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Sample records for minimum additive waste

  1. Minimum Additive Waste Stabilization (MAWS)

    International Nuclear Information System (INIS)

    1994-02-01

    In the Minimum Additive Waste Stabilization(MAWS) concept, actual waste streams are utilized as additive resources for vitrification, which may contain the basic components (glass formers and fluxes) for making a suitable glass or glassy slag. If too much glass former is present, then the melt viscosity or temperature will be too high for processing; while if there is too much flux, then the durability may suffer. Therefore, there are optimum combinations of these two important classes of constituents depending on the criteria required. The challenge is to combine these resources in such a way that minimizes the use of non-waste additives yet yields a processable and durable final waste form for disposal. The benefit to this approach is that the volume of the final waste form is minimized (waste loading maximized) since little or no additives are used and vitrification itself results in volume reduction through evaporation of water, combustion of organics, and compaction of the solids into a non-porous glass. This implies a significant reduction in disposal costs due to volume reduction alone, and minimizes future risks/costs due to the long term durability and leach resistance of glass. This is accomplished by using integrated systems that are both cost-effective and produce an environmentally sound waste form for disposal. individual component technologies may include: vitrification; thermal destruction; soil washing; gas scrubbing/filtration; and, ion-exchange wastewater treatment. The particular combination of technologies will depend on the waste streams to be treated. At the heart of MAWS is vitrification technology, which incorporates all primary and secondary waste streams into a final, long-term, stabilized glass wasteform. The integrated technology approach, and view of waste streams as resources, is innovative yet practical to cost effectively treat a broad range of DOE mixed and low-level wastes

  2. Minimum Additive Waste Stabilization (MAWS), Phase I: Soil washing final report

    International Nuclear Information System (INIS)

    1995-08-01

    As a result of the U.S. Department of Energy's environmental restoration and technology development activities, GTS Duratek, Inc., and its subcontractors have demonstrated an integrated thermal waste treatment system at Fernald, OH, as part the Minimum Additive Waste Stabilization (MAWS) Program. Specifically, MAWS integrates soil washing, vitrification of mixed waste streams, and ion exchange to recycle and remediate process water to achieve, through a synergistic effect, a reduction in waste volume, increased waste loading, and production of a durable, leach-resistant, stable waste form suitable for disposal. This report summarizes the results of the demonstration/testing of the soil washing component of the MAWS system installed at Fernald (Plant 9). The soil washing system was designed to (1) process contaminated soil at a rate of 0.25 cubic yards per hour; (2) reduce overall waste volume and provide consistent-quality silica sand and contaminant concentrates as raw material for vitrification; and (3) release clean soil with uranium levels below 35 pCi/g. Volume reductions expected ranged from 50-80 percent; the actual volume reduction achieved during the demonstration reached 66.5 percent. The activity level of clean soil was reduced to as low as 6 pCi/g from an initial average soil activity level of 17.6 pCi/g (the highest initial level of soil provided for testing was 41 pCi/g). Although the throughput of the soil washing system was inconsistent throughout the testing period, the system was online for sufficient periods to conclude that a rate equivalent to 0.25 cubic yards per hour was achieved

  3. Minimum additive waste stabilization using vitreous ceramics. Progress report, October 1994--September 1995

    International Nuclear Information System (INIS)

    Feng, X.; Hahn, W.K.; Gong, M.; Gong, W.; Wang, L.; Ewing, R.C.

    1995-01-01

    Vitreous ceramic waste forms are being developed at Pacific Northwest Laboratory to complement glass waste forms in implementing the Minimum Additive Waste Stabilization (MAWS) Program to support the US Department of Energy's environmental restoration efforts. These vitreous ceramics are composed of various metal-oxide crystalline phases embedded in a silicate-glass phase. This work extends the success of vitreous ceramic waste forms to treat wastes with both high metal and high alkali contents. Two successful approaches are discussed: developing high-durability alkali-binding crystals in a durable glassy matrix, and developing water-soluble crystals in a durable and continuous glassy matrix. Nepheline-vitreous ceramics were demonstrated for the immobilization of high-alkali wastes with alkali contents up to 21 wt%. The chemical durability of the nepheline-vitreous ceramics is better than the corresponding glasses, especially in over longer times. Vitreous ceramics with Cs 2 O loading up to 35.4 wt% have been developed. Vitreous ceramic waste forms were developed from 90 and 100% Oak Ridge National Laboratory K-25 pond sludge. Heat treatment resulted in targeted crystal formation of spinels, potassium feldspar, and Ca-P phases. The K-25 pond sludge vitreous ceramics were up to 42 times more durable than high-level environmental assessments (EA) glass. The toxicity characteristics leach procedure (TCLP) concentration of LVC-6 is at least 2,000 times lower than US Environmental Protection Agency limits. Idaho Chemical Process Plant (ICPP) calcined wastes were immobilized into vitreous ceramics with calcine loading up to 88%. These ICPP-vitreous ceramics were more durable than the EA glass by factors of 5 to 30. Vitreous ceramic waste forms are being developed to complement, not to replace, glass waste forms

  4. Radioactive waste assessment using 'minimum waste generation' scenario - summary report March 1984

    International Nuclear Information System (INIS)

    Richardson, J.A.; Goodill, D.R.; Tymons, B.J.

    1984-11-01

    This report describes an assessment of radioactive waste management arisings from a defined nuclear power generation - Scheme 1. Scheme 1 assumes a minimum waste generation scenario with raw waste arisings from 3 main groups; (i) existing and committed commercial reactors; (ii) fuel reprocessing plants, (iii) research, industry and medicine. No decommissioning wastes are considered except for arisings from the final fuel cores from decommissioned reactors. The study uses the SIMULATION2 code which models waste material flows through the system. With a knowledge of the accumulations and average production rates of the raw wastes and their isotopic compositions (or total activities), the rates at which conditioned wastes become available for transportation and disposal are calculated, with specific activity levels. The data bases for the inventory calculations and the assumptions concerning future operation of nuclear facilities were those current in 1983. Both the inventory data and plans for the future of existing nuclear installations have been updated since these calculations were completed. Therefore the results from this assessment do not represent the most up-to-date information available. The report does, however, illustrate the methodology of assessment and indicates the type of information that can be generated. (author)

  5. Low-activity waste feed delivery -- Minimum duration between successive batches

    International Nuclear Information System (INIS)

    Peters, B.B.

    1998-01-01

    The purpose of this study is to develop a defensible basis for establishing what ''minimum duration'' will provide acceptable risk mitigation for low-activity waste feed delivery to the privatization vendors. The study establishes a probabilistic-based duration for staging of low-activity waste feed batches. A comparison is made of the durations with current feed delivery plans and potential privatization vendor facility throughput rates

  6. Low-activity waste feed delivery -- Minimum duration between successive batches

    Energy Technology Data Exchange (ETDEWEB)

    Peters, B.B.

    1998-08-25

    The purpose of this study is to develop a defensible basis for establishing what ``minimum duration`` will provide acceptable risk mitigation for low-activity waste feed delivery to the privatization vendors. The study establishes a probabilistic-based duration for staging of low-activity waste feed batches. A comparison is made of the durations with current feed delivery plans and potential privatization vendor facility throughput rates.

  7. Minimum Compliance Topology Optimization of Shell-Infill Composites for Additive Manufacturing

    DEFF Research Database (Denmark)

    Wu, Jun; Clausen, Anders; Sigmund, Ole

    2017-01-01

    Additively manufactured parts are often composed of two sub-structures, a solid shell forming their exterior and a porous infill occupying the interior. To account for this feature this paper presents a novel method for generating simultaneously optimized shell and infill in the context of minimum...... interpolation model into a physical density field, upon which the compliance is minimized. Enhanced by an adapted robust formulation for controlling the minimum length scale of the base, our method generates optimized shell-infill composites suitable for additive manufacturing. We demonstrate the effectiveness...

  8. Determine Minimum Silver Flake Addition to GCM for Iodine Loaded AgZ

    Energy Technology Data Exchange (ETDEWEB)

    Garino, Terry J.; Nenoff, Tina M.; Rodriguez, Mark A.

    2014-04-01

    The minimum amount of silver flake required to prevent loss of I{sub 2} during sintering in air for a SNL Glass Composite Material (GCM) Waste Form containing AgI-MOR (ORNL, 8.7 wt%) was determined to be 1.1 wt% Ag. The final GCM composition prior to sintering was 20 wt% AgI-MOR, 1.1 wt% Ag, and 80 wt% Bi-Si oxide glass. The amount of silver flake needed to suppress iodine loss was determined using thermo gravimetric analysis with mass spectroscopic off-gas analysis. These studies found that the ratio of silver to AgI-MOR required is lower in the presence of the glass than without it. Therefore an additional benefit of the GCM is that it serves to inhibit some iodine loss during processing. Alternatively, heating the AgI-MOR in inert atmosphere instead of air allowed for densified GCM formation without I{sub 2} loss, and no necessity for the addition of Ag. The cause of this behavior is found to be related to the oxidation of the metallic Ag to Ag{sup +} when heated to above ~300{degrees}C in air. Heating rate, iodine loading levels and atmosphere are the important variables that determine AgI migration and results suggest that AgI may be completely incorporated into the mordenite structure by the 550{degrees}C sintering temperature.

  9. Crystallization behavior of nuclear waste forms

    International Nuclear Information System (INIS)

    Rusin, J.M.; Lokken, R.O.; May, R.P.; Wald, J.W.

    1981-09-01

    Several waste form options have been or are being developed for the immobilization of high-level wastes. The final selection of a waste form must take into consideration both waste form product as well as process factors. Crystallization behavior has an important role in nuclear waste form technology. For glass or vitreous waste forms, crystallization is generally controlled to a minimum by appropriate glass formulation and heat treatment schedules. With glass ceramic waste forms, crystallization is essential to convert glass products to highly crystalline waste forms with a minimum residual glass content. In the case of ceramic waste forms, additives and controlled sintering schedules are used to contain the radionuclides in specific tailored crystalline phases

  10. 40 CFR 265.341 - Waste analysis.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Waste analysis. 265.341 Section 265... FACILITIES Incinerators § 265.341 Waste analysis. In addition to the waste analyses required by § 265.13, the... minimum, the analysis must determine: (a) Heating value of the waste; (b) Halogen content and sulfur...

  11. 40 CFR 265.375 - Waste analysis.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Waste analysis. 265.375 Section 265... FACILITIES Thermal Treatment § 265.375 Waste analysis. In addition to the waste analyses required by § 265.13... of pollutants which might be emitted. At a minimum, the analysis must determine: (a) Heating value of...

  12. Note from the Radioactive Waste Section

    CERN Multimedia

    TS Department

    2008-01-01

    The Radioactive Waste Section of the Radiation Protection Group wishes to announce that the radioactive waste treatment centre will be closed on Friday, 19 December. In addition, waste reception will be limited to a strict minimum on Thursday, 18 December. Users of the centre are requested to adjust their plans accordingly. For more information, call 73875.

  13. Glassy slags as novel waste forms for remediating mixed wastes with high metal contents

    International Nuclear Information System (INIS)

    Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

    1994-01-01

    Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms

  14. Effects of waste glass additions on quality of textile sludge-based bricks.

    Science.gov (United States)

    Rahman, Ari; Urabe, Takeo; Kishimoto, Naoyuki; Mizuhara, Shinji

    2015-01-01

    This research investigated the utilization of textile sludge as a substitute for clay in brick production. The addition of textile sludge to a brick specimen enhanced its pores, thus reducing the quality of the product. However, the addition of waste glass to brick production materials improved the quality of the brick in terms of both compressive strength and water absorption. Maximum compressive strength was observed with the following composition of waste materials: 30% textile sludge, 60% clay and 10% waste glass. The melting of waste glass clogged up pores on the brick, which improved water absorption performance and compressive strength. Moreover, a leaching test on a sludge-based brick to which 10% waste glass did not detect significant heavy metal compounds in leachates, with the product being in conformance with standard regulations. The recycling of textile sludge for brick production, when combined with waste glass additions, may thus be promising in terms of both product quality and environmental aspects.

  15. Features and safety aspects of Additional Waste Tank Farm, Tarapur

    International Nuclear Information System (INIS)

    Pradhan, Sanjay; Dubey, K.; Qureshi, F.T.; Lokeswar, S.P.

    2017-01-01

    Additional Waste Tank Farm (AWTF) at Tarapur is designed to store High and Intermediate Level Liquid wastes generated on an interim basis prior to treatment at TWMP for final disposal. Defence-in-depth philosophy is adopted in the design of AWTF

  16. Reactive Additive Stabilization Process (RASP) for hazardous and mixed waste vitrification

    International Nuclear Information System (INIS)

    Jantzen, C.M.; Pickett, J.B.; Ramsey, W.G.

    1993-01-01

    Solidification of hazardous/mixed wastes into glass is being examined at the Savannah River Site (SRS) for (1) nickel plating line (F006) sludges and (2) incinerator wastes. Vitrification of these wastes using high surface area additives, the Reactive Additive Stabilization Process (RASP), has been determined to greatly enhance the dissolution and retention of hazardous, mixed, and heavy metal species in glass. RASP lowers melt temperatures (typically 1050-- 1150 degrees C), thereby minimizing volatility concerns during vitrification. RASP maximizes waste loading (typically 50--75 wt% on a dry oxide basis) by taking advantage of the glass forming potential of the waste. RASP vitrification thereby minimizes waste disposal volume (typically 86--97 vol. %), and maximizes cost savings. Solidification of the F006 plating line sludges containing depleted uranium has been achieved in both soda-lime-silica (SLS) and borosilicate glasses at 1150 degrees C up to waste loadings of 75 wt%. Solidification of incinerator blowdown and mixtures of incinerator blowdown and bottom kiln ash have been achieved in SLS glass at 1150 degrees C up to waste loadings of 50% using RASP. These waste loadings correspond to volume reductions of 86 and 94 volume %, respectively, with large associated savings in storage costs

  17. Industrial Wastes as Auxiliary Additives to Cement/Lime Stabilization of Soils

    Directory of Open Access Journals (Sweden)

    Jijo James

    2016-01-01

    Full Text Available Chemical stabilization involves the use of chemical agents for initiating reactions within the soil for modification of its geotechnical properties. Cement and lime stabilization have been the most common stabilization methods adopted for soil treatment. Cement stabilization results in good compressive strengths and is preferred for cohesionless to moderately cohesive soil but loses effectiveness when the soil is highly plastic. Lime stabilization is the most preferred method for plastic clays; however, it proves to be ineffective in sulphate rich clays and performs poorly under extreme conditions. With such drawbacks, lots of researches have been undertaken to address the issues faced with each stabilization method, in particular, the use of solid wastes for soil stabilization. Solid waste reuse has gained high momentum for achieving sustainable waste management in recent times. Research has shown that the use of solid wastes as additives with and replacement for conventional stabilizers has resulted in better results than the performance of either individually. This review provides insight into some of the works done by earlier researchers on lime/cement stabilization with industrial wastes as additives and helps to form a sound platform for further research on industrial wastes as additives to conventional stabilizers.

  18. Big Area Additive Manufacturing of High Performance Bonded NdFeB Magnets

    NARCIS (Netherlands)

    Li, L; Tirado, A.; Nlebedim, I.C.; Rios, O.; Post, B.; Kunc, V.; Lowden, R.R.; Lara-Curzio, E.; Fredette, R.; Ormerod, J.; Lograsso, T.A.; Paranthaman, M.P.

    2016-01-01

    Additive manufacturing allows for the production of complex parts with minimum material waste, offering an effective technique for fabricating permanent magnets which frequently involve critical rare earth elements. In this report, we demonstrate a novel method - Big Area Additive Manufacturing

  19. Vacuum pyrolysis of waste tires with basic additives

    International Nuclear Information System (INIS)

    Zhang Xinghua; Wang Tiejun; Ma Longlong; Chang Jie

    2008-01-01

    Granules of waste tires were pyrolyzed under vacuum (3.5-10 kPa) conditions, and the effects of temperature and basic additives (Na 2 CO 3 , NaOH) on the properties of pyrolysis were thoroughly investigated. It was obvious that with or without basic additives, pyrolysis oil yield increased gradually to a maximum and subsequently decreased with a temperature increase from 450 deg. C to 600 deg. C, irrespective of the addition of basic additives to the reactor. The addition of NaOH facilitated pyrolysis dramatically, as a maximal pyrolysis oil yield of about 48 wt% was achieved at 550 deg. C without the addition of basic additives, while a maximal pyrolysis oil yield of about 50 wt% was achieved at 480 deg. C by adding 3 wt% (w/w, powder/waste tire granules) of NaOH powder. The composition analysis of pyrolytic naphtha (i.b.p. (initial boiling point) ∼205 deg. C) distilled from pyrolysis oil showed that more dl-limonene was obtained with basic additives and the maximal content of dl-limonene in pyrolysis oil was 12.39 wt%, which is a valuable and widely-used fine chemical. However, no improvement in pyrolysis was observed with Na 2 CO 3 addition. Pyrolysis gas was mainly composed of H 2 , CO, CH 4 , CO 2 , C 2 H 4 and C 2 H 6 . Pyrolytic char had a surface area comparable to commercial carbon black, but its proportion of ash (above 11.5 wt%) was much higher

  20. The Bird Core for Minimum Cost Spanning Tree problems Revisited : Monotonicity and Additivity Aspects

    NARCIS (Netherlands)

    Tijs, S.H.; Moretti, S.; Brânzei, R.; Norde, H.W.

    2005-01-01

    A new way is presented to define for minimum cost spanning tree (mcst-) games the irreducible core, which is introduced by Bird in 1976.The Bird core correspondence turns out to have interesting monotonicity and additivity properties and each stable cost monotonic allocation rule for mcst-problems

  1. Vitrification of F006 plating waste sludge by Reactive Additive Stabilization Process (RASP)

    International Nuclear Information System (INIS)

    Martin, H.L.; Jantzen, C.M.; Pickett, J.B.

    1994-01-01

    Solidification into glass of nickel-on-uranium plating wastewater treatment plant sludge (F006 Mixed Waste) has been demonstrated at the Savannah River She (SRS). Vitrification using high surface area additives, the Reactive Additive Stabilization Process (RASP), greatly enhanced the solubility and retention of heavy metals In glass. The bench-scale tests using RASP achieved 76 wt% waste loading In both soda-lime-silica and borosilicate glasses. The RASP has been Independently verified by a commercial waste management company, and a contract awarded to vitrify the approximately 500,000 gallons of stored waste sludge. The waste volume reduction of 89% will greatly reduce the disposal costs, and delisting of the glass waste is anticipated. This will be the world's first commercial-scale vitrification system used for environmental cleanup of Mixed Waste. Its stabilization and volume reduction abilities are expected to set standards for the future of the waste management Industry

  2. Yield Stress Reduction of Radioactive Waste Slurries by Addition of Surfactants

    International Nuclear Information System (INIS)

    MICHAEL, STONE

    2005-01-01

    The Savannah River Site (SRS) and Hanford site are in the process of stabilizing millions of gallons of radioactive waste slurries remaining from production of nuclear materials for the Department of Energy (DOE). The Defense Waste Processing Facility (DWPF) at SRS is currently vitrifying the waste in borosilicate glass while the facilities at the Hanford site are in the design/construction phase. Both processes utilize slurry-fed joule heated melters to vitrify the waste slurries. The rheological properties of the waste slurries limit the total solids content that can be processed by the remote equipment during the pretreatment and melter feed processes. The use of a surface active agent, or surfactant, to increase the solids loading that can be fed to the melters would increase melt rate by reducing the heat load on the melter required to evaporate the water in the feed. The waste slurries are non-Newtonian fluids with rheological properties that were modeled using the Bingham Plastic mod el (this model is typically used by SRNL when studying the DWPF process1).The results illustrate that altering the surface chemistry of the particulates in the waste slurries can lead to a reduction in the yield stress. Dolapix CE64 is an effective surfactant over a wide range of pH values and was effective for all simulants tested. The effectiveness of the additive increased in DWPF simulants as the concentration of the additive was increased. No maxi main effectiveness was observed. Particle size measurements indicate that the additive acted as a flocculant in the DWPF samples and as a dispersant in the RPP samples

  3. Influence of industrial solid waste addition on properties of soil-cement bricks

    OpenAIRE

    Siqueira, F. B.; Amaral, M. C.; Bou-Issa, R. A.; Holanda, J. N. F.

    2016-01-01

    Abstract The reuse of pollutant solid wastes produced in distinct industrial activities (avian eggshell waste and welding flux slag waste) as a source of alternative raw material for producing soil-cement bricks for civil construction was investigated. Soil-cement bricks containing up to 30 wt% of industrial solid waste were uniaxially pressed and cured for 28 days. Special emphasis is given on the influence of solid waste addition on the technical properties (as such volumetric shrinkage, wa...

  4. Technical basis for a minimum hydroxide concentration in tanks containing dilute waste

    International Nuclear Information System (INIS)

    Zapp, P.E.

    1995-05-01

    Laboratory tests were performed to address the protection of waste tank steel from corrosion in situations of elevated temperatures up to 75 C (hot spots) in the sludge layer of Extended Sludge Processing (ESP) tanks. Coupon immersion tests were conducted at 75 C in two ESP simulants at four hydroxide (or pH) levels. The nitrite concentrations of the simulants were calculated from the ESP technical standards based on a temperature of 40 C. The results showed that a hydroxide concentration of at least 0.01 M prevented significant corrosion of the steel at the elevated temperature. This conclusion provides the technical basis for the revised minimum hydroxide concentration of 0.01 M in the draft WSRC 241-82H Control Room Process Requirements, for the ESP tanks

  5. Practical guidelines for small-volume additions of uninhibited water to waste storage tanks

    International Nuclear Information System (INIS)

    Hsu, T.C.; Wiersma, B.J.; Zapp, P.E.; Pike, J.A.

    1994-01-01

    Allowable volumes of uninhibited water additions to waste tanks are limited to volumes in which hydroxide and nitrite inhibitors reach required concentrations by diffusion from the bulk waste within five days. This diffusion process was modeled conservatively by Fick's second law of diffusion. The solution to the model was applied to all applicable conditions which exist in the waste tanks. Plant engineers adapted and incorporated the results into a practical working procedure for controlling and monitoring the addition of uninhibited water. Research, technical support, and field engineers worked together to produce an effective solution to a potential waste tank corrosion problem

  6. Using of borosilicate glass waste as a cement additive

    International Nuclear Information System (INIS)

    Han, Weiwei; Sun, Tao; Li, Xinping; Sun, Mian; Lu, Yani

    2016-01-01

    Highlights: • Borosilicate glass waste used as cement additive can improves its radiation shielding. • When content is 14.8%, the linear attenuation coefficient is 0.2457 cm"−"1 after 28 d. • From 0 to 22.2%, linear attenuation coefficient firstly increase and then decrease. - Abstract: Borosilicate glass waste is investigated as a cement additive in this paper to improve the properties of cement and concrete, such as setting time, compressive strength and radiation shielding. The results demonstrate that borosilicate glass is an effective additive, which not only improves the radiation shielding properties of cement paste, but also shows the irradiation effect on the mechanical and optical properties: borosilicate glass can increase the compressive strength and at the same time it makes a minor impact on the setting time and main mineralogical compositions of hydrated cement mixtures; and when the natural river sand in the mortar is replaced by borosilicate glass sand (in amounts from 0% to 22.2%), the compressive strength and the linear attenuation coefficient firstly increase and then decrease. When the glass waste content is 14.8%, the compressive strength is 43.2 MPa after 28 d and the linear attenuation coefficient is 0.2457 cm"−"1 after 28 d, which is beneficial for the preparation of radiation shielding concrete with high performances.

  7. Using of borosilicate glass waste as a cement additive

    Energy Technology Data Exchange (ETDEWEB)

    Han, Weiwei [State Key Laboratory of Silicate Materials for Architectures, Wuhan University of Technology, Wuhan, Hubei 430070 (China); School of Civil Engineering and Architecture, Wuhan University of Technology, Wuhan, Hubei 430070 (China); Sun, Tao, E-mail: sunt@whut.edu.cn [State Key Laboratory of Silicate Materials for Architectures, Wuhan University of Technology, Wuhan, Hubei 430070 (China); Key Laboratory of Roadway Bridge & Structure Engineering, Wuhan University of Technology, Wuhan, Hubei 430070 (China); Li, Xinping [Key Laboratory of Roadway Bridge & Structure Engineering, Wuhan University of Technology, Wuhan, Hubei 430070 (China); Sun, Mian [School of Materials Science and Engineering, Wuhan University of Technology, Wuhan, Hubei 430070 (China); Lu, Yani [Urban Construction Institute, Hubei Engineering University, Xiaogan, Hubei 432000 (China)

    2016-08-15

    Highlights: • Borosilicate glass waste used as cement additive can improves its radiation shielding. • When content is 14.8%, the linear attenuation coefficient is 0.2457 cm{sup −1} after 28 d. • From 0 to 22.2%, linear attenuation coefficient firstly increase and then decrease. - Abstract: Borosilicate glass waste is investigated as a cement additive in this paper to improve the properties of cement and concrete, such as setting time, compressive strength and radiation shielding. The results demonstrate that borosilicate glass is an effective additive, which not only improves the radiation shielding properties of cement paste, but also shows the irradiation effect on the mechanical and optical properties: borosilicate glass can increase the compressive strength and at the same time it makes a minor impact on the setting time and main mineralogical compositions of hydrated cement mixtures; and when the natural river sand in the mortar is replaced by borosilicate glass sand (in amounts from 0% to 22.2%), the compressive strength and the linear attenuation coefficient firstly increase and then decrease. When the glass waste content is 14.8%, the compressive strength is 43.2 MPa after 28 d and the linear attenuation coefficient is 0.2457 cm{sup −1} after 28 d, which is beneficial for the preparation of radiation shielding concrete with high performances.

  8. The Addition of Hatchery Liquid Waste to Dairy Manure Improves Anaerobic Digestion

    Directory of Open Access Journals (Sweden)

    WRT Lopes

    Full Text Available ABSTRACT The objective of this study was to determine the optimal inclusion level of liquid egg hatchery waste for the anaerobic co-digestion of dairy cattle manure. A completely randomized experimental was applied, with seven treatments (liquid hatchery waste to cattle manure ratios of0: 100, 5:95, 10:90, 15:85, 20:80, 25:75 and 30:70, with five replicates (batch digester model each. The evaluated variables were disappearance of total solids (TS, volatile solids (VS, and neutral detergent fiber (NDF, and specific production of biogas and of methane. Maximum TS and VS disappearance of 41.3% and 49.6%, were obtained at 15.5% and 16.0% liquid hatchery waste inclusion levels. The addition of 22.3% liquid hatchery considerably reduced NDF substrate content (53.2%. Maximum specific biogas production was obtained with 17% liquid hatchery waste, with the addition of 181.7 and 229.5 L kg-1TS and VS, respectively. The highest methane production, at 120.1 and 151.8 L CH4 kg-1TS and VS, was obtained with the inclusion of 17.5 and 18.0% liquid hatchery waste, respectively. The addition of liquid hatchery waste atratios of up to 15.5%in co-digestion with cattle manure reduced solid and fiber levels in the effluent, and improved biogas and methane production.

  9. Immobilization of radioactive waste through cementation using Cuban zeolitic rock as additive

    International Nuclear Information System (INIS)

    Chales Suarez, G.; Castillo Gomez, R.

    1997-01-01

    The cementation of both simulated and real low level aqueous wastes using Cuban zeolite as additive is described. Mechanical characteristics and leach testing of the cemented waste forms has been studied. The results obtained have shown that the presence of zeolite in the cemented waste for reduces considerably the leach rates of Cs and Co and moreover, mechanical characteristics (set time and compressive strength) are better when compared with direct cementation of aqueous wastes. (author). 13 refs, 8 tabs

  10. Analysis of transport logistics and routing requirements for radioactive waste management systems with respect to a minimum power scenario

    International Nuclear Information System (INIS)

    James, I.A.

    1984-10-01

    This report assesses the transport logistics associated with disposal of intermediate-level radioactive waste, as generated by CEGB, SSEB, UKAEA and BNFL, in accordance with a 'Minimum Power Scenario'. Transport by road and rail is analysed, as in previous reports; use of coastal shipping however has not been included but has been replaced with a combined road/rail option. (author)

  11. Study of commercial chemical additives for cementation of radioactive waste

    International Nuclear Information System (INIS)

    Mota Vieira, V.; Oliveira, C.C. de

    2015-01-01

    In this research it has been studied the effects of chemical additives (admixtures) in the cementation process of radioactive wastes, which are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market, then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 23. The measured parameters were the viscosity, the setting time, the paste and product density and the compressive strength. In this study we performed comparative analyzes of the results of compressive strength at age of 28 and 90 days and between the densities of the samples at the same ages. The compressive strength test at age of 28 days is considered a parameter essential issues related to security handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented product, but presented lower values density products. (authors)

  12. Optimization of the Municipal Waste Collection Route Based on the Method of the Minimum Pairing

    Directory of Open Access Journals (Sweden)

    Michal Petřík

    2016-01-01

    Full Text Available In the present article is shown the use of Maple program for processing of data describing the position of municipal waste sources and topology of collecting area. The data are further processed through the use of graph theory algorithms, which enable creation of collection round proposal. In this case study is described method of waste pick-up solution in a certain village of approx. 1,600 inhabitants and built-up area of approx. 30 hectares. Village has approx. 11.5 kilometers of ride able routes, with approx. 1 kilometer without waste source. The first part shows topology of the village in light of location of waste sources and capacity of the routes. In the second part are topological data converted into data that can be processed by use of the Graph Theory and the correspondent graph is shown. Optimizing collection route in a certain graph means to find the Euler circle. However, this circle can be constructed only on condition that all the vertices of the graph are of an even degree. Practically this means that is necessary to introduce auxiliary edges – paths that will be passed twice. These paths will connect vertices with odd values. The optimal solution then requires that the total length of the inserted edges was minimal possible, which corresponds to the minimum pairing method. As it is a problem of exponential complexity, it is necessary to make some simplifications. These simplifications are depicted graphically and the results are displayed in the conclusion. The resulting graph with embedded auxiliary edges can be used as a basic decision making material for creation of real collection round that respects local limitations such as one way streets or streets where is the waste collection is not possible from both sides at the same time.

  13. A direct, single-step plasma arc-vitreous ceramic process for stabilizing spent nuclear fuels, sludges, and associated wastes

    International Nuclear Information System (INIS)

    Feng, X.; Einziger, R.E.; Eschenbach, R.C.

    1997-01-01

    A single-step plasma arc-vitreous ceramic (PAVC) process is described for converting spent nuclear fuel (SNF), SNF sludges, and associated wastes into a vitreous ceramic waste form. This proposed technology is built on extensive experience of nuclear waste form development and nuclear waste treatment using the commercially available plasma arc centrifugal (PAC) system. SNF elements will be loaded directly into a PAC furnace with minimum additives and converted into vitreous ceramics with up to 90 wt% waste loading. The vitreous ceramic waste form should meet the functional requirements for borosilicate glasses for permanent disposal in a geologic repository and for interim storage. Criticality safety would be ensured through the use of batch modes, and controlling the amount of fuel processed in one batch. The minimum requirements on SNF characterization and pretreatment, the one-step process, and minimum secondary waste generation may reduce treatment duration, radiation exposure, and treatment cost

  14. Formulation of SYNROC-D additives for Savannah River Plant high-level radioactive waste

    International Nuclear Information System (INIS)

    Ryerson, F.J.; Burr, K.; Rozsa, R.

    1981-12-01

    SYNROC-D is a multiphase ceramic waste form consisting of nepheline, zirconolite, perovskite, and spinel. It has been formulated for the immobilization of high-level radioactive wastes now stored at Savannah River Plant (SRP) near Aiken, South Carolina. This report utilizes existing experimental data to develop a method for calculating additives to these waste products. This method calculates additions based on variations of mineral compositions as a function of sludge composition and radionuclide partitioning among the SYNROC phases. Based on these calculations, a FORTRAN program called ADSYN has been developed to determine the proper reagent proportions to be added to the SRP sludges

  15. The effect of leachate recirculation with enzyme cellulase addition on waste stability in landfill bioreactor

    Science.gov (United States)

    Saffira, N.; Kristanto, G. A.

    2018-01-01

    Landfill bioreactor with leachate recirculation is known to enhance waste stabilization. However, the composition of waste in Indonesia is comprised by organic waste which is lignocellulosic materials that considered take a long time to degrade under anaerobic condition. To accelerate the degradation process, enzyme addition is ought to do. Cellulase is an enzyme that can catalyse cellulose and other polysaccharide decomposition processes. Therefore, operation of waste degradation using leachate recirculation with a cellulase addition to enhance waste stabilization was investigated using anaerobic bioreactor landfill. The experiment was performed on 2 conditions; leachate recirculation with cellulase addition and recirculation only as a control. The addition of cellulase is reported to be significant in decreasing organic content, represented by volatile solid parameter. The volatile solid reduction in the cellulase augmented reactor and control reactor was 17.86% and 7.90%, respectively. Cellulase addition also resulted in the highest cellulose reduction. Settlement of the landfill in a bioreactor with enzyme addition (32.67%) was reported to be higher than the control (19.33%). Stabilization of landfill review by the decreasing rate constant of the cellulose and lignin ratio parameter was more rapidly achieved by the enzyme addition (0.014 day-1) compared to control (0.002 day-1).

  16. Influence of industrial solid waste addition on properties of soil-cement bricks

    Directory of Open Access Journals (Sweden)

    F. B. Siqueira

    Full Text Available Abstract The reuse of pollutant solid wastes produced in distinct industrial activities (avian eggshell waste and welding flux slag waste as a source of alternative raw material for producing soil-cement bricks for civil construction was investigated. Soil-cement bricks containing up to 30 wt% of industrial solid waste were uniaxially pressed and cured for 28 days. Special emphasis is given on the influence of solid waste addition on the technical properties (as such volumetric shrinkage, water absorption, bulk density, durability, and compressive strength, microstructure and mineral phases of soil-cement bricks. Microstructural evolution was evaluated via confocal microscopy. The experimental results showed that the solid wastes behave as charge material and influenced both technical properties and microstructure of the soil-cement bricks. It was found that up to 15 wt% of welding flux slag waste and up to 30 wt% of avian eggshell waste could be added into the soil-cement bricks for use as building material.

  17. 40 CFR 262.104 - What are the minimum performance criteria?

    Science.gov (United States)

    2010-07-01

    ... words “laboratory waste” or with the chemical name of the contents. If the container is too small to...) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE University Laboratories... criteria? The Minimum Performance Criteria that each University must meet in managing its Laboratory Waste...

  18. WASTES: a waste management logistics/economics model

    International Nuclear Information System (INIS)

    McNair, G.W.; Shay, M.R.; Fletcher, J.F.; Cashwell, J.W.

    1985-01-01

    The WASTES logistics model is a simulation language based model for analyzing the logistic flow of spent fuel/nuclear waste throughout the waste management system. The model tracks the movement of spent fuel/nuclear waste from point of generation to final destination. The model maintains inventories of spent fuel/nuclear waste at individual reactor sites as well as at various facilities within the waste management system. A maximum of 14 facilities may be utilized within a single run. These 14 facilities may include any combination of the following facilities: (1) federal interim storage (FIS), (2) reprocessing (REP), (3) monitored retrievable storage (MRS), (4) geological disposal facilities (GDF). The movement of spent fuel/nuclear waste between these facilities is controlled by the user specification of loading and unloading rates, annual and maximum capacities and commodity characteristics (minimum age or heat constraints) for each individual facility. In addition, the user may specify varying levels of priority on the spent fuel/nuclear waste that will be eligible for movement within a given year. These levels of priority allow the user to preferentially move spent fuel from reactor sites that are experiencing a loss of full-core-reserve (FCR) margin in a given year or from reactors that may be in the final stages of decommissioning. The WASTES model utilizes the reactor specific data available from the PNL spent fuel database. This database provides reactor specific information on items such as spent fuel basin size, reactor location, and transportation cask preference (i.e., rail or truck cask). In addition, detailed discharge data is maintained that provides the number of assemblies, metric tons, and exposure for both historic and projected discharges at each reactor site

  19. Effect of Addition of High Strength Food Wastes on Anaerobic Digestion of Sewage Sludge

    OpenAIRE

    Vaidya, Ramola Vinay

    2015-01-01

    Anaerobic co-digestion of municipal sludge and food wastes high in chemical oxygen demand (COD) has been an area of interest for waste water treatment facilities looking to increase methane production, and at the same time, dispose of the wastes and increase the revenue. However, addition of food wastes containing fats, oils and grease (FOG) to the conventional anaerobic digestion process can be difficult and pose challenges to utilities. Incorporating these wastes into the treatment plants c...

  20. Standard test method for determining liquidus temperature of immobilized waste glasses and simulated waste glasses

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2011-01-01

    1.1 These practices cover procedures for determining the liquidus temperature (TL) of nuclear waste, mixed nuclear waste, simulated nuclear waste, or hazardous waste glass in the temperature range from 600°C to 1600°C. This method differs from Practice C829 in that it employs additional methods to determine TL. TL is useful in waste glass plant operation, glass formulation, and melter design to determine the minimum temperature that must be maintained in a waste glass melt to make sure that crystallization does not occur or is below a particular constraint, for example, 1 volume % crystallinity or T1%. As of now, many institutions studying waste and simulated waste vitrification are not in agreement regarding this constraint (1). 1.2 Three methods are included, differing in (1) the type of equipment available to the analyst (that is, type of furnace and characterization equipment), (2) the quantity of glass available to the analyst, (3) the precision and accuracy desired for the measurement, and (4) candi...

  1. Methodology development for radioactive waste treatment of CDTN/BR - liquid low-level radioactive wastes

    International Nuclear Information System (INIS)

    Morais, Carlos Antonio de

    1996-01-01

    The radioactive liquid wastes generated in Nuclear Technology Development Centre (CDTN) were initially treated by precipitation/filtration and then the resulting wet solid wastes were incorporated in cement. These wastes were composed of different chemicals and different radioactivities and were generated by different sectors. The objective of the waste treatment method was to obtain minimum wet solid waste volume and decontamination and minimum operational cost. The composition of the solid wastes were taken into consideration for compatible cementation process. Approximately 5,400 litres of liquid radioactive wastes were treated by this process during 1992-1995. The volume reduction was 1/24 th and contained 20% solids. (author)

  2. Experimental Investigation of the Use of Waste Mineral Oils as a Fuel with Organic-Based Mn Additive

    Directory of Open Access Journals (Sweden)

    Bülent Özdalyan

    2018-06-01

    Full Text Available The heat values of waste mineral oils are equal to the heat value of the fuel oil. However, heat value alone is not sufficient for the use of waste minerals oils as fuel. However, the critical physical properties of fuels such as density and viscosity need to be adapted to the system in order to be used. In this study, the engine oils used in the first 10,000 km of the vehicles were used as waste mineral oil. An organic-based Mn additive was synthesized to improve the properties of the waste mineral oil. It was observed that mixing the Mn additive with the waste mineral oil at different doses (4, 8, 12, and 16 ppm improves the viscosity of the waste oil and the flash point. The resulting fuel was evaluated for emission using different loads in a 5 kW capacity generator to compare the fuel with standard diesel fuel and to determine the effect of Mn addition. In the experimental study, it was observed that the emission characteristics of the fuel obtained from waste mineral oil were worse than diesel fuel, but some improvement was observed with Mn addition. As a result, we found that the use of waste mineral oils in engines in fuel standards was not appropriate, but may be improved with additives.

  3. [Effects of superphosphate addition on NH3 and greenhouse gas emissions during vegetable waste composting].

    Science.gov (United States)

    Yang, Yan; Sun, Qin-ping; Li, Ni; Liu, Chun-sheng; Li, Ji-jin; Liu, Ben-sheng; Zou, Guo-yuan

    2015-01-01

    To study the effects of superphosphate (SP) on the NH, and greenhouse gas emissions, vegetable waste composting was performed for 27 days using 6 different treatments. In addition to the controls, five vegetable waste mixtures (0.77 m3 each) were treated with different amounts of the SP additive, namely, 5%, 10%, 15%, 20% and 25%. The ammonia volatilization loss and greenhouse gas emissions were measured during composting. Results indicated that the SP additive significantly decreased the ammonia volatilization and greenhouse gas emissions during vegetable waste composting. The additive reduced the total NH3 emission by 4.0% to 16.7%. The total greenhouse gas emissions (CO2-eq) of all treatments with SP additives were decreased by 10.2% to 20.8%, as compared with the controls. The NH3 emission during vegetable waste composting had the highest contribution to the greenhouse effect caused by the four different gases. The amount of NH3 (CO2-eq) from each treatment ranged from 59.90 kg . t-1 to 81.58 kg . t-1; NH3(CO2-eq) accounted for 69% to 77% of the total emissions from the four gases. Therefore, SP is a cost-effective phosphorus-based fertilizer that can be used as an additive during vegetable waste composting to reduce the NH3 and greenhouse gas emissions as well as to improve the value of compost as a fertilizer.

  4. Progress in radioactive graphite waste management. Additional information

    International Nuclear Information System (INIS)

    2010-06-01

    Radioactive graphite constitutes a major waste stream which arises during the decommissioning of certain types of nuclear installations. Worldwide, a total of around 250 000 tonnes of radioactive graphite, comprising graphite moderators and reflectors, will require management solutions in the coming years. 14 C is the radionuclide of greatest concern in nuclear graphite; it arises principally through the interaction of reactor neutrons with nitrogen, which is present in graphite as an impurity or in the reactor coolant or cover gas. 3 H is created by the reactions of neutrons with 6 Li impurities in graphite as well as in fission of the fuel. 36 Cl is generated in the neutron activation of chlorine impurities in graphite. Problems in the radioactive waste management of graphite arise mainly because of the large volumes requiring disposal, the long half-lives of the main radionuclides involved and the specific properties of graphite - such as stored Wigner energy, graphite dust explosibility and the potential for radioactive gases to be released. Various options for the management of radioactive graphite have been studied but a generally accepted approach for its conditioning and disposal does not yet exist. Different solutions may be appropriate in different cases. In most of the countries with radioactive graphite to manage, little progress has been made to date in respect of the disposal of this material. Only in France has there been specific thinking about a dedicated graphite waste-disposal facility (within ANDRA): other major producers of graphite waste (UK and the countries of the former Soviet Union) are either thinking in terms of repository disposal or have no developed plans. A conference entitled 'Solutions for Graphite Waste: a Contribution to the Accelerated Decommissioning of Graphite Moderated Nuclear Reactors' was held at the University of Manchester 21-23 March 2007 in order to stimulate progress in radioactive graphite waste management

  5. Bread enriched in lycopene and other bioactive compounds by addition of dry tomato waste.

    Science.gov (United States)

    Nour, Violeta; Ionica, Mira Elena; Trandafir, Ion

    2015-12-01

    The tomato processing industry generates high amounts of waste, mainly tomato skins and seeds, which create environmental problems. These residues are attractive sources of valuable bioactive components and pigments. A relatively simple recovery technology could consist of production of powders to be directly incorporated into foods. Tomato waste coming from a Romanian tomato processing unit were analyzed for the content of several bioactive compounds like ascorbic acid, β-carotene, lycopene, total phenolics, mineral and trace elements. In addition, its antioxidant capacity was assayed. Results revealed that tomato waste (skins and seeds) could be successfully utilized as functional ingredient for the formulation of antioxidant rich functional foods. Dry tomato processing waste were used to supplement wheat flour at 6 and 10 % levels (w/w flour basis) and the effects on the bread's physicochemical, baking and sensorial characteristics were studied. The following changes were observed: increase in moisture content, titratable acidity and bread crumb elasticity, reduction in specific volume and bread crumb porosity. The addition of dry tomato waste at 6 % resulted in bread with good sensory characteristics and overall acceptability but as the amount of dry tomato waste increased to 10 %, bread was less acceptable.

