.000Z

    The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

  19. Mr. John E. Kieling, Chief Hazardous Waste Bureau

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

    A UG 1 7 2012 New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe , New Mexico 87505-6303 Subject: Notification of Sampling Line Loss, Waste Isolation...

  20. New York looks to the future of waste (10 March 2006) New York City has been investigating ways to manage its waste more sustainably in years

    E-Print Network [OSTI]

    Columbia University

    and the lack of sites within the urban area itself which can process it. The city produces 46,000 tons of waste City Department of Sanitation (DSNY) attempted to build a series of waste-to-energy facilities and cleaner waste-to-energy facilities in New York City four years #12;ago, the proposal was met

  1. EA-1106: Explosive Waste Treatment Facility at Site 300, Lawrence Livermore National Laboratory, San Joaquin County, California

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to build, permit, and operate the Explosive Waste Treatment Facility to treat explosive waste at the U.S. Department of Energy's Lawrence...

  2. An overview of in situ waste treatment technologies

    SciTech Connect (OSTI)

    Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

    1992-08-01T23:59:59.000Z

    In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified.

  3. An overview of in situ waste treatment technologies

    SciTech Connect (OSTI)

    Walker, S.; Hyde, R.A.; Piper, R.B.; Roy, M.W.

    1992-01-01T23:59:59.000Z

    In situ technologies are becoming an attractive remedial alternative for eliminating environmental problems. In situ treatments typically reduce risks and costs associated with retrieving, packaging, and storing or disposing-waste and are generally preferred over ex situ treatments. Each in situ technology has specific applications, and, in order to provide the most economical and practical solution to a waste problem, these applications must be understood. This paper presents an overview of thirty different in situ remedial technologies for buried wastes or contaminated soil areas. The objective of this paper is to familiarize those involved in waste remediation activities with available and emerging in situ technologies so that they may consider these options in the remediation of hazardous and/or radioactive waste sites. Several types of in situ technologies are discussed, including biological treatments, containment technologies, physical/chemical treatments, solidification/stabilization technologies, and thermal treatments. Each category of in situ technology is briefly examined in this paper. Specific treatments belonging to these categories are also reviewed. Much of the information on in situ treatment technologies in this paper was obtained directly from vendors and universities and this information has not been verified.

  4. 309 Building transition plan

    SciTech Connect (OSTI)

    Graves, C.E.

    1994-08-31T23:59:59.000Z

    The preparation for decontamination and decommissioning (transition) of the 309 Building is projected to be completed by the end of the fiscal year (FY) 1998. The major stabilization and decontamination efforts include the Plutonium Recycle Test Reactor (PRTR), fuel storage and transfer pits, Transfer Waste (TW) tanks and the Ion Exchange Vaults. In addition to stabilizing contaminated areas, equipment, components, records, waste products, etc., will be dispositioned. All nonessential systems, i.e., heating, ventilation, and air conditioning (HVAC), electrical, monitoring, fluids, etc., will be shut down and drained/de-energized. This will allow securing of the process, laboratory, and office areas of the facility. After that, the facility will be operated at a level commensurate with its surveillance needs while awaiting D&D. The implementation costs for FY 1995 through FY 1998 for the transition activities are estimated to be $1,070K, $2,115K, $2,939K, and $4,762K, respectively. Costs include an assumed company overhead of 20% and a 30% out year contingency.

  5. buildings in Continued on p. 5

    E-Print Network [OSTI]

    Pennycook, Steve

    systems; ground-source and distributed heat pumps; and building-inte- grated, solar, combined heat for the waste heat recovery system using exhaust from the light-duty diesel engine Exhaust from diesel vehicles is fraught with promise and peril. The danger lies in its potentially hazardous pollutants and particulates

  6. FEASIBILITY AND EXPEDIENCE TO VITRIFY NPP OPERATIONAL WASTE

    SciTech Connect (OSTI)

    LIFANOV, F.A.; OJOVAN, M.I.; STEFANOVSKY, S.V.; BURCL, R.

    2003-02-27T23:59:59.000Z

    Operational radioactive waste is generated during routine operation of NPP. Process waste is mainly generated by treatment of water from reactor or ancillaries including spent fuel storage pools and some decontamination operations. Typical process wastes of pressurized water reactors (PWR or WWER) are borated water concentrates, whereas typical process wastes of boiling and RBMK type reactors are water concentrates with no boron content. NPP operational wastes are classified as low and intermediate level waste (LILW). NPP operational waste must be solidified in order to ensure safe conditions of storage and disposal. Currently the most promising solidification method for this waste is the vitrification technology. Vitrification of NPP operational waste is a relative new option being developed for last years. Nevertheless there is already accumulated operational experience on vitrifying low and intermediate level waste in Russian Federation at Moscow SIA ''Radon'' vitrification plant. This plant uses the most advanced type induction high frequency melters that facilitate the melting process and significantly reduce the generation of secondary waste and henceforth the overall cost. The plant was put into operation by the end of 1999. It has three operating cold crucible melters with the overall capacity up to 75 kg/h. The vitrification technology comprises a few stages, starting with evaporation of excess water from liquid radioactive waste, followed by batch preparation, glass melting, and ending with vitrified waste blocks and some relative small amounts of secondary waste. First of all since the original waste contain as main component water, this water is removed from waste through evaporation. Then the remaining salt concentrate is mixed with necessary technological additives, thus a glass-forming batch is formed. The batch is fed into melters where the glass melting occurs. From here there are two streams: one is the glass melt containing the most part of radioactivity and second is the off gas flow, which contains off gaseous and aerosol airborne. The melt glass is fed into containers, which are slowly cooled in an annealing tunnel furnace to avoid accumulation of mechanical stresses in the glass. Containers with glass are the final processing product containing the overwhelming part of waste contaminants. The second stream from melter is directed to gas purification system, which is a rather complex system taking into account the necessity to remove from off gas not only radionuclides but also the chemical contaminants. Operation of this purification system leads to generation of a small amount of secondary waste. This waste stream slightly contaminated with volatilized radionuclides is recycled in the same technological scheme. As a result only non-radioactive materials are produced. They are either discharged into environment or reused. Based on the experience gained during operation of vitrification plant one can conclude on high efficiency achieved through vitrification method. Another significant argument on vitrifying NPP operational waste is the minimal impact of vitrified radioactive waste onto environment. Solidified waste shall be disposed of into a near surface disposal facility. Waste forms disposed of in a near-surface wet repository eventually come into contact with groundwater. Engineered structures used or designed to prevent or postpone such contact and the subsequent radionuclide release are complex and often too expensive. Vitrification technologies provide waste forms with excellent resistance to corrosion and gave the basic possibility of maximal simplification of engineered barrier systems. The most simple disposal option is to locate the vitrified waste form packages directly into earthen trenches provided the host rock has the necessary sorption and confinement properties. Such an approach will significantly make simpler the disposal facilities thus contributing both to enhancing safety and economic al efficiency.

  7. Supplemental Immobilization of Hanford Low-Activity Waste: Cast Stone Screening Tests

    SciTech Connect (OSTI)

    Westsik, Joseph H.; Piepel, Gregory F.; Lindberg, Michael J.; Heasler, Patrick G.; Mercier, Theresa M.; Russell, Renee L.; Cozzi, Alex; Daniel, William E.; Eibling, Russell E.; Hansen, E. K.; Reigel, Marissa M.; Swanberg, David J.

    2013-09-30T23:59:59.000Z

    More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in the HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second LAW immobilization facility will be needed for the expected volume of LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with the waste acceptance criteria for the disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF. The PA is needed to satisfy both Washington State IDF Permit and DOE Order requirements. Cast Stone has been selected for solidification of radioactive wastes including WTP aqueous secondary wastes treated at the Effluent Treatment Facility (ETF) at Hanford. A similar waste form called Saltstone is used at the Savannah River Site (SRS) to solidify its LAW tank wastes.

  8. Home | Better Buildings Workforce

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

    Better Buildings Logo EERE Home | Programs & Offices | Consumer Information Search form Search Search Better Buildings Logo Connect with Us LinkedIn Twitter Better Buildings...

  9. Waste processing air cleaning

    SciTech Connect (OSTI)

    Kriskovich, J.R.

    1998-07-27T23:59:59.000Z

    Waste processing and preparing waste to support waste processing relies heavily on ventilation. Ventilation is used at the Hanford Site on the waste storage tanks to provide confinement, cooling, and removal of flammable gases.

  10. HAZARDOUS WASTE [Written Program

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    HAZARDOUS WASTE MANUAL [Written Program] Cornell University [10/7/13 #12;Hazardous Waste Program................................................... 8 3.0 MINIMIZING HAZARDOUS WASTE GENERATION.........................................................10 4.0 HAZARDOUS WASTE GENERATOR REQUIREMENTS.....................................................10

  11. Estimation and characterization of decontamination and decommissioning solid waste expected from the Plutonium Finishing Plant

    SciTech Connect (OSTI)

    Millar, J.S.; Pottmeyer, J.A.; Stratton, T.J. [and others

    1995-01-01T23:59:59.000Z

    Purpose of the study was to estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the Hanford Plutonium Finishing Plant is decontaminated and decommissioned. (Building structure and soil are not covered.) Results indicate that {approximately}5,500 m{sup 3} of solid waste is expected to result from the decontamination and decommissioning of the Pu Finishing Plant. The breakdown of the volumes and percentages of waste by category is 1% dangerous solid waste, 71% low-level waste, 21% transuranic waste, 7% transuranic mixed waste.

  12. Industrial Waste Landfill IV upgrade package

    SciTech Connect (OSTI)

    Not Available

    1994-03-29T23:59:59.000Z

    The Y-12 Plant, K-25 Site, and ORNL are managed by DOE`s Operating Contractor (OC), Martin Marietta Energy Systems, Inc. (Energy Systems) for DOE. Operation associated with the facilities by the Operating Contractor and subcontractors, DOE contractors and the DOE Federal Building result in the generation of industrial solid wastes as well as construction/demolition wastes. Due to the waste streams mentioned, the Y-12 Industrial Waste Landfill IV (IWLF-IV) was developed for the disposal of solid industrial waste in accordance to Rule 1200-1-7, Regulations Governing Solid Waste Processing and Disposal in Tennessee. This revised operating document is a part of a request for modification to the existing Y-12 IWLF-IV to comply with revised regulation (Rule Chapters 1200-1-7-.01 through 1200-1-7-.08) in order to provide future disposal space for the ORR, Subcontractors, and the DOE Federal Building. This revised operating manual also reflects approved modifications that have been made over the years since the original landfill permit approval. The drawings referred to in this manual are included in Drawings section of the package. IWLF-IV is a Tennessee Department of Environmental and Conservation/Division of Solid Waste Management (TDEC/DSWM) Class 11 disposal unit.

  13. Waste Disposal (Illinois)

    Broader source: Energy.gov [DOE]

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

  14. Rapid solidification processing of iron-base alloys for structural applications

    SciTech Connect (OSTI)

    Flinn, J.E.

    1991-09-01T23:59:59.000Z

    The response of iron-base alloys to rapid solidification is reviewed with an emphasis on the effects of processing on the microstructure and mechanical property behavior. The processing topics addressed are powder atomization, powder consolidation, joining, and thermal-mechanical exposure. The value of rapid solidification processing (RSP) lies in the ability to promote compositional homogeneity and retention of fine and stable (to high temperatures) microstructures. Achieving the maximum benefit from RSP requires proper application of the basic principles of composition control and rapid crystallization. This investigation has disclosed two very important facets of the RSP approach that can be applied using current technologies. Dissociated oxygen appears to play a significant role in stabilizing microstructural features. In conjunction with oxygen, vacancies trapped during crystallization provide a very stable matrix dispersion for enhanced strengthening. With a fundamental understanding of the response of iron-base alloys to RSP, alloys can be designed that will have substantially better properties and performance than their conventionally processed counterparts. 77 refs., 94 figs., 14 tabs.

  15. Terfenol: A study of the phase equilibrium diagram and the solidification process

    SciTech Connect (OSTI)

    Anderson, M.

    1993-12-07T23:59:59.000Z

    Terfenol is a rare earth-iron alloy that was first developed at the Naval Ordinance Laboratory because of its rare magnetostrictive properties. Terfenol is composed of terbium and dysprosium combined with iron in a composition Tb{sub x}Dy{sub 1{minus}x}Fe{sub 2}, where x{approximately}0.3. The objective of this work was to determine the growth characteristics of Terfenol and its dependence on solidification rate, temperature gradient, and stoichiometry. Specific goals of this work were to verify the phase equilibria that is currently accepted for the systems DyFe{sub 2} and TbFe{sub 2}, and establish the phase equilibria near the composition Tb{sub 0.3}Dy{sub 0.7}Fe{sub 2}; establish that Terfenol grows directly from the liquid and that the reaction is occurring under metastable conditions; evaluate whether or not Terfenol can be grown under plane front conditions with a new radiofrequency float zone apparatus, and; determine whether or not <111> seeded crystals can be grown and <111> single crystals produced by elimination of dendrites employing growth methods capable of achieving high gradient/solidification rate ratios.

  16. Safety Analysis Report for packaging (onsite) steel waste package

    SciTech Connect (OSTI)

    BOEHNKE, W.M.

    2000-07-13T23:59:59.000Z

    The steel waste package is used primarily for the shipment of remote-handled radioactive waste from the 324 Building to the 200 Area for interim storage. The steel waste package is authorized for shipment of transuranic isotopes. The maximum allowable radioactive material that is authorized is 500,000 Ci. This exceeds the highway route controlled quantity (3,000 A{sub 2}s) and is a type B packaging.

  17. Building Energy Optimization Analysis Method (BEopt) - Building...

    Energy Savers [EERE]

    about BEopt. See an example of a Building America project that used BEopt. Find more case studies of Building America projects across the country that incorporate BEopt when...

  18. Vitrification of M-Area Mixed (Hazardous and Radioactive) F006 Wastes: I. Sludge and Supernate Characterization

    SciTech Connect (OSTI)

    Jantzen, C.M.

    2001-10-05T23:59:59.000Z

    Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert low-level and mixed (hazardous and radioactive) wastes to a solid stabilized waste form for permanent disposal. One of the alternative technologies is vitrification into a borosilicate glass waste form. The Environmental Protection Agency (EPA) has declared vitrification the Best Demonstrated Available Technology (BDAT) for high-level radioactive mixed waste and produced a Handbook of Vitrification Technologies for Treatment of Hazardous and Radioactive Waste. The DOE Office of Technology Development (OTD) has taken the position that mixed waste needs to be stabilized to the highest level reasonably possible to ensure that the resulting waste forms will meet both current and future regulatory specifications. Stabilization of low level and hazardous wastes in glass are in accord with the 1988 Savannah River Technology Center (SRTC), then the Savannah River Laboratory (SRL), Professional Planning Committee (PPC) recommendation that high nitrate containing (low-level) wastes be incorporated into a low temperature glass (via a sol-gel technology). The investigation into this new technology was considered timely because of the potential for large waste volume reduction compared to solidification into cement.

  19. SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities

    E-Print Network [OSTI]

    Stephens, Larry M.

    SWAMI: An Autonomous Mobile Robot for Inspection of Nuclear Waste Storage Facilities Ron Fulbright Inspector (SWAMI) is a prototype mobile robot designed to perform autonomous inspection of nuclear waste user interface building tool called UIM/X. Introduction Safe disposal of nuclear waste is a difficult

  20. Equiaxed Dendritic Solidification with Convection: Part I1. Numerical Simulations for an AI-4 Wt Pct Cu Alloy

    E-Print Network [OSTI]

    Beckermann, Christoph

    experienced considerable progress:~,2JNucleation and growth kinetic laws have been coupled with transient heat phenomena occurring during equiaxed alloy solidification. II. MATHEMATICAL FORMULATION The physical system and adiabatic, except for the west wall which is subject to con- vective cooling for t > 0. The coolant

  1. On the control of solidification using magnetic fields and magnetic field Baskar Ganapathysubramanian and Nicholas Zabaras1

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    On the control of solidification using magnetic fields and magnetic field gradients Baskar and Aerospace Engineering, 188 Frank H.T. Rhodes Hall, Cornell University, Ithaca, NY 14853-3801, USA Abstract solidified material can be suitably affected. Most of the magnetic field approaches to melt flow control rely

  2. A STABILIZED VOLUME-AVERAGING FINITE ELEMENT METHOD FOR FLOW IN POROUS MEDIA AND BINARY ALLOY SOLIDIFICATION SYSTEMS

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    A STABILIZED VOLUME-AVERAGING FINITE ELEMENT METHOD FOR FLOW IN POROUS MEDIA AND BINARY ALLOY of Mechanical and Aerospace Engineering 188 Frank H. T. Rhodes Hall Cornell University Ithaca, NY 14853 algorithm is presented for the analysis of flow in porous media and in the solidification of binary alloys

  3. A coupled thermomechanical, thermal transport and segregation analysis of the solidification of Aluminum alloys on molds of uneven topographies

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    of Aluminum alloys on molds of uneven topographies Deep Samantaa and Nicholas Zabarasa a Materials Process and segregation analysis of Aluminum alloys solidifying on uneven surfaces is presented here. Uneven surfaces of solidification of an Aluminum alloy. The role of inverse segregation, arising from shrinkage driven flow

  4. A coupled thermomechanical, thermal transport and segregation analysis of the solidification of aluminum alloys on molds of uneven

    E-Print Network [OSTI]

    Zabaras, Nicholas J.

    of aluminum alloys on molds of uneven surface topographies Lijian Tan, Deep Samanta and Nicholas Zabaras the early stages of Aluminum alloy solidification on uneven mold topographies. At the mold-metal interface for a number of aluminum alloys. One of the main aims of the current analysis is to gain a better understanding

  5. 3612--VOLUME 27A, NOVEMBER 1996 METALLURGICAL AND MATERIALS TRANSACTIONS A Solidification of an Alloy 625 Weld Overlay

    E-Print Network [OSTI]

    DuPont, John N.