  6. UASB Treatment of Methanolic Pulp Wastewater with Addition of Waste Starch and Incinerated Ash

    Science.gov (United States)

    Takahashi, Shintaro; Kobaysashi, Takuro; Li, Yu-You; Harada, Hideki

    The pulp wastewater consists mainly of methanol. It is expected to treat using upflow anaerobic sludge blanket (UASB) process. Paper manufactories also produce waste starch and incinerated ash. The integrated treating for these wastes is desirable. In this study, two UASB reactors were operated to treat pulp wastewater with addition of waste starch and with addition of incinerated ash, receptively. Continuous operations of a UASB reactor treating pulp wastewater with addition of waste starch (PS reactor) and a UASB reactor treating pulp wastewater with addition of incinerated ash (PA reactor) , were investigated at mesophilic conditions. The PS reactor performed well with an average 93.7% total CODCr and 97.3% soluble CODCr removal efficiency in average at a maximum volumetric loading rate (VLR) of 16.0 kgCOD/m3/d. The PA reactor was also successfully operated with an average 95.3% total CODCr and 97.5% soluble CODCr removal efficiency in average at a maximum VLR of 14.6 kgCOD/m3/d. Successfully developed granules were obtained after over 140 days of operation in both reactors, and the granules were 1 to 2 mm in mean diameter. Microbial analysis revealed the genus Methanomethylovorans was predominant in the granules of both reactors.

  7. Minimum radwaste system to support commercial operation-what equipment can be deferred

    International Nuclear Information System (INIS)

    Marshall, R.W.; Tafazzoli, M.M.

    1984-01-01

    Because of cash flow problems being experienced by utilities as nuclear power stations approach completion, areas of the plant for which the completion of the construction effort could be deferred past commercial operation should be reviewed. The radwaste treatment systems are prime candidates for such a deferral because of the availability, either temporary or permanent, of alternative treatment methods for the waste streams expected to be produced. In order to identify the radwaste equipment, components and associated hardware in the radwaste building which could be deferred past commercial operation, a study was performed by Impell Corporation to evaluate the existing radwaste treatment system and determine the minimum system necessary to support commercial operation of a typical BWR. The study identified the minimum-installed radwaste treatment system which, in combination with portable temporary equipment, would accommodate the waste types and quantities likely to be produced in the first few years of operation. In addition, the minimum-installed system had to be licensable and excessive radiation exposures should not be incurred during the construction of the deferred portions of the system after commercial operation. From this study, it was concluded that a significant quantity of radwaste processing equipment and the associated piping, valves and instrumentation could be deferred. The estimated savings, in construction manhours (excluding field distributables) alone, was over 102,000 M-H

  8. Study of chemical additives in the cementation of radioactive waste of PWR reactors

    International Nuclear Information System (INIS)

    Vieira, Vanessa Mota; Tello, Cledola Cassia Oliveira de

    2012-01-01

    In this research it has been studied the effects of chemical admixtures in the cementation process of radioactive wastes. These additives are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market. Then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 23. The measured parameters were: the viscosity, the setting time, the paste and product density and the compressive strength. The parameter evaluated in this study was the compressive strength at age of 28 days, is considered essential security issues relating to the handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented products. (author)

  9. Wastes as Aggregates, Binders or Additions in Mortars: Selecting Their Role Based on Characterization

    Science.gov (United States)

    de Brito, Jorge; Veiga, Rosário

    2018-01-01

    The production of waste has increased over the years and, lacking a recycle or recovery solution, it is forwarded to landfill. The incorporation of wastes in cement-based materials is a solution to reduce waste deposition. In this regard, some researchers have been studying the incorporation of wastes with different functions: aggregate, binder and addition. The incorporation of wastes should take advantage of their characteristics. It requires a judicious analysis of their particles. This research involves the analysis of seven industrial wastes: biomass ashes, glass fibre, reinforced polymer dust, sanitary ware, fluid catalytic cracking, acrylic fibre, textile fibre and glass fibre. The main characteristics and advantages of each waste are enunciated and the best type of introduction in mortars is discussed. The characterization of the wastes as particles is necessary to identify the most suitable incorporation in mortars. In this research, some wastes are studied with a view to their re-use or recycling in mortars. Thus, this research focuses on the chemical, physical and mechanical characterization of industrial wastes and identification of the potentially most advantageous type of incorporation. PMID:29558418

  10. Wastes as Aggregates, Binders or Additions in Mortars: Selecting Their Role Based on Characterization

    Directory of Open Access Journals (Sweden)

    Catarina Brazão Farinha

    2018-03-01

    Full Text Available The production of waste has increased over the years and, lacking a recycle or recovery solution, it is forwarded to landfill. The incorporation of wastes in cement-based materials is a solution to reduce waste deposition. In this regard, some researchers have been studying the incorporation of wastes with different functions: aggregate, binder and addition. The incorporation of wastes should take advantage of their characteristics. It requires a judicious analysis of their particles. This research involves the analysis of seven industrial wastes: biomass ashes, glass fibre, reinforced polymer dust, sanitary ware, fluid catalytic cracking, acrylic fibre, textile fibre and glass fibre. The main characteristics and advantages of each waste are enunciated and the best type of introduction in mortars is discussed. The characterization of the wastes as particles is necessary to identify the most suitable incorporation in mortars. In this research, some wastes are studied with a view to their re-use or recycling in mortars. Thus, this research focuses on the chemical, physical and mechanical characterization of industrial wastes and identification of the potentially most advantageous type of incorporation.

  11. Wastes as Aggregates, Binders or Additions in Mortars: Selecting Their Role Based on Characterization.

    Science.gov (United States)

    Farinha, Catarina Brazão; de Brito, Jorge; Veiga, Rosário; Fernández, J M; Jiménez, J R; Esquinas, A R

    2018-03-20

    The production of waste has increased over the years and, lacking a recycle or recovery solution, it is forwarded to landfill. The incorporation of wastes in cement-based materials is a solution to reduce waste deposition. In this regard, some researchers have been studying the incorporation of wastes with different functions: aggregate, binder and addition. The incorporation of wastes should take advantage of their characteristics. It requires a judicious analysis of their particles. This research involves the analysis of seven industrial wastes: biomass ashes, glass fibre, reinforced polymer dust, sanitary ware, fluid catalytic cracking, acrylic fibre, textile fibre and glass fibre. The main characteristics and advantages of each waste are enunciated and the best type of introduction in mortars is discussed. The characterization of the wastes as particles is necessary to identify the most suitable incorporation in mortars. In this research, some wastes are studied with a view to their re-use or recycling in mortars. Thus, this research focuses on the chemical, physical and mechanical characterization of industrial wastes and identification of the potentially most advantageous type of incorporation.

  12. Method of solidifying radioactive solid wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Kawamura, Fumio; Kikuchi, Makoto.

    1984-01-01

    Purpose: To obtain solidification products of radioactive wastes satisfactorily and safely with no destruction even under a high pressure atmosphere by preventing the stress concentration by considering the relationships of the elastic module between the solidifying material and radioactive solid wastes. Method: Solidification products of radioactive wastes with safety and securing an aimed safety ratio are produced by conditioning the modules of elasticity of the solidifying material equal to or less than that of the radioactive wastes in a case where the elastic module of radioactive solid wastes to be solidified is smaller than that of the solidifying material (the elastic module of wastes having the minimum elastic module among various wastes). The method of decreasing the elastic module of the solidifying material usable herein includes the use of such a resin having a long distance between cross-linking points of a polymer in the case of plastic solidifying materials, and addition of rubber-like binders in the case of cement or like other inorganic solidifying materials. (Yoshihara, H.)

  13. Effect of porcelain polishing addition of waste in properties blocks ceramic

    International Nuclear Information System (INIS)

    Santana, G.L.; Barbosa Neto, M.C.; Campos, L.F.; Macedo, D.A; Dutra, R.P.S.

    2016-01-01

    This work has as objective the study of the technological properties of ceramic blocks with addition of residue porcelain polishing. The test samples are produced with clay base, where the waste is introduced in concentrations of 10% and 20% by mass, to evaluate its influence on the properties of the ceramic block. All these materials were characterized by determining their chemical composition (XRF) and X-ray diffraction Sintering was performed at temperatures of 850 ° C, 950 ° C and 1100 ° C with a heating rate of 2 ° C / me and 60 minutes of landing. After this, there was obtained the technological properties of the samples such as: Loss on fire, the burning linear shrinkage, water absorption, porosity and density, as well as, mechanical strength properties through the flexural strength test. The results show that the addition of waste influenced both the technological properties, the mechanical properties evaluated in this study. (author)

  14. Statistical study of chemical additives effects in the waste cementation

    International Nuclear Information System (INIS)

    Tello, Cledola C.O. de; Diniz, Paula S.; Haucz, Maria J.A.

    1997-01-01

    This paper presents the statistical study, that was carried out to analyse the chemical additives effect in the waste cementation process. Three different additives from two industries were tested: set accelerator, set retarder and super plasticizers, in cemented pates with and without bentonite. The experiments were planned in accordance with the 2 3 factorial design, so that the effect of each type of additive, its quantity and manufacturer in cemented paste and specimens could be evaluated. The results showed that the use of these can improve the cementation process and the product. The admixture quantity and the association with bentonite were the most important factors affecting the process and product characteristics. (author). 4 refs., 9 figs., 4 tabs

  15. Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

    International Nuclear Information System (INIS)

    Hutchinson, D.P.

    1995-07-01

    This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions

  16. Radiological, physical, and chemical characterization of additional alpha contaminated and mixed low-level waste for treatment at the advanced mixed waste treatment project

    Energy Technology Data Exchange (ETDEWEB)

    Hutchinson, D.P.

    1995-07-01

    This document provides physical, chemical, and radiological descriptive information for a portion of mixed waste that is potentially available for private sector treatment. The format and contents are designed to provide treatment vendors with preliminary information on the characteristics and properties for additional candidate portions of the Idaho National Engineering Laboratory (INEL) and offsite mixed wastes not covered in the two previous characterization reports for the INEL-stored low-level alpha-contaminated and transuranic wastes. This report defines the waste, provides background information, briefly reviews the requirements of the Federal Facility Compliance Act (P.L. 102-386), and relates the Site Treatment Plans developed under the Federal Facility Compliance Act to the waste streams described herein. Each waste is summarized in a Waste Profile Sheet with text, charts, and tables of waste descriptive information for a particular waste stream. A discussion of the availability and uncertainty of data for these waste streams precedes the characterization descriptions.

  17. Production of sodalite waste forms by addition of glass

    International Nuclear Information System (INIS)

    Pereira, C.

    1995-01-01

    Spent nuclear fuel can be treated in a molten salt electrorefiner for conversion into metal and mineral waste forms for geologic disposal. Sodalite is one of the mineral waste forms under study. Fission products in the molten salt are ion-exchanged into zeolite A, which is converted to sodalite and consolidated. Sodalite can be formed directly from mixtures of salt and zeolite A at temperatures above 975 K; however, nepheline is usually produced as a secondary phase. Addition of small amounts of glass frit to the mixture reduced nepheline formation significantly. Loss of fission products was not observed for reaction below 1000 K. Hot-pressing of the sodalite powders yielded dense pellets (∼2.3 g/cm 3 ) without any loss of fission product species. Normalized release rates were below 1 g/m 2 ·day for pre-washed samples in 28-day leach tests based on standard MCC-1 tests but increased with the presence of free salt on the sodalite

  18. 36 CFR 6.6 - Solid waste disposal sites within new additions to the National Park System.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Solid waste disposal sites... NATIONAL PARK SERVICE, DEPARTMENT OF THE INTERIOR SOLID WASTE DISPOSAL SITES IN UNITS OF THE NATIONAL PARK SYSTEM § 6.6 Solid waste disposal sites within new additions to the National Park System. (a) An operator...

  19. Solidification of intermediate level liquid waste - ILLW, CEMEX waste form qualification

    International Nuclear Information System (INIS)

    D'Andrea, V.; Guerra, M.; Pancotti, F.; Maio, V.

    2015-01-01

    In the Sogin EUREX Facility about 125 m 3 of intermediate level radioactive waste and about 113 m 3 of low level radioactive waste, produced during the re-processing of MTR and CANDU fuel, are stored. Solidification of these wastes is planned in order to fulfill the specific requirements established by the Safety Authority, taking into account the criteria set up in a Technical Guide on the issue of radioactive waste management. The design of a cementation plant (CEMEX) of all liquid radioactive wastes is currently ongoing. The process requires that the liquid waste is neutralized with NaOH (NaOH 19 M) and metered into 440 liter drum together with the cement, while the mixture is stirred by a lost paddle ('in drum mixing process'). The qualification of the Waste Form consists of all the activities demonstrating that the final cemented product has the minimum requirements (mechanical, chemical and physical characteristics) compliant with all the subsequent management phases: long-term interim storage, transport and long-term disposal of the waste. All tests performed to qualify the conditioning process for immobilizing first extraction cycle (MTR and CANDU) and second extraction cycle liquid wastes, gave results in compliance with the minimum requirements established for disposal

  20. Using waste plastic bottles as additive for stone mastic asphalt

    International Nuclear Information System (INIS)

    Ahmadinia, Esmaeil; Zargar, Majid; Karim, Mohamed Rehan; Abdelaziz, Mahrez; Shafigh, Payam

    2011-01-01

    Highlights: → The PET increased the stiffness level of the mixture improving its resistance level against permanent deformation. → The effects of waste PET on Marshall Stability, air void and bulk specific gravity of the mixture are significant. → The appropriate amount of PET was found to be 6% by weight of bitumen. -- Abstract: Currently, polymer modified asphalt mixture is a relatively costly mixture for paving roads. One way to reduce the cost of such constructions and rendering them more convenient is by using inexpensive polymers, i.e. waste polymers. The main purpose of this research is to determine the effect of incorporating waste plastic bottles (Polyethylene Terephthalate (PET)) on the engineering properties of stone mastic asphalt (SMA) mixture. The volumetric and mechanical properties of asphalt mixes that include various percentages of PET (0%, 2%, 4%, 6%, 8% and 10%) were calculated and assessed with laboratory tests. The appropriate amount of PET was found to be 6% by weight of bitumen. The outcomes were statistically analysed and the determination of the significance at certain confidence limits was performed with the two factor variance analysis (ANOVA). Moreover, some studies conducted on polyethylene modified asphalt mixture have also been taken into consideration in this paper. The results show that the addition of PET has a significant positive effect on the properties of SMA and it can promote the re-use of waste material in industry in an environmentally friendly and economical way.

  1. Matt waste from glass separated collection: an eco-sustainable addition for new building materials.

    Science.gov (United States)

    Bignozzi, M C; Saccani, A; Sandrolini, F

    2009-01-01

    Matt waste (MW), a by-product of purification processes of cullet derived from separated glass waste collection, has been studied as filler for self-compacting concrete and as an addition for newly blended cement. Properties of self-compacting concrete compared to reference samples are reported. They include characteristics at the fresh and hardened states, and the compressive strength and porosity of mortar samples that were formulated with increasing amounts of MW to be used as cement replacement (up to 50wt.%). The effects of matt waste are discussed with respect to the mechanical and microstructural characteristics of the resulting new materials.

  2. Minimum income protection in the Netherlands

    NARCIS (Netherlands)

    van Peijpe, T.

    2009-01-01

    This article offers an overview of the Dutch legal system of minimum income protection through collective bargaining, social security, and statutory minimum wages. In addition to collective agreements, the Dutch statutory minimum wage offers income protection to a small number of workers. Its

  3. Preliminary minimum detectable limit measurements in 208-L drums for selected actinide isotopes in mock-waste matrices

    International Nuclear Information System (INIS)

    Camp, D.C.; Wang, Tzu-Fang; Martz, H.E.

    1992-01-01

    Preliminary minimum detectable levels (MDLS) of selected actinide isotopes have been determined in full-scale, 55-gallon drums filled with a range of mock-waste materials from combustibles (0.14 g/CM 3 ) to sand (1.7 g/CM 3 ). Measurements were recorded from 100 to 10,000 seconds with selected actinide sources located in these drums at an edge position, on the center axis of a drum and midway between these two positions. Measurements were also made with a 166 Ho source to evaluate the attenuation of these mock-matrix materials as a function of energy. By knowing where the source activity is located within a drum, our preliminary results show that a simply collimated 90% HPGE detector can differentiate between TRU (>100 nCi/g) and LLW amounts of 239 Pu in only 100s of measurement time and with sufficient accuracy in both low and medium density, low Z materials. Other actinides measured so far include 235 U, 241 Am, and 244 Cm. These measurements begin to establish the probable MDLs achievable in the nondestructive assays of real waste drums when using active and passive CT. How future measurements may differ from these preliminary measurements is also discussed

  4. Mechanical and radiation shielding properties of mortars with additive fine aggregate mine waste

    International Nuclear Information System (INIS)

    Gallala, Wissem; Hayouni, Yousra; Gaied, Mohamed Essghaier; Fusco, Michael; Alsaied, Jasmin; Bailey, Kathryn; Bourham, Mohamed

    2017-01-01

    Highlights: • Effectiveness of mine waste as additive fine aggregate has been investigated. • Experimental results are verified by computationally from composition of synthesized samples. • Work focuses on shielding materials for nuclear systems including spent fuel storage and drycasks. - Abstract: Incorporation of barite-fluorspar mine waste (BFMW) as a fine aggregate additive has been investigated for its effect on the mechanical and shielding properties of cement mortar. Several mortar mixtures were prepared with different proportions of BFMW ranging from 0% to 30% as fine aggregate replacement. Cement mortar mixtures were evaluated for density, compressive and tensile strengths, and gamma ray radiation shielding. The results revealed that the mortar mixes containing 25% BFMW reaches the highest compressive strength values, which exceeded 50 MPa. Evaluation of gamma-ray attenuation was both measured by experimental tests and computationally calculated using MicroShield software package, and results have shown that using BFMW aggregates increases attenuation coefficient by about 20%. These findings have demonstrated that the mine waste can be suitably used as partial replacement aggregate to improve radiation shielding as well as to reduce the mortar and concrete costs.

  5. Study of chemical additives in the cementation of radioactive waste of PWR reactors

    International Nuclear Information System (INIS)

    Vieira, Vanessa Mota; Tello, Cledola Cassia Oliveira de

    2011-01-01

    Cementation is a very useful process to solidify radioactive wastes. Depending on the waste it can be necessary to use of chemical additives (admixtures) to improve the cementation process and its product. Admixtures are materials, other than cement, aggregate and water, that are added either before or during the mixing to alter some properties, such as workability, curing temperature range, and setting time. However there are a large variety of these materials that are frequently changed or taken out of the market. In this changeable scenario it is essential to know the commercially available materials and their characteristics. In this research the effects of chemical admixtures in the solidification process has been studied. For the tests it was prepared a solution simulating the evaporator concentrate waste, cemented by two different formulations, and three chemical admixtures from two manufacturers. The tested admixtures were accelerators, set retarders and super plasticizers. The experiments were organized by a planning factorial 23 to quantify the effects of formulations, of the admixtures, its quantity and manufacturer in properties of the paste and products. The measured parameters were the density, the viscosity and the setting time of the paste, and the product compressive strength. The parameter evaluated in this study was the compressive strength at age of 28 days, is considered essential security issues relating to the handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented products. (author)

  6. Natural additives and agricultural wastes in biopolymer formulations for food packaging

    Science.gov (United States)

    Valdés, Arantzazu; Mellinas, Ana Cristina; Ramos, Marina; Garrigós, María Carmen; Jiménez, Alfonso

    2014-02-01

    The main directions in food packaging research are targeted towards improvements in food quality and food safety. For this purpose, food packaging providing longer product shelf-life, as well as the monitoring of safety and quality based upon international standards, is desirable. New active packaging strategies represent a key area of development in new multifunctional materials where the use of natural additives and/or agricultural wastes is getting increasing interest. The development of new materials, and particularly innovative biopolymer formulations, can help to address these requirements and also with other packaging functions such as: food protection and preservation, marketing and smart communication to consumers. The use of biocomposites for active food packaging is one of the most studied approaches in the last years on materials in contact with food. Applications of these innovative biocomposites could help to provide new food packaging materials with improved mechanical, barrier, antioxidant and antimicrobial properties. From the food industry standpoint, concerns such as the safety and risk associated with these new additives, migration properties and possible human ingestion and regulations need to be considered. The latest innovations in the use of these innovative formulations to obtain biocomposites are reported in this review. Legislative issues related to the use of natural additives and agricultural wastes in food packaging systems are also discussed.

  7. Natural additives and agricultural wastes in biopolymer formulations for food packaging.

    Science.gov (United States)

    Valdés, Arantzazu; Mellinas, Ana Cristina; Ramos, Marina; Garrigós, María Carmen; Jiménez, Alfonso

    2014-01-01

    The main directions in food packaging research are targeted toward improvements in food quality and food safety. For this purpose, food packaging providing longer product shelf-life, as well as the monitoring of safety and quality based upon international standards, is desirable. New active packaging strategies represent a key area of development in new multifunctional materials where the use of natural additives and/or agricultural wastes is getting increasing interest. The development of new materials, and particularly innovative biopolymer formulations, can help to address these requirements and also with other packaging functions such as: food protection and preservation, marketing and smart communication to consumers. The use of biocomposites for active food packaging is one of the most studied approaches in the last years on materials in contact with food. Applications of these innovative biocomposites could help to provide new food packaging materials with improved mechanical, barrier, antioxidant, and antimicrobial properties. From the food industry standpoint, concerns such as the safety and risk associated with these new additives, migration properties and possible human ingestion and regulations need to be considered. The latest innovations in the use of these innovative formulations to obtain biocomposites are reported in this review. Legislative issues related to the use of natural additives and agricultural wastes in food packaging systems are also discussed.

  8. Natural additives and agricultural wastes in biopolymer formulations for food packaging

    Directory of Open Access Journals (Sweden)

    Arantzazu eValdés

    2014-02-01

    Full Text Available The main directions in food packaging research are targeted towards improvements in food quality and food safety. For this purpose, food packaging providing longer product shelf-life, as well as the monitoring of safety and quality based upon international standards, is desirable. New active packaging strategies represent a key area of development in new multifunctional materials where the use of natural additives and/or agricultural wastes is getting increasing interest. The development of new materials, and particularly innovative biopolymer formulations, can help to address these requirements and also with other packaging functions such as: food protection and preservation, marketing and smart communication to consumers. The use of biocomposites for active food packaging is one of the most studied approaches in the last years on materials in contact with food. Applications of these innovative biocomposites could help to provide new food packaging materials with improved mechanical, barrier, antioxidant and antimicrobial properties. From the food industry standpoint, concerns such as the safety and risk associated with these new additives, migration properties and possible human ingestion and regulations need to be considered. The latest innovations in the use of these innovative formulations to obtain biocomposites are reported in this review. Legislative issues related to the use of natural additives and agricultural wastes in food packaging systems are also discussed.

  9. Addition of liquid waste incineration capability to the INEL's low-level waste incinerator

    International Nuclear Information System (INIS)

    Steverson, E.M.; Clark, D.P.; McFee, J.N.

    1986-01-01

    A liquid waste system has recently been installed in the Waste Experimental Reduction Facility (WERF) incinerator at the Idaho National Engineering Laboratory (INEL). In this paper, aspects of the incineration system such as the components, operations, capabilities, capital cost, EPA permit requirements, and future plans are discussed. The principal objective of the liquid incineration system is to provide the capability to process hazardous, radioactively contaminated, non-halogenated liquid wastes. The system consists primarily of a waste feed system, instrumentation and controls, and a liquid burner, which were procured at a capital cost of $115,000

  10. Influence of the addition of some inorganic waste products on the composting of bark

    Energy Technology Data Exchange (ETDEWEB)

    Michiels, J.; de Vleeschauwer, D.; Verdonck, O.; de Boodt, M.

    1981-11-01

    Natural organic materials can be recycled by composting. It is possible to convert bark, a waste product from papermills or municipal refuse, into valuable materials, such as for growing ornamental plants. This article deals with the effect of the addition of certain inorganic waste products to the composting process. The compost produced was characterized physically and chemically and the value of the compost as a horticultural substrate was evaluated in plant growth experiments. (Refs. 6).

  11. The waste-to-energy framework for integrated multi-waste utilization: Waste cooking oil, waste lubricating oil, and waste plastics

    Energy Technology Data Exchange (ETDEWEB)

    Singhabhandhu, Ampaitepin; Tezuka, Tetsuo [Energy Economics Laboratory, Department of Socio-Environmental Energy Science, Graduate School of Energy Science, Kyoto University, Yoshida-honmachi, Sakyo-ku, Kyoto 606-8501 (Japan)

    2010-06-15

    Energy generation by wastes is considered one method of waste management that has the benefit of energy recovery. From the waste-to-energy point of view, waste cooking oil, waste lubricating oil, and waste plastics have been considered good candidates for feedstocks for energy conversion due to their high heating values. Compared to the independent management of these three wastes, the idea of co-processing them in integration is expected to gain more benefit. The economies of scale and the synergy of co-processing these wastes results in higher quality and higher yield of the end products. In this study, we use cost-benefit analysis to evaluate the integrated management scenario of collecting the three wastes and converting them to energy. We report the total heat of combustion of pyrolytic oil at the maximum and minimum conversion rates, and conduct a sensitivity analysis in which the parameters of an increase of the electricity cost for operating the process and increase of the feedstock transportation cost are tested. We evaluate the effects of economy of scale in the case of integrated waste management. We compare four cases of waste-to-energy conversion with the business as usual (BAU) scenario, and our results show that the integrated co-processing of waste cooking oil, waste lubricating oil, and waste plastics is the most profitable from the viewpoints of energy yield and economics. (author)

  12. Characterization of a Fe-based alloy system for an AFCI metallic waste form - 16134

    International Nuclear Information System (INIS)

    Williamson, Mark J.; Sindelar, Robert L.

    2009-01-01

    The AFCI waste management program aims to provide a minimum volume stable waste form for high level radioactive waste from the various process streams. The AFCI Integrated Waste Management Strategy document has identified a Fe-Zr metallic waste form (MWF) as the baseline alloy for disposal of Tc metal, undissolved solids, and TRUEX fission product wastes. Several candidate alloys have been fabricated using vacuum induction melting to investigate the limits of waste loading as a function of Fe and Zr content. Additional melts have been produced to investigate source material composition. These alloys have been characterized using SEM/EDS and XRD. Phase assemblage and specie partitioning of Re metal (surrogate for Tc) and noble metal FP elements into the phases is reported. (authors)

  13. Position paper, need for additional waste storage capacity and recommended path forward for project W-236a, Multi-function Waste Tank Facility

    International Nuclear Information System (INIS)

    Awadalla, N.G.

    1994-01-01

    Project W-236a, Multi-function waste Tank Facility (MWTF), was initiated to increase the safe waste storage capacity for the Tank Waste Remediation System (TWRS) by building two new one million gallon underground storage tanks in the 200 West Area and four tanks in the 200 East Area. Construction of the tanks was scheduled to begin in September 1994 with operations beginning in calendar year (CY) 1998. However, recent reviews have raised several issues regarding the mission, scope, and schedule of the MWTF. The decision to build new tanks must consider several elements, such as: Operational risk and needs -- Operational risk and flexibility must be managed such that any identified risk is reduced as soon as practicable; The amount of waste that will be generated in the future -- Additional needed tank capacity must be made available to support operations and maintain currently planned safety improvement activities; Safety issues -- The retrieval of waste from single-shell tanks (SSTs) and watch list tanks will add to the total amount of waste that must be stored in a double-shell tank (DST); Availability of existing DSTs -- The integrity of the 28 existing DSTs must be continuously managed; and Affect on other projects and programs -- Because MWTF systems have been integrated with other projects, a decision on one project will affect another. In addition the W-236a schedule is logically tied to support retrieval and safety program plans. Based on the above, two new tanks are needed for safe waste storage in the 200 West Area, and they need to be built as soon as practicable. Design should continue for the tanks in the 200 East Area with a decision made by September, on whether to construct them. Construction of the cross-site transfer line should proceed as scheduled. To implement this recommendation several actions need to be implemented

  14. Calcination of Fluorinel-sodium waste blends using sugar as a feed additive (formerly WINCO-11879)

    International Nuclear Information System (INIS)

    Newby, B.J.; Thomson, T.D.; O'Brien, B.H.

    1992-06-01

    Methods were studied for using sugar as a feed additive for converting the sodium-bearing wastes stored at the Idaho Chemical Processing Plant into granular, free flowing solids by fluidized-bed calcination at 500 degrees C. All methods studied blended sodium-bearing wastes with Fluorinel wastes but differed in the types of sugar (sucrose or dextrose) that were added to the blend. The most promising sugar additive was determined to be sucrose, since it is converted more completely to inorganic carbon than is dextrose. The effect of the feed aluminum-to-alkali metal mole ratio on calcination of these blends with sugar was also investigated. Increasing the aluminum-to-alkali metal ratio from 0.6 to 1.0 decreased the calcine product-to-fines ratio from 3.0 to 1.0 and the attrition index from 80 to 15%. Further increasing the ratio to 1.25 had no effect

  15. Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jongkwon [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of); Um, Wooyong, E-mail: wooyong.um@pnnl.gov [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of); Pacific Northwest National Laboratory, Richland, WA 99354 (United States); Choung, Sungwook [Division of Advanced Nuclear Engineering, Pohang University of Science and Technology (POSTECH), San 31, Hyoja-Dong, Pohang (Korea, Republic of)

    2014-09-15

    The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl–KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl–KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl–KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl–KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

  16. Mixed low-level waste minimization at Los Alamos

    International Nuclear Information System (INIS)

    Starke, T.P.

    1998-01-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL

  17. Mixed low-level waste minimization at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Starke, T.P.

    1998-12-01

    During the first six months of University of California 98 Fiscal Year (July--December) Los Alamos National Laboratory has achieved a 57% reduction in mixed low-level waste generation. This has been accomplished through a systems approach that identified and minimized the largest MLLW streams. These included surface-contaminated lead, lead-lined gloveboxes, printed circuit boards, and activated fluorescent lamps. Specific waste minimization projects have been initiated to address these streams. In addition, several chemical processing equipment upgrades are being implemented. Use of contaminated lead is planned for several high energy proton beam stop applications and stainless steel encapsulated lead is being evaluated for other radiological control area applications. INEEL is assisting Los Alamos with a complete systems analysis of analytical chemistry derived mixed wastes at the CMR building and with a minimum life-cycle cost standard glovebox design. Funding for waste minimization upgrades has come from several sources: generator programs, waste management, the generator set-aside program, and Defense Programs funding to INEEL.

  18. Influence of Waste Glass Powder Addition on the Pore Structure and Service Properties of Cement Mortars

    Directory of Open Access Journals (Sweden)

    José Marcos Ortega

    2018-03-01

    Full Text Available At present, reusing waste constitutes an important challenge in order to reach a more sustainable environment. The cement industry is an important pollutant industrial sector. Therefore, the reduction of its CO2 emissions is now a popular topic of study. One way to lessen those emissions is partially replacing clinker with other materials. In this regard, the reuse of waste glass powder as a clinker replacement could be possible. This is a non-biodegradable residue that permanently occupies a large amount of space in dumping sites. The aim of this work is to study the long-term effects (400 days of the addition of waste glass powder on the microstructure and service properties of mortars that incorporate up to 20% of this addition as clinker replacement. The microstructure has been characterised using the non-destructive impedance spectroscopy technique and mercury intrusion porosimetry. Furthermore, differential thermal analysis was also performed. Compressive strength and both steady-state and non-steady-state chloride diffusion coefficients have also been determined. Considering the obtained results, mortars with 10% and 20% waste glass powder showed good service properties until 400 days, similar to or even better than those made with ordinary Portland cement without additions, with the added value of contributing to sustainability.

  19. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    International Nuclear Information System (INIS)

    Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

    1985-07-01

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m 3 /MTU for no treatment to as low as 0.02 m 3 /MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs

  20. Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

    1985-07-01

    This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

  1. Innovative environmental restoration and waste management technologies at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Helt, J.E.

    1993-01-01

    Cleanup of contaminated sites and management of wastes have become major efforts of the US Department of Energy. Argonne National Laboratory (ANL) is developing several new technologies to meet the needs of this national effort. Some of these efforts are being done in collaboration with private sector firms. An overview of the ANL and private sector efforts will be presented. The following four specific technologies will be discussed in detail: (1) a minimum additive waste stabilization (MAWS) system for treating actinide-contaminated soil and groundwater; (2) a magnetic separation system, also for cleanup of actinide-contaminated soil and groundwater; (3) a mobile evaporator/concentrator system for processing aqueous radioactive and mixed waste; and (4) a continuous emission monitor for ensuring that waste incineration meets environmental goals

  2. INVESTIGATION ON UTILITY OF PLASTIC WASTE AS AN ADDITIVE FOR BITUMINOUS CONCRETE USING WET PROCESS OF MIXING

    Directory of Open Access Journals (Sweden)

    Anurag Virendra Tiwari

    2017-12-01

    Full Text Available Purpose. Plastic waste has become a major environmental issue of concern due to its exponential growth due to rapid urbanization. The paper investigates utility of plastic waste as an additive for bituminous concrete using wet process of mixing. Methodology. The methodology for the present paper has been designed with complex research consisting of Marshall mix design of the bituminous mix added with plastic waste for modifying bitumen using wet process of mixing, performing the tests on the samples and analyzing the results in the form of table and figures. In the present paper LDPE and HDPE type of plastic waste are used to modify the bitumen. Finding. The results show that addition of 6 percent of bitumen improves the Marshall properties of the mix. Use of plastic to modify the bitumen not only makes the road surface more durable but also it is an eco-friendly way of proper disposal of plastic waste. Originality. The processes used for mixing the plastic waste to the bitumen are dry process and wet process. Dry process of mixing the plastic waste to the bituminous mix is most common and lot of study is carried out on its application. In the present paper wet process of mixing has not yet been studied much. Practical Value. The practical application of utilizing the plastic waste to modify bitumen in the bituminous mix improves the stability values resulting in the more durable road surface. Also the method ensures the proper disposal of plastic waste in eco-friendly way.

  3. Performance Test on Compression Ignition Engine by Blending Ethanol and Waste Plastic Pyrolysis Oil with Cetane Additive

    Science.gov (United States)

    Padmanabhan, S.; Ganesan, S.; Jeswin Arputhabalan, J.; Chithrala, Varun; Ganesh Bairavan, P.

    2017-05-01

    The demand for diesel fuel is higher than that of petrol throughout the world hence seeking alternative to mineral diesel is a natural choice. Alternative fuels should be easily available at lower cost, environment friendly and fulfill energy needs without modifying engine’s operational parameters. Waste to energy is the trend in the selection of alternate fuels. In this work, Waste Plastic Pyrolysis oil (WPPO), Ethanol, Diesel blend with Cetane additive has been attempted as an alternative fuel. A Twin cylinder, Direct Injection engine was used to assess the engine performance and emission characteristics of waste plastic pyrolysis oil with cetane additive. Experimental results of blended plastic fuel and diesel fuel were compared.

  4. DETERMINATION OF THE MINIMUM INTACT DIMENSIONS AVAILABLE IN PRACTICAL APPLICATIONS OF LASER CUTTING

    Directory of Open Access Journals (Sweden)

    Peter Gyorgy HORVATH

    2016-06-01

    Full Text Available The reuse of wastes is one of the main requirements of sustainable wood processing. Technologies available for waste management however are currently suited to the reuse of large quantities. This study investigates the utilisation of individual pieces of sawn wood and veneer wastes by laser cutting, with special emphasis on the search for the practical minimum intact dimension that can be produced by laser cutting

  5. Glassy slag: A complementary waste form to homogeneous glass for the implementation of MAWS in treating DOE low level/mixed wastes

    International Nuclear Information System (INIS)

    Feng, X.; Ordaz, G.; Krumrine, P.

    1994-01-01

    Glassy slag waste forms are being developed to complement glass waste forms in implementing the Minimum Additive Waste Stabilization (MAWS) Program for supporting DOE's environmental restoration efforts. These glassy slags are composed of various metal oxide crystalline phases embedded in an alumino-silicate glass phase. The slags are appropriate final waste forms for waste streams that contain large amounts of scrap metals and elements with low solubilities in glass, and that have low-flux contents. Homogeneous glass waste forms are appropriate for wastes with sufficient fluxes and low metal contents. Therefore, utilization of both glass and glassy slag waste forms will make vitrification technology applicable to the treatment of a much larger range of radioactive and mixed wastes. The MAWS approach was a plied to glassy slags by blending multiple waste streams to produce the final waste form, minimizing overall waste form volume and reducing costs. The crystalline oxide phases formed in the glassy slags can be specially formulated so that they are very durable and contain hazardous and radioactive elements in their lattice structures. The Structural Bond Strength (SBS) Model was used to predict the chemical durability of the product from the slag composition so that optimized slag compositions could be obtain with a limited number of crucible melts and testing

  6. Addition of seaweed and bentonite accelerates the two-stage composting of green waste.

    Science.gov (United States)

    Zhang, Lu; Sun, Xiangyang

    2017-11-01

    Green waste (GW) is an important recyclable resource, and composting is an effective technology for the recycling of organic solid waste, including GW. This study investigated the changes in physical and chemical characteristics during the two-stage composting of GW with or without addition of seaweed (SW, Ulva ohnoi) (at 0, 35, and 55%) and bentonite (BT) (at 0.0, 2.5%, and 4.5%). During the bio-oxidative phase, the combined addition of SW and BT improved the physicochemical conditions, increased the respiration rate and enzyme activities, and decreased ammonia and nitrous oxide emissions. The combination of SW and BT also enhanced the quality of the final compost in terms of water-holding capacity, porosity, particle-size distribution, water soluble organic carbon/organic nitrogen ratio, humification, nutrient content, and phytotoxicity. The best quality compost, which matured in only 21days, was obtained with 35% SW and 4.5% BT. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Testing of variables which affect stablity of cement solidified low-level waste

    International Nuclear Information System (INIS)

    Boris, G.F.

    1989-01-01

    This paper describes the test program undertaken to investigate variables which could affect the stability of cement solidified low-level waste and to evaluate the effect of these variables on certain tests prescribed in the Technical Position on Waste Form. The majority of the testing was performed on solidified undepleted bead resin, however, six additional waste types, suggested by the NRC, were tested. The tested variables included waste loading, immersion duration, depletion level, ambient cure duration, curing environment, immersion medium and waste type. Of these, lower waste loadings, longer ambient cures prior to testing and immersion in demineralized water versus simulated sea water and potable water resulted in higher compressive strengths for bead resin samples. Immersion times longer than 90 days did not affect the resin samples. Compressive strengths for other waste types varied depending upon the waste. The strengths of all waste types exceeded the minimum criterion by at least a factor of four, up to a factor of forty. The higher waste loadings exhibit strengths less than the lower waste loadings

  8. Changes in physical conditions of a coarse textured soil by addition of organic wastes

    Directory of Open Access Journals (Sweden)

    Melis Cercioglu

    2014-01-01

    Full Text Available Effects of composted tobacco waste, chicken manure and bio-humus applied during a period of three years on a coarse textured soil (Typic Xerofluvent at Agriculture Faculty’s Research and Practise Farmyard of Ege University located on Menemen plain (Izmir, Turkey on soil physical properties were studied. The experiment was arranged in a randomized block design on 16 plots with four replications. Each plot size was 5x3 m2. Composted tobacco waste (CTW from cigarette industry and chicken manure (CM and bio-humus (BH from plant residuals were applied at rates of 50 t ha-1, 4 t ha-1, 10 t ha-1,respectively. Inorganic fertilizers (N-P-K are also added with chicken manure and bio-humus plots. Tobacco wastes obtained from cigarette industry were used after composting. The addition of organic wastes resulted in a significant (p≤0.05 decrease in bulk density (BD; increase in porosity (PO, field capacity (FC, wilting point (WP, available water content (AWC and structure stability index (SSI of soil samples when compared to the control.

  9. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    1985-01-01

    This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

  10. MEA and DEE as additives on diesel engine using waste plastic oil diesel blends

    Directory of Open Access Journals (Sweden)

    Pappula Bridjesh

    2018-05-01

    Full Text Available Waste plastic oil (WPO is a standout amongst the most promising alternative fuels for diesel in view of most of its properties similar to diesel. The challenges of waste management and increasing fuel crisis can be addressed while with the production of fuel from plastic wastes. This experimental investigation is an endeavour to supplant diesel at least by 50% with waste plastic oil alongside 2-methoxy ethyl acetate (MEA and diethyl ether (DEE as additives. Test fuels considered in this study are WPO, 50D50W (50%Diesel + 50%WPO, 50D40W10MEA (50%Diesel + 40%WPO + 10%MEA and 50D40W10DEE (50%Diesel + 40%WPO + 10%DEE. The test results are compared with diesel. An increase in brake thermal efficiency and abatement in brake specific fuel consumption are seen with 50D40W10MEA, as well as reduction in hydro carbon, carbon monoxide and smoke emissions. 50D40W10DEE showed reduced NOx emission whereas 50D40W10MEA has almost no impact. Engine performance and emission characteristics under different loads for different test fuels are discussed. Keywords: 2-Methoxy ethyl acetate, Diethyl ether, Waste plastic oil, Pyrolysis

  11. Influence of organic waste and residue mud additions on chemical, physical and microbial properties of bauxite residue sand.

    Science.gov (United States)

    Jones, Benjamin E H; Haynes, Richard J; Phillips, Ian R

    2011-02-01

    In an alumina refinery, bauxite ore is treated with sodium hydroxide at high temperatures and pressures and for every tone of alumina produced, about 2 tones of alkaline, saline bauxite processing waste is also produced. At Alcoa, a dry stacking system of disposal is used, and it is the sand fraction of the processing waste that is rehabilitated. There is little information available regarding the most appropriate amendments to add to the processing sand to aid in revegetation. The purpose of this study was to investigate how the addition of organic wastes (biosolids and poultry manure), in the presence or absence of added residue mud, would affect the properties of the residue sand and its suitability for revegetation. Samples of freshly deposited residue sand were collected from Alcoa's Kwinana refinery. Samples were treated with phosphogypsum (2% v/v), incubated, and leached. A laboratory experiment was then set up in which the two organic wastes were applied at 0 or the equivalent to 60 tones ha(-1) in combination with residue mud added at rates of 0%, 10% and 20% v/v. Samples were incubated for 8 weeks, after which, key chemical, physical and microbial properties of the residue sand were measured along with seed germination. Additions of residue mud increased exchangeable Na(+), ESP and the pH, and HCO (3) (-) and Na(+) concentrations in saturation paste extracts. Additions of biosolids and poultry manure increased concentrations of extractable P, NH (4) (+) , K, Mg, Cu, Zn, Mn and Fe. Addition of residue mud, in combination with organic wastes, caused a marked decrease in macroporosity and a concomitant increase in mesoporosity, available water holding capacity and the quantity of water held at field capacity. With increasing residue mud additions, the percentage of sample present as sand particles (2 mm diameter) increased; greatest aggregation occurred where a combination of residue mud and poultry manure were added. Stability of aggregates, as measured by

  12. Effects of Different Addition Amounts of Superphosphate on Vegetable Waste Compost

    Directory of Open Access Journals (Sweden)

    YANG Yan

    2017-01-01

    Full Text Available The effects of different addition amounts of superphosphate on vegetable waste compost were studied. Results showed that, addition of superphosphate improved the temperature during the compost. It had the highest temperature of 64.33℃, when the addition quantity of superphosphate was 10.26% of dry matter weight. At the end of the composting, adding superphosphate had no significant effect on C/N, however, it decreased pH and improved the EC of the compost. The EC values were significantly higher than CK, when the addition amount was be tween 4.10%and 10.26%of dry matter weight. When the addition below 10.26%, the GI values were significantly higher than CK(P<0.01, and the highest value was 105.61%, when the addition was 2.05%(S5. Adding superphosphate significantly reduced the nitrogen loss rate of composting(P<0.05, and the lowest was 23.94%,when the addition was 2.05%, meanwhile, the input-output ratio was 3.93, which was the highest value. Under this experimental condition, adding superphosphate promoted the compost maturity significantly, reduced the nitrogen loss rate, and the optimal addition of superphosphate was 2.05%of dry matter weight.