    3612--VOLUME 27A, NOVEMBER 1996 METALLURGICAL AND MATERIALS TRANSACTIONS A Solidification in the overlay de- posit are compared to other Nb-bearing Ni base alloys and found to be very similar to those) and various microscopy techniques for phase identification.[1] Weldability was assessed using the varestraint

  6. Implementation plan for the Waste Experimental Reduction Facility Restart Operational Readiness Review

    SciTech Connect (OSTI)

    Not Available

    1993-03-01T23:59:59.000Z

    The primary technical objective for the WERF Restart Project is to assess, upgrade where necessary, and implement management, documentation, safety, and operation control systems that enable the resumption and continued operation of waste treatment and storage operations in a manner that is compliant with all environment, safety, and quality requirements of the US Department of Energy and Federal and State regulatory agencies. Specific processes that will be resumed at WERF include compaction of low-level compatible waste; size reduction of LLW, metallic and wood waste; incineration of combustible LLW and MLLW; and solidification of low-level and mixed low-level incinerator bottom ash, baghouse fly ash, and compatible sludges and debris. WERF will also provide for the operation of the WWSB which includes storage of MLLW in accordance with Resource Conservation and Recovery Act requirements.

  7. Industrial Buildings

    Gasoline and Diesel Fuel Update (EIA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122 40 Building FloorspaceThousandWithdrawals0.0 0.0Decade4Year114,937

  8. Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...

    Office of Environmental Management (EM)

    Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility October...

  9. 3Building a Business Building a Business

    E-Print Network [OSTI]

    Arnold, Jonathan

    15 3Building a Business Building a Business This section provides direction on the kinds. If you contemplate building a "garage- based" company to sell a product into a niche market, you should-ups conjure up images of future wealth, of building the next Amgen or Microsoft, of launching what will become

  10. WASTE TO WATTS Waste is a Resource!

    E-Print Network [OSTI]

    Columbia University

    to Climate protection in light of the· Waste Framework Directive. The "energy package", e.g. the RenewablesWASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From

  11. Low-temperature ceramic radioactive waste form characteriztion of supercalcine-based monazite-cement composites

    SciTech Connect (OSTI)

    Roy, D.M.; Wakeley, L.D.; Atkinson, S.D.

    1980-04-18T23:59:59.000Z

    Simulated radioactive waste solidification by a lower temperature ceramic (cement) process is being investigated. The monazite component (simulated by NdPO/sub 4/) of supercalcine-ceramic has been solidified in cement and found to generate a solid form with low leachability. Several types of commercial cements and modifications thereof were used. No detectable release of Nd or P was found through characterizing the products of accelerated hydrothermal leaching at 473/sup 0/K (200/sup 0/C) and 30.4 MPa (300 bars) pressure.

  12. Regulatory requirements affecting disposal of asbestos-containing waste

    SciTech Connect (OSTI)

    NONE

    1995-11-01T23:59:59.000Z

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

  13. Technical Safety Requirements for the Waste Storage Facilities

    SciTech Connect (OSTI)

    Larson, H L

    2007-09-07T23:59:59.000Z

    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.

  14. Reference Alloy Waste Form Fabrication and Initiation of Reducing Atmosphere and Reductive Additives Study on Alloy Waste Form Fabrication

    SciTech Connect (OSTI)

    S.M. Frank; T.P. O'Holleran; P.A. Hahn

    2011-09-01T23:59:59.000Z

    This report describes the fabrication of two reference alloy waste forms, RAW-1(Re) and RAW-(Tc) using an optimized loading and heating method. The composition of the alloy materials was based on a generalized formulation to process various proposed feed streams resulting from the processing of used fuel. Waste elements are introduced into molten steel during alloy fabrication and, upon solidification, become incorporated into durable iron-based intermetallic phases of the alloy waste form. The first alloy ingot contained surrogate (non-radioactive), transition-metal fission products with rhenium acting as a surrogate for technetium. The second alloy ingot contained the same components as the first ingot, but included radioactive Tc-99 instead of rhenium. Understanding technetium behavior in the waste form is of particular importance due the longevity of Tc-99 and its mobility in the biosphere in the oxide form. RAW-1(Re) and RAW-1(Tc) are currently being used as test specimens in the comprehensive testing program investigating the corrosion and radionuclide release mechanisms of the representative alloy waste form. Also described in this report is the experimental plan to study the effects of reducing atmospheres and reducing additives to the alloy material during fabrication in an attempt to maximize the oxide content of waste streams that can be accommodated in the alloy waste form. Activities described in the experimental plan will be performed in FY12. The first aspect of the experimental plan is to study oxide formation on the alloy by introducing O2 impurities in the melt cover gas or from added oxide impurities in the feed materials. Reducing atmospheres will then be introduced to the melt cover gas in an attempt to minimize oxide formation during alloy fabrication. The second phase of the experimental plan is to investigate melting parameters associated with alloy fabrication to allow the separation of slag and alloy components of the melt.

  15. Influence of Alloy and Solidification Parameters on Grain Refinement in Aluminum Weld Metal due to Inoculation

    SciTech Connect (OSTI)

    Schempp, Philipp [BAM, Germany; Tang, Z. [BIAS, Germany; Cross, Carl E. [Los Alamos National Laboratory; Seefeld, T. [BIAS, Germany; Pittner, A. [BAM, Germany; Rethmeier, M. [BAM, Germany

    2012-06-28T23:59:59.000Z

    The goals are: (1) Establish how much Ti/B grain refiner is need to completely refine aluminum weld metal for different alloys and different welding conditions; (2) Characterize how alloy composition and solidification parameters affect weld metal grain refinement; and (3) Apply relevant theory to understand observed behavior. Conclusions are: (1) additions of Ti/B grain refiner to weld metal in Alloys 1050, 5083, and 6082 resulted in significant grain refinement; (2) grain refinement was more effective in GTAW than LBW, resulting in finer grains at lower Ti content - reason is limited time available for equiaxed grain growth in LBW (inability to occlude columnar grain growth); (3) welding travel speed did not markedly affect grain size within GTAW and LBW clusters; and (4) application of Hunt CET analysis showed experimental G to be on the order of the critical G{sub CET}; G{sub CET} was consistently higher for GTAW than for LBW.

  16. Diffusion, convection, and solidification in cw-mode free electron laser nitrided titanium

    SciTech Connect (OSTI)

    Hoeche, Daniel; Mueller, Sven [II. Physikalisches Institut, Universitaet Goettingen, Friedrich-Hund-Platz 1, 37077 Goettingen (Germany); Shinn, Michelle [Free Electron Laser Group, Thomas Jefferson National Accelerator Facility, Newport News, Virginia 23606 (United States); Schaaf, Peter [Institut fuer Werkstofftechnik, FG Werkstoffe der Elektrotechnik, TU Ilmenau, Postfach 10 05 65, 98684 Ilmenau (Germany)

    2009-04-15T23:59:59.000Z

    Titanium sheets were irradiated by free electron laser radiation in cw mode in pure nitrogen. Due to the interaction, nitrogen diffusion occurs and titanium nitride was synthesized in the tracks. Overlapping tracks have been utilized to create coatings in order to improve the tribological properties of the sheets. Caused by the local heating and the spatial dimension of the melt pool, convection effects were observed and related to the track properties. Stress, hardness, and nitrogen content were investigated with x-ray diffraction, nanoindention, and resonant nuclear reaction analysis. The measured results were correlated with the scan parameters, especially to the lateral track shift. Cross section micrographs were prepared and investigated by means of scanning electron microscopy. They show the solidification behavior, phase formation, and the nitrogen distribution. The experiments give an insight into the possibilities of materials processing using such a unique heat source.

  17. Haiti: Feasibility of Waste-to-Energy Options at the Trutier Waste Site

    SciTech Connect (OSTI)

    Conrad, M. D.; Hunsberger, R.; Ness, J. E.; Harris, T.; Raibley, T.; Ursillo, P.

    2014-08-01T23:59:59.000Z

    This report provides further analysis of the feasibility of a waste-to-energy (WTE) facility in the area near Port-au-Prince, Haiti. NREL's previous analysis and reports identified anaerobic digestion (AD) as the optimal WTE technology at the facility. Building on the prior analyses, this report evaluates the conceptual financial and technical viability of implementing a combined waste management and electrical power production strategy by constructing a WTE facility at the existing Trutier waste site north of Port-au-Prince.

  18. Radionuclide Retention Mechanisms in Secondary Waste-Form Testing: Phase II

    SciTech Connect (OSTI)

    Um, Wooyong; Valenta, Michelle M.; Chung, Chul-Woo; Yang, Jungseok; Engelhard, Mark H.; Serne, R. Jeffrey; Parker, Kent E.; Wang, Guohui; Cantrell, Kirk J.; Westsik, Joseph H.

    2011-09-26T23:59:59.000Z

    This report describes the results from laboratory tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate candidate stabilization technologies that have the potential to successfully treat liquid secondary waste stream effluents produced by the Hanford Tank Waste Treatment and Immobilization Plant (WTP). WRPS is considering the design and construction of a Solidification Treatment Unit (STU) for the Effluent Treatment Facility (ETF) at Hanford. The ETF, a multi-waste, treatment-and-storage unit that has been permitted under the Resource Conservation and Recovery Act (RCRA), can accept dangerous, low-level, and mixed wastewaters for treatment. The STU needs to be operational by 2018 to receive secondary liquid waste generated during operation of the WTP. The STU will provide the additional capacity needed for ETF to process the increased volume of secondary waste expected to be produced by WTP. This report on radionuclide retention mechanisms describes the testing and characterization results that improve understanding of radionuclide retention mechanisms, especially for pertechnetate, {sup 99}TcO{sub 4}{sup -} in four different waste forms: Cast Stone, DuraLith alkali aluminosilicate geopolymer, encapsulated fluidized bed steam reforming (FBSR) product, and Ceramicrete phosphate bonded ceramic. These data and results will be used to fill existing data gaps on the candidate technologies to support a decision-making process that will identify a subset of the candidate waste forms that are most promising and should undergo further performance testing.

  19. Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    This report contains information on hazardous wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, weight, and waste designation.

  20. Energy conservation in commercial and residential buildings

    SciTech Connect (OSTI)

    Chiogioji, M.H.; Oura, E.N.

    1982-01-01T23:59:59.000Z

    Energy experts have indicated that we can, by exploiting currently available technology, cut energy consumption by 30 to 50% in new buildings and 10 to 30% in existing buildings, with no significant loss in standard of living, comfort, or convenience. This book surveys the many architectural/engineering techniques for combating energy waste in residential and commercial buildings. The experts in these 10 chapters acquaint us with what is being done and with what can be done in the design, construction, and maintenance of buildings in order to foster energy efficiency; they emphasize life-cycle costing as the only sound approach toward energy conservation. A separate abstract was prepared for each chapter; all abstracts will appear in Energy Abstracts for Policy Analysis (EAPA), with 5 appearing in Energy Research Abstracts (ERA).

  1. Building America Webinar: Saving Energy in Multifamily Buildings...

    Energy Savers [EERE]

    More Documents & Publications Building America Webinar: Retrofit Ventilation Strategies in Multifamily Buildings Webinar Energy Saver Guide Building America...

  2. Eco-efficient waste glass recycling: Integrated waste management and green product development through LCA

    SciTech Connect (OSTI)

    Blengini, Gian Andrea, E-mail: blengini@polito.it [DISPEA - Department of Production Systems and Business Economics, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); CNR-IGAG, Institute of Environmental Geology and Geo-Engineering, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Busto, Mirko, E-mail: mirko.busto@polito.it [DISPEA - Department of Production Systems and Business Economics, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Fantoni, Moris, E-mail: moris.fantoni@polito.it [DITAG - Department of Land, Environment and Geo-Engineering, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy); Fino, Debora, E-mail: debora.fino@polito.it [DISMIC - Department of Materials Science and Chemical Engineering, Politecnico di Torino, Corso Duca degli Abruzzi 24, 10129 Turin (Italy)

    2012-05-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer A new eco-efficient recycling route for post-consumer waste glass was implemented. Black-Right-Pointing-Pointer Integrated waste management and industrial production are crucial to green products. Black-Right-Pointing-Pointer Most of the waste glass rejects are sent back to the glass industry. Black-Right-Pointing-Pointer Recovered co-products give more environmental gains than does avoided landfill. Black-Right-Pointing-Pointer Energy intensive recycling must be limited to waste that cannot be closed-loop recycled. - Abstract: As part of the EU Life + NOVEDI project, a new eco-efficient recycling route has been implemented to maximise resources and energy recovery from post-consumer waste glass, through integrated waste management and industrial production. Life cycle assessment (LCA) has been used to identify engineering solutions to sustainability during the development of green building products. The new process and the related LCA are framed within a meaningful case of industrial symbiosis, where multiple waste streams are utilised in a multi-output industrial process. The input is a mix of rejected waste glass from conventional container glass recycling and waste special glass such as monitor glass, bulbs and glass fibres. The green building product is a recycled foam glass (RFG) to be used in high efficiency thermally insulating and lightweight concrete. The environmental gains have been contrasted against induced impacts and improvements have been proposed. Recovered co-products, such as glass fragments/powders, plastics and metals, correspond to environmental gains that are higher than those related to landfill avoidance, whereas the latter is cancelled due to increased transportation distances. In accordance to an eco-efficiency principle, it has been highlighted that recourse to highly energy intensive recycling should be limited to waste that cannot be closed-loop recycled.

  3. and Pollutant Safeguarding Buildings

    E-Print Network [OSTI]

    commercial buildings, these flows are driven primarily by the building's ventilation system, but natural2004 Airflow and Pollutant Transport Group Safeguarding Buildings Against Chemical and Biological research since 1998 to protect buildings and building occupants from threats posed by airborne chemical

  4. Building America Webinar: Building America Research Tools | Department...

    Energy Savers [EERE]

    Building America Research Tools Building America Webinar: Building America Research Tools This webinar was held on March 18, 2015, and reviewed Building America research tools,...

  5. Building America Top Innovations Hall of Fame Profile - Building...

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

    Building America Top Innovations Hall of Fame Profile - Building Energy Optimization Analysis Method (BEopt) Building America Top Innovations Hall of Fame Profile - Building Energy...

  6. Technical Safety Requirements for the Waste Storage Facilities

    SciTech Connect (OSTI)

    Laycak, D T

    2008-06-16T23:59:59.000Z

    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.

  7. Technical Safety Requirements for the Waste Storage Facilities

    SciTech Connect (OSTI)

    Laycak, D T

    2010-03-05T23:59:59.000Z

    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.

  8. Central Waste Complex (CWC) Waste Analysis Plan

    SciTech Connect (OSTI)

    ELLEFSON, M.D.

    1999-12-01T23:59:59.000Z

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

  9. Radioactive Waste Management (Minnesota)

    Broader source: Energy.gov [DOE]

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

  10. D&D Waste Estimate Validation

    SciTech Connect (OSTI)

    Sanford, P. C.; Templeton, J. H.; Stevens, J. L.; Dorr, K.

    2002-02-25T23:59:59.000Z

    Rocky Flats Closure Project (Site) includes several multi-year decontamination and decommissioning (D&D) projects which, over the next four years, will dismantle and demolish four major plutonium facilities, four major uranium facilities, and over 400 additional facilities of different types. The projects are currently generating large quantities of transuranic, low-level, mixed, hazardous, and sanitary wastes. A previous paper described the initial conceptual estimates and methods, and the evolution of these methods based on the actual results from the decommissioning of a ''pilot'' facility. The waste estimating method that resulted from that work was used for the waste estimates incorporated into the current Site baseline. This paper discusses subsequent developments on the topic of waste estimating that have occurred since the baseline work. After several months of operation under the current Site baseline, an effort was initiated to either validate or identify improvements to the waste basis-of-estimate. Specific estimate and estimating method elements were identified for additional analysis based on the element's potential for error and the impact of that error on Site activities. The analysis took advantage of actual, more detailed data collected both from three years additional experience in decommissioning a second plutonium facility and from experience in deactivating certain non-plutonium facilities. It compared the actual transuranic and low-level waste generation against their respective estimates based on overall distribution and for individual media (i.e. equipment type), and evaluated trends. Finally, it projected the quantity of lead-characteristic low-level mixed waste that will be generated from plutonium building decommissioning and upgraded the decommissioning waste estimates of the non-plutonium buildings.

  11. Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities

    SciTech Connect (OSTI)

    Hladek, K.L.

    1997-10-07T23:59:59.000Z

    The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together) buried in three rows in the northeast comer. In addition, five eight-foot diameter caissons are located at the west end of the center row of the drum storage units. Initially, wastes disposed to the caissons and drum storage units were from the 325 and 327 building hot cells. Later, a small amount of remote-handled (RH) waste from the 309 building Plutonium Recycle Test Reactor (PRTR) cells, and the newly built 324 building hot cells, was disposed at the site.

  12. Building America

    SciTech Connect (OSTI)

    Brad Oberg

    2010-12-31T23:59:59.000Z

    Builders generally use a 'spec and purchase' business management system (BMS) when implementing energy efficiency. A BMS is the overall operational and organizational systems and strategies that a builder uses to set up and run its company. This type of BMS treats building performance as a simple technology swap (e.g. a tank water heater to a tankless water heater) and typically compartmentalizes energy efficiency within one or two groups in the organization (e.g. purchasing and construction). While certain tools, such as details, checklists, and scopes of work, can assist builders in managing the quality of the construction of higher performance homes, they do nothing to address the underlying operational strategies and issues related to change management that builders face when they make high performance homes a core part of their mission. To achieve the systems integration necessary for attaining 40% + levels of energy efficiency, while capturing the cost tradeoffs, builders must use a 'systems approach' BMS, rather than a 'spec and purchase' BMS. The following attributes are inherent in a systems approach BMS; they are also generally seen in quality management systems (QMS), such as the National Housing Quality Certification program: Cultural and corporate alignment, Clear intent for quality and performance, Increased collaboration across internal and external teams, Better communication practices and systems, Disciplined approach to quality control, Measurement and verification of performance, Continuous feedback and improvement, and Whole house integrated design and specification.

  13. Waste Management

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrincetonUsing Maps1DOE AwardsDNitrate Salt Bearing Waste

  14. APS Building Monitors

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

    Building Monitors For non-401 Building Monitors, select: LOMs Other APS Buildings 401 West WCtr Lab Wing ECtr East 5th Floor Yiying Ge na na na na 4th Floor Rick Fenner Karen...

  15. Building Performance Simulation

    E-Print Network [OSTI]

    Hong, Tianzhen

    2014-01-01T23:59:59.000Z

    a future with  very low energy buildings resulting in very consumption  of  low  energy  buildings,  with  site  EUI design and operation of low energy buildings through better 

  16. Thick Buildings [Standards

    E-Print Network [OSTI]

    Coffin, Christie Johnson

    1995-01-01T23:59:59.000Z

    on Occupant Behavior in Buildings, New Directions forSacramento, is a thin building that surrounds an atrium. (Performance of a Green Building," Urban UndQune 1992): 23-

  17. Building Energy Monitoring and Analysis

    E-Print Network [OSTI]

    Hong, Tianzhen

    2014-01-01T23:59:59.000Z

    United States and China, Energy and Buildings, 2013. Underin Singapore. Energy and Buildings, 37, 167-174. Eom, J. ,building operations. Energy and Buildings, 33, 783–791.

  18. BUILDING PROCTOR rev. April 2014

    E-Print Network [OSTI]

    BUILDING PROCTOR MANUAL rev. April 2014 #12;Building Proctor Manual rev. April 2014 2 TABLE.........................................................................................................................................5 Role of a Building Proctor ..............................................................................................................5 Authority of Building Proctor

  19. Solid Waste (New Mexico)

    Broader source: Energy.gov [DOE]

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

  20. Radioactive Waste Management

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

    1984-02-06T23:59:59.000Z

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

  1. Hazardous Wastes Management (Alabama)

    Broader source: Energy.gov [DOE]

    This legislation gives regulatory authority to the Department of Environmental Management to monitor commercial sites for hazardous wastes; fees on waste received at such sites; hearings and...

  2. Transuranic Waste Requirements

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

    1999-07-09T23:59:59.000Z

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

  3. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

    1 Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives...

  4. Quantifying capital goods for waste incineration

    SciTech Connect (OSTI)

    Brogaard, L.K., E-mail: lksb@env.dtu.dk [Department of Environmental Engineering, Building 115, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark); Riber, C. [Ramboll, Consulting Engineers, Hannemanns Allé 53, DK-2300 Copenhagen S (Denmark); Christensen, T.H. [Department of Environmental Engineering, Building 115, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark)

    2013-06-15T23:59:59.000Z

    Highlights: • Materials and energy used for the construction of waste incinerators were quantified. • The data was collected from five incineration plants in Scandinavia. • Included were six main materials, electronic systems, cables and all transportation. • The capital goods contributed 2–3% compared to the direct emissions impact on GW. - Abstract: Materials and energy used for the construction of modern waste incineration plants were quantified. The data was collected from five incineration plants (72,000–240,000 tonnes per year) built in Scandinavia (Norway, Finland and Denmark) between 2006 and 2012. Concrete for the buildings was the main material used amounting to 19,000–26,000 tonnes per plant. The quantification further included six main materials, electronic systems, cables and all transportation. The energy used for the actual on-site construction of the incinerators was in the range 4000–5000 MW h. In terms of the environmental burden of producing the materials used in the construction, steel for the building and the machinery contributed the most. The material and energy used for the construction corresponded to the emission of 7–14 kg CO{sub 2} per tonne of waste combusted throughout the lifetime of the incineration plant. The assessment showed that, compared to data reported in the literature on direct emissions from the operation of incinerators, the environmental impacts caused by the construction of buildings and machinery (capital goods) could amount to 2–3% with respect to kg CO{sub 2} per tonne of waste combusted.

  5. Unreviewed Safety Question Determination - Processing Waste in...

    Office of Environmental Management (EM)

    Unreviewed Safety Question Determination - Processing Waste in the Waste Characterization Glovebox Unreviewed Safety Question Determination - Processing Waste in the Waste...

  6. Buildings Interoperability Landscape ? DRAFT

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

    of Heating, Refrigerating, and Air-Conditioning Engineers BACS building automation and control system BCHP building-cooling-heating-power BPM Business Process Modeling BTO...

  7. Building Scale DC Microgrids

    E-Print Network [OSTI]

    Marnay, Chris

    2013-01-01T23:59:59.000Z

    Folsom CA, Integration of Renewable Resources: OperationalOffice of Energy Efficiency and Renewable Energy, BuildingOffice of Energy Efficiency and Renewable Energy, Building

  8. Office Buildings - Full Report

    Gasoline and Diesel Fuel Update (EIA)

    1). Table 1. Totals and means of of floorspace, number of workers, and hours of operation for office buildings, 2003 Buildings (thousand) Total Floorspace (million sq. ft.)...

  9. Westinghouse Waste Simulation and Optimization Software Tool - 13493

    SciTech Connect (OSTI)

    Mennicken, Kim [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Dudenstrasse 44, D-68167 Mannheim (Germany); Aign, Joerg [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)] [Westinghouse Electric Germany GmbH, Global Waste Management, Tarpenring 6, D-22419 Hamburg (Germany)

    2013-07-01T23:59:59.000Z

    Radioactive waste is produced during NPP operation and NPP D and D. Different kinds of waste with different volumes and properties have to be treated. Finding a technically and commercially optimized waste treatment concept is a difficult and time consuming process. The Westinghouse waste simulation and optimization software tool is an approach to study the total life cycle cost of any waste management facility. The tool enables the user of the simulation and optimization software to plan processes and storage buildings and to identify bottlenecks in the overall waste management design before starting detailed planning activities. Furthermore, application of the software enables the user to optimize the number of treatment systems, to determine the minimum design capacity for onsite storage facilities, to identify bottlenecks in the overall design and to identify the most cost-effective treatment paths by maintaining optimal waste treatment technologies. In combination with proven waste treatment equipment and integrated waste management solutions, the waste simulation and optimization software provides reliable qualitative results that lead to an effective planning and minimization of the total project planning risk of any waste management activity. (authors)

  10. Solid Waste and Infectious Waste Regulations (Ohio)

    Broader source: Energy.gov [DOE]

    This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste.

  11. Radioactive and chemotoxic wastes: Only radioactive wastes?

    SciTech Connect (OSTI)

    Eletti, G.F.; Tocci, M. [ENEA DISP, Rome (Italy)

    1993-12-31T23:59:59.000Z

    Radioactive waste arising from Italian Nuclear Power Plants and Research Centers, classified as 1st and 2nd Category wastes, are managed only as radioactive wastes following the Technical Guide No. 26 issued by the Italian Regulatory Body: ENEA DISP on 1987. A very important Regulatory Regime revision for Italian Nuclear Activities started at the end of 1991. This paper considers the need to develop a new strategy dedicated to mixed waste in line with current international trends.

  12. Solar buildings. Overview: The Solar Buildings Program

    SciTech Connect (OSTI)

    Not Available

    1998-04-01T23:59:59.000Z

    Buildings account for more than one third of the energy used in the United States each year, consuming vast amounts of electricity, natural gas, and fuel oil. Given this level of consumption, the buildings sector is rife with opportunity for alternative energy technologies. The US Department of Energy`s Solar Buildings Program was established to take advantage of this opportunity. The Solar Buildings Program is engaged in research, development, and deployment on solar thermal technologies, which use solar energy to produce heat. The Program focuses on technologies that have the potential to produce economically competitive energy for the buildings sector.

  13. Understanding the solidification and microstructure evolution during CSC-MIG welding of Fe–Cr–B-based alloy

    SciTech Connect (OSTI)

    Sorour, A.A., E-mail: ahmad.sorour@mail.mcgill.ca; Chromik, R.R., E-mail: richard.chromik@mcgill.ca; Gauvin, R., E-mail: raynald.gauvin@mcgill.ca; Jung, I.-H., E-mail: in-ho.jung@mcgill.ca; Brochu, M., E-mail: mathieu.brochu@mcgill.ca

    2013-12-15T23:59:59.000Z

    The present is a study of the solidification and microstructure of Fe–28.2%Cr–3.8%B–1.5%Si–1.5%Mn (wt.%) alloy deposited onto a 1020 plain carbon steel substrate using the controlled short-circuit metal inert gas welding process. The as-solidified alloy was a metal matrix composite with a hypereutectic microstructure. Thermodynamic calculation based on the Scheil–Gulliver model showed that a primary (Cr,Fe){sub 2}B phase formed first during solidification, followed by an eutectic formation of the (Cr,Fe){sub 2}B phase and a body-centered cubic Fe-based solid solution matrix, which contained Cr, Mn and Si. Microstructure analysis confirmed the formation of these phases and showed that the shape of the (Cr,Fe){sub 2}B phase was irregular plate. As the welding heat input increased, the weld dilution increased and thus the volume fraction of the (Cr,Fe){sub 2}B plates decreased while other microstructural characteristics were similar. - Highlights: • We deposit Fe–Cr–B-based alloy onto plain carbon steel using the CSC-MIG process. • We model the solidification behavior using thermodynamic calculation. • As deposited alloy consists of (Cr,Fe){sub 2}B plates embedded in Fe-based matrix. • We study the effect of the welding heat input on the microstructure.

  14. Unit operations used to treat process and/or waste streams at nuclear power plants. [R

    SciTech Connect (OSTI)

    Godbee, H.W.; Kibbey, A.H.

    1980-01-01T23:59:59.000Z

    Estimates are given of the annual amounts of each generic type of LLW (i.e., Government and commerical (fuel cycle and non-fuel cycle)) that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials (liquids (e.g., oils or solvents) and/or solids), could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends.

  15. Design and construction of the defense waste processing facility project at the Savannah River Plant

    SciTech Connect (OSTI)

    Baxter, R G

    1986-01-01T23:59:59.000Z

    The Du Pont Company is building for the Department of Energy a facility to vitrify high-level radioactive waste at the Savannah River Plant (SRP) near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes by immobilizing the waste in Processing Facility (DWPF) will solidify existing and future radioactives wastes by immobilizing the waste in borosilicate glass contained in stainless steel canisters. The canisters will be sealed, decontaminated and stored, prior to emplacement in a federal repository. At the present time, engineering and design is 90% complete, construction is 25% complete, and radioactive processing in the $870 million facility is expected to begin by late 1989. This paper describes the SRP waste characteristics, the DWPF processing, building and equipment features, and construction progress of the facility.

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

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

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

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

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

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

  18. Grout and Glass Performance in Support of Stabilization/Solidification of the MVST Tank Sludges

    SciTech Connect (OSTI)

    Gilliam, T.M.; Spence, R.D.

    1998-11-01T23:59:59.000Z

    Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) pending treatment for disposal. The waste separates into two phases: sludge and supematant. Some of the supematant from these tanks has been decanted, solidified into a grout, and stored for disposal as a solid low-level waste. The sludges in the tank bottoms have been accumulating ,for several years. Some of the sludges contain a high amount of gamma activity (e.g., `37CS concentration range of 0.01 3-11 MBq/g) and contain enough transuranic (TRU) radioisotopes to be classified as TRU wastes. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough in the available total constituent analysis for the MVST sludge to be classified as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste.

  19. Mixed waste storage facility CDR review, Paducah Gaseous Diffusion Plant; Solid waste landfill CDR review, Paducah Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    NONE

    1998-08-01T23:59:59.000Z

    This report consists of two papers reviewing the waste storage facility and the landfill projects proposed for the Paducah Gaseous Diffusion Plant complex. The first paper is a review of DOE`s conceptual design report for a mixed waste storage facility. This evaluation is to review the necessity of constructing a separate mixed waste storage facility. The structure is to be capable of receiving, weighing, sampling and the interim storage of wastes for a five year period beginning in 1996. The estimated cost is assessed at approximately $18 million. The review is to help comprehend and decide whether a new storage building is a feasible approach to the PGDP mixed waste storage problem or should some alternate approach be considered. The second paper reviews DOE`s conceptual design report for a solid waste landfill. This solid waste landfill evaluation is to compare costs and the necessity to provide a new landfill that would meet State of Kentucky regulations. The assessment considered funding for a ten year storage facility, but includes a review of other facility needs such as a radiation detection building, compactor/baler machinery, material handling equipment, along with other personnel and equipment storage buildings at a cost of approximately $4.1 million. The review is to help discern whether a landfill only or the addition of compaction equipment is prudent.

  20. Modeling Ventilation in Multifamily Buildings John Markley, University of California, Davis -Western Cooling Efficiency Center

    E-Print Network [OSTI]

    California at Davis, University of

    Modeling Ventilation in Multifamily Buildings John Markley, University of California, Davis Efficiency Center Garth Torvestad, Benningfield Group, inc. ABSTRACT Proper ventilation is an essential that require special consideration in order to avoid excessive ventilation and energy waste. Two issues

  1. 324 Building spent fuel segments pieces and fragments removal summary report

    SciTech Connect (OSTI)

    SMITH, C L

    2003-01-09T23:59:59.000Z

    As part of the 324 Building Deactivation Project, all Spent Nuclear Fuel (SNF) and Special Nuclear Material were removed. The removal entailed packaging the material into a GNS-12 cask and shipping it to the Central Waste Complex (CWC).

  2. Small- and Medium-Sized Commercial Building Monitoring and Controls Needs: A Scoping Study

    SciTech Connect (OSTI)

    Katipamula, Srinivas; Underhill, Ronald M.; Goddard, James K.; Taasevigen, Danny J.; Piette, M. A.; Granderson, J.; Brown, Rich E.; Lanzisera, Steven M.; Kuruganti, T.

    2012-10-31T23:59:59.000Z

    Buildings consume over 40% of the total energy consumption in the U.S. A significant portion of the energy consumed in buildings is wasted because of the lack of controls or the inability to use existing building automation systems (BASs) properly. Much of the waste occurs because of our inability to manage and controls buildings efficiently. Over 90% of the buildings are either small-size (<5,000 sf) or medium-size (between 5,000 sf and 50,000 sf); these buildings currently do not use BASs to monitor and control their building systems from a central location. According to Commercial Building Energy Consumption Survey (CBECS), about 10% of the buildings in the U.S. use BASs or central controls to manage their building system operations. Buildings that use BASs are typically large (>100,000 sf). Lawrence Berkeley National Laboratory (LBNL), Oak Ridge National Laboratory (ORNL) and Pacific Northwest National Laboratory (PNNL) were asked by the U.S. Department of Energy’s (DOE’s) Building Technologies Program (BTP) to identify monitoring and control needs for small- and medium-sized commercial buildings and recommend possible solutions. This study documents the needs and solutions for small- and medium-sized buildings.

  3. HAZARDOUS WASTE MANAGEMENT REFERENCE

    E-Print Network [OSTI]

    Faraon, Andrei

    Principal Investigators 7 Laboratory Personnel 8 EH&S Personnel 8 HAZARDOUS WASTE ACCUMULATION AREAS 9 Satellite Accumulation Area 9 Waste Accumulation Facility 10 HAZARDOUS WASTE CONTAINER MANAGEMENT LabelingHAZARDOUS WASTE MANAGEMENT REFERENCE GUIDE Prepared by Environment, Health and Safety Office

  4. Hazardous Waste Management Training

    E-Print Network [OSTI]

    Dai, Pengcheng

    records. The initial training of Hazardous Waste Management and Waste Minimization is done in a classHazardous Waste Management Training Persons (including faculty, staff and students) working before handling hazardous waste. Departments are re- quired to keep records of training for as long

  5. Better Buildings Neighborhood Program

    Broader source: Energy.gov [DOE]

    U.S. Department of Energy Better Buildings Neighborhood Program: Business Models Guide, October 27, 2011.

  6. NIST Preliminary Reconnaissance, Building

    E-Print Network [OSTI]

    Magee, Joseph W.

    NIST Preliminary Reconnaissance, Building Performance and Emergency Communications, Joplin)): Support R&D to improve building codes and standards and practices for design and construction of buildings of and data collection on the impact of severe wind on buildings, structures, and infrastructure ­ Section 204

  7. RESEARCH BUILDING AT NORTHWESTERN

    E-Print Network [OSTI]

    Engman, David M.

    BIOMEDICAL RESEARCH BUILDING AT NORTHWESTERN MEDICINE #12;"Our new Biomedical Research Building-intensive medical schools. Perkins+Will has designed a building that will be superbly functional and have great a magnificent 12-story Biomedical Research Building to address this priority. The new 600,000 square foot

  8. BUILDING MANAGEMENT & RESTRICTED ACCESS

    E-Print Network [OSTI]

    Johnston, Daniel

    BUILDING MANAGEMENT & RESTRICTED ACCESS Plan Annex 2014 VIII #12;#12;#12;The University of Texas at Austiniv #12;Building Management & Restricted Access Plan Annex v CONTENTS RECORD OF CHANGES .......................................................................................................15 J. BUILDING SECURITY OPERATIONS RESTRICTED ACCESS PROCEDURES FOR BUILDINGS ON ELECTRONIC ACCESS

  9. FOREST CENTRE STORAGE BUILDING

    E-Print Network [OSTI]

    deYoung, Brad

    FOREST CENTRE STORAGE BUILDING 3 4 5 6 7 8 UniversityDr. 2 1 G r e n f e l l D r i v e MULTI PURPOSE COURT STUDENT RESIDENCES GREEN HOUSE STUDENT RESIDENCES STUDENT RESIDENCES RECPLEX STORAGE BUILDING STORAGE BUILDING LIBRARY & COMPUTING FINE ARTS FOREST CENTRE ARTS &SCIENCE BUILDING ARTS &SCIENCE

  10. Community Development Building Division

    E-Print Network [OSTI]

    California Energy Commission 1516 Ninth Street Sacramento, Ca 95814-5514 Re: Green Building Ordinance of Los Altos Energy Efficiency Ordinance, Green Building Regulations under the 2005 California Building by the Board on that date. The Green Building Regulation, Chapter 12.66 of the City Municipal code, will ensure

  11. Central Waste Complex (CWC) Waste Analysis Plan

    SciTech Connect (OSTI)

    ELLEFSON, M.D.