  13. Effects of bean dregs and crab shell powder additives on the composting of green waste.

    Science.gov (United States)

    Zhang, Lu; Sun, Xiangyang

    2018-07-01

    Composting is an effective and economic technology for the recycling of organic waste. In this study, bean dregs (BD) (at 0, 35, and 45%) and crab shell powder (CSP) (at 0, 15, and 25%) were evaluated as additives during the two-stage composting of green waste (GW). The GW used in this experiment mainly consisted of branch cuttings collected during the maintenance of the urban green landscape. Combined additions of BD and CSP improved composting conditions and compost quality in terms of composting temperature, specific surface area, average pore diameter, pH and EC values, carbon dioxide release, ammonia and nitrous oxide emissions, E 4 /E 6 ratio, elemental composition and atomic ratios, organic matter degradation, microbial numbers, enzyme activities, compost phytotoxicity, and environmental and economic benefits. The combined addition of 35% BD and 25% CSP to the two-stage composting of GW resulted in the highest quality compost product in only 22 days. Copyright © 2018 Elsevier Ltd. All rights reserved.

  14. Low-level waste minimization at the Y-12 Plant

    Energy Technology Data Exchange (ETDEWEB)

    Koger, J. [Oak Ridge National Lab., TN (United States)

    1993-03-01

    The Y-12 Development Waste Minimization Program is used as a basis for defining new technologies and processes that produce minimum low-level wastes (hazardous, mixed, radioactive, and industrial) for the Y-12 Plant in the future and for Complex-21 and that aid in decontamination and decommissioning (D and D) efforts throughout the complex. In the past, the strategy at the Y-12 Plant was to treat the residues from the production processes using chemical treatment, incineration, compaction, and other technologies, which often generated copious quantities of additional wastes and, with the exception of highly valuable materials such as enriched uranium, incorporated very little recycle in the process. Recycle, in this context, is defined as material that is put back into the process before it enters a waste stream. Additionally, there are several new technology drivers that have recently emerged with the changing climate in the Nuclear Weapons Complex such as Complex 21 and D and D technologies and an increasing number of disassemblies. The hierarchies of concern in the waste minimization effort are source reduction, recycle capability, treatment simplicity, and final disposal difficulty with regard to Complex 21, disassembly efforts, D and D, and, to a lesser extent, weapons production. Source reduction can be achieved through substitution of hazardous substances for nonhazardous materials, and process changes that result in less generated waste.

  15. Effects of trace element addition on process stability during anaerobic co-digestion of OFMSW and slaughterhouse waste.

    Science.gov (United States)

    Moestedt, J; Nordell, E; Shakeri Yekta, S; Lundgren, J; Martí, M; Sundberg, C; Ejlertsson, J; Svensson, B H; Björn, A

    2016-01-01

    This study used semi-continuous laboratory scale biogas reactors to simulate the effects of trace-element addition in different combinations, while degrading the organic fraction of municipal solid waste and slaughterhouse waste. The results show that the combined addition of Fe, Co and Ni was superior to the addition of only Fe, Fe and Co or Fe and Ni. However, the addition of only Fe resulted in a more stable process than the combined addition of Fe and Co, perhaps indicating a too efficient acidogenesis and/or homoacetogenesis in relation to a Ni-deprived methanogenic population. The results were observed in terms of higher biogas production (+9%), biogas production rates (+35%) and reduced VFA concentration for combined addition compared to only Fe and Ni. The higher stability was supported by observations of differences in viscosity, intraday VFA- and biogas kinetics as well as by the 16S rRNA gene and 16S rRNA of the methanogens. Copyright © 2015 Elsevier Ltd. All rights reserved.

  16. An empirical modeling tool and glass property database in development of US-DOE radioactive waste glasses

    International Nuclear Information System (INIS)

    Muller, I.; Gan, H.

    1997-01-01

    An integrated glass database has been developed at the Vitreous State Laboratory of Catholic University of America. The major objective of this tool was to support glass formulation using the MAWS approach (Minimum Additives Waste Stabilization). An empirical modeling capability, based on the properties of over 1000 glasses in the database, was also developed to help formulate glasses from waste streams under multiple user-imposed constraints. The use of this modeling capability, the performance of resulting models in predicting properties of waste glasses, and the correlation of simple structural theories to glass properties are the subjects of this paper. (authors)

  17. Flammable gas production in Land 2 and Land 3/4 radioactive waste repositories

    International Nuclear Information System (INIS)

    1988-02-01

    Geological, radiolytic and microbiological sources of gas are considered in relation to Land 2 and Land 3/4 type radioactive waste repositories. Geological sources are potentially the most troublesome and it is concluded that site investigation work should be designed to detect gas trap structures, reservoir lithologies or source rocks. Known source and reservoir lithologies should not be considered as suitable for the siting of waste repositories. Radiolytic and microbiological sources will depend on waste characteristics. A detailed review of the literature on radiolytic gas generation is presented and conclusions from this work indicate that water in waste and matrix should be kept to a minimum. Similarly, the level of radioactivity stored in each waste container should be kept to the minimum compatible with the storage design. Microbiological gas sources will be reduced by maintaining the cellulose content of the waste at a minimum. It is suggested that the removal of organics from the waste stream would be beneficial in terms of potential gas production. (author)

  18. Bearing and Swelling Properties of Randomly Distributed Waste Jute Reinforced Soil

    Directory of Open Access Journals (Sweden)

    Murat Ozturk

    2017-10-01

    Full Text Available In this study, waste jute, which was provided from textile companies, was investigated to define effect of waste jute on swelling and bearing behavior of the sand used. Three different water content (17, 19 and 21% and four different waste jute addition amount at different percentages (0, 1, 2, and 3 by mass of dry soil were selected as design variables. With defined variables Swelling Ratio and California Bearing Ratio (CBR tests were conducted. According to test results it is concluded that minimum swelling ratio was observed in the test containing 3% jute with 19% water content and the highest value of CBR was observed in the sample containing 2% jute with 16% water content. In addition to that, CBR values of unreinforced samples were decreased when water content increased from 16% to 21%. However, CBR values of reinforced samples increased with increasing water content from 19% to 21%.

  19. Ultrafiltration membranes from waste polyethylene terephthalate and additives: synthesis and characterization

    Directory of Open Access Journals (Sweden)

    Smitha Rajesh

    2014-01-01

    Full Text Available The synthesis and characterization of asymmetric ultrafiltration membranes from recycled polyethylene terephthalate (PET and polyvinylpyrrolidone (PVP is reported. PET is currently used in many applications, including the manufacture of bottles and tableware. Monomer extraction from waste PET is expensive, and this process has not yet been successfully demonstrated on a viable scale. Hence, any method to recycle or regenerate PET once it has been used is of significant importance from scientific and environmental research viewpoints. Such a process would be a green alternative due to reduced raw monomer consumption and the additional benefit of reduced manufacturing costs. The membranes described here were prepared by a phase-inversion process, which involved casting a solution containing PET, m-cresol as solvent, and polyethylene glycol (PEG of different molecular weights as additives. The membranes were characterized in terms of pure water permeability (PWP, molecular weight cut-off (MWCO, and flux and membrane morphology. The results show that the addition of PEG with high molecular weights leads to membranes with higher PWP. The presence of additives affects surface roughness and membrane morphology.

  20. Radioactive waste management glossary

    International Nuclear Information System (INIS)

    1982-04-01

    Terminology used in documents published by the IAEA is frequently defined in glossaries in the separate documents so that understanding is enhanced, particularly for terms having unique meanings in the field of radioactive waste management. This has been found to be a good practice but frequently a burdensome one, too. In addition, terms in various documents occasionally were used differently. Thus, a common glossary of terms for radioactive waste management documents is believed to have merit. This glossary has been developed for use in IAEA documentation on radioactive waste management topics. The individual items have been compiled by selecting terms and definitions from thirty sources, listed on the next page, and numerous people. An effort has been made to use the definitions in internationally-accepted glossaries (e.g. ICRP, ICRU, ISO), with minimum modification; similarly, definitions in recently published IAEA documents have been respected. Nevertheless, when modifications were believed appropriate, they have been made. The glossary, stored on magnetic tape, is intended to be used as a standard for terminology for IAEA use; it is hoped that some benefits of common international terminology may result from its use in IAEA documentation

  1. High-level waste tank farm set point document

    International Nuclear Information System (INIS)

    Anthony, J.A. III.

    1995-01-01

    Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope

  2. High-level waste tank farm set point document

    Energy Technology Data Exchange (ETDEWEB)

    Anthony, J.A. III

    1995-01-15

    Setpoints for nuclear safety-related instrumentation are required for actions determined by the design authorization basis. Minimum requirements need to be established for assuring that setpoints are established and held within specified limits. This document establishes the controlling methodology for changing setpoints of all classifications. The instrumentation under consideration involve the transfer, storage, and volume reduction of radioactive liquid waste in the F- and H-Area High-Level Radioactive Waste Tank Farms. The setpoint document will encompass the PROCESS AREA listed in the Safety Analysis Report (SAR) (DPSTSA-200-10 Sup 18) which includes the diversion box HDB-8 facility. In addition to the PROCESS AREAS listed in the SAR, Building 299-H and the Effluent Transfer Facility (ETF) are also included in the scope.

  3. Sanitation in wilderness: Balancing minimum tool policies and wilderness values

    Science.gov (United States)

    Paul R. Lachapelle

    2000-01-01

    Officials with the four wilderness managing agencies are faced with balancing wilderness preservation values and the minimum tool policies of their respective agencies. One example is the management of sanitation, particularly human waste and the often intrusive infrastructure that accompanies its treatment and disposal. Because the treatment and disposal of human...

  4. Characterization of Secondary Solid Wastes in Trench Water in Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Taylor, P.A.; Kent, T.E.

    1994-02-01

    This project was undertaken to demonstrate that new liquid waste streams, generated as a consequence of closure activities at Waste Area Grouping (WAG) 6 and other sites, can be treated at the existing wastewater treatment facilities at Oak Ridge National Laboratory (ORNL) to meet discharge requirements without producing hazardous secondary solid wastes. Previous bench and pilot-scale treatability studies have shown that ORNL treatment operations will adequately remove the contaminants and that the secondary solid wastes produced were not hazardous when treating water from two trenches in WAG 6. This study used WAG 6 trench water spiked with the minimum concentration of Toxicity Characteristics Leaching Procedure (TCLP) constituents (chemicals that can make a waste hazardous) found in any groundwater samples at ORNL. The Wastewater Treatment Test Facility (WTTF), a 0.5 L/min pilot plant that simulates the treatment capabilities of the Process Waste Treatment Plant (PWPT) and Nonradiological Wastewater Treatment Plant (NRWTP), was used for this test. This test system, which is able to produce secondary wastes in the quantities necessary for TCLP testing, was operated for a 59-d test period with a minimum of problems and downtime. The pilot plant operating data verified that WAG 6 trench waters, spiked with the minimum concentration of TCLP contaminants measured to date, can be treated at the PWTP and NRWTP to meet current discharge limits. The results of the TCLP analysis indicated that none of the secondary solid wastes produced during the treatment of these wastewaters will be considered hazardous as defined by the Resource Conservation and Recovery Act

  5. PFP dangerous waste training plan

    International Nuclear Information System (INIS)

    Khojandi, J.

    1996-01-01

    This document establishes the minimum training requirements for the Plutonium Finishing Plant (PFP) personnel who are responsible for management of dangerous waste. The training plan outlines training requirements for handling of solid dangerous waste during generator accumulation and liquid dangerous waste during treatment and storage operations. The implementation of this training plan will ensure the PFP facility compliance with the training plan requirements of Dangerous Waste Regulation. Chapter 173-303-330. Washington Administrative Code (WAC). The requirements for such compliance is described in Section 11.0 of WHC-CM-7-5 Environmental Compliance Manual

  6. Removal of strontium and transuranics from Hanford tank waste via addition of metal cations and chemical oxidant: FY 1995 test results

    International Nuclear Information System (INIS)

    Orth, R.J.; Zacher, A.H.; Schmidt, A.J.; Elmore, M.R.; Elliott, K.R.; Neuenschwander, G.G.; Gano, S.R.

    1995-09-01

    Chelating organics and some of their degradation products in the Hanford tank waste, such as EDTA, HEDTA, and NTA act to solubilize strontium and transuranics (TRU) in the tank waste supernatant. Displacement of strontium and TRU will facilitate the removal of these radionuclides via precipitation/filtration, ion exchange, or solvent extraction so that low-level waste feed specifications can be met. Pacific Northwest Laboratory has investigated two methods for releasing organic-complexed strontium and TRU components to allow for effective pretreatment of tank waste supernatant: metal cation addition (to promote displacement and flocculation) and chemical oxidant (pennanganate) addition (to promote chelator destruction/defunctionalization and possibly flocculation). These methods, which can be conducted at near-ambient. temperatures and pressures, could be deployed as intank processes

  7. The association of minimum wage change on child nutritional status in LMICs: A quasi-experimental multi-country study.

    Science.gov (United States)

    Ponce, Ninez; Shimkhada, Riti; Raub, Amy; Daoud, Adel; Nandi, Arijit; Richter, Linda; Heymann, Jody

    2017-08-02

    There is recognition that social protection policies such as raising the minimum wage can favourably impact health, but little evidence links minimum wage increases to child health outcomes. We used multi-year data (2003-2012) on national minimum wages linked to individual-level data from the Demographic and Health Surveys (DHS) from 23 low- and middle-income countries (LMICs) that had least two DHS surveys to establish pre- and post-observation periods. Over a pre- and post-interval ranging from 4 to 8 years, we examined minimum wage growth and four nutritional status outcomes among children under 5 years: stunting, wasting, underweight, and anthropometric failure. Using a differences-in-differences framework with country and time-fixed effects, a 10% increase in minimum wage growth over time was associated with a 0.5 percentage point decline in stunting (-0.054, 95% CI (-0.084,-0.025)), and a 0.3 percentage point decline in failure (-0.031, 95% CI (-0.057,-0.005)). We did not observe statistically significant associations between minimum wage growth and underweight or wasting. We found similar results for the poorest households working in non-agricultural and non-professional jobs, where minimum wage growth may have the most leverage. Modest increases in minimum wage over a 4- to 8-year period might be effective in reducing child undernutrition in LMICs.

  8. Natural wrapping paper from banana (Musa paradisiaca Linn) peel waste with additive essential oils

    Science.gov (United States)

    Widiastuti Agustina, E. S.; Elfi Susanti, V. H.

    2018-05-01

    The research aimed to produce natural wrapping paper from banana (Musa Paradisiaca Linn.) peel waste with additive essentials oils. The method used in this research was alkalization. The delignification process is done with the use of NaOH 4% at the temperature of 100°C for 1.5 hours. Additive materials in the form of essential oils are added as a preservative and aroma agent, namely cinnamon oil, lemon oil, clove oil and lime oil respectively 2% and 3%. Chemical and physical properties of the produced papers are tested included water content (dry-oven method SNI ISO 287:2010), pH (SNI ISO 6588-1.2010), grammage (SNI ISO 536:2010) and brightness (SNI ISO 2470:2010). Testing results of each paper were compared with commercial wrapping paper. The result shows that the natural paper from banana peel waste with additive essential oil meets the standard of ISO 6519:2016 about Basic Paper for Laminated Plastic Wrapping Paper within the parameter of pH and water content. The paper produced also meet the standard of ISO 8218:2015 about Food Paper and Cardboard within the grammage parameter (high-grade grammage), except the paper with 2% lemon oil. The paper which is closest to the characteristic of commercial wrapping paper is the paper with the additive of 2% cinnamon oil, with pH of 6.95, the water content of 7.14%, grammage of 347.6 gram/m2 and the brightness level of 24.68%.

  9. Waste Generation Overview, Course 23263

    International Nuclear Information System (INIS)

    Simpson, Lewis Edward

    2016-01-01

    This course, Waste Generation Overview Live (COURSE 23263), provides an overview of federal and state waste management regulations, as well as Los Alamos National Laboratory (LANL) policies and procedures for waste management operations. The course covers the activities involved in the cradle-to-grave waste management process and focuses on waste characterization, waste compatibility determinations and classification, and the storage requirements for temporary waste accumulation areas at LANL. When you have completed this course, you will be able to recognize federal, state, and LANL environmental requirements and their impact on waste operations; recognize the importance of the cradle-to-grave waste management process; identify the roles and responsibilities of key LANL waste management personnel (e.g., Waste Generator, Waste Management Coordinator, Waste Stream Profile approver, and Waste Certification Official); characterize a waste stream to determine whether it meets the definition of a hazardous waste, as well as characterize the use and minimum requirements for use of acceptable knowledge (AK) for waste characterization and waste compatibility documentation requirements; and identify the requirements for setting up and managing temporary waste accumulation areas.

  10. Waste Generation Overview, Course 23263

    Energy Technology Data Exchange (ETDEWEB)

    Simpson, Lewis Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-11-28

    This course, Waste Generation Overview Live (COURSE 23263), provides an overview of federal and state waste management regulations, as well as Los Alamos National Laboratory (LANL) policies and procedures for waste management operations. The course covers the activities involved in the cradle-to-grave waste management process and focuses on waste characterization, waste compatibility determinations and classification, and the storage requirements for temporary waste accumulation areas at LANL. When you have completed this course, you will be able to recognize federal, state, and LANL environmental requirements and their impact on waste operations; recognize the importance of the cradle-to-grave waste management process; identify the roles and responsibilities of key LANL waste management personnel (e.g., Waste Generator, Waste Management Coordinator, Waste Stream Profile approver, and Waste Certification Official); characterize a waste stream to determine whether it meets the definition of a hazardous waste, as well as characterize the use and minimum requirements for use of acceptable knowledge (AK) for waste characterization and waste compatibility documentation requirements; and identify the requirements for setting up and managing temporary waste accumulation areas.

  11. 40 CFR 412.37 - Additional measures.

    Science.gov (United States)

    2010-07-01

    ... to the wastewater and manure storage and containment structure; (ii) Daily inspection of water lines... structures associated with such sources must include a depth marker which clearly indicates the minimum...) Results from manure, litter, process waste water, and soil sampling; (6) Explanation of the basis for...

  12. An Empirical Analysis of the Relationship between Minimum Wage ...

    African Journals Online (AJOL)

    An Empirical Analysis of the Relationship between Minimum Wage, Investment and Economic Growth in Ghana. ... In addition, the ratio of public investment to tax revenue must increase as minimum wage increases since such complementary changes are more likely to lead to economic growth. Keywords: minimum wage ...

  13. A novel approach in organic waste utilization through biochar addition in wood/polypropylene composites

    Energy Technology Data Exchange (ETDEWEB)

    Das, Oisik [Department of Civil and Environmental Engineering, University of Auckland, Auckland 1142 (New Zealand); Sarmah, Ajit K., E-mail: a.sarmah@auckland.ac.nz [Department of Civil and Environmental Engineering, University of Auckland, Auckland 1142 (New Zealand); Bhattacharyya, Debes [Department of Mechanical Engineering, Center for Advanced Composite Materials, University of Auckland, Auckland 1142 (New Zealand)

    2015-04-15

    Highlights: • Biochar made from waste wood was added with wood polypropylene composites. • 24% biochar gave the best mechanical properties. • 6% biochar had no effect on physico-mechanical properties of composites. • Coupling agent remained unreacted in composites having higher amount of biochar. - Abstract: In an attempt to concurrently address the issues related to landfill gas emission and utilization of organic wastes, a relatively novel idea is introduced to develop biocomposites where biochar made from pyrolysis of waste wood (Pinus radiata) is added with the same wood, plastic/polymer (polypropylene) and maleated anhydride polypropylene (MAPP). Experiments were conducted by manufacturing wood and polypropylene composites (WPCs) mixed with 6 wt%, 12 wt%, 18 wt%, 24 wt%, and 30 wt% biochar. Though 6 wt% addition had similar properties to that of the control (composite without biochar), increasing biochar content to 24 wt% improved the composite’s tensile/flexural strengths and moduli. The biochar, having high surface area due to fine particles and being highly carbonised, acted as reinforcing filler in the biocomposite. Composites having 12 wt% and 18 wt% of biochar were found to be the most ductile and thermally stable, respectively. This study demonstrates that, WPCs added with biochar has good potential to mitigate wastes while simultaneously producing biocomposites having properties that might be suited for various end applications.

  14. A novel approach in organic waste utilization through biochar addition in wood/polypropylene composites

    International Nuclear Information System (INIS)

    Das, Oisik; Sarmah, Ajit K.; Bhattacharyya, Debes

    2015-01-01

    Highlights: • Biochar made from waste wood was added with wood polypropylene composites. • 24% biochar gave the best mechanical properties. • 6% biochar had no effect on physico-mechanical properties of composites. • Coupling agent remained unreacted in composites having higher amount of biochar. - Abstract: In an attempt to concurrently address the issues related to landfill gas emission and utilization of organic wastes, a relatively novel idea is introduced to develop biocomposites where biochar made from pyrolysis of waste wood (Pinus radiata) is added with the same wood, plastic/polymer (polypropylene) and maleated anhydride polypropylene (MAPP). Experiments were conducted by manufacturing wood and polypropylene composites (WPCs) mixed with 6 wt%, 12 wt%, 18 wt%, 24 wt%, and 30 wt% biochar. Though 6 wt% addition had similar properties to that of the control (composite without biochar), increasing biochar content to 24 wt% improved the composite’s tensile/flexural strengths and moduli. The biochar, having high surface area due to fine particles and being highly carbonised, acted as reinforcing filler in the biocomposite. Composites having 12 wt% and 18 wt% of biochar were found to be the most ductile and thermally stable, respectively. This study demonstrates that, WPCs added with biochar has good potential to mitigate wastes while simultaneously producing biocomposites having properties that might be suited for various end applications

  15. The effect of alternative constraints in radioactive waste disposal on minimum cost scenarios

    International Nuclear Information System (INIS)

    Laundy, R.S.; James, A.R.; Groom, M.S.

    1985-01-01

    The purpose of this report is to describe the results of a set of assessments of the optimum waste assignment and disposal schedule for intermediate and low level radioactive wastes using the DISPOSALS Linear Programming Model developed by CAP Scientific. The main purpose of the present study is to demonstrate the applicability of the DISPOSALS model to the field of radioactive waste management. The results presented provide a good indication of the practicability and usefulness of the model and also provide a number of detailed conclusions regarding specific cases. (author)

  16. Treatment of radioactive organics liquid wastes

    International Nuclear Information System (INIS)

    Morales Galarce, Tania

    1999-01-01

    Because of the danger that radioactive wastes can pose to society and to the environment a viable treatment alternative must be developed to prepare these wastes for final disposal. The waste studied in this work is a liquid organic waste contaminated with the radioisotope tritium. This must be treated and then changed into solid form in a 200 liter container. This study defined an optimum formulation that immobilizes the liquid waste. The organic waste is first submitted to an absorption treatment, with Celite absorbent, which had the best physical characteristics from the point of view of radioactive waste management. Then this was solidified by forming a cement mortar, using a highly resistant local cement, Polpaico 400. Various mixes were tested, with different water/cement, waste/absorbent and absorbed waste/cement ratios, until a mixture that met the quality control requirements was achieved. The optimum mixture obtained has a water/cement ratio of 0.35 (p/p) that is the amount of water needed to make the mixture workable, and minimum water for hydrating the cement; a waste/absorbent ration of 0.5 (v/v), where the organic liquid is totally absorbed, and is incorporated in the solid's crystalline network; and an absorbed waste/cement ratio of 0.8 (p/p), which represents the minimum amount of cement needed to obtain a solid product with the required mechanical resistance. The mixture's components join together with no problem, to produce a good workable mixture. It takes about 10 hours for the mixture to harden. After 14 days, the resulting solid product has a resistance to compression of 52 Kgf/cm2. The formulation contains 22.9% immobilized organic waste, 46.5% cement, 14.3% Celite and 16.3% water. Organic liquid waste can be treated and a solid product obtained, that meets the qualitative and quantitative parameters required for its disposal. (CW)

  17. 12 CFR 932.8 - Minimum liquidity requirements.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 7 2010-01-01 2010-01-01 false Minimum liquidity requirements. 932.8 Section... CAPITAL STANDARDS FEDERAL HOME LOAN BANK CAPITAL REQUIREMENTS § 932.8 Minimum liquidity requirements. In addition to meeting the deposit liquidity requirements contained in § 965.3 of this chapter, each Bank...

  18. Integrated waste-to-energy conversion and waste transportation within island communities

    International Nuclear Information System (INIS)

    Zsigraiova, Zdena; Tavares, Gilberto; Semiao, Viriato; Carvalho, Maria de Graca

    2009-01-01

    Usually in islands both primary energy sources and drinking water are missing. Additionally, municipal solid waste (MSW) must be managed avoiding exclusive use of landfills, which limits sustainable development. Power generation from MSW incineration contributes significantly to replacing energy produced from fossil fuels and to reduce overall emissions. A solution based on thermodynamics, environmental and economic analyses and 3D-GIS modelling for the afore-mentioned problems for Cape Verde is proposed. This model integrates waste transportation optimisation and incineration with energy recovery combining production of heat and power (CHP), the heat being used for drinking water production. The results show that extraction condensing steam turbines are more suitable when power production is a priority (5.0 MW with 4000 m 3 /d of drinking water), whereas back-pressure turbines yield 5540-6650 m 3 /d of drinking water with an additional power production of 3.3-4.7 MW. The environmental and economic assessment performed shows the feasibility of the proposed CHP solution, which brings a considerable reduction in net air emissions (1.6 kt), including a significant decrease in the greenhouse gas emissions (131 ktCO 2 ), and that the revenue from energy sales ( Euro 15 million) has potential to balance the incineration cost. Moreover, when terrain relief is accounted for in the route optimisation for minimum fuel consumption, savings up to 11% are obtained.

  19. Solvent extraction as additional purification method for postconsumer plastic packaging waste

    NARCIS (Netherlands)

    Thoden van Velzen, E.U.; Jansen, M.

    2011-01-01

    An existing solvent extraction process currently used to convert lightly polluted post-industrial packaging waste into high quality re-granulates was tested under laboratory conditions with highly polluted post-consumer packaging waste originating from municipal solid refuse waste. The objective was

  20. Lining materials for waste disposal containment and waste storage facilities. (Latest citations from the NTIS bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-11-01

    The bibliography contains citations concerning the design characteristics, performance, and materials used to make liners for the waste disposal and storage industry. Liners made of concrete, polymeric materials, compacted clays, asphalt, and in-situ glass are discussed. The use of these liners to contain municipal wastes, hazardous waste liquids, and both low-level and high-level radioactive wastes is presented. Liner permeability, transport, stability, construction, and design are studied. Laboratory field measurements for specific wastes are included. (Contains a minimum of 213 citations and includes a subject term index and title list.)

  1. Effects of waste glass and waste foundry sand additions on reclaimed tiles containing sewage sludge ash.

    Science.gov (United States)

    Lin, Deng-Fong; Luo, Huan-Lin; Lin, Kuo-Liang; Liu, Zhe-Kun

    2017-07-01

    Applying sewage sludge ash (SSA) to produce reclaimed tiles is a promising recycling technology in resolving the increasing sludge wastes from wastewater treatment. However, performance of such reclaimed tiles is inferior to that of original ceramic tiles. Many researchers have therefore tried adding various industrial by-products to improve reclaimed tile properties. In this study, multiple materials including waste glass and waste foundry sand (WFS) were added in an attempt to improve physical and mechanical properties of reclaimed tiles with SSA. Samples with various combinations of clay, WFS, waste glass and SSA were made with three kiln temperatures of 1000°C, 1050°C, and 1100°C. A series of tests on the samples were next conducted. Test results showed that waste glass had positive effects on bending strength, water absorption and weight loss on ignition, while WFS contributed the most in reducing shrinkage, but could decrease the tile bending strength when large amount was added at a high kiln temperature. This study suggested that a combination of WFS from 10% to 15%, waste glass from 15% to 20%, SSA at 10% at a kiln temperature between 1000°C and 1050°C could result in quality reclaimed tiles with a balanced performance.

  2. Characterization of secondary solid waste anticipated from the treatment of trench water from Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Kent, T.E.; Taylor, P.A.

    1992-09-01

    This project was undertaken to demonstrate that new liquid waste streams, generated as a consequence of closure activities at Waste Area Grouping (WAG) 6, can be treated adequately by existing wastewater treatment facilities at Oak Ridge National Laboratory (ORNL) without producing hazardous secondary solid wastes. Previous bench-scale treatable studies indicated that ORNL treatment operations will adequately remove the contaminants although additional study was required in order to characterize the secondary waste materials produced as a result of the treatment A 0.5-L/min pilot plant was designed and constructed to accurately simulate the treatment capabilities of ORNL fill-scale (490 L/min) treatment facilities-the Process Waste Treatment Plant (PWTP) and Nonradiological Wastewater Treatment Plant (NRWTP). This new test system was able to produce secondary wastes in the quantities necessary for US Environmental Protection Agency toxicity characteristic leaching procedure (TCLP) testing. The test system was operated for a 45-d test period with a minimum of problems and downtime. The pilot plant operating data verified that the WAG 6 trench waters can be treated at the PWTP and NRWTP to meet the discharge limits. The results of TCLP testing indicate that none of the secondary solid wastes will be considered hazardous as defined by the Resource Conservation and Recovery Act

  3. Passive neutron design study for 200-L waste drums

    International Nuclear Information System (INIS)

    Menlove, H.O.; Beddingfield, D.B.; Pickrell, M.M.

    1997-09-01

    We have developed a passive neutron counter for the measurement of plutonium in 200-L drums of scrap and waste. The counter incorporates high efficiency for the multiplicity counting in addition to the traditional coincidence counting. The 252 Cf add-a-source feature is used to provide an accurate assay over a wide range of waste matrix materials. The room background neutron rate is reduced by using 30 cm of external polyethylene shielding and the cosmic-ray background is reduced by statistical filtering techniques. Monte Carlo Code calculations were used to determine the optimum detector design, including the gas pressure, size, number, and placement of the 3 He tubes in the moderator. Various moderators, including polyethylene, plastics, teflon, and graphite, were evaluated to obtain the maximum efficiency and minimum detectable mass of plutonium

  4. Mixed waste: The treatment of organic radioactive waste by means of adsorbents

    International Nuclear Information System (INIS)

    Sanhueza-Mir, A.; Morales-Galarce, T.

    2001-01-01

    Full text: The work described in this paper has been carried in the radioactive waste treatment facilities of the Nuclear Research Center Lo Aguirre, CEN LA, which are operated by Radioactive Waste Management Unit, UGDR. This last, centralizes its activities in order to manage all radioactive waste generated in the country due to the nuclear development. Features of danger and risks presented by organic radioactive liquid waste, make the need to develop a practicable alternative for its treatment and to allow the conditioning towards a suitable final disposal The raw material for this work, is an organic liquid waste arising from scintillation techniques, contaminated with Tritium. This mixed waste has to be treated and then conditioned in a solid form within a 200 I container, according with actual acceptance criteria for our temporary store for radioactive waste. The best formulation which allows to immobilize the liquid waste was determined. The first step consists in the adsorption treatment that waste is humbled. From the available adsorbents, two types were studied: adsorption granulat and diatomaceous earth. From the waste management standpoint, results with diatomaceous earth present physical characteristics better than the other Following, the second stage is the immobilization, which is achieved in a cement matrix made with puzzolanic cement (Polpaico 400) made in Chile. Later, due to cost and availability in the country, the diatomaceous earth is selected for the study, in the form of celite which is comparatively economic. The best mixture, with regard to physical feature, has the following composition: a 0.35 (w/w) water/cement ratio, which represents the needed quantity to obtain workability in the mixture, and it is the minimum amount of water to hydrating the cement; a waste/adsorbent ratio of 0.5 (v/v), in which the organic liquid is completely adsorbed and it is incorporated into the crystalline system of the solid form; and an adsorbed waste

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

    International Nuclear Information System (INIS)

    McKee, R.W.; Swanson, J.L.; Daling, P.M.

    1986-09-01

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

  6. Benefits of a formal waste management program

    International Nuclear Information System (INIS)

    Wolfe, R.A.

    1974-01-01

    The proper management of waste is of vital importance in the conservation of our environment. Mound Laboratory, which is operated by Monsanto Research Corporation for the U. S. Atomic Energy Commission, has embarked upon a waste management program designed to assure that the generation, processing, storage, and disposal of waste is conducted in such a manner as to have a minimum impact on the environment. The organizational approach taken toward waste management is discussed and some of the benefits of the waste management program at Mound Laboratory are described. Ithas been shown that the utilization of proper waste management techniques can have economic, as well as environmental protection, benefits. (U.S.)

  7. Minimizing the Moisture Damage and Drain down of Iraqi SMA Mixtures Using Waste Additives

    Directory of Open Access Journals (Sweden)

    Ali Al-Hadidy

    2013-04-01

    Full Text Available This research deals with the viability of using polyester fiber (PF, crumb rubber tire (CRT and cellulose fiber (CF as stabilizing waste additives in producing Iraqi SMA mixtures that sustain drain down phenomenon and moisture damage sensitivity. Different ratios of these additives (0.1, 0.2, and 0.3% by weight of aggregate and filler were mixed with 40/50 paving asphalt by means of dry process. Unmodified and modified SMA mixtures were subjected to drain down, Marshall, static indirect tensile strength, tensile stiffness modulus, static compressive strength, tensile strength ratio and index of retained strength tests. A set of regression equations between these tests were established. In addition, an optimization table based on these tests, which can be used to select the type or amount of additive for any field applications has been determined and reported. The results indicated that the inclusion of these additives in SMA mixtures can satisfy the performance requirement of high temperature and much rain zone.

  8. The Distribution of the Sample Minimum-Variance Frontier

    OpenAIRE

    Raymond Kan; Daniel R. Smith

    2008-01-01

    In this paper, we present a finite sample analysis of the sample minimum-variance frontier under the assumption that the returns are independent and multivariate normally distributed. We show that the sample minimum-variance frontier is a highly biased estimator of the population frontier, and we propose an improved estimator of the population frontier. In addition, we provide the exact distribution of the out-of-sample mean and variance of sample minimum-variance portfolios. This allows us t...

  9. Investigations on the long-term behaviour of high level waste forms

    International Nuclear Information System (INIS)

    Lemmens, K.

    2009-01-01

    , realistic and robust, and to describe the related uncertainties. In addition to this first objective, the study planned to give convincing qualitative or semi-qualitative arguments showing that the waste durability will most probably be larger than the proposed minimum life time, because a much lower residual rate will be reached

  10. Inhibiting pitting corrosion in carbon steel exposed to dilute radioactive waste slurries

    International Nuclear Information System (INIS)

    Zapp, P.E.; Hobbs, D.T.

    1991-01-01

    Dilute caustic high-level radioactive waste slurries can induce pitting corrosion in carbon steel. Cyclic potentiodynamic polarization tests were conducted in simulated and actual waste solutions to determine minimum concentrations of sodium nitrate which inhibit pitting in ASTM A537 class 1 steel exposed to these solutions. Susceptibility to pitting was assessed through microscopic inspection of specimens and inspection of polarization scans. Long-term coupon immersion tests were conducted to verify the nitrite concentrations established by the cyclic potentiodynamic polarization tests. The minimum effective nitrite concentration is expressed as a function of the waste nitrate concentration and temperature

  11. Radioactive waste mangement in Canada

    International Nuclear Information System (INIS)

    Didyk, J.P.

    1976-01-01

    The objectives of the Canadian radioactive waste management program are to manage the wastes so that the potential hazards of the material are minimized, and to manage the wastes in a manner which places the minimum possible burden on future generations. The Atomic Energy Control Board regulates all activities in the nuclear field in Canada, including radioactive waste management facility licensing. The Atomic Energy Control Act authorizes the Board to make rules for regulating its proceedings and the performance of its functions. The Atomic Energy Control Regulations define basic regulatory requirements for the licensing of facilities, equipment and materials, including requirements for records and inspection, for security and for health and safety

  12. Vegetable processing wastes addition to improve swine manure anaerobic digestion: Evaluation in terms of methane yield and SEM characterization

    International Nuclear Information System (INIS)

    Molinuevo-Salces, Beatriz; González-Fernández, Cristina; Gómez, Xiomar; García-González, María Cruz; Morán, Antonio

    2012-01-01

    Highlights: ► Vegetable waste as co-substrate for swine manure anaerobic digestion. ► Two hydraulic retention times of 25 and 15 d, respectively. ► SEM characterization of anaerobic sludges to observe microbial composition. ► Vegetable waste as co-substrate increases methane yields up to three times. ► Microbial composition changes after 120 d of digestion. -- Abstract: The effect of adding vegetable waste as a co-substrate in the anaerobic digestion of swine manure was investigated. The study was carried out at laboratory scale using semi-continuous stirred tank reactors working at 37 °C. Organic loading rates (OLRs) of 0.4 and 0.6 g VS L −1 d −1 were evaluated, corresponding to hydraulic retention times (HRTs) of 25 and 15 d, respectively. The addition of vegetable wastes (50% dw/dw) resulted in an improvement of 3 and 1.4-fold in methane yields at HRTs of 25 and 15 d, respectively. Changes on microbial morphotypes were studied by Scanning Electron Microscopy (SEM). Samples analyzed were sludge used as inoculum and digestate obtained from swine manure anaerobic reactors. SEM pictures demonstrated that lignocellulosic material was not completely degraded. Additionally, microbial composition was found to change to cocci and rods morphotypes after 120 d of anaerobic digestion.

  13. USAGE OF METHYL ESTER PRODUCED FROM WASTE GRAPE AND MN ADDITIVE AS ALTERNATIVE DIESEL FUEL

    Directory of Open Access Journals (Sweden)

    Hanbey Hazar

    2017-06-01

    Full Text Available In this study, methyl ester was produced from waste grape pulp sources. The produced methyl ester was mixed with diesel in different proportions, and was tested for engine performance and emission. It was found that with increasing biodiesel content, the specific fuel consumption and exhaust temperature have increased partially, while the CO, HC and smoke emissions decreased significantly. Additionally, in the scope of this study, dodecanol, propylene glycol and Mn based additives were added to fuel B50 to improve the emission and engine performance values. With the presence of additives, an increase in the exhaust temperature was observed, while a decrease in the specific fuel consumption, CO, HC, and smoke emissions were detected.

  14. Additives aided composting of green waste: effects on organic matter degradation, compost maturity, and quality of the finished compost.

    Science.gov (United States)

    Gabhane, Jagdish; William, S P M Prince; Bidyadhar, Rajnikant; Bhilawe, Priya; Anand, Duraisamy; Vaidya, Atul N; Wate, Satish R

    2012-06-01

    The effect of various additives such as fly ash, phosphogypsum, jaggery, lime, and polyethylene glycol on green waste composting was investigated through assessing their influence on microbial growth, enzymatic activities, organic matter degradation, bulk density, quality of finished compost including gradation test, heavy metal analysis, etc. A perusal of results showed that addition of jaggery and polyethylene glycol were helpful to facilitate composting process as they significantly influenced the growth of microbes and cellulase activity. The quality of finished compost prepared from jaggery and polyethylene glycol added treatments were superior to other composts, wherein reduction in C/N ratio was more than 8% in jaggery treatment. All other parameters of compost quality including gradation test also favored jaggery and polyethylene glycol as the best additives for green waste composting. Copyright © 2012 Elsevier Ltd. All rights reserved.

  15. Status of the ORNL liquid low-level waste management upgrades

    International Nuclear Information System (INIS)

    Robinson, S.M.; Kent, T.E.; DePaoli, S.M.

    1995-08-01

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

  16. Additional methods for the processing of solid radioactive wastes

    International Nuclear Information System (INIS)

    Tittlova, E.; Svrcek, A.; Hazucha, E. at el.

    1989-01-01

    An account is given of the work performed within the A 01-159-812/05 State Project concerned with the technology of and technical means for the processing of solid wastes arising during the operation of nuclear power plants. This included the development of the incineration equipment, development of the process of air filter disposal and equipment therefor, manufacture of a saw for fragmentation of wood, manufacture of a sorting box, ultimate solution of the problem of waste sorting, and use of high-pressure compression technology. (author). 1 tab., 9 refs

  17. Fabrication of Thermoelectric Devices Using Additive-Subtractive Manufacturing Techniques: Application to Waste-Heat Energy Harvesting

    Science.gov (United States)

    Tewolde, Mahder

    Thermoelectric generators (TEGs) are solid-state devices that convert heat directly into electricity. They are well suited for waste-heat energy harvesting applications as opposed to primary energy generation. Commercially available thermoelectric modules are flat, inflexible and have limited sizes available. State-of-art manufacturing of TEG devices relies on assembling prefabricated parts with soldering, epoxy bonding, and mechanical clamping. Furthermore, efforts to incorporate them onto curved surfaces such as exhaust pipes, pump housings, steam lines, mixing containers, reaction chambers, etc. require custom-built heat exchangers. This is costly and labor-intensive, in addition to presenting challenges in terms of space, thermal coupling, added weight and long-term reliability. Additive manufacturing technologies are beginning to address many of these issues by reducing part count in complex designs and the elimination of sub-assembly requirements. This work investigates the feasibility of utilizing such novel manufacturing routes for improving the manufacturing process of thermoelectric devices. Much of the research in thermoelectricity is primarily focused on improving thermoelectric material properties by developing of novel materials or finding ways to improve existing ones. Secondary to material development is improving the manufacturing process of TEGs to provide significant cost benefits. To improve the device fabrication process, this work explores additive manufacturing technologies to provide an integrated and scalable approach for TE device manufacturing directly onto engineering component surfaces. Additive manufacturing techniques like thermal spray and ink-dispenser printing are developed with the aim of improving the manufacturing process of TEGs. Subtractive manufacturing techniques like laser micromachining are also studied in detail. This includes the laser processing parameters for cutting the thermal spray materials efficiently by

  18. Composting system for waste treatment coca leaf with the addition of three biological activators in the Experimental Center Kallutaca

    Directory of Open Access Journals (Sweden)

    Apaza-Condori Emma Eva

    2015-11-01

    Full Text Available The objective of this study was to evaluate the composting process waste coca leaf with the addition of three biological activators (yogurt, whey and yeast. This work was carried out Kallutaca Experimental Center, Biofertilizers module Career Agricultural Engineering at the Public University of El Alto, La Paz municipality of Laja. Posed treatments were: T1 (+ Yogurt Coca wastes; T2 (Coca wastes + whey; T3 (Coca wastes + yeast and T4 (Control. The design was completely randomized with 4 treatments and 3 repetitions. The values in N are classified medium and high levels the quantities of P, K are classified as middle levels. The value obtained 7.9 pH, EC 12950 µS/cm and 61% organic matter belong to treatment T1. The decomposition time was a period of 105 days corresponds to treatment T3.