    2000-01-06T23:59:59.000Z

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

  12. A BIM-based system for demolition and renovation waste estimation and planning

    SciTech Connect (OSTI)

    Cheng, Jack C.P., E-mail: cejcheng@ust.hk [Department of Civil and Environmental Engineering, The Hong Kong University of Science and Technology (Hong Kong); Ma, Lauren Y.H., E-mail: yingzi@ust.hk [Department of Civil and Environmental Engineering, The Hong Kong University of Science and Technology (Hong Kong)

    2013-06-15T23:59:59.000Z

    Highlights: ? We developed a waste estimation system leveraging the BIM technology. ? The system can calculate waste disposal charging fee and pick-up truck demand. ? We presented an example scenario demonstrating this system. ? Automatic, time-saving and wide applicability are the features of the system. - Abstract: Due to the rising worldwide awareness of green environment, both government and contractors have to consider effective construction and demolition (C and D) waste management practices. The last two decades have witnessed the growing importance of demolition and renovation (D and R) works and the growing amount of D and R waste disposed to landfills every day, especially in developed cities like Hong Kong. Quantitative waste prediction is crucial for waste management. It can enable contractors to pinpoint critical waste generation processes and to plan waste control strategies. In addition, waste estimation could also facilitate some government waste management policies, such as the waste disposal charging scheme in Hong Kong. Currently, tools that can accurately and conveniently estimate the amount of waste from construction, renovation, and demolition projects are lacking. In the light of this research gap, this paper presents a building information modeling (BIM) based system that we have developed for estimation and planning of D and R waste. BIM allows multi-disciplinary information to be superimposed within one digital building model. Our system can extract material and volume information through the BIM model and integrate the information for detailed waste estimation and planning. Waste recycling and reuse are also considered in our system. Extracted material information can be provided to recyclers before demolition or renovation to make recycling stage more cooperative and more efficient. Pick-up truck requirements and waste disposal charging fee for different waste facilities will also be predicted through our system. The results could provide alerts to contractors ahead of time at project planning stage. This paper also presents an example scenario with a 47-floor residential building in Hong Kong to demonstrate our D and R waste estimation and planning system. As the BIM technology has been increasingly adopted in the architectural, engineering and construction industry and digital building information models will likely to be available for most buildings (including historical buildings) in the future, our system can be used in various demolition and renovation projects and be extended to facilitate project control.

  13. TRU waste inventory collection and work off plans for the centralization of TRU waste characterization/certification at INL - on your mark - get set - 9410

    SciTech Connect (OSTI)

    Mctaggert, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila A [Los Alamos National Laboratory; Gadbury, Casey [CBFO

    2008-01-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage of Transuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization of this TRU waste will avoid the cost of building treatment, characterization, certification, and shipping capabilities at each of the small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all of the small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number of waste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTF at the INL will reduce the volume of much of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

  14. Re-Assessing Green Building Performance: A Post Occupancy Evaluation of 22 GSA Buildings

    SciTech Connect (OSTI)

    Fowler, Kimberly M.; Rauch, Emily M.; Henderson, Jordan W.; Kora, Angela R.

    2010-06-01T23:59:59.000Z

    2nd report on the performance of GSA's sustainably designed buildings. The purpose of this study was to provide an overview of measured whole building performance as it compares to GSA and industry baselines. The PNNL research team found the data analysis illuminated strengths and weaknesses of individual buildings as well as the portfolio of buildings. This section includes summary data, observations that cross multiple performance metrics, discussion of lessons learned from this research, and opportunities for future research. The summary of annual data for each of the performance metrics is provided in Table 25. The data represent 1 year of measurements and are not associated with any specific design features or strategies. Where available, multiple years of data were examined and there were minimal significant differences between the years. Individually focused post occupancy evaluation (POEs) would allow for more detailed analysis of the buildings. Examining building performance over multiple years could potentially offer a useful diagnostic tool for identifying building operations that are in need of operational changes. Investigating what the connection is between the building performance and the design intent would offer potential design guidance and possible insight into building operation strategies. The 'aggregate operating cost' metric used in this study represents the costs that were available for developing a comparative industry baseline for office buildings. The costs include water utilities, energy utilities, general maintenance, grounds maintenance, waste and recycling, and janitorial costs. Three of the buildings that cost more than the baseline in Figure 45 have higher maintenance costs than the baseline, and one has higher energy costs. Given the volume of data collected and analyzed for this study, the inevitable request is for a simple answer with respect to sustainably designed building performance. As previously stated, compiling the individual building values into single metrics is not statistically valid given the small number of buildings, but it has been done to provide a cursory view of this portfolio of sustainably designed buildings. For all metrics except recycling cost per rentable square foot and CBE survey response rate, the averaged building performance was better than the baseline for the GSA buildings in this study.

  15. SECONDARY WASTE/ETF (EFFLUENT TREATMENT FACILITY) PRELIMINARY PRE-CONCEPTUAL ENGINEERING STUDY

    SciTech Connect (OSTI)

    MAY TH; GEHNER PD; STEGEN GARY; HYMAS JAY; PAJUNEN AL; SEXTON RICH; RAMSEY AMY

    2009-12-28T23:59:59.000Z

    This pre-conceptual engineering study is intended to assist in supporting the critical decision (CD) 0 milestone by providing a basis for the justification of mission need (JMN) for the handling and disposal of liquid effluents. The ETF baseline strategy, to accommodate (WTP) requirements, calls for a solidification treatment unit (STU) to be added to the ETF to provide the needed additional processing capability. This STU is to process the ETF evaporator concentrate into a cement-based waste form. The cementitious waste will be cast into blocks for curing, storage, and disposal. Tis pre-conceptual engineering study explores this baseline strategy, in addition to other potential alternatives, for meeting the ETF future mission needs. Within each reviewed case study, a technical and facility description is outlined, along with a preliminary cost analysis and the associated risks and benefits.

  16. The interfacial chemistry of solidification/stabilization of metals in cement and pozzolanic material systems

    SciTech Connect (OSTI)

    Yousuf, M.; Mollah, A.; Vempati, R.K.; Lin, T.C.; Cocke, D.L. [Lamar Univ., Beaumont, TX (United States)] [Lamar Univ., Beaumont, TX (United States)

    1995-11-01T23:59:59.000Z

    The chemistry of cement, its hydration and mechanisms of solidification/stabilization (s/s) of toxic metals by cement-based systems and pozzolanic materials are significantly controlled by surface, near-surface and interfacial phenomena. The adsorption conditions and the selectivity strong affinity of hazardous metals towards clay minerals, certain hydrated metal oxides and oxyhydroxides, and cementitous substances also play an important role in the s/s process for the immobilization of contaminants. Recent works from the authors` laboratory involving metal ions and superplasticizers have elucidated the mechanisms of reactions leading to the retardation of cement hydration and subsequent setting and their interactions with silicate-based systems. This article delineates the current status of interfacial chemistry at the solid-liquid boundary and places it in perspective with present and future s/s processes based on Portland cement and pozzolanic materials. The importance of surface charge, the role of interfacial phenomena on adsorption, and the importance of calcium and other types of anions and cations in s/s are also discussed. A surface charge control reaction model that accounts for the importance of calcium and other cations and anions is outlined and used to discuss the chemical nature and microstructure of the interfacial transition zone.

  17. Microstructural and solidification cracking evaluation of electron beam welds in 304L

    SciTech Connect (OSTI)

    Sturgill, P.L.; Campbell, R.D.; Henningsen, J.L.

    1991-01-01T23:59:59.000Z

    Weld hot cracking of stainless steels is a major materials-related problem in the welding industry. This present investigation evaluates the crack susceptibility of highly-constrained EB welds made in materials whose DeLong ferrite potentials range from zero to nine FN. In addition, the effect of piece part strength level on cracking is examined. This study has revealed that these deep penetration EB welds have regions that solidify as primary austenite, even when the DeLong ferrite potential is as high as 9 FN. This points out the critical role that solidification rate plays in the crack susceptibility of these highly restrained welds. In addition, 0 FN to 0 FN welds had primarily transverse cracks while 6 FN to 0 FN welds had primarily centerline cracks. Of particular interest is the observation that cracks still occur if a high ferrite (greater than 6 FN) component is welded to a zero FN component. Cracking is always associated with regions which solidify as primary austenite and these cracks occur because there are areas in the weld which do not mix. Thus it is not a recommended production practice to compensate for low ferrite in one piece part with high ferrite in its mate. Finally, it is shown that a DeLong FN threshold of 4 to prevent cracking in EB welds in not valid. 21 refs., 16 figs.

  18. Three dimensional thermal-solute phase field simulation of binary alloy solidification

    E-Print Network [OSTI]

    P. C. Bollada; C. E. Goodyer; P. K. Jimack; A. M. Mullis; F. W. Yang

    2014-09-22T23:59:59.000Z

    We employ adaptive mesh refinement, implicit time stepping, a nonlinear multigrid solver and parallel computation, to solve a multi-scale, time dependent, three dimensional, nonlinear set of coupled partial differential equations for three scalar field variables. The mathematical model represents the non-isothermal solidification of a metal alloy into a melt substantially cooled below its freezing point at the microscale. Underlying physical molecular forces are captured at this scale by a specification of the energy field. The time rate of change of the temperature, alloy concentration and an order parameter to govern the state of the material (liquid or solid) is controlled by the diffusion parameters and variational derivatives of the energy functional. The physical problem is important to material scientists for the development of solid metal alloys and, hitherto, this fully coupled thermal problem has not been simulated in three dimensions, due to its computationally demanding nature. By bringing together state of the art numerical techniques this problem is now shown here to be tractable at appropriate resolution with relatively moderate computational resources.

  19. Flow and morphological conditions associated with the directional solidification of aqueous ammonium chloride

    SciTech Connect (OSTI)

    Magirl, C.S.; Incropera, F.P.

    1993-01-01T23:59:59.000Z

    Using 27% aq. NH[sub 4]Cl solutions as transparent analog, shadowgraphy and dye injection were used to observe flow and morphology in unidirectional solidification (UDS) from below. Dendritic crystals that form at the cold surface reject lighter, solute-deficient fluid, and instability is shown by finger-type double-diffusive convection. As the mushy two-phase region grows, perturbations at the liquidus interface cause localized remelting and downward development of channels. Solsutal plumes emanate from the channels, and in time, double-diffusive convection layers also form in the melt. When the solution is chilled at the sides as well as at the bottom, conditions are influenced by detachment and settling of crystals from the sidewall and by plumes from slanted channels. When a slow, oscillatory rocking motion is imposed on UDS, the freckle-type segregates in the final cast is suppressed. Within the melt, plumes and double-diffusive convection are eliminated. Inertially induced convection mixes the melt and produces a dense slurry. Although channels are eliminated from the bottom mushy region, overall heat transfer and macrosegregation in the cavity are unaffected by the slow rocking. Numerical simulations qualitatively predict trends in the field variables and provide insights on interdendritic flows and macrosegregation (freckle-, A-type segregates), although its quantitative predictions are hampered by simplifying assumptions.

  20. Flow and morphological conditions associated with the directional solidification of aqueous ammonium chloride. Annual performance report

    SciTech Connect (OSTI)

    Magirl, C.S.; Incropera, F.P.

    1993-01-01T23:59:59.000Z

    Using 27% aq. NH{sub 4}Cl solutions as transparent analog, shadowgraphy and dye injection were used to observe flow and morphology in unidirectional solidification (UDS) from below. Dendritic crystals that form at the cold surface reject lighter, solute-deficient fluid, and instability is shown by finger-type double-diffusive convection. As the mushy two-phase region grows, perturbations at the liquidus interface cause localized remelting and downward development of channels. Solsutal plumes emanate from the channels, and in time, double-diffusive convection layers also form in the melt. When the solution is chilled at the sides as well as at the bottom, conditions are influenced by detachment and settling of crystals from the sidewall and by plumes from slanted channels. When a slow, oscillatory rocking motion is imposed on UDS, the freckle-type segregates in the final cast is suppressed. Within the melt, plumes and double-diffusive convection are eliminated. Inertially induced convection mixes the melt and produces a dense slurry. Although channels are eliminated from the bottom mushy region, overall heat transfer and macrosegregation in the cavity are unaffected by the slow rocking. Numerical simulations qualitatively predict trends in the field variables and provide insights on interdendritic flows and macrosegregation (freckle-, A-type segregates), although its quantitative predictions are hampered by simplifying assumptions.

  1. Understanding radioactive waste

    SciTech Connect (OSTI)

    Murray, R.L.

    1981-12-01T23:59:59.000Z

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

  2. Radioactive mixed waste disposal

    SciTech Connect (OSTI)

    Jasen, W.G.; Erpenbeck, E.G.

    1993-02-01T23:59:59.000Z

    Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

  3. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

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

  4. Radium bearing waste disposal

    SciTech Connect (OSTI)

    Tope, W.G.; Nixon, D.A.; Smith, M.L.; Stone, T.J.; Vogel, R.A. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Schofield, W.D. [Foster Wheeler Environmental Corp. (United States)

    1995-07-01T23:59:59.000Z

    Fernald radium bearing ore residue waste, stored within Silos 1 and 2 (K-65) and Silo 3, will be vitrified for disposal at the Nevada Test Site (NTS). A comprehensive, parametric evaluation of waste form, packaging, and transportation alternatives was completed to identify the most cost-effective approach. The impacts of waste loading, waste form, regulatory requirements, NTS waste acceptance criteria, as-low-as-reasonably-achievable principles, and material handling costs were factored into the recommended approach.

  5. Management of immunization solid wastes in Kano State, Nigeria

    SciTech Connect (OSTI)

    Oke, I.A. [Civil Engineering Department, Obafemi Awolowo University, Ile-Ife (Nigeria)], E-mail: okeia@oauife.edu.ng

    2008-12-15T23:59:59.000Z

    Inadequate management of waste generated from injection activities can have a negative impact on the community and environment. In this paper, a report on immunization wastes management in Kano State (Nigeria) is presented. Eight local governments were selected randomly and surveyed by the author. Solid wastes generated during the Expanded Programme on Immunization were characterised using two different methods: one by weighing the waste and the other by estimating the volume. Empirical data was obtained on immunization waste generation, segregation, storage, collection, transportation, and disposal; and waste management practices were assessed. The study revealed that immunization offices were accommodated in either in local government buildings, primary health centres or community health care centres. All of the stations demonstrated a high priority for segregation of the infectious wastes. It can be deduced from the data obtained that infectious waste ranged from 67.6% to 76.7% with an average of 70.1% by weight, and 36.0% to 46.1% with an average of 40.1% by volume. Non-infectious waste generated ranged from 23.3% to 32.5% with an average of 29.9% by weight and 53.9% to 64.0% with an average of 59.9% by volume. Out of non-infectious waste (NIFW) and infectious waste (IFW), 66.3% and 62.4% by weight were combustible and 33.7% and 37.6% were non-combustible respectively. An assessment of the treatment revealed that open pit burning and burial and small scale incineration were the common methods of disposal for immunization waste, and some immunization centres employed the services of the state or local government owned solid waste disposal board for final collection and disposal of their immunization waste at government approved sites.

  6. House Simulation Protocols (Building America Benchmark) - Building...

    Energy Savers [EERE]

    House Simulation Protocols. See an example of this Top Innovation in action. Find more case studies of Building America projects across the country that utilize House Simulation...

  7. Building Green in Greensburg: Business Incubator Building

    Office of Energy Efficiency and Renewable Energy (EERE)

    This poster highlights energy efficiency, renewable energy, and sustainable features of the high-performing SunChips Business Incubator building in Greensburg, Kansas.

  8. Building Green in Greensburg: City Hall Building

    Office of Energy Efficiency and Renewable Energy (EERE)

    This poster highlights energy efficiency, renewable energy, and sustainable features of the high-performing City Hall building in Greensburg, Kansas.

  9. Release of radionuclides and chelating agents from cement-solidified decontamination low-level radioactive waste collected from the Peach Bottom Atomic Power Station Unit 3

    SciTech Connect (OSTI)

    Akers, D.W.; Kraft, N.C.; Mandler, J.W. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

    1994-03-01T23:59:59.000Z

    As part of a study being performed for the Nuclear Regulatory Commission (NRC), small-scale waste-form specimens were collected during a low oxidation-state transition-metal ion (LOMI)-nitric permanganate (NP)-LOMI solidification performed in October 1989 at the Peach Bottom Atomic Power Station Unit 3. The purpose of this program was to evaluate the performance of cement-solidified decontamination waste to meet the low-level waste stability requirements defined in the NRC`s ``Technical Position on Waste Form,`` Revision 1. The samples were acquired and tested because little data have been obtained on the physical stability of actual cement-solidified decontamination ion-exchange resin waste forms and on the leachability of radionuclides and chelating agents from those waste forms. The Peach Bottom waste-form specimens were subjected to compressive strength, immersion, and leach testing in accordance with the NRC`s ``Technical Position on Waste Form,`` Revision 1. Results of this study indicate that the specimens withstood the compression tests (>500 psi) before and after immersion testing and leaching, and that the leachability indexes for all radionuclides, including {sup 14}C, {sup 99}{Tc}, and {sup 129}I, are well above the leachability index requirement of 6.0, required by the NRC`s ``Technical Position on Waste Form,`` Revision 1.

  10. Hazardous Waste Act (New Mexico)

    Broader source: Energy.gov [DOE]

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

  11. Georgia Hazardous Waste Management Act

    Broader source: Energy.gov [DOE]

    The Georgia Hazardous Waste Management Act (HWMA) describes a comprehensive, Statewide program to manage hazardous wastes through regulating hazardous waste generation, transportation, storage,...

  12. Waste Management Quality Assurance Plan

    E-Print Network [OSTI]

    Waste Management Group

    2006-01-01T23:59:59.000Z

    Revision 6 Waste Management Quality Assurance Plan Waste6 WM QA Plan Waste Management Quality Assurance Plan LBNL/4 Management Quality Assurance

  13. waste | netl.doe.gov

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

    AlternativesSupplements to Coal - Feedstock Flexibility Waste Streams Gasification can be applied to a variety of waste streams, of which municipal solid waste (MSW) and...

  14. BUILDING MATERIALS RECLAMATION PROGRAM

    SciTech Connect (OSTI)

    David C. Weggel; Shen-En Chen; Helene Hilger; Fabien Besnard; Tara Cavalline; Brett Tempest; Adam Alvey; Madeleine Grimmer; Rebecca Turner

    2010-08-31T23:59:59.000Z

    This report describes work conducted on the Building Materials Reclamation Program for the period of September 2008 to August 2010. The goals of the project included selecting materials from the local construction and demolition (C&D) waste stream and developing economically viable reprocessing, reuse or recycling schemes to divert them from landfill storage. Educational resources as well as conceptual designs and engineering feasibility demonstrations were provided for various aspects of the work. The project was divided into two distinct phases: Research and Engineering Feasibility and Dissemination. In the Research Phase, a literature review was initiated and data collection commenced, an advisory panel was organized, and research was conducted to evaluate high volume C&D materials for nontraditional use; five materials were selected for more detailed investigations. In the Engineering Feasibility and Dissemination Phase, a conceptual study for a regional (Mecklenburg and surrounding counties) collection and sorting facility was performed, an engineering feasibility project to demonstrate the viability of recycling or reuse schemes was created, the literature review was extended and completed, and pedagogical materials were developed. Over the two-year duration of the project, all of the tasks and subtasks outlined in the original project proposal have been completed. The Final Progress Report, which briefly describes actual project accomplishments versus the tasks/subtasks of the original project proposal, is included in Appendix A of this report. This report describes the scientific/technical aspects (hypotheses, research/testing, and findings) of six subprojects that investigated five common C&D materials. Table 1 summarizes the six subprojects, including the C&D material studied and the graduate student and the faculty advisor on each subproject.