  19. Membrane technology for treating of waste nanofluids coolant: A review

    Science.gov (United States)

    Mohruni, Amrifan Saladin; Yuliwati, Erna; Sharif, Safian; Ismail, Ahmad Fauzi

    2017-09-01

    The treatment of cutting fluids wastes concerns a big number of industries, especially from the machining operations to foster environmental sustainability. Discharging cutting fluids, waste through separation technique could protect the environment and also human health in general. Several methods for the separation emulsified oils or oily wastewater have been proposed as three common methods, namely chemical, physicochemical and mechanical and membrane technology application. Membranes are used into separate and concentrate the pollutants in oily wastewater through its perm-selectivity. Meanwhile, the desire to compensate for the shortcomings of the cutting fluid media in a metal cutting operation led to introduce the using of nanofluids (NFs) in the minimum quantity lubricant (MQL) technique. NFs are prepared based on nanofluids technology by dispersing nanoparticles (NPs) in liquids. These fluids have potentially played to enhance the performance of traditional heat transfer fluids. Few researchers have studied investigation of the physical-chemical, thermo-physical and heat transfer characteristics of NFs for heat transfer applications. The use of minimum quantity lubrication (MQL) technique by NFs application is developed in many metal cutting operations. MQL did not only serve as a better alternative to flood cooling during machining operation and also increases better-finished surface, reduces impact loads on the environment and fosters environmental sustainability. Waste coolant filtration from cutting tools using membrane was treated by the pretreated process, coagulation technique and membrane filtration. Nanomaterials are also applied to modify the membrane structure and morphology. Polyvinylidene fluoride (PVDF) is the better choice in coolant wastewater treatment due to its hydrophobicity. Using of polyamide nanofiltration membranes BM-20D and UF-PS-100-100, 000, it resulted in the increase of permeability of waste coolant filtration. Titanium dioxide

  20. Historical review of waste management and recycling in South Africa

    CSIR Research Space (South Africa)

    Godfrey, Linda

    2017-10-01

    Full Text Available this instrument was never utilised. Limited waste policy and regulation emerged between 1989 and 2007. With the publishing of the 1st National Waste Management Strategy (NWMS) [3] and the White Paper on Integrated Pollution and Waste Management (IP&WM) [4..., classification and disposal of waste, was developed with funding and technical support from the Danish Cooperation for Environment and Development (DANCED). The Minimum Requirements were replaced by “National Norms and Standards for the Assessment of Waste...

  1. Enhanced energy efficiency in waste water treatment plants; Steigerung der Energieeffizienz auf kommunalen Klaeranlagen

    Energy Technology Data Exchange (ETDEWEB)

    Haberkern, Bernd; Maier, Werner; Schneider, Ursula [iat - Ingenieurberatung fuer Abwassertechnik, Darmstadt und Stuttgart, Darmstadt (Germany)

    2008-03-15

    In order to implement the requests of EU-IPCC-directive in a new decree for waste water treatment in Germany, best available techniques have to be defined to optimize energy efficiency in waste water treatment plants (WWTP). Therefore energy efficiency was investigated for common treatment processes and new technologies like membrane filtration, co-digestion or phosphorus recycling. In addition, the occurrence of different technologies for waste water and sludge treatment was evaluated for different size ranges of treatment plants (in population equivalents, PE) nationwide in Germany. The definition of actual and aimed values for specific energy consumption (in kWh/(PE.a)) allowed to calculate the potential energy savings in WWTP and the additional consumption due to new processes on a national level. Under consideration of the reciprocations between optimized energy consumption in WWTP and operation practice, toe-holds to increase energy efficiency according to their relevancy for the national balance could be listed. Case studies prove the feasibility of the investigated techniques and allow proposals for minimum requirements in legal regulation concerning energy efficiency in WWTP. (orig.)

  2. Global Reverse Supply Chain Redesign for Household Plastic Waste under the Emission Trading Scheme

    NARCIS (Netherlands)

    Bing, X.; Bloemhof-Ruwaard, J.M.; Chabaane, A.; Vorst, van der J.G.A.J.

    2015-01-01

    With increasing global resource scarcity, waste becomes a resource that can be managed globally. A reverse supply chain network for waste recycling needs to process all the waste with minimum costs and environmental impact. As re-processing of waste is one of the major sources of pollution in the

  3. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    International Nuclear Information System (INIS)

    1994-02-01

    This report is DOE's first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992

  4. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is DOE`s first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992.

  5. The influence of mineral additives on the mechanical performances of the conditioning matrix of radioactive waste by cementation

    International Nuclear Information System (INIS)

    Dragolici, F.; Rotarescu, G.; Turcanu, C.N.

    1997-01-01

    To improve the quality of the conditioning matrix of radioactive waste by the cementation technology, mineral additives which are diminishing the leaching rate of the radionuclides in the disposal environment are used. The studies performed until now have as an objective the obtaining of the most propitious mixture of cement and bentonite or cement and volcanic tuff, which have the mechanical properties similar to the cement paste used for the conditioning of the radioactive waste. This mixture, cement - mineral binder, in the future is required to be used at the Radioactive Waste Treatment Plant - IPNE - HH Bucharest- Magurele for the conditioning of the radioactive wastes, taking in consideration the properties of these mineral binders: very good plasticity and capacity of adsorption, which lead at the decrease of porosity. Bentonite is a clay already used in the technology of disposal as a filling material to diminish the radioactive spreading because of degradation in time of the metallic package or the intrusion of casual water. The composition of the cement - bentonite - water system is checked by the cement to water and cement to bentonite ratio, by strength and by the separated water volume. The studies show that the best mechanical performance was obtained for a cement to water ratio 10. Taking in consideration the property of bentonite to fill compactly the free spaces in the presence of water, what entails the occurrence of internal tensions in the matrix structure, which leads, in turn, to appearance of microfissures, the mixtures examined by mechanical tests had in their composition less than 10 % bentonite. For volcanic tuff, similar results were obtained using almost the same ratios. In these conditions, the results obtained allow to draw the conclusion that the adequate usage of the mineral additives do not change the resistance of the cement paste used in the conditioning of the radioactive waste. (authors)

  6. WESF hot cells waste minimization criteria hot cells window seals evaluation

    International Nuclear Information System (INIS)

    Walterskirchen, K.M.

    1997-01-01

    WESF will decouple from B Plant in the near future. WESF is attempting to minimize the contaminated solid waste in their hot cells and utilize B Plant to receive the waste before decoupling. WESF wishes to determine the minimum amount of contaminated waste that must be removed in order to allow minimum maintenance of the hot cells when they are placed in ''laid-up'' configuration. The remaining waste should not cause unacceptable window seal deterioration for the remaining life of the hot cells. This report investigates and analyzes the seal conditions and hot cell history and concludes that WESF should remove existing point sources, replace cerium window seals in F-Cell and refurbish all leaded windows (except for A-Cell). Work should be accomplished as soon as possible and at least within the next three years

  7. Chemical composition and fermentative parameters of heart of palm waste produced from Alexander Palm ensiled with chemical additives

    Directory of Open Access Journals (Sweden)

    Geraldo Fábio Viana Bayão

    Full Text Available ABSTRACT The objective of this study was to evaluate the chemical composition and the fermentative parameters of heart of palm waste produced from Alexander Palm, ensiled with chemical additives. Treatments consisted of silage of the sheath with or without calcium oxide. In the silage without calcium oxide, we evaluated the control silage (without additive and the silage enriched with 5.0 g kg−1 urea (urea. In the silage with calcium oxide, we evaluated the silage enriched with 5.0 g kg−1 calcium oxide (control and the silage enriched with 5.0 g kg−1 urea and 5.0 g kg−1 calcium oxide (urea. Experimental silos were distributed in a completely randomized design in a 2 × 2 factorial arrangement (inclusion or lack of lime × inclusion or lack of urea, with four replicates. Crude protein concentration was greater in the silages that received urea, whereas in the case of neutral detergent fiber and acid detergent fiber, the lowest levels were found in the control silage. Control silage had the lowest pH (3.75 and the silages that received lime displayed the lowest lactic acid content. Effluent losses were greater in the control silage and in the silage with lime (56.1 kg t−1 and 58.4 kg t−1, respectively. Silages prepared with waste from heart of palm production and enriched only with urea showed a better chemical composition and improved fermentation parameter estimates. We recommend the use of this waste only with additives that can improve the chemical characteristics of the forage. Without additives, unwanted fermentation processes may occur and compromise the quality of the silage.

  8. Evaluation of alternative chemical additives for high-level waste vitrification feed preparation processing

    International Nuclear Information System (INIS)

    Seymour, R.G.

    1995-01-01

    During the development of the feed processing flowsheet for the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS), research had shown that use of formic acid (HCOOH) could accomplish several processing objectives with one chemical addition. These objectives included the decomposition of tetraphenylborate, chemical reduction of mercury, production of acceptable rheological properties in the feed slurry, and controlling the oxidation state of the glass melt pool. However, the DEPF research had not shown that some vitrification slurry feeds had a tendency to evolve hydrogen (H 2 ) and ammonia (NH 3 ) as the result of catalytic decomposition of CHOOH with noble metals (rhodium, ruthenium, palladium) in the feed. Testing conducted at Pacific Northwest Laboratory and later at the Savannah River Technical Center showed that the H 2 and NH 3 could evolve at appreciable rates and quantities. The explosive nature of H 2 and NH 3 (as ammonium nitrate) warranted significant mitigation control and redesign of both facilities. At the time the explosive gas evolution was discovered, the DWPF was already under construction and an immediate hardware fix in tandem with flowsheet changes was necessary. However, the Hanford Waste Vitrification Plant (HWVP) was in the design phase and could afford to take time to investigate flowsheet manipulations that could solve the problem, rather than a hardware fix. Thus, the HWVP began to investigate alternatives to using HCOOH in the vitrification process. This document describes the selection, evaluation criteria, and strategy used to evaluate the performance of the alternative chemical additives to CHOOH. The status of the evaluation is also discussed

  9. Minimum Analytical Chemistry Requirements for Pit Manufacturing at Los Alamos National Laboratory; TOPICAL

    International Nuclear Information System (INIS)

    Moy, Ming M.; Leasure, Craig S.

    1998-01-01

    Analytical chemistry is one of several capabilities necessary for executing the Stockpile Stewardship and Management Program at Los Alamos National Laboratory (LANL). Analytical chemistry capabilities reside in the Chemistry Metallurgy Research (CMR) Facility and Plutonium Facility (TA-55). These analytical capabilities support plutonium recovery operations, plutonium metallurgy, and waste management. Analytical chemistry capabilities at both nuclear facilities are currently being configured to support pit manufacturing. This document summarizes the minimum analytical chemistry capabilities required to sustain pit manufacturing at LANL. By the year 2004, approximately$16 million will be required to procure analytical instrumentation to support pit manufacturing. In addition,$8.5 million will be required to procure glovebox enclosures. An estimated 50% increase in costs has been included for installation of analytical instruments and glovebox enclosures. However, no general and administrative (G and A) taxes have been included. If an additional 42.5/0 G and A tax were to be incurred, approximately$35 million would be required over the next five years to prepare analytical chemistry to support a 50-pit-per-year manufacturing capability by the year 2004

  10. Chemical Composition of Vermicompost Made from Organic Wastes through the Vermicomposting and Composting with the Addition of Fish Meal and Egg Shells Flour

    Directory of Open Access Journals (Sweden)

    Nurhidayati

    2017-05-01

    Full Text Available Chemical composition of compost is an important indicator that determines the quality of compost. This study compared the chemical composition of vermicompost resulting from the process of vermicomposting alone with combined vermicomposting and composting with addition of egg shells flour and fish meal. Organic wastes used were the mixture of spent mushrooms waste, coconut husks, cow dung, vegetables residue, and leaf litter. Lumbricus rubellus was the species of earthworm used in the vermicomposting process. In the composting process, egg shells flour and fish meal are added into the vermicompost as additives materials. The results indicate that the combined vermicomposting and composting process with addition the additives materials improves the chemical composition of vermicompost compared to using vermicomposting process alone. The change of chemical composition was indicated by a decrease in C-organic content and C/N ratio by 29% and 99%, respectively, while the content of N, P, K and S increased by 52%, 67.5%, 29% and 25%, respectively due to the addition of additives material in the composting process. The largest increase of vermicompost nutrient content occurred in the Ca content by an average of up to 7-fold. While polyphenols, lignin and cellulose content of vermicompost decreased slightly. The treatment of two mixture (a spent mushrooms waste, cow dung and vegetables residue, and (b spent mushroom waste, cow dung, vegetables residue, and leaf litter gave the best chemical composition. However, to determine the quality, we need to test the product in a plant growth bioassay as a follow-up study.

  11. Impact of socioeconomic status on municipal solid waste generation rate.

    Science.gov (United States)

    Khan, D; Kumar, A; Samadder, S R

    2016-03-01

    The solid waste generation rate was expected to vary in different socioeconomic groups due to many environmental and social factors. This paper reports the assessment of solid waste generation based on different socioeconomic parameters like education, occupation, income of the family, number of family members etc. A questionnaire survey was conducted in the study area to identify the different socioeconomic groups that may affect the solid waste generation rate and composition. The average waste generated in the municipality is 0.41 kg/capita/day in which the maximum waste was found to be generated by lower middle socioeconomic group (LMSEG) with average waste generation of 0.46 kg/capita/day. Waste characterization indicated that there was no much difference in the composition of wastes among different socioeconomic groups except ash residue and plastic. Ash residue is found to increase as we move lower down the socioeconomic groups with maximum (31%) in lower socioeconomic group (LSEG). The study area is a coal based city hence application of coal and wood as fuel for cooking in the lower socioeconomic group is the reason for high amount of ash content. Plastic waste is maximum (15%) in higher socioeconomic group (HSEG) and minimum (1%) in LSEG. Food waste is a major component of generated waste in almost every socioeconomic group with maximum (38%) in case of HSEG and minimum (28%) in LSEG. This study provides new insights on the role of various socioeconomic parameters on generation of household wastes. Copyright © 2016 Elsevier Ltd. All rights reserved.

  12. Waste processing practices at waste management department from INR

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Bujoreanu, L.

    2010-01-01

    The Institute for Nuclear Research Pitesti (INR), subsidiary of the Romanian Authority for Nuclear Activities has its own Radioactive Waste Treatment Plant (STDR). The object of activity of STDR within the INR Pitesti is to treat and condition radioactive waste resulted from the nuclear facility. Also, it will must prepare and manage the decommissioning projects of its own facilities and to upgrade the facilities for the management of the radioactive waste resulting from other decommissioning activities. In according with the National Nuclear Program and the Governmental order no. 11/2003, the Institute for Nuclear Research is the main support for implementation of the methods and technologies for conditioning and disposal of radioactive waste generated by the decommissioning of nuclear facilities. The classes and criteria of classification for radioactive waste generated in operation and decommissioning in Romania are established in compliance with the classification recommended by IAEA and generally valid in EU countries. The general classification takes into consideration the disposal requirements to isolate the radioactive waste from environment. In Romania, waste minimization is considered by Order No. 56/2004 of CNCAN President for approval of Fundamental regulations on the safe management of radioactive waste. According to this regulation, the generation of radioactive waste is to be kept to the minimum practicable level in terms of both its activity and volume through appropriate design measures, facility operation and decommissioning practices. In order to meet this requirement, the operator must ensure: - selection and control of materials; - recycling and reuse of materials, including clearance of materials; - implementing adequate operating procedures, including those referring to the physical, chemical and radiological characterization of the waste and sorting of different type of materials. (orig.)

  13. Additive for reducing operational problems in waste fired grate boilers; Additiv foer att minska driftproblem vid rostfoerbraenning av avfall

    Energy Technology Data Exchange (ETDEWEB)

    Gyllenhammar, Marianne; Herstad Svaerd, Solvie; Davidsson, Kent; Hermansson, Sven; Liske, Jesper; Larsson, Erik; Jonsson, Torbjoern; Zhao, Dongmei

    2013-09-01

    The combustion of waste implies a risk for deposits and corrosion in different parts of the combustion facility. In recent years, research and tests have been performed in order to find ways to mitigate these problems in waste-fired plants. Most waste-fired plants in Sweden are grates whereas most of the research has been carried out in fluidized bed plants. The purpose of this project is to examine whether co-firing of sewage sludge and waste can reduce deposition and corrosion also in grate-fired boilers as has been shown in fludised beds. The objective is to determine the deposit growth and its composition as well as describing the initial corrosion attack. Representing sulphur-rich waste, elementary sulphur is also added to the waste and thereby compared with sludge as an additive. The target groups for this project are plant owners, researchers, consultants and authorities. Tests were performed in a 15 MWth waste-fired boiler with moving grate at Gaerstadverket, Tekniska Verken (Linkoeping). The boiler produces saturated steam of 17 bars and 207 deg C, and the normal fuel mixture contains of household and industry waste. The results show that co-firing with as heigh as 20 weight-% SLF (25 energy-%) was possible from an operational point of view, but the deposit rate increased especially at the two warmest positions. Generally the deposit rate was highest in the position closest to the boiler and decreased further downstream. During the tests a lot higher amount of SLF than normal was used (recommended mix is 5-10 % of SLF) this to be able to see effects of the different measures. Up to 23 weight-% of the rather moist sewage sludge was possible to fire when co-firing waste and SLF, without addition of oil. By adding sludge the deposit rate decreased but the increase upon adding SLF to ordinary waste was not totally eliminated. In the tests 'Avfall and SLF' the deposits were rich in chlorine. High concentrations of metal chlorides were found in the

  14. Municipal wastes and landfield gases utilization - renewable resource of energy and materials

    International Nuclear Information System (INIS)

    Kuburovic, M.; Jovovic, A.

    2002-01-01

    Urbanization and industrialization, have been fundamental causes of environmental pollution (of water, air and land) which the cities were unable to handle. There is already enough evidence of the fact that the role of technology in environmental matters is moving in two important directions: sustainable development, dealing primary with global problems, and preventive technology, designed to reduce the environmental effects of processes, operations, and products. Treatment plants for industrial and municipal wastes, emission controls for incinerators, and safe landfills for waste disposal were developed to control air, water, and land pollution. Now, this 'end-of-pipe' treatment technologies are still the way of environmental protection philosophy, particularly in the developing countries. New environmental standards demand more and more rigorous preventive environmental protection technologies, therefore further development of industrial production requires the rational use of natural sources of raw materials and energy. Production and the use of goods with the minimum municipal and industrial wastes and the development of recycling technology provided closed cycle of materials. Main principles for the development and exploitation of the technology with the minimum or without waste materials and energy are: the use of renewable sources of material and energy, maximum use of waste materials and waste energy, waste minimisation and reduction of energy losses in the production, development of new industrial processes operating with minimum material and energy losses in products exploitation period and after that, and the responsible use of natural sources, products and energy in the field of industry and consumption. (author)

  15. Waste characterization for the F/H Effluent Treatment Facility in support of waste certification

    International Nuclear Information System (INIS)

    Brown, D.F.

    1994-01-01

    The Waste Acceptance Criteria (WAC) procedures define the rules concerning packages of solid Low Level Waste (LLW) that are sent to the E-area vaults (EAV). The WACs tabulate the quantities of 22 radionuclides that require manifesting in waste packages destined for each type of vault. These quantities are called the Package Administrative Criteria (PAC). If a waste package exceeds the PAC for any radionuclide in a given vault, then specific permission is needed to send to that vault. To avoid reporting insignificant quantities of the 22 listed radionuclides, the WAC defines the Minimum Reportable Quantity (MRQ) of each radionuclide as 1/1000th of the PAC. If a waste package contains less than the MRQ of a particular radionuclide, then the package's manifest will list that radionuclide as zero. At least one radionuclide has to be reported, even if all are below the MRQ. The WAC requires that the waste no be ''hazardous'' as defined by SCDHEC/EPA regulations and also lists several miscellaneous physical/chemical requirements for the packages. This report evaluates the solid wastes generated within the F/H Effluent Treatment Facility (ETF) for potential impacts on waste certification

  16. Development of polymer concrete radioactive waste management containers

    Energy Technology Data Exchange (ETDEWEB)

    Chung, H.; Lee, M. S.; Ahn, D. H.; Won, H. J.; Kang, H. S.; Lee, H. S.; Lim, S.P.; Kim, Y. E.; Lee, B. O.; Lee, K. P.; Min, B. Y.; Lee, J.K.; Jang, W. S.; Sim, W. B.; Lee, J. C.; Park, M. J.; Choi, Y. J.; Shin, H. E.; Park, H. Y.; Kim, C. Y

    1999-11-01

    A high-integrity radioactive waste container has been developed to immobilize the spent resin wastes from nuclear power plants, protect possible future, inadvertent intruders from damaging radiation. The polymer concrete container is designed to ensure safe and reliable disposal of the radioactive waste for a minimum period of 300 years. A built-in vent system for each container will permit the release of gas. An experimental evaluation of the mechanical, chemical, and biological tests of the container was carried out. The tests showed that the polymer concrete container is adequate for safe disposal of the radioactive wastes. (author)

  17. An Experimental Study on Effect of Palm – Shell Waste Additive to Cement Strenght Enhancement

    Directory of Open Access Journals (Sweden)

    Adi Novriansyah

    2017-03-01

    Full Text Available Enhancing the cement strength through attaching chemical additive has been popular to meet the required condition for a particular well-cementing job. However, due to a low oil-price phenomenon, pouring and additive should be reconsidered because it can raise the cost and make the project become uneconomic. Another additive material in nanocomposite form will be introduced through this experimental study. The nanocomposite material consist of silica nanoparticle, known as “Nanosilica” and a palm-shell-waste, which is abundant in Indonesia. Before making a nanocomposite, the palm-shell should be burned to obtain a charcoal form, ground and sieved to attain a uniform size.   The study focuses on the two parameters, compressive strength and shear bond strength, which can reflect the strength of the cement. These values are obtained by performing a biaxial loading test to the cement sample. Various samples with different concentration of nanocomposite should be prepared and following the mixing, drying, and hardening process before the loading test is carried out. The result from the test shows a positive indication for compressive strength and shear bond strength values, according to the representative well cementing standards. Increasing the nanocomposite concentration on the cement will increase these values. Furthermore, an investigation on the temperature effect confirms that the sample with 700oC burning temperature have highest compressive-strength and shear-bond-strength values. This is a potential opportunity utilizing a waste-based material to produce another product with higher economic value.

  18. Minimum airflow reset of single-duct VAV terminal boxes

    Science.gov (United States)

    Cho, Young-Hum

    Single duct Variable Air Volume (VAV) systems are currently the most widely used type of HVAC system in the United States. When installing such a system, it is critical to determine the minimum airflow set point of the terminal box, as an optimally selected set point will improve the level of thermal comfort and indoor air quality (IAQ) while at the same time lower overall energy costs. In principle, this minimum rate should be calculated according to the minimum ventilation requirement based on ASHRAE standard 62.1 and maximum heating load of the zone. Several factors must be carefully considered when calculating this minimum rate. Terminal boxes with conventional control sequences may result in occupant discomfort and energy waste. If the minimum rate of airflow is set too high, the AHUs will consume excess fan power, and the terminal boxes may cause significant simultaneous room heating and cooling. At the same time, a rate that is too low will result in poor air circulation and indoor air quality in the air-conditioned space. Currently, many scholars are investigating how to change the algorithm of the advanced VAV terminal box controller without retrofitting. Some of these controllers have been found to effectively improve thermal comfort, indoor air quality, and energy efficiency. However, minimum airflow set points have not yet been identified, nor has controller performance been verified in confirmed studies. In this study, control algorithms were developed that automatically identify and reset terminal box minimum airflow set points, thereby improving indoor air quality and thermal comfort levels, and reducing the overall rate of energy consumption. A theoretical analysis of the optimal minimum airflow and discharge air temperature was performed to identify the potential energy benefits of resetting the terminal box minimum airflow set points. Applicable control algorithms for calculating the ideal values for the minimum airflow reset were developed and

  19. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    Collard, G.

    2007-01-01

    The primary mission of the Radioactive Waste and Clean-up division is to propose, to develop and to evaluate solutions for a safe, acceptable and sustainable management of radioactive waste. The Radioactive Waste and Clean-up division programme consists in research, studies, development and demonstration aiming to realise the objective of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation on radioactively contaminated sites. Indeed, it participates in the realisation of an objective which is to ensure that radioactive wastes are safely managed, transported, stored and disposed of, with a view to protecting human health and the environment, within a wider framework of an interactive and integrated approach to radioactive waste management and safety. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation of future power production and waste management technologies should be put on waste minimisation. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and other quality factors. SCK-CEN in general and the Radioactive Waste and Clean-up division in particular are present in international groups preparing the development of innovative nuclear reactors, as Generation 4 and INPRO. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of

  20. Operationalisation of service quality in household waste collection.

    Science.gov (United States)

    Schulte, Nico Alexander; Gellenbeck, Klaus; Nelles, Michael

    2017-04-01

    Since 2007, there has been intensive discussion at European and national levels concerning the standardisation of services including those in the sector of waste management. The drafts of the European standard prEN 16250 and the German preliminary standard DIN SPEC 1108 are intended to establish a uniform definition of corresponding services and their (minimum) service levels. Their binding application in practice requires that systematic inspections be provided to ascertain to what degree a service has been carried out as agreed upon. However, both standardisation projects give only a few examples of potential quality characteristics and offer no concrete information concerning methods of measurement. Because intersectoral or cross-service quality inspections do not exist, there is a need for the development of specific quality inspections. The study introduced in this article examines the question of how the service quality of door-to-door waste collection can be systematically measured. To this end, the quality concept applied to the process of waste collection was first concretised and then operationalised using indicators. Based upon this, the methods of the quality inspections were developed and subjected to a trial of their applicability in a German waste management company. The methods for measuring and evaluating take into account, in addition to the different boundary conditions of collection, also the possible customer influence on the collection process and consequently on the service performed by the collection crew. In order to avoid time- and therefore cost-intensive exhaustive surveys, a multilevel random-controlled selection of survey units was developed, too. Based on the analysis of the measurement data, it was possible to determine specific time requirement values for the regular performance of the data surveys, as well as minimum sample sizes as a function of the number of container locations of the waste collection tours. On the basis of this

  1. Experimental investigations of the minimum ignition energy and the minimum ignition temperature of inert and combustible dust cloud mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Addai, Emmanuel Kwasi, E-mail: emmanueladdai41@yahoo.com; Gabel, Dieter; Krause, Ulrich

    2016-04-15

    Highlights: • Ignition sensitivity of a highly flammable dust decreases upon addition of inert dust. • Minimum ignition temperature of a highly flammable dust increases when inert concentration increase. • Minimum ignition energy of a highly flammable dust increases when inert concentration increase. • The permissible range for the inert mixture to minimize the ignition risk lies between 60 to 80%. - Abstract: The risks associated with dust explosions still exist in industries that either process or handle combustible dust. This explosion risk could be prevented or mitigated by applying the principle of inherent safety (moderation). This is achieved by adding an inert material to a highly combustible material in order to decrease the ignition sensitivity of the combustible dust. The presented paper deals with the experimental investigation of the influence of adding an inert dust on the minimum ignition energy and the minimum ignition temperature of the combustible/inert dust mixtures. The experimental investigation was done in two laboratory scale equipment: the Hartmann apparatus and the Godbert-Greenwald furnace for the minimum ignition energy and the minimum ignition temperature test respectively. This was achieved by mixing various amounts of three inert materials (magnesium oxide, ammonium sulphate and sand) and six combustible dusts (brown coal, lycopodium, toner, niacin, corn starch and high density polyethylene). Generally, increasing the inert materials concentration increases the minimum ignition energy as well as the minimum ignition temperatures until a threshold is reached where no ignition was obtained. The permissible range for the inert mixture to minimize the ignition risk lies between 60 to 80%.

  2. Experimental investigations of the minimum ignition energy and the minimum ignition temperature of inert and combustible dust cloud mixtures

    International Nuclear Information System (INIS)

    Addai, Emmanuel Kwasi; Gabel, Dieter; Krause, Ulrich

    2016-01-01

    Highlights: • Ignition sensitivity of a highly flammable dust decreases upon addition of inert dust. • Minimum ignition temperature of a highly flammable dust increases when inert concentration increase. • Minimum ignition energy of a highly flammable dust increases when inert concentration increase. • The permissible range for the inert mixture to minimize the ignition risk lies between 60 to 80%. - Abstract: The risks associated with dust explosions still exist in industries that either process or handle combustible dust. This explosion risk could be prevented or mitigated by applying the principle of inherent safety (moderation). This is achieved by adding an inert material to a highly combustible material in order to decrease the ignition sensitivity of the combustible dust. The presented paper deals with the experimental investigation of the influence of adding an inert dust on the minimum ignition energy and the minimum ignition temperature of the combustible/inert dust mixtures. The experimental investigation was done in two laboratory scale equipment: the Hartmann apparatus and the Godbert-Greenwald furnace for the minimum ignition energy and the minimum ignition temperature test respectively. This was achieved by mixing various amounts of three inert materials (magnesium oxide, ammonium sulphate and sand) and six combustible dusts (brown coal, lycopodium, toner, niacin, corn starch and high density polyethylene). Generally, increasing the inert materials concentration increases the minimum ignition energy as well as the minimum ignition temperatures until a threshold is reached where no ignition was obtained. The permissible range for the inert mixture to minimize the ignition risk lies between 60 to 80%.

  3. Tomatoes in oil recovery. [Plant waste additives improve yield

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    The waste from processing tomato, squash and pepper stalks found unexpected use in recovery of oil. Even a negligible amount thereof in an aqueous solution pumped into an oil-bearing formation turned out to be sufficient to increase the yield. Substances of plant origin, which improve dramatically the oil-flushing properties of water, not only increase the recovery of oil, but reduce the volume of fluid to be pumped into the stratum. The staff of the Institute of Deep Oil and Gas Deposits of the Azerbaijan Academy of Sciences, who proved the technological and economical advantages of using the waste from plant processing, transmitted their findings to the oil workers of Baku. The scientists have concluded that there is a good raw material base in this republic for utilizing this method on oil-bearing formations.

  4. An Approach for the Analysis of Regulatory Analytes in High Level Radioactive Waste Stored at Hanford, Richland, Washington

    International Nuclear Information System (INIS)

    Wiemers, K.D.; Miller, M.; Lerchen, M.E.

    1999-01-01

    Radiation levels, salt concentration, and the oxidizing nature of the waste dictates modifications to the SW-846 methods. Modified methods will be used to meet target EQLs and QC currently in SW-846. Method modifications will be validated per SW-846 and HASQARD and will be documented consistent with WAC 173-303-910. The affect of modifications to holding times and storage conditions will be evaluated using techniques developed by Maskarinec and Bayne (1996). After validating the methods and performing the holding time study on a minimum of two Phase 1 candidate feed source tank wastes, DOE and Ecology will assess: whether different methods are needed, whether holding time/storage conditions should be altered, whether the high priority analyte list should be refined, and which additional tank waste needs to be characterized

  5. Effects of Quartz Particle Size and Sucrose Addition on Melting Behavior of a Melter Feed for High-Level Waste Glass

    International Nuclear Information System (INIS)

    Marcial, Jose; Hrma, Pavel R.; Schweiger, Michael J.; Swearingen, Kevin J.; Tegrotenhuis, Nathan E.; Henager, Samuel H.

    2010-01-01

    The behavior of melter feed (a mixture of nuclear waste and glass-forming additives) during waste-glass processing has a significant impact on the rate of the vitrification process. We studied the effects of silica particle size and sucrose addition on the volumetric expansion (foaming) of a high-alumina feed and the rate of dissolution of silica particles in feed samples heated at 5 C/min up to 1200 C. The initial size of quartz particles in feed ranged from 5 to 195 (micro)m. The fraction of the sucrose added ranged from 0 to 0.20 g per g glass. Extensive foaming occurred only in feeds with 5-(micro)m quartz particles; particles (ge) 150 (micro)m formed clusters. Particles of 5 (micro)m completely dissolved by 900 C whereas particles (ge) 150 (micro)m did not fully dissolve even when the temperature reached 1200 C. Sucrose addition had virtually zero impact on both foaming and the dissolution of silica particles.

  6. Addition of granular activated carbon and trace elements to favor volatile fatty acid consumption during anaerobic digestion of food waste.

    Science.gov (United States)

    Capson-Tojo, Gabriel; Moscoviz, Roman; Ruiz, Diane; Santa-Catalina, Gaëlle; Trably, Eric; Rouez, Maxime; Crest, Marion; Steyer, Jean-Philippe; Bernet, Nicolas; Delgenès, Jean-Philippe; Escudié, Renaud

    2018-07-01

    The effect of supplementing granular activated carbon and trace elements on the anaerobic digestion performance of consecutive batch reactors treating food waste was investigated. The results from the first batch suggest that addition of activated carbon favored biomass acclimation, improving acetic acid consumption and enhancing methane production. Adding trace elements allowed a faster consumption of propionic acid. A second batch proved that a synergy existed when activated carbon and trace elements were supplemented simultaneously. The degradation kinetics of propionate oxidation were particularly improved, reducing significantly the batch duration and improving the average methane productivities. Addition of activated carbon favored the growth of archaea and syntrophic bacteria, suggesting that interactions between these microorganisms were enhanced. Interestingly, microbial analyses showed that hydrogenotrophic methanogens were predominant. This study shows for the first time that addition of granular activated carbon and trace elements may be a feasible solution to stabilize food waste anaerobic digestion. Copyright © 2018 Elsevier Ltd. All rights reserved.

  7. How much radiation dose, to whom? Long-term storage, surveillance, retrieval and long processes cause additional dose to employees; Wie viel Strahlendosis fuer wen? Lange Lagerung, Offenhaltung und ein langer Entsorgungsprozess bedeuten zusaetzliche Dosis fuer Beschaeftigte

    Energy Technology Data Exchange (ETDEWEB)

    Walther, Clemens [Hannover Univ. (Germany). Inst. fuer Radiooekologie und Strahlenschutz; Riemann, Moritz [Kiel Univ. (Germany). Lehrstuhl fuer Philosophie und Ethik der Umwelt

    2017-09-01

    In the case of final nuclear waste disposal there are concurrent interests with respect to radiation protection: The realization of a disposal option with minimum required follow-up care needs time causing additional radiation exposure for the employees, also the option of long-term storage, surveillance and retrieval possibilities cause additional dose to employees. The contribution discusses possible consideration of requests for the different options.

  8. Radioactive waste disposal: Waste isolation pilot plants (WIPP). (Latest citations from the NTIS Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-09-01

    The bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, and examine research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in separate bibliographies. (Contains a minimum of 228 citations and includes a subject term index and title list.)

  9. Field test results for radioactive waste drum characterization with Waste Inspection Tomography (WIT)

    Energy Technology Data Exchange (ETDEWEB)

    Bernardi, R.T. [Bio-Imaging Research, Inc., Lincolnshire, IL (United States)

    1997-11-01

    This paper summarizes the design, fabrication, factory testing, evaluation and demonstration of waste inspection tomography (WIT). WIT consists of a self-sufficient, mobile semi-trailer for Non-Destructive Evaluation and Non-Destructive Assay (NDE/NDA) characterization of nuclear waste drums using X-ray and gamma-ray tomographic techniques. The 23-month WIT Phase I initial test results include 2 MeV Digital Radiography (DR), Computed Tomography (CT), Anger camera imaging, Single Photon Emission Computed Tomography (SPECT), Gamma-Ray Spectroscopy, Collimated Gamma Scanning (CGS), and Active and Passive Computed Tomography (A&PCT) using a 1.4 mCi source of {sup 166}Ho. These techniques were initially demonstrated on a 55-gallon phantom drum with three simulated waste matrices of combustibles, heterogeneous metals, and cement using check sources of gamma active isotopes. Waste matrix identification, isotopic identification, and attenuation-corrected gamma activity determination were all demonstrated nondestructively and noninvasively. Preliminary field tests results with nuclear waste drums are summarized. WIT has inspected drums with 0 to 20 grams plutonium 239. The minimum measured was 0.131 gram plutonium 239 in cement. 8 figs.

  10. Remote waste handling and feed preparation for Mixed Waste Management

    International Nuclear Information System (INIS)

    Couture, S.A.; Merrill, R.D.; Densley, P.J.

    1995-05-01

    The Mixed Waste Management Facility (MWMF) at the Lawrence Livermore National Laboratory (LLNL) will serve as a national testbed to demonstrate mature mixed waste handling and treatment technologies in a complete front-end to back-end --facility (1). Remote operations, modular processing units and telerobotics for initial waste characterization, sorting and feed preparation have been demonstrated at the bench scale and have been selected for demonstration in MWMF. The goal of the Feed Preparation design team was to design and deploy a robust system that meets the initial waste preparation flexibility and productivity needs while providing a smooth upgrade path to incorporate technology advances as they occur. The selection of telerobotics for remote handling in MWMF was made based on a number of factors -- personnel protection, waste generation, maturity, cost, flexibility and extendibility. Modular processing units were selected to enable processing flexibility and facilitate reconfiguration as new treatment processes or waste streams are brought on line for demonstration. Modularity will be achieved through standard interfaces for mechanical attachment as well as process utilities, feeds and effluents. This will facilitate reconfiguration of contaminated systems without drilling, cutting or welding of contaminated materials and with a minimum of operator contact. Modular interfaces also provide a standard connection and disconnection method that can be engineered to allow convenient remote operation

  11. Industrial Wastes as Alternative Mineral Addition in Portland Cement and as Aggregate in Coating Mortars

    OpenAIRE

    Oliveira, Kamilla Almeida; Nazário, Bruna Inácio; Oliveira, Antonio Pedro Novaes de; Hotza, Dachamir; Raupp-Pereira, Fabiano

    2017-01-01

    This paper presents an evaluation study of wastes from pulp and paper as well as construction and demolition industries for application in cement-based materials. The alternative raw materials were used as a source of calcium carbonate (CaCO3) and as pozzolanic material (water-reactive SiO2) in partial replacement of Portland cement. In addition to the hydraulic binder, coating mortars were composed by combining the pulp and paper fluidized bed sand residue with construction and demolition wa...

  12. THE USE OF POULTRY SLAUGHTERHOUSE WASTE TO PRODUCE COMPOST

    OpenAIRE

    Michał Kopeć; Krzysztof Gondek; Kalina Orłowska; Zdzisław Kulpa

    2014-01-01

    Poultry industry generates large amounts of waste, which in the biological treatment process creates a number of problems. One of them is a high amount of fat and creatine which is hard to decompose. Composting process was carried out with the waste from poultry farms and abattoirs mixed with maize straw, which was used to improve the structure and to increase the amount of carbon in the substrate. The chemical composition of composts from poultry waste involving maize straw meets the minimum...

  13. Wastes from the light water reactor fuel cycle

    International Nuclear Information System (INIS)

    Steindler, M.J.; Trevorrow, L.E.

    1976-01-01

    The LWR fuel cycle is represented, in the minimum detail necessary to indicate the origin of the wastes, as a system of operations that is typical of those proposed for various commercial fuel cycle ventures. The primary wastes (before any treatment) are described in terms of form, volume, radioactivity, chemical composition, weight, and combustibility (in anticipation of volume reduction treatments). Properties of the wastes expected from the operation of reactors, fuel reprocessing plants, and mixed oxide fuel fabrication plants are expressed in terms of their amounts per unit of nuclear energy produced

  14. Impact of coagulant and flocculant addition to an anaerobic dynamic membrane bioreactor (AnDMBR) treating waste-activated sludge

    NARCIS (Netherlands)

    Kooijman, G.; Lopes, Wilton; Zhou, Z.; Guo, H.; de Kreuk, M.K.; Spanjers, H.L.F.M.; van Lier, J.B.

    2017-01-01

    In this work, we investigated the effects of flocculation aid (FA) addition to an anaerobic dynamic membrane bioreactor (AnDMBR) (7 L, 35°C) treating waste-activated sludge (WAS). The experiment consisted of three distinct periods. In period 1 (day 1–86), the reactor was operated as a

  15. IJER@2014 Page 57 Disposal Criteria of Bhanpur Solid Waste Landfill Site: Investigation and Suggestions

    OpenAIRE

    Tapas Dasgpta

    2014-01-01

    The solid waste management and design assist waste management officials in developing and encouraging environmentally sound methods for the disposal of "nonhazardous" solid waste. Promulgated under the authority of municipal act, the Municipal Solid Waste Landfill (MSWLF) regulation act establish a framework for planning and implementing municipal solid waste landfill programs at the state and local levels. This framework sets minimum standards for protecting h...

  16. Utilization of waste tire rubber in manufacture of oriented strandboard.

    Science.gov (United States)

    Ayrilmis, Nadir; Buyuksari, Umit; Avci, Erkan

    2009-09-01

    Some physical and mechanical properties of oriented strandboards (OSBs) containing waste tire rubber at various addition levels based on the oven-dry strand weight, using the same method as that used in the manufacture of OSB. Two resin types, phenol-formaldehyde (PF) and polyisocyanate, were used in the experiments. The manufacturing parameters were: a specific gravity of 0.65 and waste tire rubber content (10/90, 20/80 and 30/70 by wt.% of waste tire rubber/wood strand). Average internal bond values of PF-bonded OSB panels with rubber chips were between 17.6% and 48.5% lower than the average of the control samples while polyisocyanate bonded OSBs were 16.5-50.6%. However, water resistance and mechanical properties of OSBs made using polyisocyanate resin were found to comply with general-purpose OSB minimum property requirements of EN 300 Type 1 (1997) values for use in dry conditions at the lowest tire rubber loading level (10%) based on the oven-dry panel weight. The tire rubber improved water resistance of the OSB panel due to its almost hydrophobic property. Based on the findings obtained from this study, we concluded that waste tire rubber could be used for general-purpose OSB manufacturing up to 10% ratio based on the oven-dry panel weight.

  17. Management, treatment and final disposal of solid hazardous hospital wastes

    International Nuclear Information System (INIS)

    Sebiani Serrano, T.

    2000-01-01

    Medical Waste is characterized by its high risk to human health and the environment. The main risk is biological, due to the large amount of biologically contaminated materials present in such waste. However, this does not mean that the chemical and radioactive wastes are less harmful just because they represent a smaller part of the total waste. Hazardous wastes from hospitals can be divided in 3 main categories: Solid Hazardous Hospital Wastes (S.H.H.W.), Liquid Hazardous Hospital Wastes (L.H.H.W.) and Gaseous Hazardous Hospital Wastes (G.H.H.W.) Most gaseous and liquid hazardous wastes are discharged to the environment without treatment. Since this inappropriate disposal practice, however, is not visible to society, there is no societal reaction to such problem. On the contrary, hazardous solid wastes (S.H.H.W.) are visible to society and create worries in the population. As a result, social and political pressures arise, asking for solutions to the disposal problems of such wastes. In response to such pressures and legislation approved by Costa Rica on waste handling and disposal, the Caja Costarricense de Seguro Social developed a plan for the handling, treatment, and disposal of hazardous solid wastes at the hospitals and clinics of its system. The objective of the program is to reduce the risk to society of such wastes. In this thesis a cost-effectiveness analysis was conducted to determine the minimum cost at which it is possible to reach a maximum level of reduction in hazardous wastes, transferring to the environment the least possible volume of solid hazardous wastes, and therefore, reducing risk to a minimum. It was found that at the National Children's Hospital the internal handling of hazard solid wastes is conducted with a high level of effectiveness. However, once out of the hospital area, the handling is not effective, because hazardous and common wastes are all mixed together creating a larger amount of S.H.H.W. and reducing the final efficiency

  18. Low-Level Burial Grounds Dangerous Waste Permit Application design documents

    International Nuclear Information System (INIS)

    1990-01-01

    This document presents the Functional Design Criteria for trenches to be constructed to receive solid radioactive mixed waste (RMW) from on and offsite generators. The new RMW disposal facilities are considered modifications to or lateral expansion of the existing low-level waste burial grounds. The new facilities upgrade the existing disposal practice for RMW to the minimum technology requirements of the Resource Conservation and Recovery Act. The proposed locations for the two facilities are: 218-E-10 for drag-off-waste packages and, 218-W-4C for non drag-off waste packages

  19. A minimum achievable PV electrical generating cost

    International Nuclear Information System (INIS)

    Sabisky, E.S.