  15. Public Comment Period for Portsmouth Site D&D and Waste Disposition...

    Office of Environmental Management (EM)

    2014 8:00AM EST to March 11, 2015 5:00PM EDT Public Comment Period for the Process Buildings and Complex Facilities Decontamination and Decommissioning and Site-Wide Waste...

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

    Broader source: Energy.gov [DOE]

    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...

  17. Tank waste remediation system (TWRS) privatization contractor samples waste envelope D material 241-C-106

    SciTech Connect (OSTI)

    Esch, R.A.

    1997-04-14T23:59:59.000Z

    This report represents the Final Analytical Report on Tank Waste Remediation System (TWRS) Privatization Contractor Samples for Waste Envelope D. All work was conducted in accordance with ''Addendum 1 of the Letter of Instruction (LOI) for TWRS Privatization Contractor Samples Addressing Waste Envelope D Materials - Revision 0, Revision 1, and Revision 2.'' (Jones 1996, Wiemers 1996a, Wiemers 1996b) Tank 241-C-1 06 (C-106) was selected by TWRS Privatization for the Part 1A Envelope D high-level waste demonstration. Twenty bottles of Tank C-106 material were collected by Westinghouse Hanford Company using a grab sampling technique and transferred to the 325 building for processing by the Pacific Northwest National Laboratory (PNNL). At the 325 building, the contents of the twenty bottles were combined into a single Initial Composite Material. This composite was subsampled for the laboratory-scale screening test and characterization testing, and the remainder was transferred to the 324 building for bench-scale preparation of the Privatization Contractor samples.

  18. WRPS MEETING THE CHALLENGE OF TANK WASTE

    SciTech Connect (OSTI)

    BRITTON JC

    2012-02-21T23:59:59.000Z

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

  19. Joseph Vance Building, The

    High Performance Buildings Database

    Seattle, WA In 2006, the Rose Smart Growth Investment Fund acquired the historic Joseph Vance Building with the purpose of transforming it into "the leading green and historic class B" building in the marketplace. The terra cotta Vance Building was constructed in 1929 and has 14 floors - 13 floors of offices over ground-floor retail with a basement for mechanical equipment and storage. In 2009 the U.S. Green Building Council (USGBC) awarded the Vance Building LEED for Existing Buildings (EB) Gold certification.

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

    Office of Environmental Management (EM)

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

  1. TREATMENT OF METAL-LADEN HAZARDOUS WASTES WITH ADVANCED CLEAN COAL TECHNOLOGY BY-PRODUCTS

    SciTech Connect (OSTI)

    James T. Cobb, Jr.

    2003-09-12T23:59:59.000Z

    Metal-laden wastes can be stabilized and solidified using advanced clean coal technology by-products (CCTBs)--fluid bed combustor ash and spray drier solids. These utility-generated treatment chemicals are available for purchase through brokers, and commercial applications of this process are being practiced by treaters of metal-laden hazardous waste. A complex of regulations governs this industry, and sensitivities to this complex has discouraged public documentation of treatment of metal-laden hazardous wastes with CCTBs. This report provides a comprehensive public documentation of laboratory studies that show the efficacy of the stabilization and solidification of metal-laden hazardous wastes--such as lead-contaminated soils and sandblast residues--through treatment with CCTBs. It then describes the extensive efforts that were made to obtain the permits allowing a commercial hazardous waste treater to utilize CCTBs as treatment chemicals and to install the equipment required to do so. It concludes with the effect of this lengthy process on the ability of the treatment company to realize the practical, physical outcome of this effort, leading to premature termination of the project.

  2. Building America Top Innovations Hall of Fame Profile - Building...

    Energy Savers [EERE]

    Top Innovations Hall of Fame Profile - Building America's Top Innovations Propel the Home Building Industry toward Higher Performance Building America Top Innovations Hall of Fame...

  3. Building Science-Based Climate Maps - Building America Top Innovation...

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

    Science-Based Climate Maps - Building America Top Innovation Building Science-Based Climate Maps - Building America Top Innovation Photo showing climate zone maps based on the IECC...

  4. Trends in Commercial Buildings--Buildings and Floorspace

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

    Home > Trends in Commercial Buildings > Trends in Buildings Floorspace Data tables Commercial Buildings TrendDetail Commercial Floorspace TrendDetail Background: Adjustment to...

  5. Building operating systems services: An architecture for programmable buildings.

    E-Print Network [OSTI]

    Dawson-Haggerty, Stephen

    2014-01-01T23:59:59.000Z

    7.3.2 Building Performance Analysis . . . . . . 7.4 RelatedWork 2.1 Building Physical Design . . . . . . . . . .3.2.6 Building Applications . . . . . . . . . . .

  6. Solid waste operations complex W-113: Preliminary design report. Volume I

    SciTech Connect (OSTI)

    NONE

    1995-01-01T23:59:59.000Z

    This document is Volume I of a Preliminary Design Report (Title I) for the Solid Waste Retrieval Facilities-Phase I (Project W-113) at Hanford. It was prepared by Raytheon and BNFL Inc. and submitted to Westinghouse Hanford Company in January 1995. This volume provides a project overview and a discussion of the waste handling systems, the data acquisition and control systems, the building systems, and the site/building structure.

  7. The dilemma of siting a high-level nuclear waste repository

    SciTech Connect (OSTI)

    Easterline, D.; Kunreuther, H.

    1995-12-31T23:59:59.000Z

    This books presents a siting process that the authors believe will prove successful within the adversarial world that characterizes most attempts to build waste-disposal facilities. They come to the following conclusions: a volunatary siting process stands the best chance of breaking the `not-in-my-backyard` problem; and without public acknowledgement that a facility is needed, any proposal to build a high-level nuclear waste storage facility will meet with opposition.

  8. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

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

  9. Decommissioning and Dismantling of Liquid Waste Storage and Liquid Waste Treatment Facility from Paldiski Nuclear Site, Estonia

    SciTech Connect (OSTI)

    Varvas, M. [AS ALARA, Leetse tee 21, Paldiski, 76806 (Estonia); Putnik, H. [Delegation of the European Commission to Russia, Kadashevskaja nab. 14/1 119017 Moscow (Russian Federation); Nirvin, B.; Pettersson, S. [SKB, Box 5864, Stockholm, SE-102 40 (Sweden); Johnsson, B. [Studsvik RadWaste, Nykoping, SE-611 82 (Sweden)

    2006-07-01T23:59:59.000Z

    The Paldiski Nuclear Facility in Estonia, with two nuclear reactors was owned by the Soviet Navy and was used for training the navy personnel to operate submarine nuclear reactors. After collapse of Soviet Union the Facility was shut down and handed over to the Estonian government in 1995. In co-operation with the Paldiski International Expert Reference Group (PIERG) decommission strategy was worked out and started to implement. Conditioning of solid and liquid operational waste and dismantling of contaminated installations and buildings were among the key issues of the Strategy. Most of the liquid waste volume, remained at the Facility, was processed in the frames of an Estonian-Finnish co-operation project using a mobile wastewater purification unit NURES (IVO International OY) and water was discharged prior to the site take-over. In 1999-2002 ca 120 m{sup 3} of semi-liquid tank sediments (a mixture of ion exchange resins, sand filters, evaporator and flocculation slurry), remained after treatment of liquid waste were solidified in steel containers and stored into interim storage. The project was carried out under the Swedish - Estonian co-operation program on radiation protection and nuclear safety. Contaminated installations in buildings, used for treatment and storage of liquid waste (Liquid Waste Treatment Facility and Liquid Waste Storage) were then dismantled and the buildings demolished in 2001-2004. (authors)

  10. Brownfield reuse of dredged New York Harbor sediment by cement-based solidification/stabilization

    SciTech Connect (OSTI)

    Loest, K. [ECDC Environmental L.C., Pembroke, MA (United States). Eastern Operations; Wilk, C.M. [Portland Cement Association, Skokie, IL (United States)

    1998-12-31T23:59:59.000Z

    Newly effective federal regulations restrict the ocean disposal of sediments dredged from the harbors of New York and Newark. The New York Port Authority is faced with a critical situation: find land-based disposal/uses for 10`s of millions cubic yards of sediments or lose standing as a commercial port for ocean-going ships. One of the technologies now being employed to manage the sediments is portland cement-based solidification/stabilization (S/S) treatment. At least 4 million cubic yards of the sediments will undergo cement-based S/S treatment. This treatment will immobilize heavy metals, dioxin, PCBs and other organic contaminants in the sediment. The treatment changes the sediment from a environmental liability into a valuable structural fill. This structural fill is being used at two properties. The first property is an old municipal landfill in Port Newark, New Jersey. The treated sediments are being used as structural fill to cover about 20 acres of the landfill. This will allow planned redevelopment of the landfill property into a shopping mall. The second property called the Seaboard site, was the location of a coal gasification facility and later a wood preservation facility. This 160-acre property has been designated for brownfield redevelopment. Over 4 million cubic yards of treated sediments will eventually cover this site. Portland cement is the selected S/S binding reagent. Nearly 500,000 tons of cement will eventually be used to treat the sediments. Cement was selected for its ability to (a) change the peanut butter-like consistency of the sediments into a structural material and (b) to physically and chemically immobilize hazardous constituents in the sediment.

  11. BuildingName The Description of the Project

    E-Print Network [OSTI]

    Kamat, Vineet R.

    . Construction of new masonry and drywall/metal stud walls and partitions. 4. Architectural finishes and interior natural gas, vacuum, domestic hot and cold water, purified water piping, and drainage, waste and vent SERVICES (BFS). FOR A COMPLETE LISTING, REFER TO DESIGN GUIDELINE SID-F. B. The building in which

  12. Radiological Laboratory, Utility, Office Building LEED Strategy & Achievement

    SciTech Connect (OSTI)

    Seguin, Nicole R. [Los Alamos National Laboratory

    2012-07-18T23:59:59.000Z

    Missions that the Radiological Laboratory, utility, Office Building (RLUOB) supports are: (1) Nuclear Materials Handling, Processing, and Fabrication; (2) Stockpile Management; (3) Materials and Manufacturing Technologies; (4) Nonproliferation Programs; (5) Waste Management Activities - Environmental Programs; and (6) Materials Disposition. The key capabilities are actinide analytical chemistry and material characterization.

  13. Building Name: ____________________________________________ Address: __________________________________________ Completed by: ___________________________________________ Date: ______________ File Number: ___________________

    E-Print Network [OSTI]

    s Rated Btu input Condition s Combustion air: is there at least one square inch free area per 2,000 Btu input? s Fuel or combustion odors Cooling Tower s Clean? no leaks or overflow? Slime or algae growth? s Waste oil and refrigerant properly stored and disposed of? #12;Building Name

  14. NEBRASKA WATER RESOURCES RESEARCH INSTITUTE 212 AGRICULTURAL ENGINEERING BUILDING

    E-Print Network [OSTI]

    Nebraska-Lincoln, University of

    NEBRASKA WATER RESOURCES RESEARCH INSTITUTE 212 AGRICULTURAL ENGINEERING BUILDING THE UNIVERSITY Resources Research Institute, 212 Agricultural ~ngineering, East Campus. OBJECTIVES OF THE NWRRI The Hater for centralization of data collection, analysis, storage and retrieval waste-water reuse economics of pollution

  15. Solid Waste Management Written Program

    E-Print Network [OSTI]

    Pawlowski, Wojtek

    Solid Waste Management Program Written Program Cornell University 8/28/2012 #12;Solid Waste.................................................................... 4 4.2.1 Compost Solid Waste Treatment Facility.................................................................... 4 4.2.2 Pathological Solid Waste Treatment Facility

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

    SciTech Connect (OSTI)

    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

    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.

  17. Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  18. Building, landscape and section

    E-Print Network [OSTI]

    Johnson, Daniel B. (Daniel Bryant)

    1992-01-01T23:59:59.000Z

    All buildings have in their section a relationship to the landscape on which they are sited. Therefore we as inhabitants of these buildings may or may not have a relationship with the landscape. It is the supposition of ...

  19. Special Building Renovations

    Broader source: Energy.gov [DOE]

    A number of building types have specific energy uses and needs, and as such the renewable opportunities may be different from a typical office building. This section briefly discusses the following...

  20. Model Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  1. APS Building Managers

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

    Building Managers BUILDING CONTACT 400,401,402,411,412,413,415,420,431-436,438 Steven Downey 450 Glenn Kailus 382 Joe Gagliano 378 Ed Theres 314 Ed Russell...

  2. Building Energy Code

    Broader source: Energy.gov [DOE]

    Note: Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For more...

  3. Building Energy Code

    Broader source: Energy.gov [DOE]

    ''Note: Much of the information presented in this summary is drawn from the U.S. Department of Energy’s (DOE) Building Energy Codes Program and the Building Codes Assistance Project (BCAP). For...

  4. Financing green buildings

    E-Print Network [OSTI]

    Pierce, Christopher John, S.M. Massachusetts Institute of Technology

    2013-01-01T23:59:59.000Z

    An emerging trend in real estate is the development of sustainable buildings, partially due to the huge environmental impact of the design, construction and operation of commercial buildings. This thesis provides a brief ...

  5. Building Energy Code

    Broader source: Energy.gov [DOE]

    In 2009 S.B. 1182 created the Oklahoma Uniform Building Code Commission. The 11-member Commission was given the power to conduct rulemaking processes to adopt new building codes. The codes adopted...

  6. Building Energy Code

    Broader source: Energy.gov [DOE]

    Prior to 1997, South Carolina's local governments adopted and enforced the building codes. In 1997, the law required statewide use of the most up-to-date building codes, which then required the...

  7. Change in historic buildings

    E-Print Network [OSTI]

    Yin, Chien-Ni

    1992-01-01T23:59:59.000Z

    Change in historic buildings is inevitable. If these changes are not well-managed, the cityscape will be threatened because a city is composed of buildings. A good city should combine both growth and preservation. Controlling ...

  8. PROGRESS IN ENERGY EFFICIENT BUILDINGS

    E-Print Network [OSTI]

    Wall, L.W.

    2009-01-01T23:59:59.000Z

    I Figure 21. Sample building energy use label expressed inanalyses of actual buildings energy consumption data confirm1983. PROGRESS IN ENERGY EFFICIENT BUILDINGS Leonard W. Wall

  9. The Economics of Green Building

    E-Print Network [OSTI]

    Eichholtz, Piet; Kok, Nils; Quigley, John M.

    2010-01-01T23:59:59.000Z

    Benjamin. "Do LEED-Certified Buildings Save Energy? Yes,But,." Energy and Buildings, 2009, 41, pp. 897-905. Royalrating, and publicizing buildings along these dimensions (

  10. Building Energy Monitoring and Analysis

    E-Print Network [OSTI]

    Hong, Tianzhen

    2014-01-01T23:59:59.000Z

    Center for Building Energy Efficiency, and the China Center on Building Energy Efficiency (CERC-BEE) November,1)  CERC  Building  Energy  Efficiency  (CERC?BEE) 

  11. The Economics of Green Building

    E-Print Network [OSTI]

    Eichholtz, Piet; Kok, Nils; Quigley, John M.

    2010-01-01T23:59:59.000Z

    Environment Quality in Green Buildings: A Review," Nationalof Popular Attention to Green Building Notes: Sources:2007 - 2009 panel of green buildings and nearby control

  12. Building Operator Certification

    E-Print Network [OSTI]

    Lilley, D.

    2013-01-01T23:59:59.000Z

    Building Operator Certification Energy Efficiency through Operator Training CATEE December 18, 2013 – San Antonio, TX Dennis Lilley, CEM, PMP ESL-KT-13-12-49 CATEE 2013: Clean Air Through Energy Efficiency Conference, San Antonio, Texas Dec. 16...-18 Building Operator Certification Energy Efficiency through Operator Training What is Building Operator Certification? Industry-recognized credential in energy efficient building operation practices Created with 100 industry experts Launched in 1996 9...

  13. Building Songs 5

    E-Print Network [OSTI]

    Zla ba sgrol ma

    2009-10-28T23:59:59.000Z

    . Sman shad building song 5.WAV Length of track 00:02:14 Related tracks (include description/relationship if appropriate) Title of track Building Songs 5 Translation of title Description (to be used in archive entry) Skar ma chos mdzin... sings a building song. Such songs are traditionally sung antiphonally between two groups of men while they are ramming walls. Genre or type (i.e. epic, song, ritual) Building song Name of recorder (if different from collector) Zla ba sgrol ma...

  14. Building Songs 8

    E-Print Network [OSTI]

    Zla ba sgrol ma

    2009-10-28T23:59:59.000Z

    . Sman shad building song 8.WAV Length of track 00:01:28 Related tracks (include description/relationship if appropriate) Title of track Building Songs 8 Translation of title Description (to be used in archive entry) Skar ma chos mdzin... sings a building song. Such songs are traditionally sung antiphonally between two groups of men while they are ramming walls. Genre or type (i.e. epic, song, ritual) Building song Name of recorder (if different from collector) Zla ba sgrol ma...

  15. Building Songs 7

    E-Print Network [OSTI]

    Zla ba sgrol ma

    2009-10-28T23:59:59.000Z

    . Sman shad building song 7.WAV Length of track 00:09:57 Related tracks (include description/relationship if appropriate) Title of track Building Songs 7 Translation of title Description (to be used in archive entry) Skar ma chos mdzin... sings a building song. Such songs are traditionally sung antiphonally between two groups of men while they are ramming walls. Genre or type (i.e. epic, song, ritual) Building song Name of recorder (if different from collector) Zla ba sgrol ma...

  16. Building Performance Evaluation

    E-Print Network [OSTI]

    King, A.; Harris, J.; Mbentin, B.

    2012-01-01T23:59:59.000Z

    Building Performance Evaluation Anne King and Jo Harris, MBEKTN and BSRIA Agenda ? Background to funding and programme ? The Building Performance Evaluation Programme in the UK ? Requirements ? Results ? Impact ? Discussion ? Do you/ How do... you do Building Performance Evaluation? ? What gaps are there and what could research do to fill them? Background ? The Technology Strategy Board ? the funders ? Low Impact Building programme ? BSRIA and others ? evaluators ? Soft Landings...