    1996-01-01

    The role and share of photovoltaic (PV) generated electricity in our nation's future energy arsenal is primarily dependent on its future production cost. This paper provides a framework for obtaining a minimum achievable electrical generating cost (a lower bound) for fixed, flat-plate photovoltaic systems. A cost of 2.8 $cent/kWh (1990$) was derived for a plant located in Southwestern USA sunshine using a cost of money of 8%. In addition, a value of 22 $cent/Wp (1990$) was estimated as a minimum module manufacturing cost/price

  20. The Effectivity of Marine Bio-activator and Surimi Liquid Waste Addition of Characteristics Liquid Organic Fertilizer from Sargassum sp.

    Directory of Open Access Journals (Sweden)

    Putri Wening Ratrinia

    2017-02-01

    Full Text Available AbstractOrganic fertilizer is highly recommended for soil and plant because it can improve the productivity and repair physical, chemical, and biological of soil. Sargassum sp. and surimi liquid wastes contain organic matter and nutrient needed by plants and soils. The addition of marine bio-activator which contains bacterial isolates from litter mangrove serves to accelerate the composting time and increases the activity of microorganisms in the decomposition process. The purpose of this study was to determine optimum time and the best formulation of decomposition process organic fertilizer. Raw materials used a waste of seaweed Sargassum sp., marine bio-activator and surimi liquid waste from catfish (Clarias sp.. The research was conducted six treatments control, Sargassum sp. + marine bio-activator, surimi liquid waste , Sargassum sp. + marine bio-activator + surimi liquid waste 80%, 90%, 100%. All treatments were fermented for 9 days and analysed the C-organic, total N, C/N ratio, P2O5, K2O on days 0, 3, 6 and 9. The results showed the optimum fermentation period was on the 6th day. The most optimum concentration of surimi liquid waste added was at a concentration of 90%, with characteristics of the products was C-organic 0.803±0.0115%, total N 740.063±0.0862 ppm, C/N ratio 10.855±0.1562, P2O5 425.603±0.2329 ppm, K2O 2738.627±0.2836 ppm.

  1. The Effectivity of Marine Bio-activator and Surimi Liquid Waste Addition of Characteristics Liquid Organic Fertilizer from Sargassum sp.

    Directory of Open Access Journals (Sweden)

    Putri Wening Ratrinia

    2016-12-01

    Full Text Available Organic fertilizer is highly recommended for soil and plant because it can improve the productivity and repair physical, chemical, and biological of soil. Sargassum sp. and surimi liquid wastes contain organic matter and nutrient needed by plants and soils. The addition of marine bio-activator which contains bacterial isolates from litter mangrove serves to accelerate the composting time and increases the activity of microorganisms in the decomposition process. The purpose of this study was to determine optimum time and the best formulation of decomposition process organic fertilizer. Raw materials used a waste of seaweed Sargassum sp., marine bio-activator and surimi liquid waste from catfish (Clarias sp.. The research was conducted six treatments control, Sargassum sp. + marine bio-activator, surimi liquid waste , Sargassum sp. + marine bio-activator + surimi liquid waste 80%, 90%, 100%. All treatments were fermented for 9 days and analysed the C-organic, total N, C/N ratio, P2 O5 , K2 O on days 0, 3, 6 and 9. The results showed the optimum fermentation period was on the 6th day. The most optimum concentration of surimi liquid waste added was at a concentration of 90%, with characteristics of the products was C-organic 0.803 ± 0.0115 %, total N 740.063 ± 0.0862 ppm, C/N ratio 10.855 ± 0.1562, P2 O5 425.603 ± 0.2329 ppm, K2 O 2738.627 ± 0.2836 ppm.

  2. Waste-to-energy: Dehalogenation of plastic-containing wastes.

    Science.gov (United States)

    Shen, Yafei; Zhao, Rong; Wang, Junfeng; Chen, Xingming; Ge, Xinlei; Chen, Mindong

    2016-03-01

    The dehalogenation measurements could be carried out with the decomposition of plastic wastes simultaneously or successively. This paper reviewed the progresses in dehalogenation followed by thermochemical conversion of plastic-containing wastes for clean energy production. The pre-treatment method of MCT or HTT can eliminate the halogen in plastic wastes. The additives such as alkali-based metal oxides (e.g., CaO, NaOH), iron powders and minerals (e.g., quartz) can work as reaction mediums and accelerators with the objective of enhancing the mechanochemical reaction. The dehalogenation of waste plastics could be achieved by co-grinding with sustainable additives such as bio-wastes (e.g., rice husk), recyclable minerals (e.g., red mud) via MCT for solid fuels production. Interestingly, the solid fuel properties (e.g., particle size) could be significantly improved by HTT in addition with lignocellulosic biomass. Furthermore, the halogenated compounds in downstream thermal process could be eliminated by using catalysts and adsorbents. Most dehalogenation of plastic wastes primarily focuses on the transformation of organic halogen into inorganic halogen in terms of halogen hydrides or salts. The integrated process of MCT or HTT with the catalytic thermal decomposition is a promising way for clean energy production. The low-cost additives (e.g., red mud) used in the pre-treatment by MCT or HTT lead to a considerable synergistic effects including catalytic effect contributing to the follow-up thermal decomposition. Copyright © 2015 Elsevier Ltd. All rights reserved.

  3. Sampling and analysis strategies to support waste form qualification

    International Nuclear Information System (INIS)

    Westsik, J.H. Jr.; Pulsipher, B.A.; Eggett, D.L.; Kuhn, W.L.

    1989-04-01

    As part of the waste acceptance process, waste form producers will be required to (1) demonstrate that their glass waste form will meet minimum specifications, (2) show that the process can be controlled to consistently produce an acceptable waste form, and (3) provide documentation that the waste form produced meets specifications. Key to the success of these endeavors is adequate sampling and chemical and radiochemical analyses of the waste streams from the waste tanks through the process to the final glass product. This paper suggests sampling and analysis strategies for meeting specific statistical objectives of (1) detection of compositions outside specification limits, (2) prediction of final glass product composition, and (3) estimation of composition in process vessels for both reporting and guiding succeeding process steps. 2 refs., 1 fig., 3 tabs

  4. Microstructural analysis of ceramic masses with waste kaolin addition for the red ceramic production

    International Nuclear Information System (INIS)

    Vida, Talita Almeida; Fagury Neto, Elias; Rabelo, Adriano Alves

    2010-01-01

    Incorporating reject industrial ceramic mixtures has proved viable in the reduction of environmental liabilities. In this study, we sought to study the potential use of ceramic formulations with the addition of tailings from the production of kaolin clay to the region of the city of Maraba-PA. Formulations were obtained with two clays of this region with the addition of up to 60% by weight of kaolin waste. The microstructural analyses were carried out from the preparation of specimens that were sintered at 1000 and 1200 °C with level 3 hours. The samples prepared were used to observe the microstructure by optical microscope, to determine the constituents of each formulation after burning. And later analysis was performed X-rays diffraction, to quantify the phases present. It was observed that increasing the content of the mixture of kaolin clay caused the reaction of kaolinite forming the primary mullite from 1000 ° C. For a firing temperature around 1200 ° C showed the presence of mullite even the addition of 20% kaolin, noting also the presence of secondary kaolinite. (author)

  5. Performance of cellulose acetate membrane with different additives for palm oil mill effluent (POME) liquid waste treatment

    Science.gov (United States)

    Aprilia, N. A. S.; Fauzi; Azmi, N.; Najwan, N.; Amin, A.

    2018-03-01

    Performance of cellulose acetate membrane for treatment of POME liquid has studied with different additives. Cellulose acetate membranes were prepared with different additive ie formamide and polyethylene glycol and used acetone as solvent. The function of formamide and polyethylene glycol (PEG) is to increase the porosity of the membrane surface. Performance of the membrane were included SEM, FT-IR and coefficient permeability. Membrane performance has been performed for percent rejection of total suspended solid (TSS) and turbidity of POME liquid waste. Cellulose acetate with formamide shows an increased percentage of rejection in removing TSS and turbidity than cellulose acetate with PEG.

  6. Hazardous waste incinerators under waste uncertainty: balancing and throughput maximization via heat recuperation.

    Science.gov (United States)

    Tsiliyannis, Christos Aristeides

    2013-09-01

    Hazardous waste incinerators (HWIs) differ substantially from thermal power facilities, since instead of maximizing energy production with the minimum amount of fuel, they aim at maximizing throughput. Variations in quantity or composition of received waste loads may significantly diminish HWI throughput (the decisive profit factor), from its nominal design value. A novel formulation of combustion balance is presented, based on linear operators, which isolates the wastefeed vector from the invariant combustion stoichiometry kernel. Explicit expressions for the throughput are obtained, in terms of incinerator temperature, fluegas heat recuperation ratio and design parameters, for an arbitrary number of wastes, based on fundamental principles (mass and enthalpy balances). The impact of waste variations, of recuperation ratio and of furnace temperature is explicitly determined. It is shown that in the presence of waste uncertainty, the throughput may be a decreasing or increasing function of incinerator temperature and recuperation ratio, depending on the sign of a dimensionless parameter related only to the uncertain wastes. The dimensionless parameter is proposed as a sharp a' priori waste 'fingerprint', determining the necessary increase or decrease of manipulated variables (recuperation ratio, excess air, auxiliary fuel feed rate, auxiliary air flow) in order to balance the HWI and maximize throughput under uncertainty in received wastes. A 10-step procedure is proposed for direct application subject to process capacity constraints. The results may be useful for efficient HWI operation and for preparing hazardous waste blends. Copyright © 2013 Elsevier Ltd. All rights reserved.

  7. Does industrial waste taxation contribute to reduction of landfilled waste? Dynamic panel analysis considering industrial waste category in Japan.

    Science.gov (United States)

    Sasao, Toshiaki

    2014-11-01

    Waste taxes, such as landfill and incineration taxes, have emerged as a popular option in developed countries to promote the 3Rs (reduce, reuse, and recycle). However, few studies have examined the effectiveness of waste taxes. In addition, quite a few studies have considered both dynamic relationships among dependent variables and unobserved individual heterogeneity among the jurisdictions. If dependent variables are persistent, omitted variables cause a bias, or common characteristics exist across the jurisdictions that have introduced waste taxes, the standard fixed effects model may lead to biased estimation results and misunderstood causal relationships. In addition, most existing studies have examined waste in terms of total amounts rather than by categories. Even if significant reductions in total waste amounts are not observed, some reduction within each category may, nevertheless, become evident. Therefore, this study analyzes the effects of industrial waste taxation on quantities of waste in landfill in Japan by applying the bias-corrected least-squares dummy variable (LSDVC) estimators; the general method of moments (difference GMM); and the system GMM. In addition, the study investigates effect differences attributable to industrial waste categories and taxation types. This paper shows that industrial waste taxes in Japan have minimal, significant effects on the reduction of final disposal amounts thus far, considering dynamic relationships and waste categories. Copyright © 2014 Elsevier Ltd. All rights reserved.

  8. Recent developments in biochar utilization as an additive in organic solid waste composting: A review.

    Science.gov (United States)

    Xiao, Ran; Awasthi, Mukesh Kumar; Li, Ronghua; Park, Jonghwan; Pensky, Scott M; Wang, Quan; Wang, Jim J; Zhang, Zengqiang

    2017-12-01

    In recent years, considerable studies have been devoted to investigating the effect of biochar application on organic solid waste composting. This review provides an up-to-date overview of biochar amendment on composting processes and compost quality. Biochar production, characteristics, and its application coupled with the basic concepts of composting are briefly introduced before detailing the effects of biochar addition on composting. According to recent studies, biochar has exhibited great potential for enhancing composting. It is evident that biochar addition in composting can: (1) improve compost mixture physicochemical properties, (2) enhance microbial activities and promote organic matter decomposition, (3) reduce ammonia (NH 3 ) and greenhouse gas (GHG) emissions, and (4) upgrade compost quality by increasing the total/available nutrient content, enhancing maturity, and decreasing phytotoxicity. Despite that, further research is needed to explore the mechanism of biochar addition on composting and to evaluate the agricultural and environmental performances of co-composted biochar compost. Copyright © 2017 Elsevier Ltd. All rights reserved.

  9. Aqueous nitrate waste treatment: Technology comparison, cost/benefit, and market analysis

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The purpose of this analysis is to provide information necessary for the Department of Energy (DOE) to evaluate the practical utility of the Nitrate to Ammonia and Ceramic or Glass (NAC/NAG/NAX) process, which is under development in the Oak Ridge National Laboratory. The NAC/NACx/NAX process can convert aqueous radioactive nitrate-laden waste to a glass, ceramic, or grout solid waste form. The tasks include, but are not limited to, the following: Identify current commercial technologies to meet hazardous and radiological waste disposal requirements. The technologies may be thermal or non-thermal but must be all inclusive (i.e., must convert a radionuclide-containing nitrate waste with a pH around 12 to a stable form that can be disposed at permitted facilities); evaluate and compare DOE-sponsored vitrification, grouting, and minimum additive waste stabilization projects for life-cycle costs; compare the technologies above with respect to material costs, capital equipment costs, operating costs, and operating efficiencies. For the NAC/NAG/NAX process, assume aluminum reactant is government furnished and ammonia gas may be marketed; compare the identified technologies with respect to frequency of use within DOE for environmental management applications with appropriate rationale for use; Assess the potential size of the DOE market for the NAC/NAG/NAX process; assess and off-gas issues; and compare with international technologies, including life-cycle estimates.

  10. Aqueous nitrate waste treatment: Technology comparison, cost/benefit, and market analysis

    International Nuclear Information System (INIS)

    1994-01-01

    The purpose of this analysis is to provide information necessary for the Department of Energy (DOE) to evaluate the practical utility of the Nitrate to Ammonia and Ceramic or Glass (NAC/NAG/NAX) process, which is under development in the Oak Ridge National Laboratory. The NAC/NACx/NAX process can convert aqueous radioactive nitrate-laden waste to a glass, ceramic, or grout solid waste form. The tasks include, but are not limited to, the following: Identify current commercial technologies to meet hazardous and radiological waste disposal requirements. The technologies may be thermal or non-thermal but must be all inclusive (i.e., must convert a radionuclide-containing nitrate waste with a pH around 12 to a stable form that can be disposed at permitted facilities); evaluate and compare DOE-sponsored vitrification, grouting, and minimum additive waste stabilization projects for life-cycle costs; compare the technologies above with respect to material costs, capital equipment costs, operating costs, and operating efficiencies. For the NAC/NAG/NAX process, assume aluminum reactant is government furnished and ammonia gas may be marketed; compare the identified technologies with respect to frequency of use within DOE for environmental management applications with appropriate rationale for use; Assess the potential size of the DOE market for the NAC/NAG/NAX process; assess and off-gas issues; and compare with international technologies, including life-cycle estimates

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

    International Nuclear Information System (INIS)

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

    1995-04-01

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

  12. UPGMA and the normalized equidistant minimum evolution problem

    OpenAIRE

    Moulton, Vincent; Spillner, Andreas; Wu, Taoyang

    2017-01-01

    UPGMA (Unweighted Pair Group Method with Arithmetic Mean) is a widely used clustering method. Here we show that UPGMA is a greedy heuristic for the normalized equidistant minimum evolution (NEME) problem, that is, finding a rooted tree that minimizes the minimum evolution score relative to the dissimilarity matrix among all rooted trees with the same leaf-set in which all leaves have the same distance to the root. We prove that the NEME problem is NP-hard. In addition, we present some heurist...

  13. Solving a multi-objective location routing problem for infectious waste disposal using hybrid goal programming and hybrid genetic algorithm

    Directory of Open Access Journals (Sweden)

    Narong Wichapa

    2018-01-01

    Full Text Available Infectious waste disposal remains one of the most serious problems in the medical, social and environmental domains of almost every country. Selection of new suitable locations and finding the optimal set of transport routes for a fleet of vehicles to transport infectious waste material, location routing problem for infectious waste disposal, is one of the major problems in hazardous waste management. Determining locations for infectious waste disposal is a difficult and complex process, because it requires combining both intangible and tangible factors. Additionally, it depends on several criteria and various regulations. This facility location problem for infectious waste disposal is complicated, and it cannot be addressed using any stand-alone technique. Based on a case study, 107 hospitals and 6 candidate municipalities in Upper-Northeastern Thailand, we considered criteria such as infrastructure, geology and social & environmental criteria, evaluating global priority weights using the fuzzy analytical hierarchy process (Fuzzy AHP. After that, a new multi-objective facility location problem model which hybridizes fuzzy AHP and goal programming (GP, namely the HGP model, was tested. Finally, the vehicle routing problem (VRP for a case study was formulated, and it was tested using a hybrid genetic algorithm (HGA which hybridizes the push forward insertion heuristic (PFIH, genetic algorithm (GA and three local searches including 2-opt, insertion-move and interexchange-move. The results show that both the HGP and HGA can lead to select new suitable locations and to find the optimal set of transport routes for vehicles delivering infectious waste material. The novelty of the proposed methodologies, HGP, is the simultaneous combination of relevant factors that are difficult to interpret and cost factors in order to determine new suitable locations, and HGA can be applied to determine the transport routes which provide a minimum number of vehicles

  14. Safe management of radioactive waste in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2000-01-01

    The Ghana Atomic Energy Commission was established in 1963 by an Act of Parliament, Act 204 for the Promotion, Development and Peaceful Application of Nuclear Techniques for the Benefit of Ghana. As in many developing countries the use of nuclear application is growing considerably in importance within the national economy. The Radiation Protection Board was established as the national regulatory authority and empowered by the Radiation Protection Instrument LI 1559 (1993). The above regulations, Act 204 and LI 1559 provided a minimum legal basis for regulatory control of radioactive waste management as it deals with waste management issues in a very general way and is of limited practical use to the waste producer. Hence the National Radioactive Waste Management Centre was established in July 1995 to carry out waste safety operations in Ghana. This paper highlights steps that have been taken to develop a systemic approach for the safe management of radioactive waste in the future and those already in existence. (author)

  15. Effect of addition of organic waste on reduction of Escherichia coli during cattle feces composting under high-moisture condition.

    Science.gov (United States)

    Hanajima, Dai; Kuroda, Kazutaka; Fukumoto, Yasuyuki; Haga, Kiyonori

    2006-09-01

    To ensure Escherichia coli reduction during cattle feces composting, co-composting with a variety of organic wastes was examined. A mixture of dairy cattle feces and shredded rice straw (control) was blended with organic wastes (tofu residue, rice bran, rapeseed meal, dried chicken feces, raw chicken feces, or garbage), and composted using a bench-scale composter under the high-moisture condition (78%). The addition of organic waste except chicken feces brought about maximum temperatures of more than 55 degrees C and significantly reduced the number of E. coli from 10(6) to below 10(2)CFU/g-wet after seven days composting, while in the control treatment, E. coli survived at the same level as that of raw feces. Enhancements of the thermophilic phase and E. coli reduction were related to the initial amount of easily digestible carbon in mass determined as BOD. BOD value more than 166.2 mg O2/DMg brought about significant E. coli reduction.

  16. Other Special Waste

    DEFF Research Database (Denmark)

    Brogaard, Line Kai-Sørensen; Christensen, Thomas Højlund

    2011-01-01

    In addition to the main types of special waste related to municipal solid waste (MSW) mentioned in the previous chapters (health care risk waste, WEEE, impregnated wood, hazardous waste) a range of other fractions of waste have in some countries been defined as special waste that must be handled...... separately from MSW. Some of these other special wastes are briefly described in this chapter with respect to their definition, quantity and composition, and management options. The special wastes mentioned here are batteries, tires, polyvinylchloride (PVC) and food waste....

  17. Old waste products - new requirements. Preparations for the later repository

    International Nuclear Information System (INIS)

    Graf, A.; Merx, H.

    2003-01-01

    For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

  18. Old waste products - new requirements. Preparations for the later repository

    Energy Technology Data Exchange (ETDEWEB)

    Graf, A.; Merx, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Dekontaminationsbetriebe

    2003-07-01

    For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

  19. [Co-composting of high moisture vegetable waste, flower waste and chicken litter in pilot scale].

    Science.gov (United States)

    Zhang, Xiangfeng; Wang, Hongtao; Nie, Yongfeng; Qiu, Xiangyang

    2003-03-01

    Co-composting of different mixture made of vegetable waste, flower waste and chicken litter were studied. The first stage of composting was aerobic static bed based temperature feedback and control via aeration rate regulation. The second stage was window composting. At first stage, the pile was insulated and temperatures of at least 55 degrees C were maintained for a minimum of 3 days. The highest temperature was up to 73.3 degrees C. This is enough to kill pathogens. Moisture of pile decreased from 75% to 56% and organic matter was degraded from 65% to 50% during composting. The value of pH was stable at 8. Analysis of maturity and nutrition of compost showed that end-products of composting ware bio-stable and had abundant nutrition. This shows that co-composting of vegetable waste, flower waste and chicken litter can get high quality compost by optimizing composting process during 45 days. Composting can decrease nonpoint resource of organic solid waste by recycling nutrition to soil and improve fertility of soil.

  20. DOE's performance evaluation project for mixed low-level waste disposal

    International Nuclear Information System (INIS)

    Waters, R.D.; Chu, M.S.Y.; Gruebel, M.M.; Lee, D.W.

    1995-01-01

    A performance evaluation (PE) is an analysis that estimates radionuclide concentration limits for 16 potential Department of Energy (DOE) mixed low-level waste (ULLW) disposal sites based on the analysis of two environmental exposure pathways (air and water) to an off-site individual and an inadvertent-intruder exposure pathway. Sites are analyzed for their ability to attenuate concentrations of specific radionuclides that could be released from wastes in a hypothetical ULLW disposal facility. Site-specific data and knowledge are used within a generic framework that is consistent across all sites being evaluated. After estimates of waste concentrations for the three pathways are calculated, the minimum of the waste concentration values is selected as the permissible waste concentration for each radionuclide. The PE results will be used as input to the process for DOE's ULLW disposal configuration. Preliminary comparisons of results from the PE and site-specific performance assessments indicate that the simple PE results generally agree with results of the performance assessments, even when site conditions are complex. This agreement with performance-assessment results increases confidence that similar results can be obtained at other sites that have good characterization data. In addition, the simple analyses contained in the PE illustrate a potential method to satisfy the needs of many regulators and the general public for a simple, conservative, defensible, and easily understandable analysis that provides results similar to those of more complex analyses

  1. Acceptable knowledge document for INEEL stored transuranic waste - Rocky Flats Plant waste. Revision 2

    International Nuclear Information System (INIS)

    1998-01-01

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems

  2. Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-23

    This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

  3. Laboratory Waste Disposal Manual. Revised Edition.

    Science.gov (United States)

    Stephenson, F. G., Ed.

    This manual is designed to provide laboratory personnel with information about chemical hazards and ways of disposing of chemical wastes with minimum contamination of the environment. The manual contains a reference chart section which has alphabetical listings of some 1200 chemical substances with information on the health, fire and reactivity…

  4. Copper (II) addition to accelerate lactic acid production from co-fermentation of food waste and waste activated sludge: Understanding of the corresponding metabolisms, microbial community and predictive functional profiling.

    Science.gov (United States)

    Ye, Tingting; Li, Xiang; Zhang, Ting; Su, Yinglong; Zhang, Wenjuan; Li, Jun; Gan, Yanfei; Zhang, Ai; Liu, Yanan; Xue, Gang

    2018-03-20

    Bio-refinery of food waste and waste activated sludge to high value-added chemicals, such as lactic acid, has attracted particular interest in recent years. In this paper, the effect of copper (II) dosing to the organic waste fermentation system on lactic acid production was evaluated, which proved to be a promising method to stimulate high yield of lactic acid (77.0% higher than blank) at dosage of 15 μM-Cu 2+ /g VSS. As mechanism study suggested, copper addition enhanced the activity of α-glycosidase and glycolysis, which increased the substrate for subsequent acidification; whereas, the high dosage (70 μM-Cu 2+ /g VSS) inhibited the conversion of lactic acid to VFA, thus stabilized lactic acid concentration. Microbial community study revealed that small amount of copper (II) at 15 μM/g VSS resulted in the proliferation of Lactobacillus to 82.6%, which mainly produced lactic acid. Finally, the variation of functional capabilities implied that the proposed homeostatic system II was activated at relatively low concentration of copper. Meanwhile, membrane transport function and carbohydrate metabolism were also strengthened. This study provides insights into the effect of copper (II) on the enhancement of lactic acid production from co-fermentation of food waste and waste activated sludge. Copyright © 2018 Elsevier Ltd. All rights reserved.

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

    International Nuclear Information System (INIS)

    Buelt, J.L.

    1985-08-01

    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 3 waste, whereas quoted costs for cementation and disposal from reactor operators range from $155 to $350/ft 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

  6. Delayed addition of nitrogen-rich substrates during composting of municipal waste: Effects on nitrogen loss, greenhouse gas emissions and compost stability.

    Science.gov (United States)

    Nigussie, Abebe; Bruun, Sander; Kuyper, Thomas W; de Neergaard, Andreas

    2017-01-01

    Municipal waste is usually composted with an N-rich substrate, such as manure, to increase the N content of the product. This means that a significant amount of nitrogen can be lost during composting. The objectives of this study were (i) to investigate the effect of split addition of a nitrogen-rich substrate (poultry manure) on nitrogen losses and greenhouse gas emissions during composting and to link this effect to different bulking agents (coffee husks and sawdust), and (ii) to assess the effect of split addition of a nitrogen-rich substrate on compost stability and sanitisation. The results showed that split addition of the nitrogen-rich substrate reduced nitrogen losses by 9% when sawdust was used and 20% when coffee husks were used as the bulking agent. Depending on the bulking agent used, split addition increased cumulative N 2 O emissions by 400-600% compared to single addition. In contrast, single addition increased methane emissions by up to 50% compared to split addition of the substrate. Hence, the timing of the addition of the N-rich substrate had only a marginal effect on total non-CO 2 greenhouse gas emissions. Split addition of the N-rich substrate resulted in compost that was just as stable and effective at completely eradicating weed seeds as single addition. These findings therefore show that split addition of a nitrogen-rich substrate could be an option for increasing the fertilising value of municipal waste compost without having a significant effect on total greenhouse gas emissions or compost stability. Copyright © 2016 Elsevier Ltd. All rights reserved.

  7. Stabilization of inorganic mixed waste to pass the TCLP and STLC tests using clay and pH-insensitive additives

    Energy Technology Data Exchange (ETDEWEB)

    Bowers, J.S.; Anson, J.R.; Painter, S.M. [Lawrence Livermore National Lab., CA (United States)] [and others

    1995-12-31

    Stabilization is a best demonstrated available technology, or BDAT. This technology traps toxic contaminants in a matrix so that they do not leach into the environment. The stabilization process routinely uses pozzolanic materials. Portland cement, fly ash-lime mixes, gypsum cements, and clays are some of the most common materials. In many instances, materials that can pass the Toxicity Characteristic Leaching Procedure (TCLP the federal leach test) or the Soluble Threshold Leachate Concentration (STLC the California leach test) must have high concentrations of lime or other caustic material because of the low pH of the leaching media. Both leaching media, California`s and EPA`s, have a pH of 5.0. California uses citric acid and sodium citrate while EPA uses acetic acid and sodium acetate. The concentration in the leachate is approximately ten times higher for the STLC procedure than the TCLP. These media can form ligands that provide excellent metal leaching. Because of the aggressive nature of the leaching medium, stabilized wastes in many cases will not pass the leaching tests. At the Lawrence Livermore National Laboratory (LLNL), additives such as dithiocarbamates and thiocarbonates, which are pH-insensitive and provide resistance to ligand formation, are used in the waste stabilization process. Attapulgite, montmorillonite, and sepiolite clays are used because they are forgiving (recipe can be adjusted before the matrix hardens) when formulating a stabilization matrix, and they have a neutral pH. By using these clays and additives, LLNL`s highly concentrated wastewater treatment sludges have passed the TCLP and STLC tests. The most frequently used stabilization process consists of a customized recipe involving waste sludge, clay and dithiocarbamate salt, mixed with a double planetary mixer into a pasty consistency. TCLP and STLC data on this waste matrix have shown that the process matrix meets land disposal requirements.

  8. Effects of additives on the co-pyrolysis of municipal solid waste and paper sludge by using thermogravimetric analysis.

    Science.gov (United States)

    Fang, Shiwen; Yu, Zhaosheng; Lin, Yan; Lin, Yousheng; Fan, Yunlong; Liao, Yanfen; Ma, Xiaoqian

    2016-06-01

    By using thermogravimetric analysis (TGA), the effects of different additives (MgO, Al2O3 and ZnO) on the pyrolysis characteristics and activation energy of municipal solid waste (MSW), paper sludge (PS) and their blends in N2 atmosphere had been investigated in this study. The experiments resulted that these additives were effective in reducing the initial temperature and activation energy. However, not all the additives were beneficial to reduce the residue mass and enhance the index D. For the different ratios of MSW and PS, the same additive even had the different influences. The catalytic effects of additives were not obvious and the pyrolysis became difficult with the increase of the proportion of PS. Based on all the contrast of the pyrolysis characteristics, MgO was the best additive and 70M30P was the best ratio, respectively. Copyright © 2016 Elsevier Ltd. All rights reserved.

  9. Post treatment of high-level nuclear fuel wastes

    International Nuclear Information System (INIS)

    Berreth, J.R.; Cole, H.S.; Hoskins, A.P.; Lewis, L.C.; Samsel, E.G.

    1975-01-01

    The glass-ceramic product prepared from fluidized-bed calcined synthetic commercial wastes, based on data obtained to date, has many of the properties desired for long-term storage. Although more characterization is necessitated, the product's high-calcine content will decrease the number of storage canisters required and use a minimum of product-forming additives, resulting in significant process cost savings. The product remains in a solid, nonflowing form at temperatures close to the preparation temperature and yet is prepared at relatively low temperatures. The product has void spaces to accommodate radiolytic gas formation, but is hard and dense and has very low leach rates. Process features, such as no direct product contact with furnace or storage canisters, will minimize corrosion of both process equipment and storage canisters

  10. Minimization of municipal solid waste transportation route in West Jakarta using Tabu Search method

    Science.gov (United States)

    Chaerul, M.; Mulananda, A. M.

    2018-04-01

    Indonesia still adopts the concept of collect-haul-dispose for municipal solid waste handling and it leads to the queue of the waste trucks at final disposal site (TPA). The study aims to minimize the total distance of waste transportation system by applying a Transshipment model. In this case, analogous of transshipment point is a compaction facility (SPA). Small capacity of trucks collects the waste from waste temporary collection points (TPS) to the compaction facility which located near the waste generator. After compacted, the waste is transported using big capacity of trucks to the final disposal site which is located far away from city. Problem related with the waste transportation can be solved using Vehicle Routing Problem (VRP). In this study, the shortest distance of route from truck pool to TPS, TPS to SPA, and SPA to TPA was determined by using meta-heuristic methods, namely Tabu Search 2 Phases. TPS studied is the container type with total 43 units throughout the West Jakarta City with 38 units of Armroll truck with capacity of 10 m3 each. The result determines the assignment of each truck from the pool to the selected TPS, SPA and TPA with the total minimum distance of 2,675.3 KM. The minimum distance causing the total cost for waste transportation to be spent by the government also becomes minimal.

  11. Minimum K_2,3-saturated Graphs

    OpenAIRE

    Chen, Ya-Chen

    2010-01-01

    A graph is K_{2,3}-saturated if it has no subgraph isomorphic to K_{2,3}, but does contain a K_{2,3} after the addition of any new edge. We prove that the minimum number of edges in a K_{2,3}-saturated graph on n >= 5 vertices is sat(n, K_{2,3}) = 2n - 3.

  12. Overview of management programs for plutonium-contaminated solid waste in the U.S.A

    International Nuclear Information System (INIS)

    Ramsey, R.W. Jr.; Daly, G.H.

    1975-01-01

    Programs for transuranium-contaminated solid wastes (TRU) in the U.S.A. are emphasizing a reduction in waste generation and the development of appropriate treatments to reduce the volume of wastes requiring interim storage and final disposal. Research and Development is emphasizing the establishment of sufficient information on treatment, hazards and storage to adopt a standardized procedure for handling wastes during an interim retrievable period and for final disposal. Federal responsibility for TRU waste is being proposed except for minimum amounts acceptable for commercial burial

  13. Enhanced Fuzzy-OWA model for municipal solid waste landfill site selection

    Science.gov (United States)

    Ahmad, Siti Zubaidah; Ahamad, Mohd Sanusi S.; Yusoff, Mohd Suffian; Abujayyab, Sohaib K. M.

    2017-10-01

    In Malaysia, the municipal solid waste landfill site is an essential facility that needs to be evaluated as its demand is infrequently getting higher. The increment of waste generation forces the government to cater the appropriate site for waste disposal. However, the selection process for new landfill sites is a difficult task with regard to land scarcity and time consumption. In addition, the complication will proliferate when there are various criteria to be considered. Therefore, this paper intends to show the significance of the fuzzy logic-ordered weighted average (Fuzzy-OWA) model for the landfill site suitability analysis. The model was developed to generalize the multi-criteria combination that was extended to the GIS applications as part of the decision support module. OWA has the capability to implement different combination operators through the selection of appropriate order weight that is possible in changing the form of aggregation such as minimum, intermediate and maximum types of combination. OWA give six forms of aggregation results that have their specific significance that indirectly evaluates the environmental, physical and socio-economic (EPSE) criteria respectively. Nevertheless, one of the aggregated results has shown similarity with the weighted linear combination (WLC) method.

  14. Great expectations: Reservation wages and the minimum wage reform

    OpenAIRE

    Fedorets, Alexandra; Filatov, Alexey; Shupe, Cortnie

    2018-01-01

    We use the German Socio-Economic Panel to show that introducing a high-impact statutory minimum wage causes an increase in reservation wages of approximately 4 percent at the low end of the distribution. The shifts in reservation wages and observed wages due to the minimum wage reform are comparable in their magnitude. Additional results show that German citizens adjust their reservation wages more than immigrants. Moreover, suggestive evidence points to a compensation mechanism in which immi...

  15. Effect of addition of sewage sludge and coal sludge on bioavailability of selected metals in the waste from the zinc and lead industry.

    Science.gov (United States)

    Sobik-Szołtysek, Jolanta; Wystalska, Katarzyna; Grobelak, Anna

    2017-07-01

    This study evaluated the content of bioavailable forms of selected heavy metals present in the waste from Zn and Pb processing that can potentially have an effect on the observed difficulties in reclamation of landfills with this waste. The particular focus of the study was on iron because its potential excess or deficiency may be one of the causes of the failure in biological reclamation. The study confirmed that despite high content of total iron in waste (mean value of 200.975gkg -1 ), this metal is present in the forms not available to plants (mean: 0.00009gkg -1 ). The study attempted to increase its potential bioavailability through preparation of the mixtures of this waste with additions in the form of sewage sludge and coal sludge in different proportions. Combination of waste with 10% of coal sludge and sewage sludge using the contents of 10%, 20% and 30% increased the amounts of bioavailable iron forms to the level defined as sufficient for adequate plant growth. The Lepidum sativum test was used to evaluate phytotoxicity of waste and the mixtures prepared based on this waste. The results did not show unambiguously that the presence of heavy metals in the waste had a negative effect on the growth of test plant roots. Copyright © 2017 Elsevier Inc. All rights reserved.

  16. The Constitution, waste facility performance standards, and radioactive waste classification: Is equal protection possible?

    Energy Technology Data Exchange (ETDEWEB)

    Eye, R.V. [Kansas Dept. of Health and Environment, Topeka, KS (United States)

    1993-03-01

    The process for disposal of so-called low-level radioactive waste is deadlocked at present. Supporters of the proposed near-surface facilities assert that their designs will meet minimum legal and regulatory standards currently in effect. Among opponents there is an overarching concern that the proposed waste management facilities will not isolate radiation from the biosphere for an adequate length of time. This clash between legal acceptability and a perceived need to protect the environment and public health by requiring more than the law demand sis one of the underlying reasons why the process is deadlocked. Perhaps the most exhaustive public hearing yet conducted on low-level radioactive waste management has recently concluded in Illinois. The Illinois Low-Level Radioactive Waste Disposal Facility Sitting Commission conducted 71 days of fact-finding hearings on the safety and suitability of a site near Martinsville, Illinois, to serve as a location for disposition of low-level radioactive waste. Ultimately, the siting commission rejected the proposed facility site for several reasons. However, almost all the reasons were related, to the prospect that, as currently conceived, the concrete barrier/shallow-land burial method will not isolate radioactive waste from the biosphere. This paper reviews the relevant legal framework of the radioactive waste classification system and will argue that it is inadequate for long-lived radionuclides. Next, the paper will present a case for altering the classification system based on high-level waste regulatory considerations.

  17. Residual Sorption and leaching of the herbicide diuron following de-oiled two-phase olive mill waste addition to soil

    Energy Technology Data Exchange (ETDEWEB)

    Lopez-Pineiro, A.; Albarran, A.; Cabrera, D.; Rato, J. M.; Munoz, A.; Flores, S.

    2009-07-01

    The residual sorption, desorption, degradation, and leaching of the herbicide diuron (3-(3,4-dichlorophenyl)-1,1-dimethylurea) a herbicide widely used in olive groves, was studied following the addition to soils of de oiled two-phase olive mill waste (DTPOMW). Field experiments were conducted on an olive grove soil amended over seven years with DTPOMW. (Author)

  18. Residual Sorption and leaching of the herbicide diuron following de-oiled two-phase olive mill waste addition to soil

    International Nuclear Information System (INIS)

    Lopez-Pineiro, A.; Albarran, A.; Cabrera, D.; Rato, J. M.; Munoz, A.; Flores, S.

    2009-01-01

    The residual sorption, desorption, degradation, and leaching of the herbicide diuron (3-(3,4-dichlorophenyl)-1,1-dimethylurea) a herbicide widely used in olive groves, was studied following the addition to soils of de oiled two-phase olive mill waste (DTPOMW). Field experiments were conducted on an olive grove soil amended over seven years with DTPOMW. (Author)

  19. Mixed waste and waste minimization: The effect of regulations and waste minimization on the laboratory

    International Nuclear Information System (INIS)

    Dagan, E.B.; Selby, K.B.

    1993-08-01

    The Hanford Site is located in the State of Washington and is subject to state and federal environmental regulations that hamper waste minimization efforts. This paper addresses the negative effect of these regulations on waste minimization and mixed waste issues related to the Hanford Site. Also, issues are addressed concerning the regulations becoming more lenient. In addition to field operations, the Hanford Site is home to the Pacific Northwest Laboratory which has many ongoing waste minimization activities of particular interest to laboratories

  20. Solid waste management - Pakistan's perspective

    International Nuclear Information System (INIS)

    Hussain, M.

    2003-01-01

    The discipline of 'Solid Waste Management' is as old as human civilization itself. The problem had been felt when the human beings commenced living together in the form of communities. The situation got worsened with ever-increasing population and growing industrialization. The developed nations have endeavored to tackle the issue of the industrial and municipal wastes according to the principles of engineering and environment. Most of the developing countries have not dealt with the 'Third Pollution' in the eco-friendly manner. Ironically Pakistan is facing this serious menace because of ever-expanding population (2.2% per annum) and ill management of the wastes and effluents being generated from multifarious activities. These pollutants are degrading the land, air and water resources at alarming rates. In Pakistan about 7,250 tonnes of solid waste is generated per day. Of this quantity only 60-70% is collected and the remaining quantity is allowed to burn indiscriminately or decay in situ. Unfortunately the industrial waste, animal dung and hospital waste are allowed to mix with the municipal waste, which adds to inefficiency of the existing 'Solid Waste Management System'. Scores of faecal, fly, rodent and mosquito born diseases are caused due to open dumping of the waste besides aesthetic impairment of the surroundings. None of the scientifically recognized methods of disposal is practiced. It is not based on administrative, financial, environmental and technical consideration. There is dire necessity of educating the masses to adopt clean habits and resort to generation of minimum waste. Further, nothing is waste as the so-called 'waste material' is the raw material after reuse and recycling for another process. (author)

  1. Impact of Strontium Nitrate and Sodium Permanganate Addition on Solid-Liquid Separation of SRS High Level Waste

    International Nuclear Information System (INIS)

    Poirier, M.R.

    2002-01-01

    As a pretreatment step for the caustic side solvent extraction (CSSX) flowsheet, the process contacts the incoming salt solution containing entrained sludge with monosodium titanate (MST) to adsorb strontium and actinides. An operation filters the resulting slurry to remove the sludge and MST. Previous work for the River Protection Program at Hanford suggests that addition of strontium nitrate and sodium permanganate for strontium and actinide removal, rather than MST, improves the filtration rate for comparable waste streams

  2. MINIMUM ENTROPY DECONVOLUTION OF ONE-AND MULTI-DIMENSIONAL NON-GAUSSIAN LINEAR RANDOM PROCESSES

    Institute of Scientific and Technical Information of China (English)

    程乾生

    1990-01-01

    The minimum entropy deconvolution is considered as one of the methods for decomposing non-Gaussian linear processes. The concept of peakedness of a system response sequence is presented and its properties are studied. With the aid of the peakedness, the convergence theory of the minimum entropy deconvolution is established. The problem of the minimum entropy deconvolution of multi-dimensional non-Gaussian linear random processes is first investigated and the corresponding theory is given. In addition, the relation between the minimum entropy deconvolution and parameter method is discussed.

  3. Defense Waste Processing Facility (DWPF): The vitrification of high-level nuclear waste. (Latest citations from the Bibliographic database). Published Search

    International Nuclear Information System (INIS)

    1993-09-01

    The bibliography contains citations concerning a production-scale facility and the world's largest plant for the vitrification of high-level radioactive nuclear wastes (HLW) located in the United States. Initially based on the selection of borosilicate glass as the reference waste form, the citations present the history of the development including R ampersand D projects and the actual construction of the production facility at the DOE Savannah River Plant (SRP). (Contains a minimum of 177 citations and includes a subject term index and title list.)

  4. Residential Waste

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund; Fruergaard, Thilde; Matsufuji, Y.

    2011-01-01

    are discussed in this chapter. Characterizing residential waste is faced with the problem that many residences already divert some waste away from the official collection systems, for example performing home composting of vegetable waste and garden waste, having their bundled newspaper picked up by the scouts...... twice a year or bringing their used furniture to the flea markets organized by charity clubs. Thus, much of the data available on residential waste represents collected waste and not necessarily all generated waste. The latter can only be characterized by careful studies directly at the source......, but such studies are very expensive if fair representation of both spatial and temporal variations should be obtained. In addition, onsite studies may affect the waste generation in the residence because of the increased focus on the issue. Residential waste is defined in different ways in different countries...

  5. Disposal options for radioactive waste

    International Nuclear Information System (INIS)

    Olivier, J.P.

    1991-01-01

    On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

  6. Nuclear waste solidification

    Science.gov (United States)

    Bjorklund, William J.

    1977-01-01

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

  7. Nuclear waste solidification

    International Nuclear Information System (INIS)

    Bjorklund, W.J.

    1977-01-01

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

  8. Nuclear waste disposal: two social criteria

    International Nuclear Information System (INIS)

    Rochlin, G.I.