  17. Kiowa County Commons Building

    Office of Energy Efficiency and Renewable Energy (EERE)

    This poster describes the energy efficiency features and sustainable materials used in the Kiowa County Commons Building in Greensburg, Kansas.

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

    E-Print Network [OSTI]

    Columbia University

    ;20031970 The Solid Waste Challenge Waste Explosion 1,200 t/d1,200 t/d 6,900 t/d6,900 t/d #12;Waste ManagementWaste Management and WasteWaste Management and Waste--toto--EnergyEnergy Status in Singapore #12;Singapore's Waste Management · In 2003, 6877 tonnes/day (2.51 M tonnes/year) of MSW collected

  19. 324 Building REC and HLV Tank Closure Plan

    SciTech Connect (OSTI)

    Becker-Khaleel, B; Schlick, K. [Scienfific Ecology Group, Inc. Richland, WA (United States)

    1995-12-01T23:59:59.000Z

    This closure plan describes the activities necessary to close the 324 Radiochemical Engineering Cells (REC) and High-Level Vault (HLV) in accordance with the Washington State Dangerous Waste regulations. To provide a complete description of the activities required, the closure plan relies on information contained in the 324 Building B-Cell Safety Cleanout Project (BCCP) plans, the 324 Building REC HLV Interim Waste Management Plan (IWMP), the Project Management Plan for Nuclear Facilities Management 300 Area Compliance Program, and the 324 High Level Vault Interim Removal Action Project (project management plan [PMP]). The IWMP addresses the management of mixed waste in accordance with state and federal hazardous waste regulations. It provides a strategy for managing high-activity mixed waste in compliance with Resource Conservation and Recovery Act (RCRA) requirements or provides for an alternative management approach for the waste. The BCCP outlines the past, present, and future activities necessary for removing from B-Cell the solid waste, including mixed waste generated as a result of historical research and development (R&D) activities conducted in the cell. The BCCP also includes all records and project files associated with the B-Cell cleanout. This information is referenced throughout the closure plan. The PMP sets forth the plans, organization, and systems that Pacific Northwest National Laboratory (PNNL) will use to direct and control the 324 High-Level Vault Interim Removal Action Project. This project will develop and implement a treatment strategy that will remove and stabilize the inventory of liquid waste from the 324 HLV tanks. The PMP also provides for flushing and sampling the flush solution.

  20. Hazardous Waste Management (Arkansas)

    Broader source: Energy.gov [DOE]

    The Hazardous Waste Program is carried out by the Arkansas Department of Environmental Quality which administers its' program under the Hazardous Waste management Act (Arkansas Code Annotated 8-7...

  1. Hazardous Waste Management (Delaware)

    Broader source: Energy.gov [DOE]

    The act authorizes the Delaware Department of Natural Resources and Environment Control (DNREC) to regulate hazardous waste and create a program to manage sources of hazardous waste. The act...

  2. Hazardous Waste Management (Oklahoma)

    Broader source: Energy.gov [DOE]

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

  3. Executive report Building knowledge

    E-Print Network [OSTI]

    Geffner, Hector

    Executive report Building knowledge To build citizens To build cities UPF CAMPUS ICŔRIA INTERNATIONAL PROJECT 2010 International Campus of Excellence Programme #12;2 UPF CAMPUS ICŔRIA INTERNATIONAL this presentation from the one submitted in the CEI 2009 programme where UPF was classified as a `promising

  4. Archive Reference Buildings by Building Type: Primary school

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  5. Building America Webinar: Building America: Research for Real...

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

    Building America Webinar: Building America: Research for Real-World Results Building America Webinar: Building America: Research for Real-World Results December 17, 2014 3:00PM to...

  6. Archive Reference Buildings by Building Type: Stand-alone retail

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  7. Archive Reference Buildings by Building Type: Small office

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  8. Archive Reference Buildings by Building Type: Large office

    Office of Energy Efficiency and Renewable Energy (EERE)

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  9. Archive Reference Buildings by Building Type: Fast food

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  10. Archive Reference Buildings by Building Type: Strip mall

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  11. Archive Reference Buildings by Building Type: Secondary school

    Broader source: Energy.gov [DOE]

    Here you will find past versions of the reference buildings for new construction commercial buildings, organized by building type and location. A summary of building types and climate zones is...

  12. Solid waste handling

    SciTech Connect (OSTI)

    Parazin, R.J.

    1995-05-31T23:59:59.000Z

    This study presents estimates of the solid radioactive waste quantities that will be generated in the Separations, Low-Level Waste Vitrification and High-Level Waste Vitrification facilities, collectively called the Tank Waste Remediation System Treatment Complex, over the life of these facilities. This study then considers previous estimates from other 200 Area generators and compares alternative methods of handling (segregation, packaging, assaying, shipping, etc.).

  13. Overheating in Hot Water- and Steam-Heated Multifamily Buildings

    SciTech Connect (OSTI)

    Dentz, J.; Varshney, K.; Henderson, H.

    2013-10-01T23:59:59.000Z

    Apartment temperature data have been collected from the archives of companies that provide energy management systems (EMS) to multifamily buildings in the Northeast U.S. The data have been analyzed from more than 100 apartments in eighteen buildings where EMS systems were already installed to quantify the degree of overheating. This research attempts to answer the question, 'What is the magnitude of apartment overheating in multifamily buildings with central hot water or steam heat?' This report provides valuable information to researchers, utility program managers and building owners interested in controlling heating energy waste and improving resident comfort. Apartment temperature data were analyzed for deviation from a 70 degrees F desired setpoint and for variation by heating system type, apartment floor level and ambient conditions. The data shows that overheating is significant in these multifamily buildings with both hot water and steam heating systems.

  14. Waste disposal package

    DOE Patents [OSTI]

    Smith, M.J.

    1985-06-19T23:59:59.000Z

    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.

  15. Final Report Waste Incineration

    E-Print Network [OSTI]

    solid waste, the composition and com- bustion of it. A main focus is on the European emission from municipal solid waste incineration. In the latter area, concepts of treatment, such as physical with municipal solid waste incineration (MSWI) and the problems that occur in connection to this. The emphasis

  16. Rethinking the Waste Hierarchy

    E-Print Network [OSTI]

    principles of EU waste policies. The environmental damage caused by waste depends on which type of manage, Environmental Assessment Institute For further information please contact: Environmental Assessment Institute.imv.dk #12;Environmental Assessment Institute Rethinking the Waste Hierarchy March 2005 Recommendations

  17. UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation into the implementation of a solid waste accounting system in the new

    E-Print Network [OSTI]

    into the implementation of a solid waste accounting system in the new Student Union Building Nattália Muttoni, Karl Jensen of a project/report". #12;1 An Investigation into the implementation of a solid waste accounting system In this paper, we outline our process and investigation into the implementation of a solid waste accounting

  18. Building Diagnostic Market Deployment - Final Report

    SciTech Connect (OSTI)

    Katipamula, S.; Gayeski, N.

    2012-04-30T23:59:59.000Z

    Operational faults are pervasive across the commercial buildings sector, wasting energy and increasing energy costs by up to about 30% (Mills 2009, Liu et al. 2003, Claridge et al. 2000, Katipamula and Brambley 2008, and Brambley and Katipamula 2009). Automated fault detection and diagnostic (AFDD) tools provide capabilities essential for detecting and correcting these problems and eliminating the associated energy waste and costs. The U.S. Department of Energy's (DOE) Building Technology Program (BTP) has previously invested in developing and testing of such diagnostic tools for whole-building (and major system) energy use, air handlers, chillers, cooling towers, chilled-water distribution systems, and boilers. These diagnostic processes can be used to make the commercial buildings more energy efficient. The work described in this report was done as part of a Cooperative Research and Development Agreement (CRADA) between the U.S. Department of Energy's Pacific Northwest National Laboratory (PNNL) and KGS Building LLC (KGS). PNNL and KGS both believe that the widespread adoption of AFDD tools will result in significant reduction to energy and peak energy consumption. The report provides an introduction and summary of the various tasks performed under the CRADA. The CRADA project had three major focus areas: (1) Technical Assistance for Whole Building Energy Diagnostician (WBE) Commercialization, (2) Market Transfer of the Outdoor Air/Economizer Diagnostician (OAE), and (3) Development and Deployment of Automated Diagnostics to Improve Large Commercial Building Operations. PNNL has previously developed two diagnostic tools: (1) whole building energy (WBE) diagnostician and (2) outdoor air/economizer (OAE) diagnostician. WBE diagnostician is currently licensed non-exclusively to one company. As part of this CRADA, PNNL developed implementation documentation and provided technical support to KGS to implement the tool into their software suite, Clockworks. PNNL also provided validation data sets and the WBE software tool to validate the KGS implementation. OAE diagnostician automatically detects and diagnoses problems with outdoor air ventilation and economizer operation for air handling units (AHUs) in commercial buildings using data available from building automation systems (BASs). As part of this CRADA, PNNL developed implementation documentation and provided technical support to KGS to implement the tool into their software suite. PNNL also provided validation data sets and the OAE software tool to validate the KGS implementation. Finally, as part of this CRADA project, PNNL developed new processes to automate parts of the re-tuning process and transfer those process to KGS for integration into their software product. The transfer of DOE-funded technologies will transform the commercial buildings sector by making buildings more energy efficient and also reducing the carbon footprint from the buildings. As part of the CRADA with PNNL, KGS implemented the whole building energy diagnostician, a portion of outdoor air economizer diagnostician and a number of measures that automate the identification of re-tuning measures.

  19. Passive solar buildings

    SciTech Connect (OSTI)

    Balcomb, J.D. [ed.] [Solar Energy Research Inst., Golden, CO (United States)

    1992-10-01T23:59:59.000Z

    Developments in passive solar buildings that took place from the early 1970`s through 1989 are described. Much of the work covered was federally sponsored during the period 1975 through 1986. About half the volume is devoted to quantitative methods for modeling, simulation, and design analysis of passive buildings; the other half summarizes the quantitative results of testing and monitoring of models and buildings. The following are covered: building solar gain modeling, simulation analysis, simplified methods, materials and components, analytical results for specific systems, test modules, building integration, performance monitoring and results, and design tools. (MHR)

  20. Passive solar buildings

    SciTech Connect (OSTI)

    Balcomb, J.D. (ed.) (Solar Energy Research Inst., Golden, CO (United States))

    1992-01-01T23:59:59.000Z

    Developments in passive solar buildings that took place from the early 1970's through 1989 are described. Much of the work covered was federally sponsored during the period 1975 through 1986. About half the volume is devoted to quantitative methods for modeling, simulation, and design analysis of passive buildings; the other half summarizes the quantitative results of testing and monitoring of models and buildings. The following are covered: building solar gain modeling, simulation analysis, simplified methods, materials and components, analytical results for specific systems, test modules, building integration, performance monitoring and results, and design tools. (MHR)

  1. Waste Isolation Pilot Plant (WIPP) fact sheet

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    Pursuant to the Solid Waste Disposal Act, as amended by the Resource Conservation and Recovery Act (RCRA), as amended (42 USC 6901, et seq.), and the New Mexico Hazardous Waste Act (Section 74-4-1 et seq., NMSA 1978), Permit is issued to the owner and operator of the US DOE, WIPP site (hereafter called the Permittee(s)) to operate a hazardous waste storage facility consisting of a container storage unit (Waste Handling Building) and two Subpart X miscellaneous below-ground storage units (Bin Scale Test Rooms 1 and 3), all are located at the above location. The Permittee must comply with all terms and conditions of this Permit. This Permit consists of the conditions contained herein, including the attachments. Applicable regulations cited are the New Mexico Hazardous Waste Management Regulations, as amended 1992 (HWMR-7), the regulations that are in effect on the date of permit issuance. This Permit shall become effective upon issuance by the Secretary of the New Mexico Environment Department and shall be in effect for a period of ten (10) years from issuance. This Permit is also based on the assumption that all information contained in the Permit application and the administrative record is accurate and that the activity will be conducted as specified in the application and the administrative record. The Permit application consists of Revision 3, as well as associated attachments and clarifying information submitted on January 25, 1993, and May 17, 1993.

  2. INSERT YOUR BUILDING NAME HERE: BUILDING EMERGENCY PLAN

    E-Print Network [OSTI]

    INSERT YOUR BUILDING NAME HERE: BUILDING EMERGENCY PLAN Date Adopted: 6/4/13 Date Revised: 6/4/13 Prepared By: Tracey Simmerman #12;PURDUE UNIVERSITY BUILDING EMERGENCY PLAN VERSION 3 2 Table of Contents Suspension or Campus Closure SECTION 3: BUILDING INFORMATION 3.1 Building Deputy/Alternate Building Deputy

  3. Buildings and Areas 1001 Broadway Building D1 BDWY

    E-Print Network [OSTI]

    Carter, John

    Design (LEED) Green Building Rating System is a nationally accepted benchmark for the designBuildings and Areas 1001 Broadway Building D1 BDWY 1313 East Columbia Building B3 CLMB Administration Building D1 ADMN Admissions & C2 ADAL Alumni Building Archbishop Murphy A1 ATMA Apartments Arrupe

  4. Performance evaluation of rotating pump jet mixing of radioactive wastes in Hanford Tanks 241-AP-102 and -104

    SciTech Connect (OSTI)

    Onishi, Y.; Recknagle, K.P.

    1998-07-01T23:59:59.000Z

    The purpose of this study was to confirm the adequacy of a single mixer pump to fully mix the wastes that will be stored in Tanks 241-AP-102 and -104. These Hanford double-shell tanks (DSTs) will be used as staging tanks to receive low-activity wastes from other Hanford storage tanks and, in turn, will supply the wastes to private waste vitrification facilities for eventual solidification. The TEMPEST computer code was applied to Tanks AP-102 and -104 to simulate waste mixing generated by the 60-ft/s rotating jets and to determine the effectiveness of the single rotating pump to mix the waste. TEMPEST simulates flow and mass/heat transport and chemical reactions (equilibrium and kinetic reactions) coupled together. Section 2 describes the pump jet mixing conditions the authors evaluated, the modeling cases, and their parameters. Section 3 reports model applications and assessment results. The summary and conclusions are presented in Section 4, and cited references are listed in Section 5.

  5. Embedded Commissioning for Building Design

    E-Print Network [OSTI]

    Akin, O.; Turkaslan-Bulbul, M. T.; Gursel, I.; Garrett, J. H.; Akinci, B.; Wang, H.

    2004-01-01T23:59:59.000Z

    Building Commissioning has a broad scope that extends to all phases of building delivery. We view commissioning as a building delivery embedded process that persistently verifies and validates design intent throughout the building lifecycle process...

  6. Commercial Buildings Characteristics, 1992

    SciTech Connect (OSTI)

    Not Available

    1994-04-29T23:59:59.000Z

    Commercial Buildings Characteristics 1992 presents statistics about the number, type, and size of commercial buildings in the United States as well as their energy-related characteristics. These data are collected in the Commercial Buildings Energy Consumption Survey (CBECS), a national survey of buildings in the commercial sector. The 1992 CBECS is the fifth in a series conducted since 1979 by the Energy Information Administration. Approximately 6,600 commercial buildings were surveyed, representing the characteristics and energy consumption of 4.8 million commercial buildings and 67.9 billion square feet of commercial floorspace nationwide. Overall, the amount of commercial floorspace in the United States increased an average of 2.4 percent annually between 1989 and 1992, while the number of commercial buildings increased an average of 2.0 percent annually.

  7. Mobile encapsulation and volume reduction system for wet low-level wastes

    SciTech Connect (OSTI)

    Buelt, J.L.

    1985-08-01T23:59:59.000Z

    This report describes the results of the program entitled ''A Preconceptual Study for a Transportable Vitrification Process''. The objective of the study is to determine the feasibility of a Mobile Encapsulation and Volume Reduction System (MEVS). The report contains design criteria, a preconceptual design of the system, a comparison of disposal costs with other solidification technologies, and an assessment of utility interests in the transportable volume reduction service MEVS can provide. The MEVS design employs the use of a joule-heated glass melter to convert the wet low-level wastes into glass. The process is self-sufficient, requiring no direct facility services or reactor personnel. It is capable of servicing one waste type from a minimum of three reactors. The design was used to prepare capital and operating cost estimates. The capital cost for the MEVS is $4,680,000, which includes all labor necessary for design, engineering, inspection, and licensing. The operating cost of the system for servicing a minimum of three reactors is $1,530,000/y for resins or $2,280,000/y for concentrated liquids. The cost estimates compared favorably to the more common solidification process of cementation. Total MEVS operating costs which include processing, transportation and burial, are $191 to $218/ft/sup 3/ waste, whereas quoted costs for cementation and disposal from reactor operators range from $155 to $350/ft/sup 3/. The report concludes with the requirements for additional development, which can be accomplished for less than one sixth of the capital costs. The report also presents the results of an assessment conducted with utility representatives to obtain their expressions of interest in a service of this type.

  8. Method of energy load management using PCM for heating and cooling of buildings

    DOE Patents [OSTI]

    Stovall, Therese K. (Knoxville, TN); Tomlinson, John J. (Knoxville, TN)

    1996-01-01T23:59:59.000Z

    A method of energy load management for the heating and cooling of a building. The method involves utilizing a wallboard as a portion of the building, the wallboard containing about 5 to about 30 wt. % a phase change material such that melting of the phase change material occurs during a rise in temperature within the building to remove heat from the air, and a solidification of the phase change material occurs during a lowering of the temperature to dispense heat into the air. At the beginning of either of these cooling or heating cycles, the phase change material is preferably "fully charged". In preferred installations one type of wallboard is used on the interior surfaces of exterior walls, and another type as the surface on interior walls. The particular PCM is chosen for the desired wall and room temperature of these locations. In addition, load management is achieved by using PCM-containing wallboard that form cavities of the building such that the cavities can be used for the air handling duct and plenum system of the building. Enhanced load management is achieved by using a thermostat with reduced dead band of about the upper half of a normal dead band of over three degree. In some applications, air circulation at a rate greater than normal convection provides additional comfort.

  9. Method of energy load management using PCM for heating and cooling of buildings

    DOE Patents [OSTI]

    Stovall, T.K.; Tomlinson, J.J.