    1977-01-01

    Two criteria--technical irreversibility and site multiplicity--have been suggested for use in establishing standards for the disposal of nuclear wastes. They have been constructed specifically to address the reduction of future risk in the face of inherent uncertainty concerning the social and political developments that might occur over the required periods of waste isolation, to provide for safe disposal without the requirement of a guaranteed future ability to recognize, detect, or repair errors and failures. Decisions as to how to apply or weigh these criteria in conjunction with other waste management goals must be made by societies and their governments. The purpose of this paper was not to preempt this process, but to construct a framework that facilitates consideration of the ethical and normative components of the problem of nuclear waste disposal. The minimum ethical obligation of a waste disposal plan is to examine most thoroughly the potential consequences of present actions, to acknowledge them openly, and to minimize the potential for irremediable harm. An ethically sound waste management policy must reflect not only our knowledge and skills, but our limitations as well

  9. Composite Gypsum Binders with Silica-containing Additives

    Science.gov (United States)

    Chernysheva, N. V.; Lesovik, V. S.; Drebezgova, M. Yu; Shatalova, S. V.; Alaskhanov, A. H.

    2018-03-01

    New types of fine mineral additives are proposed for designing water-resistant Composite Gypsum Binders (CGB); these additives significantly differ from traditional quartz feed: wastes from wet magnetic separation of Banded Iron Formation (BIF WMS waste), nanodispersed silica powder (NSP), chalk. Possibility of their combined use has been studied as well.

  10. Waste fatty acid addition to black liquor to decrease tall oil soap solubility and increase skimming efficiency in kraft mills pulping mountain pine beetle-infested wood

    Energy Technology Data Exchange (ETDEWEB)

    Uloth, V.; Guy, E. [FPInnovations, Prince George, BC (Canada). PAPRICAN Div.; Shewchuk, D. [Cariboo Pulp and Paper, Quesnel, BC (Canada); Van Heek, R. [Aker Kvaerner, Vancouver, BC (Canada)

    2009-07-01

    This paper presented the results of tests conducted to determine if the addition of waste fatty acids from vegetable oil processing might decrease tall oil soap solubility in pine-beetle impacted wood from British Columbia (BC). The soap recovery and tall oil production at BC mills has fallen by 30 to 40 percent in recent years due to the pulping of high proportions of grey-stage beetle-impacted wood. Full-scale mill tests were conducted over a 4-day period. The study showed that the addition of tall oil fatty acids or waste fatty acids from vegetable oil processing could decrease tall oil soap solubility and increase the soup skimming efficiency in mills pulping a large percentage of grey stage beetle-infested wood. The addition of fatty acids increased tall oil soap skimming efficiency from 50.2 percent in the baseline tests to 71.8 percent based on the total soap available, and from 76.7 percent in the baseline tests to 87.5 percent based on insoluble soap only. The economic analyses indicated that waste fatty acid addition could be economical when natural gas and oil prices are high. 4 tabs., 9 figs.

  11. Waste-to-Energy Plant Environmental Assessment, Dyess Air Force Base, Texas

    Science.gov (United States)

    2011-09-01

    Integrated Material Management Plan IWMP Integrated Waste Management Plan MACT Maximum Achievable Control Technology MRL Minimum Risk Level MRR...Education, Cerro Coso College, CA, 1994 Years of Experience: 15 Kevin J. Peter, Program Manager B.A., Anthropology, Pomona College, CA, 1975 M.A...hazardous wastes would occur with selection of any proposed action alternative. Under the no-action alternative, existing procedures for the management

  12. Boiling water reactor liquid radioactive waste processing system

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    The standard sets forth minimum design, construction and performance requirements with due consideration for operation of the liquid radioactive waste processing system for boiling water reactor plants for routine operation including design basis fuel leakage and design basis occurrences. For the purpose of this standard, the liquid radioactive waste processing system begins at the interfaces with the reactor coolant pressure boundary, at the interface valve(s) in lines from other systems and at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material. The system terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system and at the point of recycle back to storage for reuse. The standard does not include the reactor coolant clean-up system, fuel pool clean-up system, sanitary waste system, any nonaqueous liquid system or controlled area storm drains

  13. Role of biochar as an additive in organic waste composting

    NARCIS (Netherlands)

    Sánchez-Monedero, M.A.; Cayuela, M.L.; Roig, A.; Jindo, Keiji; Mondini, C.; Bolan, N.S.

    2018-01-01

    The use of biochar in organic waste composting has attracted interest in the last decade due to the environmental and agronomical benefits obtained during the process. Biochar presents favourable physicochemical properties, such as large porosity, surface area and high cation exchange capacity,

  14. Comparative analysis of compressive strength tests at age of 28 and 90 days and density of products using chemical additives in cementing radioactive waste

    International Nuclear Information System (INIS)

    Vieira, Vanessa Mota; Tello, Cledola Cassia Oliveira de

    2013-01-01

    In this research it has been studied the effects of chemical additives (admixtures) in the cementation process of radioactive wastes, which are used to improve the properties of waste cementation process, both of the paste and of the solidified product. However there are a large variety of these materials that are frequently changed or taken out of the market, then it is essential to know the commercially available materials and their effects. The tests were carried out with a solution simulating the evaporator concentrate waste coming from PWR nuclear reactors. It was cemented using two formulations, A and B, incorporating higher or lower amount of waste, respectively. It was added chemical admixtures from two manufacturers (S and H), which were: accelerators, set retarders and superplasticizers. The experiments were organized by a factorial design 2 3 . The measured parameters were the viscosity, the setting time, the paste and product density and the compressive strength. In this study we performed comparative analyzes of the results of compressive strength at age of 28 and 90 days and between the densities of the samples at the same ages.The compressive strength test at age of 28 days is considered a parameter essential issues related to security handling, transport and storage of cemented waste product. The results showed that the addition of accelerators improved the compressive strength of the cemented product, but presented lower values density products. (author)

  15. Economic and ecologic considerations for bidding procedures and contracting for bio-waste fermentation plants

    International Nuclear Information System (INIS)

    Raussen, Thomas; Lootsma, Auke; Oldhafer, Nils

    2013-01-01

    The use of the energetic and mass potentials of biological wastes in an integrated fermentation and composting plant needs extensive conceptual and planning activities. The call for tenders for the construction of plants is an EU-wide open procedure. Public waste management organizations are interested to receive profitable solutions with reliable operation and minimized ecological impacts. The minimum requirements and technical aspects are defined by the public waste management organizations.

  16. THE USE OF POULTRY SLAUGHTERHOUSE WASTE TO PRODUCE COMPOST

    Directory of Open Access Journals (Sweden)

    Michał Kopeć

    2014-10-01

    Full Text Available Poultry industry generates large amounts of waste, which in the biological treatment process creates a number of problems. One of them is a high amount of fat and creatine which is hard to decompose. Composting process was carried out with the waste from poultry farms and abattoirs mixed with maize straw, which was used to improve the structure and to increase the amount of carbon in the substrate. The chemical composition of composts from poultry waste involving maize straw meets the minimum requirements for organic fertilizers. It seems that recycling of organic waste from the poultry industry should be the primary method of nutrient recovery for plants and organic matter contained in them, however on condition that the health safety is preserved.

  17. Prospective framework for collection and exploitation of waste cooking oil as feedstock for energy conversion

    International Nuclear Information System (INIS)

    Singhabhandhu, Ampaitepin; Tezuka, Tetsuo

    2010-01-01

    From the viewpoint of waste-to-energy, waste cooking oil is one of the attractive and available recycled feedstocks, apart from agricultural residues. The generation of energy from waste cooking oil is considered as an effective technique for waste management, as well as a beneficial form of energy recovery. Two alternative systems and a conventional system of waste cooking oil collection and conversion are evaluated by the cost benefit analysis in order to find a suitable method for waste-to-energy conversion. The results show that the collection of waste cooking oil with waste lubricating oil (System II) a useful alternative to the management of waste cooking oil (B/C > 1). The total heat produced by the combustion of pyrolytic oil at maximum and minimum conversion rates is also determined. The separate collection of waste cooking oil, subjected to chemical pre-treatment prior to introduction in a pyrolysis reactor (System III), is considered an undesirable option (B/C < 1) due to the cost of the chemicals involved. Although the exclusion of chemical pre-treatment makes System III a desirable option, the total amount of heat of combustion generated is less. The increased electricity cost required for the process has no effect on the benefit-cost ratio of System II. However, System III, excluding chemical pre-treatment, becomes an unprofitable alternative when the electricity cost reaches 100% of the fixed capital cost at the minimum conversion rate.

  18. The characterization of cement waste form for final disposal of decommissioned concrete waste

    International Nuclear Information System (INIS)

    Lee, K.W.; Lee, Y.J.; Hwang, D.S.; Moon, J.K.

    2015-01-01

    Since the decommissioning of nuclear plants and facilities, large quantities of slightly contaminated concrete waste have been generated. In Korea, the decontamination and decommissioning of the KRR-1, 2 at the KAERI have been under way. In addition, 83 drums of 200 l, and 41 containers of 4 m 3 of concrete waste were generated. Conditioning of concrete waste is needed for final disposal. Concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled into a void space after concrete rubble pre-placement into 200 l drums. Thus, this research developed an optimizing mixing ratio of concrete waste, water, and cement, and evaluated the characteristics of a cement waste form to meet the requirements specified in the disposal site specific waste acceptance criteria. The results obtained from compressive strength test, leaching test, and thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested to have 75:15:10 as the optimized mixing ratio. In addition, the compressive strength of cement waste form was satisfied, including fine powder up to a maximum 40 wt% in concrete debris waste of about 75%. (authors)

  19. 40 CFR 761.75 - Chemical waste landfills.

    Science.gov (United States)

    2010-07-01

    ... than 1×10−7; (iii) Percent soil passing No. 200 Sieve, >30; (iv) Liquid Limit, >30; and (v) Plasticity... volume of liquid initially contained in the well before obtaining a sample for analysis. The discharge... waste landfill. (iii) Water analysis. As a minimum, all samples shall be analyzed for the following...

  20. Characterization of cement and bitumen waste forms containing simulated low-level waste incinerator ash

    International Nuclear Information System (INIS)

    Westsik, J.H. Jr.

    1984-08-01

    Incinerator ash from the combustion of general trash and ion exchange resins was immobilized in cement and bitumen. Tests were conducted on the resulting waste forms to provide a data base for the acceptability of actual low-level waste forms. The testing was done in accordance with the US Nuclear Regulatory Commission Technical Position on Waste Form. Bitumen had a measured compressive strength of 130 psi and a leachability index of 13 as measured with the ANS 16.1 leach test procedure. Cement demonstrated a compressive strength of 1400 psi and a leachability index of 7. Both waste forms easily exceed the minimum compressive strength of 50 psi and leachability index of 6 specified in the Technical Position. Irradiation to 10 8 Rad and exposure to 31 thermal cycles ranging from +60 0 ) to -30 0 C did not significantly impact these properties. Neither waste form supported bacterial or fungal growth as measured with ASTM G21 and G22 procedures. However, there is some indication of biodegradation due to co-metabolic processes. Concentration of organic complexants in leachates of the ash, cement and bitumen were too low to significantly affect the release of radionuclides from the waste forms. Neither bitumen nor cement containing incinerator ash caused any corrosion or degradation of potential container materials including steel, polyethylene and fiberglass. However, moist ash did cause corrosion of the steel

  1. Laboratory experience in the analysis of orphan waste

    International Nuclear Information System (INIS)

    Leventhal, L.; Kharkar, D.P.

    1986-01-01

    Energy related low level radioactive waste mixed with inorganic and organic hazardous waste derive from all stages of the fuel cycle. In order to comply with EPA and NRC regulations, prior to disposal this waste must be analyzed. For the analytical laboratory, the samples comprise both a potential radiation and chemical hazard. Screening procedures for handling such samples are described. Sophisticated instrumentation is necessary to identify the contaminants with the sensitivity required by the EPA and NRC. Aliquotting and dilution techniques have been adequate to reduce the activity levels sufficiently to allow operations in an uncontrolled laboratory and meet the minimum detection levels. Higher level samples are analyzed in a controlled area employing dedicated instrumentation and health physics precautions

  2. An Evaluation of Recent Evidence on the Employment Effects of Minimum and Subminimum Wages

    OpenAIRE

    David Card; Lawrence F. Katz; Alan B. Krueger

    1993-01-01

    We re-examine recent cross-state evidence on the employment effect of the minimum wage. A re-evaluation of the data used in Neumark and Wascher's (1992) study of the minimum wage provides no support for their conclusion that the minimum wage has an adverse effect on teenage employment. Neumark and Wascher's findings are shown to be due to an inadvertent mistake in the definition of their school enrollment variable. In addition, Neumark and Wascher's coverage-weighted relative minimum wage ind...

  3. Induction melting of simulated transuranic waste

    International Nuclear Information System (INIS)

    Tenaglia, R.D.; McCall, J.L.

    1983-06-01

    Coreless induction melting was investigated as a method to melt and consolidate waste material representative of the transuranic waste (TRU) stored at the Idaho National Engineering Laboratory (INEL). Waste material was introduced onto the surface of a molten cast iron bath in a coreless induction furnace. Waste metallics were incorporated into the bath. Noncombustibles formed a slag which was poured or skimmed from the bath surface. Stack sampling was performed to characterize the off-gas and particulate matter evolved. Experimental melting tests were performed for a variety of types of wastes including metallics, chemical sludge, soil, concrete, and glass. Each test also included a representative level of combustible materials consisting of paper, wood, cloth, polyvinyl chloride and polyethylene. Metallic wastes were readily processed by induction melting with a minimum of slag production. Test waste consisting primarily of chemical sludge provided fluid slags which could be poured from the bath surface. Processing of wastes consisting of soil, concrete, or glass was limited by the inability to achieve fluid slags. It appears from test results that coreless induction melting is a feasible method to process INEL-type waste materials if two problems can be resolved. First, slag fluidity must be improved to facilitate the collection of slags formed from soil, concrete, or glass containing wastes. Secondly, refractory life must be further optimized to permit prolonged processing of the waste materials. The use of a chrome-bearing high-alumina refractory was found to resist slag line attach much better than a magnesia refractory, although some attack was still noted

  4. Information base for waste repository design. Volume 3. Waste/rock interactions

    International Nuclear Information System (INIS)

    Koplick, C.M.; Pentz, D.L.; Oston, S.G.; Talbot, R.

    1979-01-01

    This report describes the important effects resulting from interaction between radioactive waste and the rock in a nuclear waste repository. The state of the art in predicting waste/rock interactions is summarized. Where possible, independent numerical calculations have been performed. Recommendations are made pointing out areas which require additional research

  5. Intelligent Information System for Waste Management; Jaetehuollon aelykaes tietojaerjestelmae iWaste

    Energy Technology Data Exchange (ETDEWEB)

    Mustonen, T. [Kuopio Univ. (Finland)

    2003-07-01

    'iWaste' is a project for developing and testing intelligent computational methods for more comprehensive waste management. Important issues are automated reporting, optimisation of waste collection, forecasting of waste formation, data handling of waste disposal sites and simulation and modelling of regional waste management. The main objective of the project is to identify and analyse known sources of information and to link them to the existing information processing systems in the field of waste management. Additionally, the goal is to identify and test functional elements that could be developed further to software products and services. The results of the project can be categorized into three sectors. Firstly, the guidelines for a comprehensive information system in waste management will be created. This includes the requirement specifications of different parties, definitions for the data exchange interfaces and an architectural plan for software products capable of co-operative processing. Secondly, the central parts of the intelligent information system will be piloted using the research database collected in the early stage of the project. The main topics investigated are data quality, the use of Geographical Information Systems (GIS), automated reporting, optimisation of waste collection and forecasting of waste formation. Additionally, the pilot information system can be utilized in derivative projects to speed up the starting phases of them. This makes it possible to create persistent development of waste management information systems both academically and commercially. (orig.)

  6. Immobilization of antimony in waste-to-energy bottom ash by addition of calcium and iron containing additives.

    Science.gov (United States)

    Van Caneghem, Jo; Verbinnen, Bram; Cornelis, Geert; de Wijs, Joost; Mulder, Rob; Billen, Pieter; Vandecasteele, Carlo

    2016-08-01

    The leaching of Sb from waste-to-energy (WtE) bottom ash (BA) often exceeds the Dutch limit value of 0.32mgkg(-1) for recycling of BA in open construction applications. From the immobilization mechanisms described in the literature, it could be concluded that both Ca and Fe play an important role in the immobilization of Sb in WtE BA. Therefore, Ca and Fe containing compounds were added to the samples of the sand fraction of WtE BA, which in contrast to the granulate fraction is not recyclable to date, and the effect on the Sb leaching was studied by means of batch leaching tests. Results showed that addition of 0.5 and 2.5% CaO, 5% CaCl2, 2.5% Fe2(SO4)3 and 1% FeCl3 decreased the Sb leaching from 0.62±0.02mgkgDM(-1) to 0.20±0.02, 0.083±0.044, 0.25±0.01, 0.27±0.002 and 0.29±0.02mgkgDM(-1), respectively. Due to the increase in pH from 11.41 to 12.53 when 2.5% CaO was added, Pb and Zn leaching increased and exceeded the respective leaching limits. Addition of 5% CaCO3 had almost no effect on the Sb leaching, as evidenced by the resulting 0.53mgkgDM(-1) leaching concentration. This paper shows a complementary enhancement of the effect of Ca and Fe, by comparing the aforementioned Sb leaching results with those of WtE BA with combined addition of 2.5% CaO or 5% CaCl2 with 2.5% Fe2(SO4)3 or 1% FeCl3. These lab scale results suggest that formation of romeites with a high Ca content and formation of iron antimonate (tripuhyite) with a very low solubility are the main immobilization mechanisms of Sb in WtE BA. Besides the pure compounds and their mixtures, also addition of 10% of two Ca and Fe containing residues of the steel industry, hereafter referred to as R1 and R2, was effective in decreasing the Sb leaching from WtE BA below the Dutch limit value for reuse in open construction applications. To evaluate the long term effect of the additives, pilot plots of WtE BA with 10% of R1 and 5% and 10% of R2 were built and samples were submitted to leaching tests at

  7. Do Minimum Wages Fight Poverty?

    OpenAIRE

    David Neumark; William Wascher

    1997-01-01

    The primary goal of a national minimum wage floor is to raise the incomes of poor or near-poor families with members in the work force. However, estimates of employment effects of minimum wages tell us little about whether minimum wages are can achieve this goal; even if the disemployment effects of minimum wages are modest, minimum wage increases could result in net income losses for poor families. We present evidence on the effects of minimum wages on family incomes from matched March CPS s...

  8. Use of additive and pretreatment to control odors in municipal kitchen waste during aerobic composting.

    Science.gov (United States)

    Yuan, Jing; Yang, Qingyuan; Zhang, Zhiye; Li, Guoxue; Luo, Wenhai; Zhang, Difang

    2015-11-01

    The effects of adding a bulking agent and chemically pretreating municipal kitchen waste before aerobic composting were studied using a laboratory-scale system. The system used 20-L reactors and each test lasted 28days. The objective was to decrease NH3 and H2S emissions during composting. The bulking agent, dry cornstalks, was mixed with the kitchen waste to give a mixture containing 15% (wet weight) bulking agent. A combined treatment was also conducted, in which kitchen waste mixed with the bulking agent was pretreated with ferric chloride (FeCl3). Less leachate was produced by the composted kitchen waste mixed with bulking agent than by the kitchen waste alone, when the materials had reached the required maturity. The presence of cornstalks also caused less H2S to be emitted, but had little impact on the amount of NH3 emitted. The FeCl3 was found to act as an effective chemical flocculant, and its presence significantly decreased the amounts of NH3 and H2S emitted. Kitchen waste mixed with cornstalks and treated with FeCl3 emitted 42% less NH3 and 76% less H2S during composting than did pure kitchen waste. Copyright © 2015. Published by Elsevier B.V.

  9. Training waste generators: The first responder in proper waste management

    International Nuclear Information System (INIS)

    Jones, E.

    1989-01-01

    Dealing with waste effectively requires a ''cradle to grave'' approach to waste management. The first step in that chain of custody is the waste generator. The waste generator plays the key role in the correct identification, packaging, and disposal of waste. The Technical Resources and Training Section at the Oak Ridge National Laboratory (ORNL) has developed several short training programs for waste generators. This training presents a consistent approach to proper handling of waste within the ORNL waste management system. This training has been developed for generators of solid low-level radioactive waste, hazardous and mixed waste, and transuranic waste. In addition to the above, a Waste Minimization training program has been developed for use by all organizations at ORNL who generate any type of hazardous waste. These training programs represent a combined effort of the training staff and the technical staff to assure that all ORNL staff accept their responsibility for handling all types of radioactive and hazardous wastes correctly from its generation to its disposal. 4 refs

  10. USING GENETIC ALGORTIHM TO SOLVE STEINER MINIMUM SPANNING TREE PROBLEM

    Directory of Open Access Journals (Sweden)

    Öznur İŞÇİ

    2006-03-01

    Full Text Available Genetic algorithms (GA are a stochastic research methods, and they produce solutions that are close to optimum or near optimum. In addition to GA's successful application to traveling salesman problem, square designation, allocation, workshop table, preparation of lesson/examination schedules, planning of communication networks, assembling line balanced, minimum spanning tree type many combinatorial optimization problems it would be applicable to make the best comparison in optimization. In this study a Java program is developed to solve Steiner minimum spanning tree problem by genetic algorithm and its performance is examined. According to the tests carried out on the problems that were given before in the literature, results that are close to optimum are obtained in by GA approach that is recommended in this study. For the predetermined points in the study, length and gain are calculated for Steiner minimum spanning tree problem and minimum spanning tree problem.

  11. Radioactive wastes eliminating device

    International Nuclear Information System (INIS)

    Mitsutsuka, Norimasa.

    1979-01-01

    Purpose: To eliminate impurities and radioactive wastes by passing liquid sodium in a cold trap and an adsorption device. Constitution: Heated sodium is partially extracted from the core of a nuclear reactor by way of a pump, flown into and cooled in heat exchangers and then introduced into a cold trap for removal of impurities. The liquid sodium eliminated with impurities is introduced into an adsorption separator and purified by the elimination of radioactive wastes. The purified sodium is returned to the nuclear reactor. A heater is provided between the cold trap and the adsorption separator, so that the temperature of the liquid sodium introduced into the adsorption separator is not lower than the minimum temperature in the cold trap to thereby prevent deposition of impurities in the adsorption separator. (Kawakami, Y.)

  12. Productive efficiency of public and private solid waste logistics and its implications for waste management policy

    Directory of Open Access Journals (Sweden)

    Daisuke Ichinose

    2013-03-01

    Full Text Available This paper measures the productive efficiency of municipal solid waste (MSW logistics by applying data envelopment analysis (DEA to cross-sectional data of prefectures in Japan. Either through public operations or by outsourcing to private waste collection operators, prefectural governments possess the fundamental authority over waste processing operations in Japan. Therefore, we estimate a multi-input multi-output production efficiency at the prefectural level via DEA, employing several different model settings. Our data classify the MSW into household solid waste (HSW and business solid waste (BSW collected by both private and public operators as separate outputs, while the numbers of trucks and workers used by private and public operators are used as inputs. The results consistently show that geographical characteristics, such as the number of inhabited remote islands, are relatively more dominant factors for determining inefficiency. While the implication that a minimum efficient scale is not achieved in these small islands is in line with the literature suggesting that waste logistics has increasing returns at the municipal level, our results indicate that waste collection efficiency in Japan is well described by CRS technology at the prefectural level. The results also show that prefectures with higher private-sector participation, measured in terms of HSW collection, are more efficient, whereas a higher private–labor ratio negatively affects efficiency. We also provide evidence that prefectures with inefficient MSW logistics have a higher tendency of suffering from the illegal dumping of industrial waste.

  13. Modelling approach to evaluate safety of LILW-SL disposal in slovenia considering different waste packaging options

    International Nuclear Information System (INIS)

    Perko, J.; Mallants, D.

    2007-01-01

    The long-term safety of radioactive waste repositories is usually demonstrated by means of a safety assessment which normally includes modelling of radionuclide release from a multi-barrier surface or deep repository to the geosphere and biosphere. The present quantitative evaluation performed emphasizes on contrasting disposal options under consideration in Slovenia and concerns siting, disposal concept (deep versus surface), and waste packaging. The assessment has identified a number of conditions that would lead to acceptable waste disposal solutions, while at the same time results also revealed options that would result in exceeding the radiological criteria. Results presented are the output of a collective effort of a Quintessa-led Consortium with SCK-CEN and Belgatom, in the framework of a recent PHARE project. The key objective of this work was to identify the preferred disposal concept and packaging option from a number of alternatives being considered by the Slovenian radioactive waste management agency (ARAO) for low and intermediate level short-lived waste (LILW-SL). The emphasis of the assessment was the consideration of several waste treatment and packaging options in an attempt to identify the minimum required containment characteristics which would result in safe disposal and the cost-benefit of additional safety measures. Waste streams for which alternative treatment and packaging solutions were developed and evaluated include decommissioning waste and NPP operational wastes containing drums with unconditioned ion exchange resins in overpacked tube type containers (TTCs). For the former the disposal options under consideration were either direct disposal of loose pieces grouted into a vault or use of high integrity containers. For the latter three options were foreseen. The first is overpacking of resin containing TTCs grouted into high integrity containers, the second option is complete treatment with hydration, neutralisation, and cementation of

  14. Experimental investigation on the properties of concrete containing post-consumer plastic waste as coarse aggregate replacement

    Directory of Open Access Journals (Sweden)

    Zasiah TAFHEEM

    2018-03-01

    Full Text Available The consumption of various forms of plastic has been increased in recent days due to the boost in industrialization and other human activities. Most of the plastic wastes are abandoned and require large landfill area for storage. More importantly, the low biodegradability of plastic poses a serious threat to environment protection issue. Various methods have been followed for the disposal of plastic in an attempt to reduce the negative impact of the plastic on the environment. Recently, various types of plastic have been incorporated in concrete to minimize the exposure of plastic to the environment. The aim of this study is to investigate the properties of concrete containing polyethylene terephthalate (PET, and high density polyethylene (HDPE plastic that were used as partial replacement of coarse aggregate (CA. In this study, four compositions of stone aggregate(S: plastic waste ratios have been used by volume basis: 100% S: 0% Plastic (control concrete, 90% S: 10% PET, 90% S: 10% HDPE, and 90% S: 5% PET+5% HDPE. The effects of waste plastic addition on the mechanical properties of concrete are presented in this paper. Test results reveal that minimum reduction in compressive strength has been found 35% in case of 10% PET plastic replaced concrete whereas splitting tensile strength for 10% PET replaced concrete has been increased by 21% while compared to control concrete. In addition, fresh unit weight of concrete containing plastic waste has been decreased by 4% in comparison to control concrete.

  15. From waste to traffic fuel (W-fuel)

    Energy Technology Data Exchange (ETDEWEB)

    Kask, Ue.; Andrijevskaja, J.; Kask, L. [and others

    2012-11-01

    The EU directive on the promotion of the use of energy from renewable sources (Directive 2009/28/EC) sets a mandatory minimum target for the use of fuels produced using renewable energy sources of 10% of total petrol and diesel consumption in the transport sector by the year 2020. In addition, it states that production of renewable fuels should be consistent with sustainable development and must not endanger biodiversity. In the INTERREG IVA Southern Finland - Estonia Sub-programme, efforts towards finding solutions to the tasks set by the EU were undertaken in co-operation with Finnish and Estonian researchers. The purpose of the 'From Waste to Traffic Fuel' (W-Fuel) project was to promote the sustainable production and use of biogas using locally-sourced biodegradable waste materials from the food and beverage industry and the agricultural and municipal sectors. The ultimate aim of the project was to upgrade the biogas (produced based on anaerobic digestion of biodegradable wastes, sludge, manure, slurry and energy crops) to biomethane with a methane content similar to natural gas, to be further used as transport fuel with the aim of reducing traffic-borne emissions, in particular CO{sub 2}. The project combined waste, energy and traffic solutions in order to decrease emissions, costs and the use of materials. Six case areas in southern Finland and northern Estonia were selected. The two case areas in Estonia were the counties of Harju and Laeaene-Viru in northern Estonia. The project aimed to promote waste and sludge prevention and to commence biogas production and its subsequent upgrading to biomethane for use as a renewable fuel. The project promoted regional businesses and employment in waste treatment and 'green energy' production. On basis of the gathered data, the biogas potentials and prerequisites of each case county were analysed. Furthermore, the environmental, economic and other regional effects of the different options were

  16. Waste management in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I. [Japan Atomic Energy Research Institute, Dept. of Safety Research Technical Support, Tokai-Mura, Naka-Gun, Ibaraki-Ken (Japan)

    2000-07-01

    In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)

  17. Waste management in NUCEF

    International Nuclear Information System (INIS)

    Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I.

    2000-01-01

    In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)

  18. The effect of alternative cost and environmental impact minimisation strategies on radioactive waste disposal strategies

    International Nuclear Information System (INIS)

    Laundy, R.S.; James, A.R.; Groom, M.S.; Dalrymple, G.J.

    1985-06-01

    The study reported here investigates the effects of different cost and environmental impact minimisation strategies for a single waste disposal scenario. Four disposal options are considered. The study examines the environmental impacts from waste storage and transport and the disposal impacts in terms of collective dose, maximum individual dose and individual dose from intrusion. The total cost of disposing of waste takes account of storage, transport and disposal costs to each of the four facilities. Two minimum cost scenarios and seven minimum impact assessments were performed. The results showed clearly that a trade-off has to be made between the environmental impacts from transport and storage of waste. A low objective risk of transport is achieved by directing waste to the engineered trench, assumed to have a central location. This waste is stored until the facility is available in 1995 thus increasing the potential impact from storage. The results also show a trade-off has to be made between minimising the maximum individual dose from disposal and collective dose. The study shows that for relatively little cost large reductions in the impacts can be obtained particularly in short and long-term collective dose and the individual dose from intrusion. (author)

  19. Treatment of mercury containing waste

    Science.gov (United States)

    Kalb, Paul D.; Melamed, Dan; Patel, Bhavesh R; Fuhrmann, Mark

    2002-01-01

    A process is provided for the treatment of mercury containing waste in a single reaction vessel which includes a) stabilizing the waste with sulfur polymer cement under an inert atmosphere to form a resulting mixture and b) encapsulating the resulting mixture by heating the mixture to form a molten product and casting the molten product as a monolithic final waste form. Additional sulfur polymer cement can be added in the encapsulation step if needed, and a stabilizing additive can be added in the process to improve the leaching properties of the waste form.

  20. Exemplary design of climate-friendly waste management in the State of Berlin; Vorbildhafte Konzeption einer klimavertraeglichen Abfallentsorgung im Land Berlin

    Energy Technology Data Exchange (ETDEWEB)

    Vogt, Regine; Fehrenbach, Horst [ifeu - Institut fuer Energie- und Umweltforschung Heidelberg GmbH, Heidelberg (Germany); Wiegel, Ulrich; Ebert, Knud [ICU - Ingenieurconsulting Umwelt und Bau Berlin, Berlin (Germany); Schwilling, Thomas; Mehner, Heidelinde [SenStadtUm - Senatsverwaltung fuer Stadtentwicklung und Umwelt, Berlin (Germany). Referat Abfallwirtschaft

    2013-05-15

    On behalf of the Senate Department for Environment of the State of Berlin IFEU Heidelberg and ICU Berlin analysed a climate friendly waste treatment for the 36 most important waste types. The inventory for 2010 showed that the management of the 6.7 million tonnes of waste in the State of Berlin led to a remarkable prevention of greenhouse gas emissions of about -900,000 tonnes of CO{sub 2}-equivalents. Treatment optimisation for half of the waste types and increased source separation of dry recyclables and organics can lead to an additional mitigation of greenhouse gases of about -248,000 tonnes CO{sub 2}-equivalents. The impact of waste management on the global warming potential was determined using the standardised LCA method modified for waste management. A key element of the study was the intensive and constructive exchange with stakeholders. The results were integrated into an action plan based on the findings of the analysis of potentials and optimisation scenarios. For the relevant waste types of municipal origin property specifications were prepared. The specifications include distinct minimum criteria for an optimised treatment to reach the identified waste specific greenhouse gas reductions. The focus of the study was on climate change. A second study will be extended to further important environmental impacts like resource saving. (orig.)

  1. Centralized management for LA and MA waste selection and optimization of processes

    International Nuclear Information System (INIS)

    Medal, G.

    1985-01-01

    The procedure currently used for removal of process waste produced by EDF Nuclear Power Plants consists in the local embedding of the waste on each EDF site, the embedded waste is then shipped to a National Final Storage Center. The method used is a financial limitation of opportunities for amendment of containement and volume reduction techniques. The work made by the Commissariat a l'Energie Atomique and its subsidiary TECHNICATOME on behalf of the French Electricite Board (EDF) aim at the removal of waste ''in bulk'' with minimum possible pretreatment in compliance with transport regulation, treatment and conditioning taking place in a centralized waste treatment station so as to allow final storage. This method enables: optimization of the management of waste, selection of safe treatment-processes, storage volume reduction, lower investment and operating costs [fr

  2. Policy gridlock in waste management: Balancing federal and state concerns

    Energy Technology Data Exchange (ETDEWEB)

    Feldman, D.L. [Oak Ridge National Lab., TN (United States); Peretz, J.H.; Jendrucko, B.K. [Univ. of Tennessee, Knoxville, TN (United States)

    1993-12-31

    Current federal hazardous and low-level radioactive waste management policies fail to balance national concerns for policy consistency with state concerns for equity, discretion, and adequate resources. Failure to balance these competing values has resulted in {open_quotes}policy gridlock{close_quotes} - exemplified by conflicts over the Resource Conservation and Recovery Act and the Low-Level Radioactive Waste Policy Acts. Both conflicts have resulted in recent U.S. Supreme Court litigation. After reviewing federal-state conflict in hazardous and low-level radioactive waste management, we propose that the solution to gridlock lies in modifying conjoint federalism. Conjoint federalism allows for joint responsibility for waste policy between federal and state governments, with state programs meeting minimum standards set by federal programs. However, conjoint federalism does not currently allow for sufficient state discretion, which is paramount for successful waste management programs. Specifically, Congress should expand conjoint federalism, to allow states to charge differential fees on imported hazardous waste as is done for low-level radioactive waste. This expansion would encourage waste minimization and better interstate planning.

  3. Policy gridlock in waste management: Balancing federal and state concerns

    International Nuclear Information System (INIS)

    Feldman, D.L.; Peretz, J.H.; Jendrucko, B.K.

    1993-01-01

    Current federal hazardous and low-level radioactive waste management policies fail to balance national concerns for policy consistency with state concerns for equity, discretion, and adequate resources. Failure to balance these competing values has resulted in open-quotes policy gridlockclose quotes - exemplified by conflicts over the Resource Conservation and Recovery Act and the Low-Level Radioactive Waste Policy Acts. Both conflicts have resulted in recent U.S. Supreme Court litigation. After reviewing federal-state conflict in hazardous and low-level radioactive waste management, we propose that the solution to gridlock lies in modifying conjoint federalism. Conjoint federalism allows for joint responsibility for waste policy between federal and state governments, with state programs meeting minimum standards set by federal programs. However, conjoint federalism does not currently allow for sufficient state discretion, which is paramount for successful waste management programs. Specifically, Congress should expand conjoint federalism, to allow states to charge differential fees on imported hazardous waste as is done for low-level radioactive waste. This expansion would encourage waste minimization and better interstate planning

  4. Modeling of NOx Destruction Options for INEEL Sodium-Bearing Waste Vitrification

    Energy Technology Data Exchange (ETDEWEB)

    Wood, Richard Arthur

    2001-09-01

    Off-gas NOx concentrations in the range of 1-5 mol% are expected as a result of the proposed vitrification of sodium-bearing waste at the Idaho National Engineering and Environmental Laboratory. An existing kinetic model for staged combustion (originally developed for NOx abatement from the calcination process) was updated for application to vitrification offgas. In addition, two new kinetic models were developed to assess the feasibility of using selective non-catalytic reduction (SNCR) or high-temperature alone for NOx abatement. Each of the models was developed using the Chemkin code. Results indicate that SNCR is a viable option, reducing NOx levels to below 1000 ppmv. In addition, SNCR may be capable of simultaneously reducing CO emissions to below 100 ppmv. Results for using high-temperature alone were not as promising, indicating that a minimum NOx concentration of 3950 ppmv is achievable at 3344°F.

  5. Low-level waste management - suggested solutions for problem wastes

    International Nuclear Information System (INIS)

    Pechin, W.H.; Armstrong, K.M.; Colombo, P.

    1984-01-01

    Problem wastes are those wastes which are difficult or require unusual expense to place into a waste form acceptable under the requirements of 10 CFR 61 or the disposal site operators. Brookhaven National Laboratory has been investigating the use of various solidification agents as part of the DOE Low-Level Waste Management Program for several years. Two of the leading problem wastes are ion exchange resins and organic liquids. Ion exchange resins can be solidified in Portland cement up to about 25 wt % resin, but waste forms loaded to this degree exhibit significantly reduced compressive strength and may disintegrate when immersed in water. Ion exchange resins can also be incorporated into organic agents. Mound Laboratory has been investigating the use of a joule-heated glass melter as a means of disposing of ion exchange resins and organic liquids in addition to other combustible wastes

  6. On the Minimum Cable Tensions for the Cable-Based Parallel Robots

    Directory of Open Access Journals (Sweden)

    Peng Liu

    2014-01-01

    Full Text Available This paper investigates the minimum cable tension distributions in the workspace for cable-based parallel robots to find out more information on the stability. First, the kinematic model of a cable-based parallel robot is derived based on the wrench matrix. Then, a noniterative polynomial-based optimization algorithm with the proper optimal objective function is presented based on the convex optimization theory, in which the minimum cable tension at any pose is determined. Additionally, three performance indices are proposed to show the distributions of the minimum cable tensions in a specified region of the workspace. An important thing is that the three performance indices can be used to evaluate the stability of the cable-based parallel robots. Furthermore, a new workspace, the Specified Minimum Cable Tension Workspace (SMCTW, is introduced, within which all the minimum tensions exceed a specified value, therefore meeting the specified stability requirement. Finally, a camera robot parallel driven by four cables for aerial panoramic photographing is selected to illustrate the distributions of the minimum cable tensions in the workspace and the relationship between the three performance indices and the stability.

  7. In Situ Modular Waste Retrieval and Treatment System

    International Nuclear Information System (INIS)

    Walker, M.S.

    1996-10-01

    As part of the Comprehensive Environmental Response, Compensation, and Liability Act process from remediation of Waste Area Grouping (WAG 6) at ORNL, a public meeting was held for the Proposed Plan. It was recognized that contaminant releases from WAG 6 posed minimal potential risk to the public and the environment. The US DOE in conjunction with the US EPA and the TDEC agreed to defer remedial action at WAG 6 until higher risk release sites were first remediated. This report presents the results of a conceptual design for an In Situ Modular Retrieval and Treatment System able to excavate, shred, and process buried waste on site, with minimum disturbance and distribution of dust and debris. the system would bring appropriate levels of treatment to the waste then encapsulate and leave it in place. The system would be applicable to areas in which waste was disposed in long trenches

  8. Enhanced high-solids anaerobic digestion of waste activated sludge by the addition of scrap iron.

    Science.gov (United States)

    Zhang, Yaobin; Feng, Yinghong; Yu, Qilin; Xu, Zibin; Quan, Xie

    2014-05-01

    Anaerobic digestion of waste activated sludge usually requires pretreatment procedure to improve the bioavailability of sludge, which involves considerable energy and high expenditures. This study proposes a cost-effective method for enhanced anaerobic digestion of sludge without a pretreatment by directly adding iron into the digester. The results showed that addition of Fe(0) powder could enhance 14.46% methane yield, and Fe scrap (clean scrap) could further enhance methane yield (improving rate 21.28%) because the scrap has better mass transfer efficiency with sludge and liquid than Fe(0) powder. The scrap of Fe with rust (rusty scrap) could induce microbial Fe(III) reduction, which resulted in achieving the highest methane yield (improving rate 29.51%), and the reduction rate of volatile suspended solids (VSS) was also highest (48.27%) among Fe powder, clean scrap and rusty scrap. PCR-DGGE proved that the addition of rusty scrap could enhance diversity of acetobacteria and enrich iron-reducing bacteria to enhance degradation of complex substrates. Copyright © 2014 Elsevier Ltd. All rights reserved.

  9. Industrial Waste

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    generation rates and material composition as well as determining factors are discussed in this chapter. Characterizing industrial waste is faced with the problem that often only a part of the waste is handled in the municipal waste system, where information is easily accessible. In addition part...... of the industrial waste may in periods, depending on market opportunities and prices, be traded as secondary rawmaterials. Production-specificwaste from primary production, for example steel slag, is not included in the current presentation. In some countries industries must be approved or licensed and as part...... of the system industry has to inform at the planning stage and afterwards in yearly reports on their waste arising and how the waste is managed. If available such information is very helpful in obtaining information about that specific industry. However, in many countries there is very little information...

  10. An innovative in-situ mixing technology and its applications in the waste remediation industry

    International Nuclear Information System (INIS)

    Toor, I.A.; Lanter, R.

    1994-01-01

    An innovative in-situ remediation technology has been developed for solidification and stabilization of hazardous wastes. The system incorporates a specially designed rotary mixing head attached to the boom of a long-reach backhoe or other dirt-moving equipment. A variety of mixing-head configurations are available to treat various types of wastes, ranging from oil sludge to very dry contaminated soils containing significant amounts of large aggregates and gravel. The system has been successfully applied in the field to remediate hazardous petroleum sludge, mine tailings, and steel mill process sediments containing heavy metals (e.g., chromium, arsenic, cadmium, and lead). A very elaborate quality assurance/quality control program was implemented to ensure minimum variation in additive concentration and thorough mixing. The mixing effectiveness and reagent injection capabilities of this unit have resulted in the in-situ treatment of listed hazardous wastes to below delisting thresholds at depths in excess of 15 ft. Applications of this unit are currently being reviewed for incorporating and mixing nutrients in a bioremediation process. The new technology provides a very economical means for treatment, with excellent product quality

  11. Drinking water treatment sludge as an effective additive for biogas production from food waste; kinetic evaluation and biomethane potential test.

    Science.gov (United States)

    Ebrahimi-Nik, Mohammadali; Heidari, Ava; Ramezani Azghandi, Shamim; Asadi Mohammadi, Fatemeh; Younesi, Habibollah

    2018-07-01

    The effect of drinking water treatment sludge (DWTS) as a mixture additive, on biogas and methane production from food waste was studied. Mesophilic anaerobic digestion of food waste with 5 concentrations of DWTS (0, 2, 6, 12, and 18 ppm) was carried out. It was found that DWTS can significantly enhance biogas and methane yield. The highest biogas (671 Nml/g VS) as well as methane yield (522 Nml/g VS) was observed when 6 mg/kg DWTS was added. This is equal to 65 and 58 percent increase in comparison with the control digester. The calculated lag time for methane was found to be in between 3.3 and 4.7 days. The DWTS also reduced the lag phase and retention time. The biogas experimental data was fitted with the modified Gompertz and the first-order kinetic models with R 2 higher than 0.994 and 0.949, respectively. The ratio of the experimental biogas production to the theoretical biogas production (ɛ) for control sample was 0.53 while for other samples containing additive were higher than 0.78. Copyright © 2018 Elsevier Ltd. All rights reserved.

  12. Stabilization of inorganic mixed waste to pass the TCLP and STLC tests using clay and pH-insensitive additives

    International Nuclear Information System (INIS)

    Bowers, J.S.; Anson, J.R.; Painter, S.M.; Maitino, R.E.

    1995-03-01

    Stabilization traps toxic contaminants (usually both chemically and physically) in a matrix so that they do not leach into the environment. Typical contaminants are metals (mostly transition metals) that exhibit the characteristic of toxicity. The stabilization process routinely uses pozzolanic materials. Portland cement, fly ash-lime mixes, gypsum cements, and clays are some of the most common materials. In many instances, materials that can pass the Toxicity Characteristic Leaching Procedure (TCLP-the federal leach test) or the Soluble Threshold Leachate Concentration (STLC-the California leach test) must have high concentrations of lime or other caustic material because of the low pH of the leaching media. Both leaching media, California's and EPA's, have a pH of 5.0. California uses citric acid and sodium citrate while EPA uses acetic acid and sodium acetate. These media can form ligands that provide excellent metal leaching. Because of the aggressive nature of the leaching medium, stabilized wastes in many cases will not pass the leaching tests. At the Lawrence Livermore National Laboratory, additives such as dithiocarbamates and thiocarbonates, which are pH-insensitive and provide resistance to ligand formation, are used in the waste stabilization process. Attapulgite, montmorillonite, and sepiolite clays are used because they are forgiving (recipe can be adjusted before the matrix hardens). The most frequently used stabilization process consists of a customized recipe involving waste sludge, clay and dithiocarbamate salt, mixed with a double planetary mixer into a pasty consistency. TCLP and STLC data on this waste matrix have shown that the process matrix meets land disposal requirements

  13. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits, Area 5 Waste Management Division, Nevada National Security Site, Final CQA Report

    International Nuclear Information System (INIS)

    2012-01-01

    The report is the Final Construction Quality Assurance (CQA) Report for the 92-Acrew Evapotranspiration Cover, Area 5 Waste Management Division Retired Mixed Waste Pits, Nevada National Security Site, Nevada, for the period of January 20, 2011, to January 31, 2012 The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location, waste types and regulatory requirements: (1) Pit 3 Mixed Waste Disposal Unit (MWDU); (2) Corrective Action Unit (CAU) 111; (3) CAU 207; (4) Low-level waste disposal units; (5) Asbestiform low-level waste disposal units; and (6) One transuranic (TRU) waste trench.

  14. Studies on treatment of low level radioactive liquid waste for removal of anionic species of 125Sb, 99Tc and 106Ru. Contributed Paper RD-14

    International Nuclear Information System (INIS)

    Shivakamy, K.; Chitra, S.; Rao, S.V.S.; Paul, Biplob

    2014-01-01

    The treatment of intermediate level waste at Waste Immobilization Plant generates low level radioactive waste which would require further management before discharge to sea. This waste is expected to contain polymeric oxo anions of 125 Sb, 99 Tc, 106 Ru in addition to cationic species like 137 Cs, 90 Sr etc. Chemical treatment takes care of the major contributors to radioactivity viz 137 Cs, 90 Sr etc but traces of activity due to anionic species remain in the treated waste effluent. Novel composite anionic exchanger namely Polyurethane foam coated with Hydrous Zirconium Oxide was developed for removal of these anionic species. This material was successfully employed for removal of anionic 1 25S b from radioactive waste effluent at Waste Management Division, Trombay. Based on our experience with Sb removal using the above material it was decided to assess the ability of the exchanger in removal of other anionic species bearing Ru and Tc. It was observed that in addition to complete removal of Sb, 50% Ru removal and 40% Tc could also be removed using this material from radioactive waste effluents. In lab experiments, similar results were obtained with simulated low level waste bearing inactive Ru. Among several hydrous oxides tried in a batch study, Hydrous Zirconium Oxide showed a maximum removal of 40% for Tc in actual waste generated from reprocessing plant. Based on the above it has been planned to set up an anion exchange column with Hydrous Zirconium Oxide coated Polyurethane foam for final treatment of chemically treated waste effluent prior to discharge as a prime step towards achieving our goal of minimum discharge to Sea. (author)

  15. Nuclear waste and hazardous waste in the public perception

    International Nuclear Information System (INIS)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael

    2015-01-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  16. Nuclear waste and hazardous waste in the public perception

    Energy Technology Data Exchange (ETDEWEB)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

    2015-07-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  17. Rising above the Minimum Wage.

    Science.gov (United States)

    Even, William; Macpherson, David

    An in-depth analysis was made of how quickly most people move up the wage scale from minimum wage, what factors influence their progress, and how minimum wage increases affect wage growth above the minimum. Very few workers remain at the minimum wage over the long run, according to this study of data drawn from the 1977-78 May Current Population…

  18. IMPACTS OF ANTIFOAM ADDITIONS AND ARGON BUBBLING ON DEFENSE WASTE PROCESSING FACILITY REDUCTION/OXIDATION

    Energy Technology Data Exchange (ETDEWEB)

    Jantzen, C.; Johnson, F.

    2012-06-05

    During melting of HLW glass, the REDOX of the melt pool cannot be measured. Therefore, the Fe{sup +2}/{Sigma}Fe ratio in the glass poured from the melter must be related to melter feed organic and oxidant concentrations to ensure production of a high quality glass without impacting production rate (e.g., foaming) or melter life (e.g., metal formation and accumulation). A production facility such as the Defense Waste Processing Facility (DWPF) cannot wait until the melt or waste glass has been made to assess its acceptability, since by then no further changes to the glass composition and acceptability are possible. therefore, the acceptability decision is made on the upstream process, rather than on the downstream melt or glass product. That is, it is based on 'feed foward' statistical process control (SPC) rather than statistical quality control (SQC). In SPC, the feed composition to the melter is controlled prior to vitrification. Use of the DWPF REDOX model has controlled the balanjce of feed reductants and oxidants in the Sludge Receipt and Adjustment Tank (SRAT). Once the alkali/alkaline earth salts (both reduced and oxidized) are formed during reflux in the SRAT, the REDOX can only change if (1) additional reductants or oxidants are added to the SRAT, the Slurry Mix Evaporator (SME), or the Melter Feed Tank (MFT) or (2) if the melt pool is bubble dwith an oxidizing gas or sparging gas that imposes a different REDOX target than the chemical balance set during reflux in the SRAT.

  19. Nuclear waste solutions

    Science.gov (United States)

    Walker, Darrel D.; Ebra, Martha A.

    1987-01-01

    High efficiency removal of technetium values from a nuclear waste stream is achieved by addition to the waste stream of a precipitant contributing tetraphenylphosphonium cation, such that a substantial portion of the technetium values are precipitated as an insoluble pertechnetate salt.

  20. Encapsulation of radioactive waste

    International Nuclear Information System (INIS)

    Pordes, O.; Plows, J.P.

    1980-01-01

    A method is described for encapsulating a particular radioactive waste which consists of suspending the waste in a viscous liquid encapsulating material, of synthetic resin monomers or prepolymers, and setting the encapsulating material by addition or condensation polymerization to form a solid material in which the waste is dispersed. (author)

  1. Municipal Solid Waste Resources

    Energy Technology Data Exchange (ETDEWEB)

    None

    2016-06-01

    Municipal solid waste (MSW) is a source of biomass material that can be utilized for bioenergy production with minimal additional inputs. MSW resources include mixed commercial and residential garbage such as yard trimmings, paper and paperboard, plastics, rubber, leather, textiles, and food wastes. Waste resources such as landfill gas, mill residues, and waste grease are already being utilized for cost-effective renewable energy generation. MSW for bioenergy also represents an opportunity to divert greater volumes of residential and commercial waste from landfills.

  2. Minimum intervention dentistry: periodontics and implant dentistry.

    Science.gov (United States)

    Darby, I B; Ngo, L

    2013-06-01

    This article will look at the role of minimum intervention dentistry in the management of periodontal disease. It will discuss the role of appropriate assessment, treatment and risk factors/indicators. In addition, the role of the patient and early intervention in the continuing care of dental implants will be discussed as well as the management of peri-implant disease. © 2013 Australian Dental Association.

  3. Management of nontritium radioactive wastes from fusion power plants

    International Nuclear Information System (INIS)

    Kaser, J.D.; Postma, A.K.; Bradley, D.J.

    1976-09-01

    This report identifies nontritium radioactive waste sources for current conceptual fusion reactor designs. Quantities and compositions of the radwaste are estimated for the tokamaks of the University of Wisconsin (UWMAK-I), the Princeton Plasma Physics Laboratory (PPPL), and the Oak Ridge National Laboratory (ORNL); the Reference Theta Pinch Reactor of the Los Alamos Scientific Laboratory (LASL); and the Minimum Activation Blanket of the Brookhaven National Laboratory (BNL). Disposal of large amounts of radioactive waste appears necessary for fusion reactors. Although the curie (Ci) level of the wastes is comparable to that of fission products in fission reactors, the isotopes are less hazardous, and have shorter half-lives. Therefore radioactivity from fusion power production should pose a smaller risk than radioactivity from fission reactors. Radioactive waste sources identified for the five reference plants are summarized. Specific radwaste treatments or systems had to be assumed to estimate these waste quantities. Future fusion power plant conceptual designs should include radwaste treatment system designs so that assumed designs do not have to be used to assess the environmental effects of the radioactive waste

  4. Waste Isolation Pilot Plant contact-handled transuranic waste preoperational checkout: Final report

    International Nuclear Information System (INIS)

    1988-07-01

    This report documents the results of the WIPP CH TRU Preoperational Checkout which was completed between June 8 and June 14, 1988 during which period, a total of 10 TRUPACT shipping containers were processed from site receipt through emplacement of the simulated waste packages in the underground storage area. Since the design of WIPP includes provisions to unload an internally contaminated TRUPACT, in the controlled environment of the Overpack and Repair Room, one TRUPACT was partially processed through this sequence of operations to verify this portion of the waste handling process as part of the checkout. The successful completion of the CH TRU Preoperational Checkout confirmed the acceptability of WIPP operating procedures, personnel, equipment, and techniques. Extrapolation of time-line data using a computer simulation model of the waste handling process has confirmed that WIPP operations can achieve the design throughput capability of 500,000 ft 3 /year, if required, using two waste handling shifts. The single shift throughput capability of 273,000 ft 3 /year exceeds the anticipated operating receival rate of about 230,000 ft 3 /year. At the 230,000 ft 3 /year rate, the combined CH TRU annual operator dose and the average individual dose (based on minimum crew size) is projected to be 13.7 rem and 0.7 rem, respectively. 6 refs., 27 figs., 3 tabs

  5. Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry. Additional Information

    International Nuclear Information System (INIS)

    2010-01-01

    The oil and gas industry, a global industry operating in many Member States, makes extensive use of radiation generators and sealed and unsealed radioactive sources, some of which are potentially dangerous to human health and the environment if not properly controlled. In addition, significant quantities of naturally occurring radioactive material (NORM) originating from the reservoir rock are encountered during production, maintenance and decommissioning. The oil and gas industry operates in all climates and environments, including the most arduous conditions, and is continuously challenged to achieve high efficiency of operation while maintaining a high standard of safety and control - this includes the need to maintain control over occupational exposures to radiation, as well as to protect the public and the environment through proper management of wastes that may be radiologically and chemically hazardous. The oil and gas industry is organizationally and technically complex, and relies heavily on specialized service and supply companies to provide the necessary equipment and expertise, including expertise in radiation safety. This training manual is used by the IAEA as the basis for delivering its training course on radiation protection and the management of radioactive waste in the oil and gas industry. Enclosed with this manual is a CD-ROM that contains the presentational material used in the training course, the course syllabus and additional notes for course presenters. The course material is based principally on IAEA Safety Reports Series No. 34 Radiation Protection and the Management of Radioactive Waste in the Oil and Gas Industry, published by the IAEA in 2003. The training course is aimed at regulatory bodies; oil and gas field operators and support companies; workers and their representatives; health, safety and environmental professionals; and health and safety training officers. A pilot training course was held in the Syrian Arab Republic in 2000 as

  6. Low-level waste disposal performance assessments - Total source-term analysis

    Energy Technology Data Exchange (ETDEWEB)

    Wilhite, E.L.

    1995-12-31

    Disposal of low-level radioactive waste at Department of Energy (DOE) facilities is regulated by DOE. DOE Order 5820.2A establishes policies, guidelines, and minimum requirements for managing radioactive waste. Requirements for disposal of low-level waste emplaced after September 1988 include providing reasonable assurance of meeting stated performance objectives by completing a radiological performance assessment. Recently, the Defense Nuclear Facilities Safety Board issued Recommendation 94-2, {open_quotes}Conformance with Safety Standards at Department of Energy Low-Level Nuclear Waste and Disposal Sites.{close_quotes} One of the elements of the recommendation is that low-level waste performance assessments do not include the entire source term because low-level waste emplaced prior to September 1988, as well as other DOE sources of radioactivity in the ground, are excluded. DOE has developed and issued guidance for preliminary assessments of the impact of including the total source term in performance assessments. This paper will present issues resulting from the inclusion of all DOE sources of radioactivity in performance assessments of low-level waste disposal facilities.

  7. Talc-silicon glass-ceramic waste forms for immobilization of high- level calcined waste

    International Nuclear Information System (INIS)

    Vinjamuri, K.

    1993-06-01

    Talc-silicon glass-ceramic waste forms are being evaluated as candidates for immobilization of the high level calcined waste stored onsite at the Idaho Chemical Processing Plant. These glass-ceramic waste forms were prepared by hot isostatically pressing a mixture of simulated nonradioactive high level calcined waste, talc, silicon and aluminum metal additives. The waste forms were characterized for density, chemical durability, and glass and crystalline phase compositions. The results indicate improved density and chemical durability as the silicon content is increased

  8. Legal incentives for minimizing waste

    International Nuclear Information System (INIS)

    Clearwater, S.W.; Scanlon, J.M.

    1991-01-01

    Waste minimization, or pollution prevention, has become an integral component of federal and state environmental regulation. Minimizing waste offers many economic and public relations benefits. In addition, waste minimization efforts can also dramatically reduce potential criminal requirements. This paper addresses the legal incentives for minimizing waste under current and proposed environmental laws and regulations

  9. Los Alamos Waste Management FY96 and FY97 Tactical Plan, March 1, 1996

    International Nuclear Information System (INIS)

    1996-01-01

    The Los Alamos National Laboratory (LANL) Waste Management Program (WMP) began a transition to become a open-quotes best of classclose quotes waste management program during fiscal year 1995 (FY95). A best of class waste management program means that LANL will provide cost-effective and compliant management of the minimum amount of waste. In FY94, the WMP could be characterized as a level of effort program requiring several new facilities and new LANL-developed technologies to carry out its waste management responsibilities. By the end of FY95, significant progress had been made in the transition to best of class. The FY96 WMP is realigned and reorganized. Its budget and scope of work are built upon discrete work packages. It is committed to achieving improved cost-effectiveness, providing significant tangible technical results, and to having its performance measured. During FY95, over $11,000,000 in facility and operational costs were avoided. The need for three new major facilities was reexamined and lower cost solutions, not requiring the development of new facilities, were agreed to. Technology development activities were terminated and replaced with the use of commercial facilities to achieve aggressive reductions in the Low-Level Mixed Waste legacy inventory. In addition, over $14,000,000 in improved cost-effectiveness has been included in the FY96 Baseline. An overall WMP vision, specific milestones, performance measures, and commitments are in place for FY96 to ensure that LANL continues the transition to a best of class waste management program. The following table identifies the overall vision and success indicators for FY96

  10. Nuclear waste management at DOE

    International Nuclear Information System (INIS)

    Perge, A.F.

    1979-01-01

    DOE is responsible for interim storage for some radioactive wastes and for the disposal for most of them. Of the wastes that have to be managed a significant part are a result of treatment systems and devices for cleaning gases. The long term waste management objectives place minimal reliance on surveillance and maintenance. Thus, the concerns about the chemical, thermal, and radiolytic degradation of wastes require technology for converting the wastes to forms acceptable for long term isolation. The strategy of the DOE airborne radioactive waste management program is to increase the service life and reliability of filters; to reduce filter wastes; and in anticipation of regulatory actions that would require further reductions in airborne radioactive releases from defense program facilities, to develop improved technology for additional collection, fixation, and long-term management of gaseous wastes. Available technology and practices are adequate to meet current health and safety standards. The program is aimed primarily at cost effective improvements, quality assurance, and the addition of new capability in areas where more restrictive standards seem likely to apply in the future

  11. Transuranic waste management program and facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-01-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  12. Transuranic Waste Management Program and Facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-02-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  13. ISOCELL trademark proof-of-concept for retrieval of wastes and contaminated soil

    International Nuclear Information System (INIS)

    Chatwin, T.D.; Krieg, R.K.

    1992-01-01

    ISOCELL TM cryogenic technology is designed to immobilize buried hazardous, radioactive, and mixed waste and contaminated soil by creating a block of frozen waste and soil that can be safely retrieved, stored, transported, and treated with a minimum of dust or aerosol production. A ''proof-of-concept'' test of the ISOCELL process was conducted in clean soil by RKK, Ltd., for the Idaho National Engineering Laboratory (INEL). Results indicate ISOCELL technology successfully froze moist soil into a solid block capable of being lifted and retrieved. Test conditions were compared to characteristics of possible buried waste sites in the INEL

  14. Composting of waste paint sludge containing melamine resin as affected by nutrients and gypsum addition and microbial inoculation

    International Nuclear Information System (INIS)

    Tian Yongqiang; Chen Liming; Gao Lihong; Michel, Frederick C.; Wan Caixia; Li Yebo; Dick, Warren A.

    2012-01-01

    Melamine formaldehyde resins have hard and durable properties and are found in many products, including automobile paints. These resins contain high concentrations of nitrogen and, if properly composted, can yield valuable products. We evaluated the effects of starter compost, nutrients, gypsum and microbial inoculation on composting of paint sludge containing melamine resin. A bench-scale composting experiment was conducted at 55 °C for 91 days and then at 30 °C for an additional 56 days. After 91 days, the composts were inoculated with a mixed population of melamine-degrading microorganisms. Melamine resin degradation after the entire 147 days of composting varied between 73 and 95% for the treatments with inoculation of microorganisms compared to 55–74% for the treatments without inoculation. Degradation was also enhanced by nutrients and gypsum additions. Our results infer that large scale composting of melamine resins in paint sludge is possible. - Highlights: ► Melamine resin in waste paint sludges could be efficiently composted at bench scale. ► Melamine resin degradation after 147 days of composting was 73–95% complete. ► Nutrients, gypsum and melamine-degrading microorganisms increased composting rate. ► Melamine degradation products first increased and then decreased in the compost. ► Final compost was enriched in nitrogen and other essential plant nutrients. - Melamine resin in waste paint sludges was efficiently composted at bench scale, with finished composts having low levels of heavy metals and enriched in plant nutrients.

  15. Employment effects of minimum wages

    OpenAIRE

    Neumark, David

    2014-01-01

    The potential benefits of higher minimum wages come from the higher wages for affected workers, some of whom are in low-income families. The potential downside is that a higher minimum wage may discourage employers from using the low-wage, low-skill workers that minimum wages are intended to help. Research findings are not unanimous, but evidence from many countries suggests that minimum wages reduce the jobs available to low-skill workers.

  16. Effects of the Minimum Wage on the Employment Status of Youths. An Update.

    Science.gov (United States)

    Wellington, Alison J.

    1991-01-01

    Using data from 1954-86, including the 1980s period of relative decline in the value of the minimum wage, a study found that a 10 percent increase in minimum wage reduced teen unemployment by less than 1 percent. In addition, no apparent effect on employment of adults aged 20-24 was found, and minimal differences appeared for sex and race. (SK)

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

    International Nuclear Information System (INIS)

    Hladek, K.L.

    1997-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    Hladek, K.L.

    1997-10-07

    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

  19. Influence of assumptions about household waste composition in waste management LCAs

    International Nuclear Information System (INIS)

    Slagstad, Helene; Brattebø, Helge

    2013-01-01

    Highlights: ► Uncertainty in waste composition of household waste. ► Systematically changed waste composition in a constructed waste management system. ► Waste composition important for the results of accounting LCA. ► Robust results for comparative LCA. - Abstract: This article takes a detailed look at an uncertainty factor in waste management LCA that has not been widely discussed previously, namely the uncertainty in waste composition. Waste composition is influenced by many factors; it can vary from year to year, seasonally, and with location, for example. The data publicly available at a municipal level can be highly aggregated and sometimes incomplete, and performing composition analysis is technically challenging. Uncertainty is therefore always present in waste composition. This article performs uncertainty analysis on a systematically modified waste composition using a constructed waste management system. In addition the environmental impacts of several waste management strategies are compared when applied to five different cities. We thus discuss the effect of uncertainty in both accounting LCA and comparative LCA. We found the waste composition to be important for the total environmental impact of the system, especially for the global warming, nutrient enrichment and human toxicity via water impact categories.

  20. 40 CFR 265.273 - Waste analysis.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Waste analysis. 265.273 Section 265... FACILITIES Land Treatment § 265.273 Waste analysis. In addition to the waste analyses required by § 265.13... listed as a hazardous waste. As required by § 265.13, the waste analysis plan must include analyses...

  1. Properties of radioactive wastes and waste containers

    International Nuclear Information System (INIS)

    Morcos, N.; Dayal, R.

    1982-01-01

    This program is sponsored by the Nuclear Regulatory Commission to address basic concerns in assessing the performance of solidified radwaste. Experiments were initiated to address these concerns. In particular, leachability of solidified radwastes and the physical stability of the ensuing waste forms were evaluated. In addition, leaching experiments designed to address the effects of alternating wet/dry cycles and of varying the length of these cycles on the leach behavior of waste forms were initiated

  2. Criticality safety study of Pu contaminated carbon waste stored in 100 L steel drums

    International Nuclear Information System (INIS)

    Anno, J.; Simonneau, M.

    1995-01-01

    The notion of the minimum critical areal density (D minca ) used to ensure the Criticality-Safety of poor solid waste is recalled with its deficiencies. D minca is assumed constant, independent of the fissile material concentration. This assumption is only true for unreflected mediums. Corrective factors are established. Furthermore, the usual norm of the Pu-H 2 O, which is 0.20 g/cm 2 , (concrete reflected) is greater than that for other mediums, such as Pu contaminated graphite waste (Pu-C), which is 0.036 g/cm 2 . D minca calculated on infinite slabs is confirmed by calculations on infinite planar multilayers arrays of 100 l cubical waste drums. Moreover, d minca increases linearly with the steel thickness of the drums' walls and goes up to 0.17 g/cm 2 for 0.105 cm of steel. The safety analysis on a real storage case takes into account the limited amount of Pu (100 g) and C (100 kg), the minimum thickness of 0.07 cm of drums' steel, their geometrical arrangement, the heterogeneity and size of contamination and the occurrence of neutronic poison (N and Cl) in the waste. Because of these parameters, the Keff are very less than 0.95 and the taken norm of 0.1 g/cm 2 for the Pu-C waste is fulfilled. Finally, it is demonstrated that the mixing of Pu-C waste drums and Pu-H 2 O wastes drums is allowed. (authors). 14 refs., 5 figs., 6 tabs

  3. Hanford Site Solid Waste Landfill permit application

    International Nuclear Information System (INIS)

    1991-01-01

    Daily activities at the Hanford Site generate sanitary solid waste (nonhazardous and nonradioactive) that is transported to and permanently disposed of at the Hanford Site Solid Waste Landfill. This permit application describes the manner in which the solid Waste Landfill will be operated under Washington State Department of Ecology Minimum Functional Standards for Solid Waste Handling, Washington Administrative Code 173-304. The solid Waste Landfill is owned by the US Department of Energy -- Richland Operations Office and is used for disposal of solid waste generated at the US Department of Energy Hanford Site. The jurisdictional health department's permit application form for the Solid Waste Landfill is provided in Chapter 1.0. Chapter 2.0 provides a description of the Hanford Site and the Solid Waste Landfill and reviews applicable locational, general facility, and landfilling standards. Chapter 3.0 discusses the characteristics and quantity of the waste disposed of in the Solid Waste Landfill. Chapter 4.0 reviews the regional and site geology and hydrology and the groundwater and vadose zone quality beneath the landfill. Chapters 5.0, 6.0, and 7.0 contain the plan of operation, closure plan, and postclosure plan, respectively. The plan of operation describes the routine operation and maintenance of the Solid Waste Landfill, the environmental monitoring program, and the safety and emergency plans. Chapter 5.0 also addresses the operational cover, environmental controls, personnel requirements, inspections, recordkeeping, reporting, and site security. The postclosure plan describes requirements for final cover maintenance and environmental monitoring equipment following final closure. Chapter 8.0 discusses the integration of closure and postclosure activities between the Solid Waste Landfill and adjacent Nonradioactive Dangerous Waste Landfill. 76 refs., 48 figs, 15 tabs

  4. Evaluating non-incinerative treatment of organically contaminated low level mixed waste

    International Nuclear Information System (INIS)

    Shuck, D.L.; Wade, J.F.

    1993-01-01

    This investigation examines the feasibility of using non-incinerator technologies effectively to treat organically contaminated mixed waste. If such a system is feasible now, it would be easier to license because it would avoid the stigma that incineration has in the publics' perception. As other DOE facilities face similar problems, this evaluation is expected to be of interest to both DOE and the attendees of WM'93. This investigation considered treatment to land disposal restriction (LDR) standards of 21 different low level mixed (LLM) waste streams covered by the Rocky Flats Federal Facilities Compliance Agreement (FFCA) agreement with the Environmental Protection Agency (EPA). Typically the hazardous components consists of organic solvent wastes and the radioactive component consists of uranic/transuranic wastes. Limited amounts of cyanide and lead wastes are also involved. The primary objective of this investigation was to identify the minimum number of non-thermal unit processes needed to effectively treat this collection of mixed waste streams

  5. Project B-589, 300 Area transuranic waste interim storage project engineering study

    International Nuclear Information System (INIS)

    Greenhalgh, W.O.

    1985-08-01

    The purpose of the study was to look at various alternatives of taking newly generated, remote-handled transuranic waste (caisson waste) in the 300 Area, performing necessary transloading operations and preparing the waste for storage. The prepared waste would then be retrieved when the Waste Isolation Pilot Plant becomes operational and transshipped to the repository in New Mexico with a minimum of inspection and packaging. The scope of this study consisted of evaluating options for the transloading of the TRU wastes for shipment to a 200 Area storage site. Preconceptual design information furnished as part of the engineering study is listed below: produce a design for a clean, sealed waste canister; hot cell loadout system for the waste; in-cell loading or handling equipment; determine transshipment cask options; determine assay system requirements (optional); design or specify transport equipment required; provide a SARP cost estimate; determine operator training requirements; determine waste compaction equipment needs if desirable; develop a cost estimate and approximate schedule for a workable system option; and update the results presented in WHC Document TC-2025

  6. Using cement, lignite fly ash and baghouse filter waste for solidification of chromium electroplating treatment sludge

    Directory of Open Access Journals (Sweden)

    Wantawin, C.

    2004-02-01

    Full Text Available The objective of the study is to use baghouse filter waste as a binder mixed with cement and lignite fly ash to solidify sludge from chromium electroplating wastewater treatment. To save cost of solidification, reducing cement in binder and increasing sludge in the cube were focused on. Minimum percent cement in binder of 20 for solidification of chromium sludge was found when controlling lignite fly ash to baghouse filter waste at the ratio of 30:70, sludge to binder ratio of 0.5, water to mixer ratio of 0.3 and curing time of 7 days. Increase of sludge to binder ratio from 0.5 to 0.75 and 1 resulted in increase in the minimum percent cement in binder up to 30 percent in both ratios. With the minimum percent cement in binder, the calculated cement to sludge ratios for samples with sludge to binder ratios of 0.5, 0.75 and 1 were 0.4, 0.4 and 0.3 respectively. Leaching chromium and compressive strength of the samples with these ratios could achieve the solidified waste standard by the Ministry of Industry. For solidification of chromium sludge at sludge to binder ratio of 1, the lowest cost binder ratio of cement to lignite fly ash and baghouse filter waste in this study was 30:21:49. The cost of binder in this ratio was 718 baht per ton dry sludge.

  7. FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Templeton, K.J.

    1996-05-23

    For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

  8. FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

    International Nuclear Information System (INIS)

    Templeton, K.J.

    1996-01-01

    For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

  9. Characterization mixtures of thick gypsum with addition of treated waste from laminated plasterboards

    Directory of Open Access Journals (Sweden)

    Rodríguez-Orejón, A.

    2014-06-01

    Full Text Available nvironmental protection involves the reuse of construction and demolition waste. In order to improve recycling, waste from laminated plasterboards is used in the cement and laminated gypsum boards manufacture.This article analyzes the use of ground and burnt laminated plasterboard (BLG waste mixed with thick gypsum (TG. Physical-mechanical characterization of superficial hardness and mechanical strength has been performed on different batches of plaster powder materials with different BLG waste particle sizes to determine its suitability. Coarse particle sizes were preferred in order to reduce the waste treatment. From all the mixtures studied, the one with the best results was TG + 5% BLG1.25 which forms a material of higher superficial hardness and strength. The results obtained in the study have proved suitable products for building use (both as renders and as prefabricated elements enabling for a reduction in the consumption of natural resources.La protección del medio ambiente implica la reutilización de los residuos de construcción y demolición. Los residuos de placas de yeso laminado se utilizan en la fabricación de cemento y de placas de yeso laminado. En este artículo se ha estudiado la utilización deresiduos de placa de yeso laminado cocido (YLC mezclado con yeso grueso (YG, realizándose la caracterización físico-mecánica de dureza superficial y resistencias mecánicas, para determinar su idoneidad formando materiales de yeso en polvo con distintas granulometrías de residuos de (YLC, teniendo preferencia por granulometrías gruesas, que reducen el tratamiento del residuo. De las mezclas estudiadas la que mejores resultados ha ofrecido es YG + 5%YLC1,25 formando un material de mayor dureza superficial y resistencia. De los resultados obtenidos en el estudio se puede afirmar que se han conseguido productos aptos para su utilización en edificación posibilitando una reducción del consumo de recursos naturales.

  10. Tank waste chemistry: A new understanding of waste aging

    International Nuclear Information System (INIS)

    Babad, H.; Camaioni, D.M.; Lilga, M.A.; Samuels, W.D.; Strachan, D.M.

    1993-02-01

    There is concern about the risk of uncontrolled exothermic reactions(s) in Hanford Site waste tanks containing NO 3 minus /NO 2 minus based salts and/or metal hydroxide sludges in combination with organics or ferrocyanides. However, gradual oxidation of the waste in the tanks to less reactive species appears to have reduced the risk. In addition, wastes sampled to date contain sufficiently large quantities of water so that propagation reactions are highly unlikely. This report details an investigation into the risk of an uncontrolled exothermic reaction in Hanford Site high-activity water tanks

  11. Minimum Wages and Poverty

    OpenAIRE

    Fields, Gary S.; Kanbur, Ravi

    2005-01-01

    Textbook analysis tells us that in a competitive labor market, the introduction of a minimum wage above the competitive equilibrium wage will cause unemployment. This paper makes two contributions to the basic theory of the minimum wage. First, we analyze the effects of a higher minimum wage in terms of poverty rather than in terms of unemployment. Second, we extend the standard textbook model to allow for incomesharing between the employed and the unemployed. We find that there are situation...

  12. Biodiesel production from waste animal fat and improvement of its characteristics by synthesized nickel and magnesium additive

    Energy Technology Data Exchange (ETDEWEB)

    Guerue, Metin; Artukoglu, Bursev Dogan [Gazi University, Engineering and Architecture Faculty, Chemical Engineering Department, 06570 Ankara (Turkey); Keskin, Ali [Mersin University, Technical Education Faculty, 33500 Mersin (Turkey); Koca, Atilla [Gazi University, Technical Education Faculty, 06500 Ankara (Turkey)

    2009-03-15

    The purpose of this study is to produce trimethyl ester from waste animal fat at optimum conditions and improve its characteristics by synthesized nickel and magnesium additives. In this study, a two step catalytic process for synthesis of biodiesel was studied by reacting waste animal fats with methanol. The temperature, amount of methanol and type and amount of catalyst are investigated as parameters, and the changes in viscosity and flash point of animal fat biodiesel were determined. Furthermore, the effects of organic based Ni and Mg additives on the methyl ester pour point were specified. Optimum producing conditions were determined experimentally. At the end of these experiments, the maximum yield of 89% was obtained in two steps with total 0.35 (w/w) methanol/fat, at 62 {+-} 1 C reaction temperature for 2 h reaction period and by catalysing with 0.08 (w/w) H{sub 2}SO{sub 4}/fat and 0.01 (w/w) NaOH/fat ratios. Organic based metal compounds were synthesized by reacting abietic acid in the tall oil resinic acid with NiO and MgO compounds in order to improve the animal fat methyl ester characteristics. Reduction of the pour point was achieved by adding organic based nickel and magnesium compounds to biodiesel at a ratio of 12 {mu}mol/l oil methyl ester. Also, the blend of animal fat methyl ester-Diesel fuel was tested in a direct injection Diesel engine. The maximum effect of the new fuel blend on the engine performance was reached at 2200 min{sup -1} of engine torque. The lowest specific fuel consumptions were obtained at 2200 min{sup -1} for both fuels. (author)

  13. Biodiesel production from waste animal fat and improvement of its characteristics by synthesized nickel and magnesium additive

    International Nuclear Information System (INIS)

    Guerue, Metin; Artukoglu, Bursev Dogan; Keskin, Ali; Koca, Atilla

    2009-01-01

    The purpose of this study is to produce trimethyl ester from waste animal fat at optimum conditions and improve its characteristics by synthesized nickel and magnesium additives. In this study, a two step catalytic process for synthesis of biodiesel was studied by reacting waste animal fats with methanol. The temperature, amount of methanol and type and amount of catalyst are investigated as parameters, and the changes in viscosity and flash point of animal fat biodiesel were determined. Furthermore, the effects of organic based Ni and Mg additives on the methyl ester pour point were specified. Optimum producing conditions were determined experimentally. At the end of these experiments, the maximum yield of 89% was obtained in two steps with total 0.35 (w/w) methanol/fat, at 62 ± 1 deg. C reaction temperature for 2 h reaction period and by catalysing with 0.08 (w/w) H 2 SO 4 /fat and 0.01 (w/w) NaOH/fat ratios. Organic based metal compounds were synthesized by reacting abietic acid in the tall oil resinic acid with NiO and MgO compounds in order to improve the animal fat methyl ester characteristics. Reduction of the pour point was achieved by adding organic based nickel and magnesium compounds to biodiesel at a ratio of 12 μmol/l oil methyl ester. Also, the blend of animal fat methyl ester-Diesel fuel was tested in a direct injection Diesel engine. The maximum effect of the new fuel blend on the engine performance was reached at 2200 min -1 of engine torque. The lowest specific fuel consumptions were obtained at 2200 min -1 for both fuels

  14. Waste minimisation. Home digestion trials of biodegradable waste

    Energy Technology Data Exchange (ETDEWEB)

    Bench, M.L.; Woodard, R.; Harder, M.K.; Stantzos, N. [Waste and Energy Research Group (WERG), Faculty of Science and Engineering, University of Brighton, East Sussex BN2 4GJ (United Kingdom)

    2005-09-01

    Minimisation of municipal solid waste and diversion from landfill are necessary for the UK to manage waste sustainably and achieve legislative compliance. A survey of householder attitudes and experiences of a trial for minimising household food waste from waste collection in the county of West Sussex, UK is described. The minimisation method used the Green Cone food digester, designed for garden installation. A postal questionnaire was distributed to 1000 householders who had bought a cone during the trial and a total of 433 responses were received. The main reason for people buying the Green Cone had been concerns about waste (88%), with 78% and 67% of respondents, respectively, claiming to have participated in recycling and home composting in the last 30 days. The waste material most frequently put in the digester was cooked food (91%), followed by fruit waste, vegetable matter and bones/meat. Some respondents were using it for garden and animal waste from pets. Most users found the Green Cone performed satisfactorily. Approximately, 60% of respondents had seen a reduction of 25-50% in the amount of waste they normally put out for collection, with analysis showing reported levels of reduction to be significant (p<0.05). Additional weight surveys by householders recorded an average of 2.7kg/(hweek) diverted to the food digester.

  15. Radioactive waste management at AECL

    International Nuclear Information System (INIS)

    Gadsby, R.D.; Allan, C.J.

    2003-01-01

    AECL has maintained an active program in radioactive waste management since 1945, when the Canadian nuclear program commenced activities at the Chalk River Laboratories (CRL). Waste management activities have included operation of waste management storage and processing facilities at AECL's CRL and Whiteshell Laboratories (WL); operation of the Low Level Radioactive Waste Management Office on behalf of Natural Resources Canada to resolve historic radioactive waste problems (largely associated with radioactive ore recovery, transport and processing operations) that are the responsibility of the Federal Government; development of the concept and related technology for geological disposal of Canada's nuclear fuel waste; development of the Intrusion-Resistant Underground Structure (IRUS) disposal concept for low-level nuclear waste; development of dry storage technology for the interim storage of used fuel; and development and assessment of waste processing technology for application in CANDU nuclear power plants and at CRL and WL. Today these activities are continuing. In addition, AECL is: preparing to decommission the nuclear facilities at WL; carrying out a number of smaller decommissioning projects at CRL; putting in place projects to upgrade the low-level liquid waste processing capabilities of the CRL Waste Treatment Centre, recover and process highly active liquid wastes currently in storage, and recover, condition and improve the storage of selected fuel wastes currently stored in below-ground standpipes in the CRL waste management areas; and assessing options for additional remediation projects to improve the management of other wastes currently in storage and to address environmental contamination from past practices. (author)

  16. 75 FR 6151 - Minimum Capital

    Science.gov (United States)

    2010-02-08

    ... capital and reserve requirements to be issued by order or regulation with respect to a product or activity... minimum capital requirements. Section 1362(a) establishes a minimum capital level for the Enterprises... entities required under this section.\\6\\ \\3\\ The Bank Act's current minimum capital requirements apply to...

  17. A Pareto-Improving Minimum Wage

    OpenAIRE

    Eliav Danziger; Leif Danziger

    2014-01-01

    This paper shows that a graduated minimum wage, in contrast to a constant minimum wage, can provide a strict Pareto improvement over what can be achieved with an optimal income tax. The reason is that a graduated minimum wage requires high-productivity workers to work more to earn the same income as low-productivity workers, which makes it more difficult for the former to mimic the latter. In effect, a graduated minimum wage allows the low-productivity workers to benefit from second-degree pr...

  18. Glassceramics obtained from industrial waste

    Energy Technology Data Exchange (ETDEWEB)

    Cimdins, R.; Rozenstrauha, I.; Berzina, L. [Riga Technical University, Faculty of Chemical Technology, Biomaterials R and D Laboratory, 14/24 Azenes St., LV-1048 Riga (Latvia); Bossert, J.; Buecker, M. [Technisches Institut Materialwissenschaft, Friedrich-Schiller Universitaet, Loebdegraben 32, 07743 Jena (Germany)

    2000-06-01

    Large areas of Latvia are contaminated with industrial waste: metallurgical slag, fly-ash, etching refuse, peat, and coal ash as well as glass waste which often contain dangerous substances. From the environmental point of view this waste should be neutralised. As this waste also contains valuable chemical compounds, it can be considered as a raw material for the generation of new materials. One method of utilisation is to produce recycled materials - street plates, decorative tiles, or floor tiles. Dense sintered glassceramics with a water uptake of 0.34-3.23 wt.%, a final density of 2.93-3.05 g/cm{sup 3}, and a bending strength of 80-96 MPa have been created from industrial waste. The mast chemically durable glassceramics contained clay additions. Thus, the material containing only waste had a durability (mass loss) of 3.02% in 0.1 N HCl, while the composition containing 30% clay addition had a durability of 0.2% in 0.1 N HCl.

  19. Hanford waste-form release and sediment interaction: A status report with rationale and recommendations for additional studies

    International Nuclear Information System (INIS)

    Serne, R.J.; Wood, M.I.

    1990-05-01

    This report documents the currently available geochemical data base for release and retardation for actual Hanford Site materials (wastes and/or sediments). The report also recommends specific laboratory tests and presents the rationale for the recommendations. The purpose of this document is threefold: to summarize currently available information, to provide a strategy for generating additional data, and to provide recommendations on specific data collection methods and tests matrices. This report outlines a data collection approach that relies on feedback from performance analyses to ascertain when adequate data have been collected. The data collection scheme emphasizes laboratory testing based on empiricism. 196 refs., 4 figs., 36 tabs

  20. Influence of assumptions about household waste composition in waste management LCAs.

    Science.gov (United States)

    Slagstad, Helene; Brattebø, Helge

    2013-01-01

    This article takes a detailed look at an uncertainty factor in waste management LCA that has not been widely discussed previously, namely the uncertainty in waste composition. Waste composition is influenced by many factors; it can vary from year to year, seasonally, and with location, for example. The data publicly available at a municipal level can be highly aggregated and sometimes incomplete, and performing composition analysis is technically challenging. Uncertainty is therefore always present in waste composition. This article performs uncertainty analysis on a systematically modified waste composition using a constructed waste management system. In addition the environmental impacts of several waste management strategies are compared when applied to five different cities. We thus discuss the effect of uncertainty in both accounting LCA and comparative LCA. We found the waste composition to be important for the total environmental impact of the system, especially for the global warming, nutrient enrichment and human toxicity via water impact categories. Copyright © 2012 Elsevier Ltd. All rights reserved.

  1. 76 FR 47985 - Standard Instrument Approach Procedures, and Takeoff Minimums and Obstacle Departure Procedures...

    Science.gov (United States)

    2011-08-08

    ...;Prices of new books are listed in the first FEDERAL REGISTER issue of each #0;week. #0; #0; #0; #0;#0... and Takeoff Minimums and ODP copies may be obtained from: 1. FAA Public Inquiry Center (APA-200), FAA... Minimums and ODPs, in addition to their complex nature and the need for a special format make publication...

  2. Harmonization of industrial and oilfield waste management issues in Alberta

    International Nuclear Information System (INIS)

    Halla, S.

    1999-01-01

    There has been an ongoing discussion concerning the harmonization of waste management requirements within Alberta between the Alberta Energy and Utilities Board (EUB) and Alberta Environment (AENV), with the ultimate goal of publishing a memorandum of understanding (MOU) that will lay out the division of responsibilities between the two authorities on this matter. An overview is included of waste management in Alberta and of the harmonization agreements attained to date, with a stress on oil field waste issues. The EUB and AENV developed a MOE on the harmonization of waste management in Alberta, and a discussion is made of the concept of equivalency, which is used in the development of 'EUB guide 58: oilfield waste management requirements for the upstream petroleum industry' and will be a guiding principle for the MOU. Although the EUB's processes for waste management will not be exactly the same as AENV's, the EUB has made the commitment that, as a minimum, the requirements will provide the same level of environmental protection and public safety equivalent to that provided by AENV

  3. Feasibility of deep ocean disposal of heat generating waste. V.1

    International Nuclear Information System (INIS)

    Hemming, C.R.