    1996-03-26T23:59:59.000Z

    A method is described for energy load management for the heating and cooling of a building. The method involves utilizing a wallboard as a portion of the building, the wallboard containing about 5 to about 30 wt.% phase change material such that melting of the phase change material occurs during a rise in temperature within the building to remove heat from the air, and a solidification of the phase change material occurs during a lowering of the temperature to dispense heat into the air. At the beginning of either of these cooling or heating cycles, the phase change material is preferably ``fully charged``. In preferred installations one type of wallboard is used on the interior surfaces of exterior walls, and another type as the surface on interior walls. The particular PCM is chosen for the desired wall and room temperature of these locations. In addition, load management is achieved by using PCM-containing wallboards that form cavities of the building such that the cavities can be used for the air handling duct and plenum system of the building. Enhanced load management is achieved by using a thermostat with reduced dead band of about the upper half of a normal dead band of over three degrees. In some applications, air circulation at a rate greater than normal convection provides additional comfort. 7 figs.

  10. Also Known As (Room or Building)

    E-Print Network [OSTI]

    Mottram, Nigel

    Room No. Also Known As (Room or Building) Hearing Assistance Type 702 InfraRed 704 InfraRed 706 Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam Smith Building Adam

  11. Building Energy Monitoring and Analysis

    E-Print Network [OSTI]

    Hong, Tianzhen

    2014-01-01T23:59:59.000Z

    platforms and  building automation systems (BAS), a building  automation  control,  fault  detection  and  diagnostics  (FDD),  and  continuous  system 

  12. A technique for the observation of rapid solidification and annealing of powders in a transmission electron microscope

    SciTech Connect (OSTI)

    Kaufman, M.J.; Fraser, H.L.

    1983-01-01T23:59:59.000Z

    In the recent past, there has been considerable interest in the general area of rapid solidification processing (RSP). It is highly desirable to be able to make observations of not only the as-solidified microstructure of RSP materials, but also to determine its response to thermal excursions. This paper describes a new technique for in-situ studies of such processes where the electron beam in a TEM is used not only for imaging, diffraction and analytical purposes, but also as a local heating source. Thus, when making observations on submicron powders, produced by electrohydrodynamic atomization (EHD), it is possible to anneal and even melt particulate by focusing the electron beam in a controlled manner. The molten droplets can then be rapidly solidified by occluding the beam from the area of interest. A wide range of cooling rates may be achieved, the maximum being at least as rapid as that estimated for the EHD process, about 10/sup 5/ K/s (dependent on powder size). Two examples of the use of this technique are given. The first involves the melting, rapid solidification and subsequent heat treatment of an AL-4.5wt.%Cu alloy. The second is an example of how this technique may be used in studies of the crystallization of metallic glasses, in this case a Cu-45at.%Zr alloy.

  13. Radioactive Waste Management Manual

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

    1999-07-09T23:59:59.000Z

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

  14. Radioactive Waste Management Basis

    SciTech Connect (OSTI)

    Perkins, B K

    2009-06-03T23:59:59.000Z

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

  15. Municipal waste processing apparatus

    DOE Patents [OSTI]

    Mayberry, J.L.

    1988-04-13T23:59:59.000Z

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

  16. Mixed waste: Proceedings

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

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

  17. An Analysis of the DER Adoption Climate in Japan Using Optimization Results for Prototype Buildings with U.S. Comparisons

    E-Print Network [OSTI]

    Zhou, Nan; Marnay, Chris; Firestone, Ryan; Gao, Weijun; Nishida, Masaru

    2006-01-01T23:59:59.000Z

    Office Building Jul Electricity Load Provision with CHP NGdecrement from CHP NG for heating NG for NG-only y g NG OnlyGas Load Provision with CHP Cooling offset by waste heat

  18. BuildSense Compressed natural gas (CNG) bi-fuel conversions for two Ford F-series pickup trucks.

    E-Print Network [OSTI]

    BuildSense Compressed natural gas (CNG) bi-fuel conversions for two Ford F-series pickup trucks $141,279 $35,320 $176,599 City of Charlotte Solid Waste Services Compressed natural gas ( CNG) up fits

  19. Waste Characterization, Reduction, and Repackaging Facility ...

    Office of Environmental Management (EM)

    Waste Characterization, Reduction, and Repackaging Facility (WCRRF) Waste Characterization Glovebox Operations Waste Characterization, Reduction, and Repackaging Facility (WCRRF)...

  20. Figure-of-merit analysis and cost effectiveness of low-level radioactive waste treatment systems

    SciTech Connect (OSTI)

    Cox, N.D.; Falconer, K.L.; McCormack, M.D.; Hootman, H.D.; Thompson, T.K.

    1982-01-01T23:59:59.000Z

    Two studies were performed to assess low-level waste treatment systems that are available commercially for volume reduction and/or solidification. In the first, a Figure-of-Merit (FOM) decision analysis technique was used to evaluate fourteen low-level radioactive waste processing systems on their ability to treat power reactor wastes. The assessment of the various processing systems was accomplished using a five member task force. The systems were judged on eleven major criteria and twenty subcriteria. The system judged superior to all the others was compaction of dry wastes with liquid wastes and sludges being directly incorporated into concrete. This was also the lowest cost system. The controlled air incinerator was judged the preferred incineration process. The Werner-Pfleider bitumen extruder was the preferred liquid waste treatment system. In the second study, the cost economy of volume reduction measured in land disposal dollars was investigated. The greatest cost savings with volume reduction were realized with a BWR using a deep bed condensate polishing system; the least with a PWR with condensate polishing. For both BWR systems and PWRs without condensate cleanup, over 80% of the savings in land disposal dollars resulted from volume reduction of liquid waste streams (concentrated liquids and filter sludge). For a PWR with a condensate polishing system, which had the least cost effective system for volume reduction, about one-third of the savings resulting from incineration of spent resin and compactible trash was offset by the increased expense of casks required for transporting concentrated liquids which have undergone additional volume reduction.

  1. Final waste forms project: Performance criteria for phase I treatability studies

    SciTech Connect (OSTI)

    Gilliam, T.M. [Oak Ridge National Lab., TN (United States); Hutchins, D.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Chodak, P. III [Massachusetts Institute of Technology (United States)

    1994-06-01T23:59:59.000Z

    This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide {open_quotes}proof-of-principle{close_quotes} data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.).

  2. Waste Isolation Pilot Plant 2005 Site Environmental Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services

    2006-10-13T23:59:59.000Z

    The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to make WIPP environmental information available to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2004. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through defense activities and programs. TRU waste is defined, in the WIPP LWA, as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting TRU isotopes per gram of waste, with half-lives greater than 20 years except for high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools; sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. TRU waste is eligible for disposal at WIPP if it has been generated in whole or in part by one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management,defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

  3. Acceleration of Los Alamos National Laboratory transuranic waste disposition

    SciTech Connect (OSTI)

    O'Leary, G.A.; Palmer, B.A.; Starke, T.P.; Phelps, A.K. [Los Alamos National Security, L.L.C., Los Alamos National Laboratory, Los Alamos, NM (United States)

    2007-07-01T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuranic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dis-positioning the transuranic waste inventory requires retrieval of the containers from above and below- ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad, New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LANL does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contractor in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquarters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approach include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safely remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Reduction Fa

  4. ACCELERATION OF LOS ALAMOS NATIONAL LABORATORY TRANSURANIC WASTE DISPOSITION

    SciTech Connect (OSTI)

    O'LEARY, GERALD A. [Los Alamos National Laboratory

    2007-01-04T23:59:59.000Z

    One of Los Alamos National Laboratory's (LANL's) most significant risks is the site's inventory of transuranic waste retrievably stored above and below-ground in Technical Area (TA) 54 Area G, particularly the dispersible high-activity waste stored above-ground in deteriorating facilities. The high activity waste represents approximately 50% (by activity) of the total 292,000 PE-Ci inventory remaining to be disposed. The transuramic waste inventory includes contact-handled and remote-handled waste packaged in drums, boxes, and oversized containers which are retrievably stored both above and below-ground. Although currently managed as transuranic waste, some of the inventory is low-level waste that can be disposed onsite or at approved offsite facilities. Dispositioning the transuranic waste inventory requires retrieval of the containers from above and below-ground storage, examination and repackaging or remediation as necessary, characterization, certification and loading for shipment to the Waste Isolation Pilot Plant in Carlsbad New Mexico, all in accordance with well-defined requirements and controls. Although operations are established to process and characterize the lower-activity contact-handled transuranic waste containers, LAN L does not currently have the capability to repack high activity contact-handled transuranic waste containers (> 56 PE-Ci) or to process oversized containers with activity levels over 0.52 PE-Ci. Operational issues and compliance requirements have resulted in less than optimal processing capabilities for lower activity contact-handled transuranic waste containers, limiting preparation and reducing dependability of shipments to the Waste Isolation Pilot Plant. Since becoming the Los Alamos National Laboratory contract in June 2006, Los Alamos National Security (LANS) L.L.C. has developed a comprehensive, integrated plan to effectively and efficiently disposition the transuranic waste inventory, working in concert with the Department of Energy Los Alamos Site Office, Carlsbad Field Office and the Department of Energy Headquaeters. Rather than simply processing containers as retrieved, the plan places priority on efficient curie disposition, a direct correlation to reducing risk. Key elements of the approch include balancing inventory and operational risks, tailoring methods to meet requirements, optimizing existing facilities, equipment and staff, and incorporating best practices from other Department of Energy sites. With sufficient funding this will enable LANL to ship the above-ground high activity contact-handled transuranic waste offsite by the end of Fiscal Year (FY) 2007 and to disposition the remaining above- and below-ground contact-handled and remote-handled transuranic waste inventory by December 2010. Nearly 70% of the contact-handled transuranic waste containers, including the high activity waste, require processing and repackaging before characterization and certification for shipment to the Waste Isolation Pilot Plant. LANL is employing a balanced risk approach that accomplishes significant long-term risk reduction by accepting short-term increased facility operations risk under well-developed and justified interim controls. Reviews of facility conditions and additional analyses show that the Waste Characterization, Reduction and Repackaging Facility and the Radioassay and Nondestructive Testing Facility are the most appropriate facilities to safetly remediate, repackage, and ship lower activity and the remaining high activity drums. Updated safety documentation supporting limited Hazard Category 2 operations in these facilities has been developed. Once approved, limited-term operations to process the high activity drums can begin in early 2007, building upon the experience base established performing Hazard Category 3 operations processing lower activity waste in these facilities. LANL is also implementing a series of actions to improve and sustain operations for processing contact-handled transuranic waste inventory. Building 412 Decontamination and Volume Facility and Dom

  5. BUILDING EMERGENCY ACTION PLAN [Medical Sciences Building, Building # 192] / [506 S. Mathews, Urbana

    E-Print Network [OSTI]

    Gilbert, Matthew

    BUILDING EMERGENCY ACTION PLAN [Medical Sciences Building, Building # 192] / [506 S. Mathews requires the BUILDING EMERGENCY MANAGEMENT TEAM: Building Command Post1 1. M2 classroom, Carle Forum This Building Emergency Action Plan (BEAP) is to be used in conjunction with the Emergency Response Guide (ERG

  6. Liquid and Gaseous Waste Operations Project Annual Operating Report CY 1999

    SciTech Connect (OSTI)

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

    2000-03-01T23:59:59.000Z

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

  7. Solid Waste Management Plan. Revision 4

    SciTech Connect (OSTI)

    NONE

    1995-04-26T23:59:59.000Z

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

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

    Office of Environmental Management (EM)

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

  9. Transuranic (TRU) Waste | Department of Energy

    Office of Environmental Management (EM)

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

  10. New Waste Calcining Facility (NWCF) Waste Streams

    SciTech Connect (OSTI)

    K. E. Archibald

    1999-08-01T23:59:59.000Z

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

  11. Evaluation of solidification/stabilization for treatment of a petroleum hydrocarbon contaminated sludge from Fort Polk Army Installation, Louisiana. Final report

    SciTech Connect (OSTI)

    Channell, M.G.; Preston, K.T.

    1996-09-01T23:59:59.000Z

    In the course of normal operations and training, soldiers and civilian personnel operate many Army vehicles on a day-today basis. These vehicles must be cleaned before they can be returned to the motor pool area of an Army base. The cleaning of these vehicles bas posed a problem with the operation and maintenance of oil/water separators located at vehicle washrack facilities. An oily sludge forms in the oil/water separator and is hard to handle and cannot be disposed of in an ordinary manner. This study used solidification/stabilization to treat the oily sludge found in the vehicle washrack oil/water separators. Solidification/stabilization is usually used to treat soils and sludges that contain heavy metals. Organic compounds, such as petroleum hydrocarbons found in the sludge, interfere with the setting of the solidification binding materials and thus produce a material that is not desirable for a treatment alternative. This study incorporates the use of dicalcium silicate as an additive to the solidification process to increase the strength and reduce the leachability of the petroleum hydrocarbons found in the sludge. This study shows that dicalcium silicate improves the handling characteristics of the sludge and reduces the leachability of the contaminants from the washrack sludge.

  12. Inverse Problems 16 (2000) 483494. Printed in the UK PII: S0266-5611(00)04848-6 Imaging the solidification of molten metal by eddy currents: II

    E-Print Network [OSTI]

    Hua, Yingbo

    2000-01-01T23:59:59.000Z

    the solidification of molten metal by eddy currents: II Minh H Pham, Yingbo Hua and Neil B Gray The Department by the induced eddy currents inside the innermost cylinder. Identification of the CSG of an infinitely long space. The existing eddy-current inverse techniques [5,6] solve very different problems. In this paper

  13. Inverse Problems 16 (2000) 469482. Printed in the UK PII: S0266-5611(00)04847-4 Imaging the solidification of molten metal by eddy currents: I

    E-Print Network [OSTI]

    Hua, Yingbo

    2000-01-01T23:59:59.000Z

    the solidification of molten metal by eddy currents: I Minh H Pham, Yingbo Hua and Neil B Gray The Department@ee.mu.oz.au Received 27 May 1999, in final form 20 December 1999 Abstract. This paper presents an eddy-current for this imaging task other than that of eddy currents. The eddy-current technique is a nondestructive technique

  14. Modeling of Casting, Welding and Advanced Solidification Processes IX Edited by Peter R. Sahm, Preben N. Hansen and James G. Conley

    E-Print Network [OSTI]

    Taylor, Gary

    Modeling of Casting, Welding and Advanced Solidification Processes IX Edited by Peter R. Sahm to the Modelling of Welding Phenomena G. A. Taylor, M. Hughes and K. Pericleous Centre for Numerical Modelling of welding phenomena is presented. The framework includes models from both the fields of Computational Fluid

  15. Composites Part B: Engineering, 2011, 42(4): p. 916-925 Analysis of active cooling through nickel coated carbon fibers in the solidification

    E-Print Network [OSTI]

    Gupta, Nikhil

    nickel coated carbon fibers in the solidification processing of aluminum matrix composites Nikhil Gupta1 , Nguyen Q. Nguyen2 , and Pradeep K. Rohatgi2 1 Composite Materials and Mechanics Laboratory, Mechanical In carbon fiber reinforced aluminum or aluminum alloy matrix composites a barrier coating is applied

  16. Waste IncIneratIon and Waste PreventIon

    E-Print Network [OSTI]

    and heat. In 2005/2006, German waste incineration plants provided some 6 terawatt hours (TWh-/Abfallgesetz) continues to hold: Waste prevention has priority over recovery and disposal. Nevertheless, the use of waste for en- ergy recovery is an indispensable element of sus- tainable waste management. Waste incineration

  17. Energy from Waste UK Joint Statement on Energy from Waste

    E-Print Network [OSTI]

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

  18. www.d-waste.com info@d-waste.com

    E-Print Network [OSTI]

    marketplace, about 47 grams of waste is produced-- with worldwide municipal solid waste generation totaling, the International Solid Waste Association, GIZ/SWEEP-Net, the Waste to Energy Research Council (WTERT) and the Solid management data available". According to David Newman, president of the International Solid Waste Association

  19. Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill

    E-Print Network [OSTI]

    Aluminum Waste Reaction Indicators in a Municipal Solid Waste Landfill Timothy D. Stark, F.ASCE1 landfills may contain aluminum from residential and commercial solid waste, industrial waste, and aluminum American Society of Civil Engineers. CE Database subject headings: Solid wastes; Leaching; Aluminum

  20. Waste Disposal Guide HOW TO PROPERLY DISPOSE OF WASTE MATERIALS

    E-Print Network [OSTI]

    Schaefer, Marcus

    Waste Disposal Guide HOW TO PROPERLY DISPOSE OF WASTE MATERIALS GENERATED AT DEPAUL UNIVERSITY.4 Hazardous Waste Defined p.5 Chemical Waste Procedure for Generating Departments p.6 o A of Containers p.8 o E. Disposal of Empty Containers p.8 o F. Storage of Waste Chemicals p.8,9 o G

  1. Hazardous Waste Compliance Program Plan

    SciTech Connect (OSTI)

    Potter, G.L.; Holstein, K.A.

    1994-05-01T23:59:59.000Z

    The Hazardous Waste Compliance Program Plan (HWCPP) describes how the Rocky Flats Plant institutes a more effective waste management program designed to achieve and maintain strict adherence to the Resource Conservation and Recovery Act (RCRA) requirements. Emphasis is given to improve integration of line operations with programmatic and functional support activities necessary to achieve physical compliance to RCRA regulated equipment, facilities and operations at the floor level. This program focuses on specific activities occurring or which need to occur within buildings containing RCRA regulated units and activities. The plan describes a new approach to achieving and maintaining compliance. This approach concentrates authority and accountability for compliance with the line operating personnel, with support provided from the programmatic functions. This approach requires a higher degree of integration and coordination between operating and program support organizations. The principal changes in emphases are; (1) increased line operations involvement, knowledge and accountability in compliance activities, (2) improved management systems to identify, correct and/or avoid deficiencies and (3) enhanced management attention and employee awareness of compliance related matters.

  2. Regulatory Approaches for Solid Radioactive Waste Storage in Russia

    SciTech Connect (OSTI)

    Griffith, A.; Testov, S.; Diaschev, A.; Nazarian, A.; Ustyuzhanin, A.

    2003-02-26T23:59:59.000Z

    The Russian Navy under the Arctic Military Environmental Cooperation (AMEC) Program has designated the Polyarninsky Shipyard as the regional recipient for solid radioactive waste (SRW) pretreatment and storage facilities. Waste storage technologies include containers and lightweight modular storage buildings. The prime focus of this paper is solid radioactive waste storage options based on the AMEC mission and Russian regulatory standards. The storage capability at the Polyarninsky Shipyard in support of Mobile Pretreatment Facility (MPF) operations under the AMEC Program will allow the Russian Navy to accumulate/stage the SRW after treatment at the MPF. It is anticipated that the MPF will operate for 20 years. This paper presents the results of a regulatory analysis performed to support an AMEC program decision on the type of facility to be used for storage of SRW. The objectives the study were to: analyze whether a modular storage building (MSB), referred in the standards as a lightweight building, would comply with the Russian SRW storage building standard, OST 95 10517-95; analyze the Russian SRW storage pad standard OST 95 10516-95; and compare the two standards, OST 95 10517-95 for storage buildings and OST 95 10516-95 for storage pads.

  3. The Lovejoy Building

    High Performance Buildings Database

    Portland, OR Originally built in 1910 as the stables for the Marshall-Wells Hardware Company, the Lovejoy Building is the home of Opsis Architects. The owner/architects purchased and renovated the historic building to house their growing business and to provide ground-floor office lease space and second-floor offices for their firm. Opsis wanted to use the building to experience and demonstrate the technologies and practices it promotes with clients.

  4. Building Songs 10

    E-Print Network [OSTI]

    Zla ba sgrol ma

    2009-11-06T23:59:59.000Z

    . Sman shad building song 10.WAV Length of track 00:06:03 Related tracks (include description/relationship if appropriate) Title of track Building Songs 10 Translation of title Description (to be used in archive entry) Male villagers... sing a building song. Genre or type (i.e. epic, song, ritual) Building song Name of recorder (if different from collector) Zla ba sgrol ma Date of recording November 6th 2009. Place of recording Gad dmar khug market Mda' ma Township, Sde dge...

  5. What is Building America?

    SciTech Connect (OSTI)

    None

    2013-06-20T23:59:59.000Z

    DOE's Building America program is helping to bridge the gap between homes with high energy costs and homes that are healthy, durable, and energy efficient.

  6. Building Songs 11

    E-Print Network [OSTI]

    Zla ba sgrol ma

    2009-11-06T23:59:59.000Z

    . Sman shad building song 11.WAV Length of track 00:21:12 Related tracks (include description/relationship if appropriate) Title of track Building Songs 11 Translation of title Description (to be used in archive entry) Male villagers... sing a building song. Genre or type (i.e. epic, song, ritual) Building song Name of recorder (if different from collector) Zla ba sgrol ma Date of recording November 6th 2009. Place of recording Gad dmar khug market Mda' ma Township, Sde dge...

  7. ORISE: Capacity Building

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

    Capacity Building Because public health agencies must maintain the resources to respond to public health challenges, critical situations and emergencies, the Oak Ridge Institute...

  8. What is Building America?

    ScienceCinema (OSTI)

    None

    2013-07-22T23:59:59.000Z

    DOE's Building America program is helping to bridge the gap between homes with high energy costs and homes that are healthy, durable, and energy efficient.

  9. Building Science- Ventilation

    Broader source: Energy.gov [DOE]

    This presentation was given at the Summer 2012 DOE Building America meeting on July 25, 2012, and addressed the question Ť"What are the best ventilation techniques"

  10. High Performance Sustainable Buildings

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

    to achieve Leadership in Energy and Environmental Design gold certification from the U.S. Green Building Council. The Center for Integrated Nanotechnologies brings together...

  11. Forest Road Building Regulations

    Broader source: Energy.gov [DOE]

    The Wisconsin Department of Natural Resources has regulations for building a forest road, if development requires one. Regulations include zoning ordinances and permits for stream crossing, grading...

  12. building.ppt

    E-Print Network [OSTI]

    Building Parenting Skills and Interactions with Kangaroo Care. Sharon A. Wilkerson, PhD, RN. Associate Professor of Nursing. Purdue University. West Lafayette ...

  13. Whole Building Energy Simulation

    Broader source: Energy.gov [DOE]

    Whole building energy simulation, also referred to as energy modeling, can and should be incorporated early during project planning to provide energy impact feedback for which design considerations...

  14. Building bridges for fish

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

    Building-bridges-for-fish Sign In About | Careers | Contact | Investors | bpa.gov Search News & Us Expand News & Us Projects & Initiatives Expand Projects & Initiatives...

  15. Chapter 3: Building Siting

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

    and up, especially at doors and loading docks, requires loading docks on the south side of buildings. significant effort and energy for snow removal. Desirable locations of...

  16. Rev. 01072013 Biology Buildings Laboratory Infectious Waste Disposal Guide*

    E-Print Network [OSTI]

    Plotkin, Joshua B.

    bottles must be triple rinsed and label defaced. Line cardboard glassware boxes with clear plastic bags infectious agents or was used in animal or human patient care or treatment, including plastic pipettes and other used plasticware that is recognizable after autoclaving or made of plastic that shatters

  17. Waste Isolation Pilot Plant 2003 Site Environmental Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services

    2005-09-03T23:59:59.000Z

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

  18. Guidelines for mixed waste minimization

    SciTech Connect (OSTI)

    Owens, C.

    1992-02-01T23:59:59.000Z

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

  19. Underground waste barrier structure

    DOE Patents [OSTI]

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

    1988-01-01T23:59:59.000Z

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

  20. IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

    SciTech Connect (OSTI)

    UYTIOCO EM

    2007-11-14T23:59:59.000Z

    The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation & Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington, the Department of Energy, and the Environmental Protection Agency. These commitments require waste containers to be shipped off site for disposal and/or treatment within a certain time frame. Because the program was struggling to meet production demands, the Production and Planning group was tasked with developing a method to assist the LLW Program in fulfilling its requirements. Using existing databases for container management, a single electronic spreadsheet was created to visually map every waste container within the CWC. The file displays the exact location (e.g., building, module, tier, position) of each container in a format that replicates the actual layout in the facility. In addition, each container was placed into a queue defined by the LLW and TRU waste management programs. The queues were developed based on characterization requirements, treatment type and location, and potential final disposition. This visual aid allows the user to select containers from similar queues and view their location within the facility. The user selects containers in a centralized location, rather than random locations, to expedite shipments out of the facility. This increases efficiency for generating the shipments, as well as decreasing worker exposure and container handling time when gathering containers for shipment by reducing movements of waste container. As the containers are collected for shipment, the remaining containers are segregated by queue, which further reduces future container movements.

  1. Comparison of Building Energy Modeling Programs: Building Loads

    E-Print Network [OSTI]

    LBNL-6034E Comparison of Building Energy Modeling Programs: Building Loads Dandan Zhu1 , Tianzhen Energy, the U.S.-China Clean Energy Research Center for Building Energy Efficiency, of the U;Comparison of Building Energy Modeling Programs: Building Loads A joint effort between Lawrence Berkeley

  2. New! Building Energy Standards Essentials for Plans Examiners & Building Inspectors

    E-Print Network [OSTI]

    New! Building Energy Standards Essentials for Plans Examiners & Building Inspectors Building energy codes are complex. Plans examiners and building inspectors are expected to understand and enforce energy savings. This new, hands-on course strives to provide plans examiners and building inspectors

  3. Building and Facility Codes Code Building Location Bldg # Coordinates

    E-Print Network [OSTI]

    Russell, Lynn

    Building and Facility Codes Code Building Location Bldg # Coordinates APM Applied Physics & Mathematics Building Muir 249 F7 ASANT Asante Hall Eleanor Roosevelt 446 F5 BIO Biology Building Muir 259 F7 BIRCH Birch Aquarium SIO 2300 S-D7 BONN Bonner Hall Revelle 131 G8 BSB Biomedical Sciences Building

  4. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    1999-08-24T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2018 are projected based on assumption as of July 1999. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement.

  5. Operational Waste Volume Projection

    SciTech Connect (OSTI)

    STRODE, J.N.

    2000-08-28T23:59:59.000Z

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

  6. Operational waste volume projection

    SciTech Connect (OSTI)

    Koreski, G.M.

    1996-09-20T23:59:59.000Z

    Waste receipts to the double-shell tank system are analyzed and wastes through the year 2015 are projected based on generation trends of the past 12 months. A computer simulation of site operations is performed, which results in projections of tank fill schedules, tank transfers, evaporator operations, tank retrieval, and aging waste tank usage. This projection incorporates current budget planning and the clean-up schedule of the Tri-Party Agreement. Assumptions were current as of June 1996.

  7. Building & Fire Assist Director

    E-Print Network [OSTI]

    Yetisgen-Yildiz, Meliha

    Sites / Underground StorageTanks PCB Disposal Chemical Spill Advice Chemical Waste Hazardous Materials & Reporting Animal / Research Protocol Hazardous Materials Review Animal UseMedicalScreening Biological Safety) Air Quality Chemical Inventories (My Chem) Hazardous Materials Recycling Water Quality Contaminated

  8. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, George G. (Aiken, SC)

    1999-01-01T23:59:59.000Z

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

  9. Vitrification of waste

    DOE Patents [OSTI]

    Wicks, G.G.

    1999-04-06T23:59:59.000Z

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

  10. Solid Waste Management (Connecticut)

    Broader source: Energy.gov [DOE]

    Solid waste facilities operating in Connecticut must abide by these regulations, which describe requirements and procedures for issuing construction and operating permits; environmental...

  11. Solid Waste Policies (Iowa)

    Broader source: Energy.gov [DOE]

    This statute establishes the support of the state for alternative waste management practices that reduce the reliance upon land disposal and incorporate resource recovery. Cities and counties are...

  12. Solid Waste Permits (Louisiana)

    Broader source: Energy.gov [DOE]

    The Louisiana Department of Environmental Quality administers the rules and regulations governing the storage, collection, processing, recovery, and reuse of solid waste protect the air,...

  13. Norcal Waste Systems, Inc.

    SciTech Connect (OSTI)

    Not Available

    2002-12-01T23:59:59.000Z

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

  14. Hazardous Waste Management (Indiana)

    Broader source: Energy.gov [DOE]

    The state supports the implementation of source reduction, recycling, and other alternative solid waste management practices over incineration and land disposal. The Department of Environmental...

  15. Solid Waste Management (Indiana)

    Broader source: Energy.gov [DOE]

    The state supports the implementation of source reduction, recycling, and other alternative solid waste management practices over incineration and land disposal. The Indiana Department of...

  16. Solid Waste Management (Michigan)

    Broader source: Energy.gov [DOE]

    This Act encourages the Department of Environmental Quality and Health Department representatives to develop and encourage methods for disposing solid waste that are environmentally sound, that...

  17. Waste Heat Recovery

    Office of Environmental Management (EM)

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

  18. BUILDING ENERGY 1987 Edition

    E-Print Network [OSTI]

    changes in lighting control and HVAC requirements. The lighting control requirements in Section 2-5319(a, are required for all alterations. The HVAC requirements of new buildings are requ ired for some HVAC alterat for a wide variety of building shapes. "SECOND GENERATioN" ALTERNATIVE HVAC COMPLIANCE CODIFIED 4

  19. Building Technologies Research and

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    Impact of Buildings Centers of Excellence · 40% of total primary energy consumption · 74% of electricity consumption · 56% of natural gas consumption (including gas-generated electricity used in buildings) · 39 the nation accounts for its energy consumption, making the energy savings potential even greater. National

  20. High Performance Sustainable Building

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

    2008-06-20T23:59:59.000Z

    The guide supports DOE O 413.3A and provides useful information on the incorporation of high performance sustainable building principles into building-related General Plant Projects and Institutional General Plant Projects at DOE sites. Canceled by DOE G 413.3-6A. Does not cancel other directives.

  1. 200 Market Building

    High Performance Buildings Database

    Portland, OR The 200 Market Building is a high-rise built in 1973 and located in downtown Portland, Oregon. It was purchased in 1988 by its current owner, 200 Market Associates, primarily because of its optimal location in Portland's central business district. Since 1989 the building has undergone continuous improvements in multiple phases.

  2. PHOTOVOLTAICS AND COMMERCIAL BUILDINGS--

    E-Print Network [OSTI]

    Perez, Richard R.

    management of electricity demand. · PV applications are now being integrated directly into building roofs, Valuation of Demand-Side Commercial PV Systems in the United States, we sought to measure the costPHOTOVOLTAICS AND COMMERCIAL BUILDINGS-- A NATURAL MATCH A study highlighting strategic

  3. Reference Buildings by Building Type: Small Hotel

    Office of Energy Efficiency and Renewable Energy (EERE)

    In addition to the ZIP file for each building type, you can directly view the "scorecard" spreadsheet that summarizes the inputs and results for each location. This Microsoft Excel spreadsheet is also included in the ZIP file. For version 1.4, only the IDF file is included.

  4. Reference Buildings by Building Type: Large Hotel

    Office of Energy Efficiency and Renewable Energy (EERE)

    In addition to the ZIP file for each building type, you can directly view the "scorecard" spreadsheet that summarizes the inputs and results for each location. This Microsoft Excel spreadsheet is also included in the ZIP file. For version 1.4, only the IDF file is included.

  5. Waste Isolation Pilot Plant (WIPP) Waste Isolation Pilot Plant...

    National Nuclear Security Administration (NNSA)

    licensed to safely and permanently dispose of transuranic radioactive waste, or TRU waste, left over from the production of nuclear weapons. After more than 20 years of...

  6. Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)

    Broader source: Energy.gov [DOE]

    This act provides for planning for the processing and disposal of municipal waste; requires counties to submit plans for municipal waste management systems within their boundaries; authorizes...

  7. BUILDING PERFORMANCE ENGINEERING DURING CONSTRUCTION

    E-Print Network [OSTI]

    Toole, T. Michael

    1 BUILDING PERFORMANCE ENGINEERING DURING CONSTRUCTION T. Michael Toole1 and Matthew Hallowell2 of building performance engineering tasks on design-bid-build projects are typically provided by entities building construction projects. Twenty four building performance engineering tasks were required

  8. About Singapore Green Building Council

    E-Print Network [OSTI]

    About Singapore Green Building Council About SGBC Green Building Conference Conference Programme Green Building Conference In line with the mission of the Singapore Green Building Council (SGBC is please to present the inaugural SGBC Green Building Conference 2010 to be held from 13 ­ 16 September

  9. NREL Buildings Research Video

    ScienceCinema (OSTI)

    None

    2013-05-29T23:59:59.000Z

    Through research, the National Renewable Energy Laboratory (NREL) has developed many strategies and design techniques to ensure both commercial and residential buildings use as little energy as possible and also work well with the surroundings. Here you will find a video that introduces the work of NREL Buildings Research, highlights some of the facilities on the NREL campus, and demonstrates these efficient building strategies. Watch this video to see design highlights of the Science and Technology Facility on the NREL campus?the first Federal building to be LEED® Platinum certified. Additionally, the video demonstrates the energy-saving features of NRELs Thermal Test Facility. For a text version of this video visit http://www.nrel.gov/buildings/about_research_text_version.html

  10. Solid Waste Act (New Mexico)

    Broader source: Energy.gov [DOE]

    The main purpose of the Solid Waste Act is to authorize and direct the establishment of a comprehensive solid waste management program. The act states details about specific waste management...

  11. Virginia Waste Management Act (Virginia)

    Broader source: Energy.gov [DOE]

    Solid waste and hazardous waste are regulated under a number of programs at the Department of Environmental Quality. These programs are designed to encourage the reuse and recycling of solid waste...

  12. Hazardous Waste Management (North Carolina)

    Broader source: Energy.gov [DOE]

    These rules identify and list hazardous waste and set standards for the generators and operators of such waste as well as owners or operators of waste facilities. They also stats standards for...

  13. Solid Waste Disposal Act (Texas)

    Broader source: Energy.gov [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...

  14. Georgia Waste Control Law (Georgia)

    Broader source: Energy.gov [DOE]

    The Waste Control Law makes it unlawful to dump waste in any lakes, streams or surfaces waters of the State or on any private property without consent of the property owner. Waste is very broadly...

  15. City of Scottsdale- Green Building Policy for Public Buildings

    Broader source: Energy.gov [DOE]

    In 2005, Scottsdale approved a green building policy for new city buildings and remodels. The resolution requires all new, occupied city buildings of any size to be designed, contracted and built...

  16. Simple Waste Solutions for Complex Facilities - 12433

    SciTech Connect (OSTI)

    King, Terry I. [Washington Closure Hanford, Richland, Washington 99352 (United States); Stephan, Clifford J. [Lucas Engineering and Management Services, Richland Washington 99352 (United States)

    2012-07-01T23:59:59.000Z

    The buildings in the 300 Area, including several Category 3 nuclear facilities are undergoing deactivation, decommissioning, decontamination and demolition (D4) by Washington Closure Hanford (WCH) as part of the River Corridor Closure Contract (RCCC). The D4 process has generated a wide variety of low-level radioactive and low-level radioactive mixed waste as well as TRU. The Hanford Site-wide Transportation Safety Document (TSD) has been successfully utilized to transport waste streams that otherwise would not be able to be shipped. The TSD accomplished this by establishing a comprehensive set of onsite transportation and packaging performance standards and risk-based standards. The requirements and standards presented are equivalent to DOT and NRC standards (10 CFR 71). (authors)

  17. Irradiation effects on borosilicate waste glasses

    SciTech Connect (OSTI)

    Roberts, F.P.

    1980-06-01T23:59:59.000Z

    The effects of alpha decay on five borosilicate glasses containing simulated nuclear high-level waste oxides were studied. Irradiations carried out at room temperature were achieved by incorporating 1 to 8 wt % /sup 244/Cm/sub 2/O/sub 3/ in the glasses. Density changes and stored-energy build-up saturated at doses less than 2 x 10/sup 21/ alpha decays/kg. Damage manifested by stored energy was completely annealed at 633/sup 0/K. Positive and negative density changes were observed which never exceeded 1%. Irradiation had very little effect on mechanical strength or on chemical durability as measured by aqueous leach rates. Also, no effects were observed on the microstructure for vitreous waste glasses, although radiation-induced microcracking could be achieved on specimens that had been devitrified prior to irradiation.

  18. Presentation: Better Buildings Residential Program Solution Center...

    Office of Environmental Management (EM)

    Presentation: Better Buildings Residential Program Solution Center Presentation: Better Buildings Residential Program Solution Center Presentation: Better Buildings Residential...

  19. Building Technologies Program | Clean Energy | ORNL

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

    Building Technologies Program SHARE Building Technologies Program The Building Technologies Program Office administratively facilitates the integration of ORNL research across...

  20. Information Technology Tools for Multifamily Building Programs...

    Energy Savers [EERE]

    Information Technology Tools for Multifamily Building Programs Information Technology Tools for Multifamily Building Programs Better Buildings Neighborhood Program Multifamily ...