    1988-06-01

    This report summarises the research performed in the UK during the period 1977 to 1987 as part of the international programme investigating the feasibility of ocean disposal of heat generating radioactive waste. This study has involved: (i) the definition of the disposal operations needed to meet the minimum requirements for safely emplacing waste on or under the floor of the deep ocean; (ii) the identification and characterisation of areas of the deep ocean that might be suitable for containing heat generating waste; (iii) a study of the processes by which radionuclides might migrate through the multiple barriers that isolate the waste from man's environment; and (iv) a calculation of the radiological impact of the conceptual deep ocean repository. It is concluded that, from a technical and scientific viewpoint, disposal of heat generating waste in the deep ocean could provide a safe, economic and feasible alternative to deep disposal on land. (author)

  4. Bread enriched in lycopene and other bioactive compounds by addition of dry tomato waste

    OpenAIRE

    Nour, Violeta; Ionica, Mira Elena; Trandafir, Ion

    2015-01-01

    The tomato processing industry generates high amounts of waste, mainly tomato skins and seeds, which create environmental problems. These residues are attractive sources of valuable bioactive components and pigments. A relatively simple recovery technology could consist of production of powders to be directly incorporated into foods. Tomato waste coming from a Romanian tomato processing unit were analyzed for the content of several bioactive compounds like ascorbic acid, β-carotene, lycopene,...

  5. The effect of moisture regimes on the anaerobic degradation of municipal solid waste from Metepec (Mexico)

    International Nuclear Information System (INIS)

    Hernandez-Berriel, Ma.C.; Marquez-Benavides, L.; Gonzalez-Perez, D.J.; Buenrostro-Delgado, O.

    2008-01-01

    The State of Mexico, situated in central Mexico, has a population of about 14 million, distributed in approximately 125 counties. Solid waste management represents a serious and ongoing pressure to local authorities. The final disposal site ('El Socavon') does not comply with minimum environmental requirements as no liners or leachate management infrastructure are available. Consequently, leachate composition or the effects of rain water input on municipal solid waste degradation are largely unknown. The aim of this work was to monitor the anaerobic degradation of municipal solid waste (MSW), simulating the water addition due to rainfall, under two different moisture content regimes (70% and 80% humidity). The study was carried out using bioreactors in both laboratory and pilot scales. The variation of organic matter and pH was followed in the solid matrix of the MSW. The leachate produced was used to estimate the field capacity of the MSW and to determine the pH, COD, BOD and heavy metals. Some leachate parameters were found to be within permitted limits, but further research is needed in order to analyze the leachate from lower layers of the disposal site ('El Socavon')

  6. Rethinking Timber: Investigation into the Use of Waste Macadamia Nut Shells for Additive Manufacturing

    Science.gov (United States)

    Girdis, Jordan; Gaudion, Lauren; Proust, Gwénaëlle; Löschke, Sandra; Dong, Andy

    2017-03-01

    In this article, the feasibility of turning macadamia nutshells, a waste product from the forestry and agricultural industries, into a three-dimensional (3D) printed, innovative, microtimber product is examined by composing a wood plastic feed stock for fusion deposition modeling. Different ratios of micro-ground macadamia nutshells and acrylonitrile butadiene styrene (ABS) plastics were mixed with a binding agent to extrude a range of filaments. By using a commercial 3D printer, these filaments helped to fabricate specimens that were tested in tension and compression. The results show that printed samples of macadamia-nutshell—ABS composites offer a viable alternative to commercially available wood polymer composite filaments. Although they possess similar mechanical properties, they have a lower density, making them suitable for a range of lightweight product applications. The research demonstrates that there are new opportunities for the use of macadamia nutshell filament in additive manufacturing as a result of its enhanced properties compared with traditional wood filaments.

  7. The radioactive waste management at IAEA laboratories

    International Nuclear Information System (INIS)

    Deron, S.; Ouvrard, R.; Hartmann, R.; Klose, H.

    1992-10-01

    The report gives a brief description of the nature of the radioactive wastes generated at the IAEA Laboratories in Seibersdorf, their origin and composition, their management and monitoring. The management of the radioactive waste produced at IAEA Laboratories in Seibersdorf is governed by the Technical Agreements of 1985 between the IAEA and the Austrian Health Ministry. In the period of 1982 to 1991 waste containers of low activity and radiotoxicity generated at laboratories other than the Safeguards Analytical Laboratory (SAL) were transferred to the FZS waste treatment and storage plant: The total activity contained in these drums amounted to < 65 MBq alpha activity; < 1030 MBq beta activity; < 2900 MBq gamma activity. The radioactive waste generated at SAL and transferred to the FZs during the same period included. Uranium contaminated solid burnable waste in 200 1 drums, uranium contaminated solid unburnable waste in 200 1 drums, uranium contaminated liquid unburnable waste in 30 1 bottles, plutonium contaminated solid unburnable waste in 200 1 drums. In the same period SAL received a total of 146 Kg uranium and 812 g plutonium and exported out of Austria, unused residues of samples. The balance, i.e.: uranium 39 kg, plutonium 133 g constitutes the increase of the inventory of reference materials, and unused residues awaiting export, accumulated at SAL and SIL fissile store as a result of SAL operation during this 10 year period. The IAEA reexports all unused residues of samples of radioactive and fissile materials analyzed at his laboratories, so that the amount of radioactive materials ending in the wastes treated and stored at FZS is kept to a minimum. 5 refs, 7 figs, 3 tabs

  8. Improved anaerobic biodegradation of biosolids by the addition of food waste as a co-substrate

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H.-W.; Han, S.-K.; Song, Y.-C.; Baek, B.-C.; Yoo, K.-S.; Lee, J.-J.; Shin, H.-S.

    2003-07-01

    The temperature phased anaerobic digestion (TPAD) process was applied to increase the performance of anaerobic treatment of biosolids. Previously obtained results indicate that this system showed the advantages of thermophilic and mesophilic anaerobic digestion process. By comparing the performance of each reactor of the system, it was illustrated that the main stage of methane production was the thermophilic reactor which has faster microbial metabolism. However, the result revealed that substrate characteristics of low VS/TS limited the system performance. Therefore, to evaluate the effect of food waste as a co-substrate for improving anaerobic biodegradability, biochemical methane potential (BMP) tests were conducted in thermophilic conditions with biomass of thermophilic reactor. It was confirmed that the co-digestion of sewage sludge mixed with food waste had a distinct improvement on biodegradability. The most significant advantages were the preferable environment provided by food waste for the growth and activity of anaerobes and the mutual assistance between biosolids and food waste. (author)

  9. Waste segregation procedures and benefits

    International Nuclear Information System (INIS)

    Fish, J.D.; Massey, C.D.; Ward, S.J.

    1990-01-01

    Segregation is a critical first step in handling hazardous and radioactive materials to minimize the generation of regulated wastes. In addition, segregation can significantly reduce the complexity and the total cost of managing waste. Procedures at Sandia National Laboratories, Albuquerque require that wastes be segregated, first, by waste type (acids, solvents, low level radioactive, mixed, classified, etc.). Higher level segregation requirements, currently under development, are aimed at enhancing the possibilities for recovery, recycle and reapplication; reducing waste volumes; reducing waste disposal costs, and facilitating packaging storage, shipping and disposal. 2 tabs

  10. Low-level waste management

    International Nuclear Information System (INIS)

    Levin, G.B.

    1980-01-01

    An overview of the current situation in the United States and a look to the future of low-level waste management are presented. Current problems and challenges are discussed, such as: the need of additional disposal sites in the future; risks and costs involved in transport of low-level wastes; reduction of low-level waste volume through smelting, incineration, and storage for wastes containing nuclides with short half lives; development of a national policy for the management of low-level waste, and its implementation through a sensible system of regulations. Establishing a success with low-level waste management should provide the momentum and public confidence needed to continue on and to resolve the technical and politically more difficult low-level waste problems

  11. Determination of service standard time for liquid waste parameter in certification institution

    Science.gov (United States)

    Sembiring, M. T.; Kusumawaty, D.

    2018-02-01

    Baristand Industry Medan is a technical implementation unit under the Industrial and Research and Development Agency, the Ministry of Industry. One of the services often used in Baristand Industry Medan is liquid waste testing service. The company set the standard of service 9 working days for testing services. At 2015, 89.66% on testing services liquid waste does not meet the specified standard of services company. The purpose of this research is to specify the standard time of each parameter in testing services liquid waste. The method used is the stopwatch time study. There are 45 test parameters in liquid waste laboratory. The measurement of the time done 4 samples per test parameters using the stopwatch. From the measurement results obtained standard time that the standard Minimum Service test of liquid waste is 13 working days if there is testing E. coli.

  12. Reforming the minimum wage: Toward a psychological perspective.

    Science.gov (United States)

    Smith, Laura

    2015-09-01

    The field of psychology has periodically used its professional and scholarly platform to encourage national policy reform that promotes the public interest. In this article, the movement to raise the federal minimum wage is presented as an issue meriting attention from the psychological profession. Psychological support for minimum wage reform derives from health disparities research that supports the causal linkages between poverty and diminished physical and emotional well-being. Furthermore, psychological scholarship relevant to the social exclusion of low-income people not only suggests additional benefits of financially inclusive policymaking, it also indicates some of the attitudinal barriers that could potentially hinder it. Although the national living wage debate obviously extends beyond psychological parameters, psychologists are well-positioned to evaluate and contribute to it. (PsycINFO Database Record (c) 2015 APA, all rights reserved).

  13. Minimum critical mass systems

    International Nuclear Information System (INIS)

    Dam, H. van; Leege, P.F.A. de

    1987-01-01

    An analysis is presented of thermal systems with minimum critical mass, based on the use of materials with optimum neutron moderating and reflecting properties. The optimum fissile material distributions in the systems are obtained by calculations with standard computer codes, extended with a routine for flat fuel importance search. It is shown that in the minimum critical mass configuration a considerable part of the fuel is positioned in the reflector region. For 239 Pu a minimum critical mass of 87 g is found, which is the lowest value reported hitherto. (author)

  14. Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the US Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.; Chang, Y.S.

    1996-12-01

    This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II) and presents the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)

  15. Effect of waste polymer addition on the rheology of modified bitumen

    Energy Technology Data Exchange (ETDEWEB)

    M. Garcia-Morales; P. Partal; F.J. Navarro; C. Gallegos [Universidad de Huelva, Huelva (Spain). Departamento de Ingenieria Quimica, Facultad de Ciencias Experimentales

    2006-05-15

    This paper deals with the modification of petroleum bitumen with four different types of waste polymers. EVA, EVA/LDPE blend, crumb tire rubber and ABS, all of them coming from recycling plants of waste plastic materials, were used as modifying agents of the bitumen employed in the pavement building. Optical microscopy, modulated calorimetry and a set of different rheological tests were developed in order to characterise the modified bitumens. The results obtained reveal that tire rubber as well as its blends with other polymers can be considered as an interesting modifier of the bitumen in a wide range of temperatures. As an elastomer, it endows the pavement a higher flexibility, which makes it more resistant to the traffic loading. The blend composed of EVA and LDPE displays quite promising results at high in-service temperatures, due to the development of a polymer network throughout the modified bitumen. Furthermore, the calorimetry tests carried out demonstrate different degrees of compatibility between the bitumen and the polymers used. 45 refs., 8 figs., 3 tabs.

  16. Radiolytic decomposition of dioxins in liquid wastes

    International Nuclear Information System (INIS)

    Zhao Changli; Taguchi, M.; Hirota, K.; Takigami, M.; Kojima, T.

    2006-01-01

    The dioxins including polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) are some of the most toxic persistent organic pollutants. These chemicals have widely contaminated the air, water, and soil. They would accumulate in the living body through the food chains, leading to a serious public health hazard. In the present study, radiolytic decomposition of dioxins has been investigated in liquid wastes, including organic waste and waste-water. Dioxin-containing organic wastes are commonly generated in nonane or toluene. However, it was found that high radiation doses are required to completely decompose dioxins in the two solvents. The decomposition was more efficient in ethanol than in nonane or toluene. The addition of ethanol to toluene or nonane could achieve >90% decomposition of dioxins at the dose of 100 kGy. Thus, dioxin-containing organic wastes can be treated as regular organic wastes after addition of ethanol and subsequent γ-ray irradiation. On the other hand, radiolytic decomposition of dioxins easily occurred in pure-water than in waste-water, because the reaction species is largely scavenged by the dominant organic materials in waste-water. Dechlorination was not a major reaction pathway for the radiolysis of dioxin in water. In addition, radiolytic mechanism and dechlorinated pathways in liquid wastes were also discussed. (authors)

  17. Acid gas control process and apparatus for waste fired incinerators

    International Nuclear Information System (INIS)

    Kubin, P.Z.; Stepan, J.E.

    1992-01-01

    This patent describes a process for reducing noxious emission produced in a waste material incinerator. It comprises incinerating solid waste material in a furnace section of the waste material incinerator; providing an additive to an additive supply storage unit; conveying the additive to an additive injection means that communicates with the furnace section of the waste material incinerator; injecting the additive into a turbulent reaction zone of the furnace section such that acid gas content, acid dewpoint temperature and the level of corrosion in the incinerator are reduced

  18. TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

    International Nuclear Information System (INIS)

    1989-01-01

    Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig

  19. Amendment of the administrative skeleton provision for minimum requirements to be met by waste water discharged into bodies of water. Administrative skeleton provision on waste water of 25 November, 1992

    International Nuclear Information System (INIS)

    1994-01-01

    This provision applies to waste water to be discharged into bodies of water and whose pollution load stems mainly from the sectors indicated in appendices. Without prejudice to stricter requirements governing the execution of the Water Resources Act, the requirements to be met by the discharge of waste water, as indicated in appendices, are defined in accordance with section 7a, subsection 1, number 3 of the Water Resources Act. - The maximum concentrations indicated in appendices, for instance for waste water from brown coal briquetting plant, black coal treatment plant, petroleum refineries and flue gas scrubbers at combustion plant, relate to waste water in the discharge pipe of the waste water treatment plant. Contrary to technical rules that may apply in each instance, these concentrations must not be attained by dilution or mixing. (orig.) [de

  20. Improved cement mortars by addition of carbonated fly ash from solid waste incinerators

    Directory of Open Access Journals (Sweden)

    López-Zaldívar, O.

    2015-09-01

    Full Text Available This article presents the results of a research developing high performance cement mortars with the addition of municipal solid waste incineration fly ash (MSWIFA stabilized as insoluble carbonates. The encapsulation of hazardous wastes in mortar matrixes has also been achieved. The ashes present high concentrations of chlorides, Zn and Pb. A stabilization process with NaHCO3 has been developed reducing 99% the content of chlorides. Developed mortars replace 10% per weight of the aggregates by treated MSWIFA. Physical/mechanical properties of these mortars have been studied. Presence of Zn, Pb, Cu and Cd has been also analyzed confirming that leaching of these heavy metal ions is mitigated. Conclusions prove better behavior of CAC and CSA mortars than those of CEM-I and CEM-II cement. Results are remarkable for the CAC mortars, improving reference strengths in more than 25%, which make them a fast-curing product suitable for the repair of structures or industrial pavements.Este artículo presenta los resultados del desarrollo de morteros mejorados con la incorporación de cenizas volantes de residuos sólidos urbanos inertizadas en forma de carbonatos. Además se consigue la encapsulación de un residuo peligroso. Las cenizas presentan una alta concentración de cloruros, Zn y Pb. Se ha desarrollado un proceso de estabilización con NaHCO3 reduciendo en un 99% el contenido de cloruros. Los morteros reemplazan un 10% en peso del árido por cenizas tratadas. Se han analizado sus propiedades físico/mecánicas y la presencia de Zn, Pb, Cu y Cd. Se demuestra un mejor comportamiento de los morteros de CAC y CSA que los de CEM-I y CEM-II y se mitiga el lixiviado de metales pesados. Los resultados son significativos en los morteros CAC al mejorar las resistencias de los de referencia en un 25%. Los morteros desarrollados son de curado rápido adecuados para la reparación de estructuras o soleras industriales.

  1. Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

    International Nuclear Information System (INIS)

    FR-EEMAN, D.A.

    2003-01-01

    Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency

  2. Pyrolysis of virgin and waste polypropylene and its mixtures with waste polyethylene and polystyrene.

    Science.gov (United States)

    Kiran Ciliz, Nilgun; Ekinci, Ekrem; Snape, Colin E

    2004-01-01

    A comparison of waste and virgin polypropylene (PP) plastics under slow pyrolysis conditions is presented. Moreover, mixtures of waste PP with wastes of polyethylene (PE) and polystyrene (PS) were pyrolyzed under the same operating conditions. Not only the impact of waste on degradation products but also impacts of the variations in the mixing ratio were investigated. The thermogravimetric weight loss curves and their derivatives of virgin and waste PP showed differences due to the impurities which are dirt and food residues. The liquid yield distribution concerning the aliphatic, mono-aromatic and poly-aromatic compounds varies as the ratio of PP waste increases in the waste plastic mixtures. In addition to this, the alkene/alkane ratio of gas products shows variations depending on the mixing ratio of wastes.

  3. EVALUATION OF WASTE PACKAGE EXTERNAL ENVIRONMENTAL CONDITION STUDY

    International Nuclear Information System (INIS)

    E. N. Lindner and E. F. Dembowski

    1998-01-01

    The U. S. Department of Energy (DOE) is studying Yucca Mountain as the possible site for a permanent underground repository for disposal of spent nuclear fuel (SNF) and other high-level waste (HLW). The emplacement of high-level radioactive waste in Yucca Mountain will release a large amount of heat into the rock above and below the repository. Due to this heat, the rock temperature will rise, and then decrease when the production of decay heat falls below the rate at which heat escapes from the hot zone. In addition to raising the rock temperature, the heat will vaporize water, which will condense in cooler regions. The condensate water may drain back toward the emplacement drifts or it may ''shed'' through the pillars between emplacement drifts. Other effects, such as coupled chemical and mechanical processes, may influence the movement of water above, within, and below the emplacement drifts. This study examined near field environmental parameters that could have an effect on the waste package, including temperature, humidity, seepage rate, pH of seepage, chemistry (dissolved salts/minerals) of seepage, composition of drift atmosphere, colloids, and biota. This report is a Type I analysis performed in support of the development of System Description Documents (SDDs). A Type I analysis is a quantitative or qualitative analysis that may fulfill any of a variety of purposes associated with the Monitored Geologic Repository (MGR), other than providing direct analytical support for design output documents. A Type I analysis may establish design input, as defined in the ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998). This study establishes a technical basis for emplacement drift (i.e. at the waste package surface) environment criteria to be considered in the development of the waste package design. The information will support development of several SDDs and resolve emplacement drift external environment questions in the criteria of those

  4. 5 CFR 551.301 - Minimum wage.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Minimum wage. 551.301 Section 551.301... FAIR LABOR STANDARDS ACT Minimum Wage Provisions Basic Provision § 551.301 Minimum wage. (a)(1) Except... employees wages at rates not less than the minimum wage specified in section 6(a)(1) of the Act for all...

  5. Solid low-level waste forecasting guide

    International Nuclear Information System (INIS)

    Templeton, K.J.; Dirks, L.L.

    1995-03-01

    Guidance for forecasting solid low-level waste (LLW) on a site-wide basis is described in this document. Forecasting is defined as an approach for collecting information about future waste receipts. The forecasting approach discussed in this document is based solely on hanford's experience within the last six years. Hanford's forecasting technique is not a statistical forecast based upon past receipts. Due to waste generator mission changes, startup of new facilities, and waste generator uncertainties, statistical methods have proven to be inadequate for the site. It is recommended that an approach similar to Hanford's annual forecasting strategy be implemented at each US Department of Energy (DOE) installation to ensure that forecast data are collected in a consistent manner across the DOE complex. Hanford's forecasting strategy consists of a forecast cycle that can take 12 to 30 months to complete. The duration of the cycle depends on the number of LLW generators and staff experience; however, the duration has been reduced with each new cycle. Several uncertainties are associated with collecting data about future waste receipts. Volume, shipping schedule, and characterization data are often reported as estimates with some level of uncertainty. At Hanford, several methods have been implemented to capture the level of uncertainty. Collection of a maximum and minimum volume range has been implemented as well as questionnaires to assess the relative certainty in the requested data

  6. Radioactive waste management registry. A software tool for managing information on waste inventory

    International Nuclear Information System (INIS)

    Miaw, S.T.W.

    2001-01-01

    The IAEA developed a software tool, the RWM Registry (Radioactive Waste Management Registry) which is primarily concerned with the management and recording of reliable information on the radioactive waste during its life-cycle, i.e. from generation to disposal and beyond. In the current version, it aims to assist the management of waste from nuclear applications. the Registry is a managerial tool and offers an immediate overview of the various waste management steps and activities. This would facilitate controlling, keeping track of waste and waste package, planning, optimizing of resources, monitoring of related data, disseminating of information, taking actions and making decisions related to the waste management. Additionally, the quality control of waste products and a Member State's associated waste management quality assurance programme are addressed. The tool also facilitates to provide information on waste inventory as required by the national regulatory bodies. The RWM Registry contains two modules which are described in detail

  7. Waste management capabilities for alpha bearing wastes at the Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    Keenan, T.K.

    1977-01-01

    Waste Management activities at the Los Alamos Scientific Laboratory (LASL) involve a broad range of effort. There are requirements for daily processing of both liquid and solid radioactive and chemical wastes using a variety of technical operations. Approximately 4.5 x 10 7 l/y of liquids and 9 x 10 3 m 3 /y of solids are processed by the Waste Management Group of the LASL. In addition, a vigorous program of research, development, and demonstration studies leading to improved methods of waste treatment is also carried out within the same group. The current developmental studies involve incineration of transuranic-contaminated combustible wastes as well as other waste management aspects of alpha emitting transuranic (TRU) isotopes

  8. Waste management capabilities for alpha bearing wastes at the Los Alamos Scientific Laboratory

    International Nuclear Information System (INIS)

    Keenan, T.K.

    1978-01-01

    Waste Management activities at the Los Alamos Scientific Laboratory (LASL) involve a broad range of effort. There are requirements for daily processing of both liquid and solid radioactive and chemical wastes using a variety of technical operations. Approximately 4.5 x 10 7 l/yr of liquids and 9x10 3 m 3 /yr of solids are processed by the Waste Management Group of the LASL. In addition, a vigorous program of research, development, and demonstration studies leading to improved methods of waste treatment is also carried out within the same group. The current developmental studies involve incineration of transuranic-contaminated combustible wastes as well as other waste management aspects of alpha emitting transuranic (TRU) isotopes

  9. UO2-7%Gd2O3 fuel process development by mechanical blending with reprocessing of waste products and usage of densification additive

    International Nuclear Information System (INIS)

    Santos, Lauro Roberto dos

    2009-01-01

    In the nuclear fuel cycle, reprocessing and storage of 'burned' fuels, either temporary or permanent, demand high investments and, in addition, can potentially generate environmental problems. A strategy to decrease these problems is to adopt measures to reduce the amount of waste generated. The usage of integrated burnable poison based on gadolinium is a measure that contributes to achieve this goal. The reason to use burnable poison is to control the neutron population in the reactor during the early life of the fresh reactor core or the beginning of each recharging fuel cycle, extending its cycle duration. Another advantage of using burnable poison is to be able to operate the reactor with higher burning rate, optimizing the usage of the fuel. The process of manufacturing UO 2 -Gd 2 O 3 integrated burnable fuel poison generates waste that, as much as possible, needs to be recycled. Blending of Gd 2 O 3 in UO 2 powder requires the usage of a special additive to achieve the final fuel pellet specified density. The objective of this work is to develop the process of obtaining UO 2 - 7% Gd 2 O 3 integrated burnable poison using densification additives, aluminum hydroxide (Al(OH)3), and reprocessing manufacturing waste products by mechanical blending. The content of 7%- Gd 2 O 3 is based on commercial PWR reactor fuels - Type Angra 2. The results show that the usage of Al(OH) 3 as an additive is a very effective choice that promotes the densification of fuel pellets with recycle up to 10%. Concentrations of 0,20 % of Al(OH) 3 were found to be the indicated amount on an 7 industrial scale, specially when the recycled products come from U 3 O 8 obtained by calcination of sintered pellets. This is particularly interesting because it is following the steps of sintering and rectifying of the pellets, which is generating the largest amounts of recycled material. (author)

  10. UO2-7%Gd2O3 fuel process development by mechanical blending with reprocessing of waste products and usage of densification additive

    International Nuclear Information System (INIS)

    Santos, Lauro Roberto dos

    2009-01-01

    In the nuclear fuel cycle, reprocessing and storage of 'burned' fuels, either temporary or permanent, demand high investments and, in addition, can potentially generate environmental problems. A strategy to decrease these problems is to adopt measures to reduce the amount of waste generated. The usage of integrated burnable poison based on gadolinium is a measure that contributes to achieve this goal. The reason to use burnable poison is to control the neutron population in the reactor during the early life of the fresh reactor core or the beginning of each recharging fuel cycle, extending its cycle duration. Another advantage of using burnable poison is to be able to operate the reactor with higher burning rate, optimizing the usage of the fuel. The process of manufacturing UO 2 -Gd 2 O 3 integrated burnable fuel poison generates waste that, as much as possible, needs to be recycled. Blending of Gd 2 O 3 in UO 2 powder requires the usage of a special additive to achieve the final fuel pellet specified density. The objective of this work is to develop the process of obtaining UO 2 - 7% Gd 2 O 3 integrated burnable poison using densification additives, aluminum hydroxide (Al(OH) 3 ), and reprocessing manufacturing waste products by mechanical blending. The content of 7%- Gd 2 O 3 is based on commercial PWR reactor fuels - Type Angra 2. The results show that the usage of Al(OH) 3 as an additive is a very effective choice that promotes the densification of fuel pellets with recycle up to 10%. Concentrations of 0,20 % of Al(OH) 3 were found to be the indicated amount on an industrial scale, specially when the recycled products come from U 3 O 8 obtained by calcination of sintered pellets. This is particularly interesting because it is following the steps of sintering and rectifying of the pellets, which is generating the largest amounts of recycled material. (author)

  11. Risk assessment for the transportation of hazardous waste and hazardous waste components of low-level mixed waste and transuranic waste for the U.S. Department of Energy waste management programmatic environmental impact statement

    International Nuclear Information System (INIS)

    Lazaro, M.A.; Policastro, A.J.; Hartmann, H.M.

    1995-04-01

    This report, a supplement to Appendix E (Transportation Risk) of the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS), provides additional information supporting the accident data for chemical risk assessment and health risk methodology described in that appendix (Part II), as well as providing the uncertainty analysis and on-site risk calculations. This report focuses on hazardous material truck accident rates, release probabilities, and release quantities; provides the toxicological values derived for each hazardous chemical assessed in the WM PEIS and further details on the derivation of health criteria; describes the method used in the transportation risk assessments to address potential additivity of health effects from simultaneous exposure to several chemicals and the method used to address transportation risks for maximally exposed individuals; presents an expanded discussion of the uncertainty associated with transportation risk calculations; and includes the results of the on-site transportation risk analysis. In addition, two addenda are provided to detail the risk assessments conducted for the hazardous components of low-level mixed waste (Addendum I) and transuranic waste (Addendum II)

  12. Intense volume reduction of mixed and low-level waste, solidification in sulphur polymer concrete, and excellent disposal at minimum cost

    International Nuclear Information System (INIS)

    Darnell, G.R.

    1990-01-01

    Progressive changes in regulations governing the disposal of the nation's radioactive and hazardous wastes demand the development of more advanced treatment and disposal systems. The U.S. Department of Energy's Radioactive Waste Technology Support Program (formerly the Defense Low-Level Waste Management Program) was given the task of demonstrating the degree of excellence that could be achieved at reasonable cost using existing technology. The resulting concept is a Waste Treatment and Disposal Complex that will fully treat contact-handled mixed and low-level radioactive waste to a disposable product that is totally liquid-free and approximately 98% inorganic. An excellent volume reduction factor is achieved through sorting, sizing, incineration, vitrification, and final grouting. Inorganic waste items larger than 1/4 in. will be placed in inexpensive, uniform-sized, smooth-sided, thin-walled steel boxes. The smaller particles will be mixed with sulfur polymer concrete and pumped into the boxes, filling most voids. The appendage-free boxes measuring 1 by 1 by 1 m will be stacked tightly in an abovegrade, earth-mounded, concrete disposal vault where a temporary roof will protect them from rain and snow. A concrete roof poured directly on top of the dense, essentially voidless waste stack will be topped by an engineered, water-shedding earthen cover. Total cost for design, construction, testing, 30 years of treatment and disposal, administration, decontamination and decommissioning, site closure, and postclosure monitoring and maintenance will cost less per cubic foot than is currently expended for subsurface disposal. A radiological performance assessment shows this concept will exceed the nation's existing disposal systems and governmental performance objectives for the protection of the general public by a factor of 30,000

  13. Additional Equipment for Soil Biodegradation

    Science.gov (United States)

    Vondráčková, Terezie; Kraus, Michal; Šál, Jiří

    2017-12-01

    Intensification of industrial production, increasing citizens’ living standards, expanding the consumer assortment mean in the production - consumption cycle a constantly increasing occurrence of waste material, which by its very nature must be considered as a source of useful raw materials in all branches of human activity. In addition to strict legislative requirements, a number of circumstances characterize waste management. It is mainly extensive transport associated with the handling and storage of large volumes of substances with a large assortment of materials (substances of all possible physical and chemical properties) and high demands on reliability and time coordination of follow-up processes. Considerable differences in transport distances, a large number of sources, processors and customers, and not least seasonal fluctuations in waste and strong price pressures cannot be overlooked. This highlights the importance of logistics in waste management. Soils that are contaminated with oil and petroleum products are hazardous industrial waste. Methods of industrial waste disposal are landfilling, biological processes, thermal processes and physical and chemical methods. The paper focuses on the possibilities of degradation of oil pollution, in particular biodegradation by bacteria, which is relatively low-cost among technologies. It is necessary to win the fight with time so that no ground water is contaminated. We have developed two additional devices to help reduce oil accident of smaller ranges. In the case of such an oil accident, it is necessary to carry out the permeability test of contaminated soil in time and, on this basis, to choose the technology appropriate to the accident - either in-sit biodegradation - at the site of the accident, or on-sit - to remove the soil and biodegrade it on the designated deposits. A special injection drill was developed for in-sit biodegradation, tossing and aeration equipment of the extracted soil was developed for

  14. Alternative additives; Alternative additiver

    Energy Technology Data Exchange (ETDEWEB)

    2007-08-15

    In this project a number of industrial and agricultural waste products have been characterised and evaluated in terms of alkali-getter performance. The intended use is for biomass-fired power stations aiming at reducing corrosion or slagging related problems. The following products have been obtained, characterised and evaluated: 1) Brewery draff 2) Danish de-gassed manure 3) Paper sludge 4) Moulding sand 5) Spent bleaching earth 6) Anorthosite 7) Sand 8) Clay-sludge. Most of the above alternative additive candidates are deemed unsuitable due to insufficient chemical effect and/or expensive requirements for pre-treatment (such as drying and transportation). 3 products were selected for full-scale testing: de-gassed manure, spent bleaching earth and clay slugde. The full scale tests were undertaken at the biomass-fired power stations in Koege, Slagelse and Ensted. Spent bleaching earth (SBE) and clay sludge were the only tested additive candidates that had a proven ability to react with KCl, to thereby reduce Cl-concentrations in deposits, and reduce the deposit flux to superheater tubes. Their performance was shown to nearly as good as commercial additives. De-gassed manure, however, did not evaluate positively due to inhibiting effects of Ca in the manure. Furthermore, de-gassed manure has a high concentration of heavy metals, which imposes a financial burden with regard to proper disposal of the ash by-products. Clay-sludge is a wet clay slurring, and drying and transportation of this product entails substantial costs. Spent bleaching does not require much pre-treatment and is therefore the most promising alternative additive. On the other hand, bleaching earth contains residual plant oil which means that a range of legislation relating to waste combustion comes into play. Not least a waste combustion fee of 330 DKK/tonne. For all alternative (and commercial) additives disposal costs of the increase ash by-products represents a significant cost. This is

  15. Acid fractionation for low level liquid waste cleanup and recycle

    International Nuclear Information System (INIS)

    Gombert, D. II; McIntyre, C.V.; Mizia, R.E.; Schindler, R.E.

    1990-01-01

    At the Idaho Chemical Processing Plant, low level liquid wastes containing small amounts of radionuclides are concentrated via a thermosyphon evaporator for calcination with high level waste, and the evaporator condensates are discharged with other plant wastewater to a percolation pond. Although all existing discharge guidelines are currently met, work has been done to reduce all waste water discharges to an absolute minimum. In this regard, a 15-tray acid fractionation column will be used to distill the mildly acidic evaporator condensates into concentrated nitric acid for recycle in the plant. The innocuous overheads from the fractionator having a pH greater than 2, are superheated and HEPA filtered for atmospheric discharge. Nonvolatile radionuclides are below detection limits. Recycle of the acid not only displaces fresh reagent, but reduces nitrate burden to the environment, and completely eliminates routine discharge of low level liquid wastes to the environment

  16. Waste Management Process Improvement Project

    International Nuclear Information System (INIS)

    Atwood, J.; Borden, G.; Rangel, G. R.

    2002-01-01

    The Bechtel Hanford-led Environmental Restoration Contractor team's Waste Management Process Improvement Project is working diligently with the U.S. Department of Energy's (DOE) Richland Operations Office to improve the waste management process to meet DOE's need for an efficient, cost-effective program for the management of dangerous, low-level and mixed-low-level waste. Additionally the program must meet all applicable regulatory requirements. The need for improvement was highlighted when a change in the Groundwater/Vadose Zone Integration Project's waste management practices resulted in a larger amount of waste being generated than the waste management organization had been set up to handle

  17. 40 CFR 265.252 - Waste analysis.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Waste analysis. 265.252 Section 265... FACILITIES Waste Piles § 265.252 Waste analysis. In addition to the waste analyses required by § 265.13, the... in the pile to which it is to be added. The analysis conducted must be capable of differentiating...

  18. Bioremediation of cooking oil waste using lipases from wastes.

    Directory of Open Access Journals (Sweden)

    Clarissa Hamaio Okino-Delgado

    Full Text Available Cooking oil waste leads to well-known environmental impacts and its bioremediation by lipase-based enzymatic activity can minimize the high cytotoxic potential. In addition, they are among the biocatalysts most commercialized worldwide due to the versatility of reactions and substrates. However, although lipases are able to process cooking oil wastes, the products generated from this process do not necessarily become less toxic. Thus, the aim of the current study is to analyze the bioremediation of lipase-catalyzed cooking oil wastes, as well as their effect on the cytotoxicity of both the oil and its waste before and after enzymatic treatment. Thus, assessed the post-frying modification in soybean oil and in its waste, which was caused by hydrolysis reaction catalyzed by commercial and home-made lipases. The presence of lipases in the extracts obtained from orange wastes was identified by zymography. The profile of the fatty acid esters formed after these reactions was detected and quantified through gas chromatography and fatty acids profile compared through multivariate statistical analyses. Finally, the soybean oil and its waste, with and without enzymatic treatment, were assessed for toxicity in cytotoxicity assays conducted in vitro using fibroblast cell culture. The soybean oil wastes treated with core and frit lipases through transesterification reaction were less toxic than the untreated oils, thus confirming that cooking oil wastes can be bioremediated using orange lipases.

  19. Radiation Vulcanization of Polymeric Blends Based on Ethylene Propylene Diene Monomer Rubber/ Waste Materials in Presence of Different Additives

    International Nuclear Information System (INIS)

    MOHAMED, R.M.

    2015-01-01

    In this investigation, the mechanical blending technique was applied for preparation of elastomeric blend of ethylene propylene diene monomer rubber (EPDM)and nitrile butadiene rubber (NBR) having a fixed ratio of (50/50) by weight. The prepared blend of EPDM/NBR (50/50) was used as a rubber matrix to be loaded with waste materials, namely rice husk (RH) as a natural waste filler and then with ground tire rubber (GTR) as an artificial one. The degree of loading varied from 5 p hr to 20 p hr. Ionizing radiation, namely ,gamma rays were applied for inducing vulcanization of prepared and loaded rubber blends, in the range from 5 kGy to 250 kGy. Different properties of prepared composites were followed up as a function of degree of loading with the waste material and dose of irradiation. The mechanical properties, namely tensile strength and elongation at break percent of the composites slightly decreased as the filler loading increased over the whole range of irradiation .Tensile modulus and hardness, on the other hand, showed an opposite trend, i.e. the increased. Other properties, namely physical, thermal and morphological confirmed the mechanical ones. Obtained results were affiliated with lack of interface adhesion between the waste materials and the rubber matrix elastomers. The lack of interface adhesion was improved by filling the composite with a limited content, up to 7 p hr, of the compatibilizer, namely, maleic anhydride (MAH). Measurements of different properties was carried out for composite loaded with 10 p hr of waste material. It has been found that the tensile properties were significantly improved with addition of the compatibilizing agent Further and significant improvement was attained in properties of prepared later composite by its loading with 40 p hr of either HAF- carbon black or Hisil as reinforcing fillers that participates in chemical as well as physical bonding. Similarly and lastly 8 p hr of N, N- methylene di acrylamide (MDA) were loaded

  20. Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240

    Energy Technology Data Exchange (ETDEWEB)

    Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

    2013-07-01

    Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m{sup 3} (55-gal) drum which contains either a 0.04 m{sup 3} or 0.06 m{sup 3} (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ∼12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated

  1. Review of information on the radiation chemistry of materials around waste canisters in salt and assessment of the need for additional experimental information

    Energy Technology Data Exchange (ETDEWEB)

    Jenks, G.H.; Baes, C.F. Jr.

    1980-03-01

    The brines, vapors, and salts precipitated from the brines will be exposed to gamma rays and to elevated temperatures in the regions close to a waste package in the salt. Accordingly, they will be subject to changes in composition brought about by reactions induced by the radiations and heat. This report reviews the status of information on the radiation chemistry of brines, gases, and solids which might be present around a waste package in salt and to assess the need for additional laboratory investigations on the radiation chemistry of these materials. The basic aspects of the radiation chemistry of water and aqueous solutions, including concentrated salt solutions, were reviewed briefly and found to be substantially unchanged from those presented in Jenks's 1972 review of radiolysis and hydrolysis in salt-mine brines. Some additional information pertaining to the radiolytic yields and reactions in brine solutions has become available since the previous review, and this information will be useful in the eventual, complete elucidation of the radiation chemistry of the salt-mine brines. 53 references.

  2. Preliminary safety evaluation for 241-C-106 waste retrieval, project W-320

    International Nuclear Information System (INIS)

    Conner, J.C.

    1994-01-01

    This document presents the Preliminary Safety Evaluation for Project W-320, Tank 241-C-106 Waste Retrieval Sluicing System (WRSS). The US DOE has been mandated to develop plans for response to safety issues associated with the waste storage tanks at the Hanford Site, and to report the progress of implementing those plans to Congress. The objectives of Project W-230 are to design, fabricate, develop, test, and operate a new retrieval system capable of removing a minimum of about 75% of the high-heat waste contained in C-106. It is anticipated that sluicing operations can remove enough waste to reduce the remaining radiogenic heat load to levels low enough to resolve the high-heat safety issue as well as allow closure of the tank safety issue

  3. Storing solid radioactive wastes at the Savannah River Plant

    International Nuclear Information System (INIS)

    Horton, J.H.; Corey, J.C.

    1976-06-01

    The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

  4. Disasters And Minimum Health Standards In Disaster Response

    Directory of Open Access Journals (Sweden)

    Sibel GOGEN

    Full Text Available Millions of people are affected by natural or man made disasters all over the world. The number of people affected by disasters increase globally, due to global climate changes, increasing poverty, low life standards, inappropriate infrastructure, lack of early response systems, abuse of natural sources, and beside these, nuclear weapons, wars and conflicts, terrorist actions, migration, displacement and population movements. 95 % of life loss due to disasters are in the underdeveloped or developing countries. Turkey is a developing country, highly affected by disasters. For coping with disasters, not only national action plans, but also International Action Plans and cooperations are needed. Since all the disasters have direct and indirect effects on health, applications of minimal health standarts in disaster response, will reduce the morbidity and mortality rates. In this paper, water supplies and sanitation, vector control, waste control, burial of corpses, nutrition and minimum health standards in disaster response, are reviewed. [TAF Prev Med Bull 2004; 3(12.000: 296-306

  5. Influences of Fuel Additive, Crude Palm and Waste Cooking Oil on Emission Characteristics of Small Diesel Engine

    Science.gov (United States)

    Khalid, Amir; Jaat, Norrizam; Manshoor, Bukhari; Zaman, Izzuddin; Sapit, Azwan; Razali, Azahari; Basharie, Mariam

    2017-08-01

    Major research has been conducted on the use of input products, such as rapeseed, canola, soybean, sunflower oil, waste cooking oil (WCO), crude palm oil (CPO) and crude jatropha oil as alternative fuels. Biodiesel is renewable, biodegradable and oxygenated, where it can be easily adopted by current existing conventional diesel engine without any major modification of the engine. To meet the future performance and emission regulations, is urged to improve the performance and exhaust emissions from biodiesel fuels. Hence, further investigation have been carried out on the emission characteristics of small diesel engine that fuelled by variant blending ratio of WCO and CPO with booster additive. For each of the biodiesel blends ratio from 5 to 15 percent volume which are WCO5, WCO10 and WCO15 for WCO biodiesel and CPO5, CPO10 and CPO15 for CPO biodiesel. The exhaust emissions were measured at engine speeds varied at 2000 rpm and 2500 rpm with different booster additive volume DRA (biodiesel without additive), DRB (0.2 ml) and DRC (0.4 ml). Emissions characteristics that had been measured were Hydrocarbon (HC), Carbon Monoxide (CO), Carbon Dioxide (CO2), Nitrogen Oxide (NOx), and smoke opacity. The results showed that increased of blending ratio with booster additive volume significantly decreased the CO emission, while increased in NOx and CO2 due to changes of fuel characteristics in biodiesel fuel blends.

  6. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits:Interim CQA Report

    International Nuclear Information System (INIS)

    2011-01-01

    This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. Construction was approved by the Nevada Division of Environmental Protection (NDEP) under the Approval of Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for Corrective Action Unit (CAU) 111: Area 5 WMD Retired Mixed Waste Pits, Nevada National Security Site, Nevada, on January 6, 2011, pursuant to Subpart XII.8a of the Federal Facility Agreement and Consent Order. The project is located in Area 5 of the Radioactive Waste Management Complex (RWMC) at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site, located in southern Nevada, approximately 65 miles northwest of Las Vegas, Nevada, in Nye County. The project site, in Area 5, is located in a topographically closed basin approximately 14 additional miles north of Mercury Nevada, in the north-central part of Frenchman Flat. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location

  7. Evapotranspiration Cover for the 92-Acre Area Retired Mixed Waste Pits:Interim CQA Report

    Energy Technology Data Exchange (ETDEWEB)

    The Delphi Groupe, Inc., and J. A. Cesare and Associates, Inc.

    2011-06-20

    This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. This Interim Construction Quality Assurance (CQA) Report is for the 92-Acre Evapotranspiration Cover, Area 5 Waste Management Division (WMD) Retired Mixed Waste Pits, Nevada National Security Site, Nevada for the period of January 20, 2011 to May 12, 2011. Construction was approved by the Nevada Division of Environmental Protection (NDEP) under the Approval of Corrective Action Decision Document/Corrective Action Plan (CADD/CAP) for Corrective Action Unit (CAU) 111: Area 5 WMD Retired Mixed Waste Pits, Nevada National Security Site, Nevada, on January 6, 2011, pursuant to Subpart XII.8a of the Federal Facility Agreement and Consent Order. The project is located in Area 5 of the Radioactive Waste Management Complex (RWMC) at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site, located in southern Nevada, approximately 65 miles northwest of Las Vegas, Nevada, in Nye County. The project site, in Area 5, is located in a topographically closed basin approximately 14 additional miles north of Mercury Nevada, in the north-central part of Frenchman Flat. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. The 92-Acre Area encompasses the southern portion of the Area 5 RWMS, which has been designated for the first final closure operations. This area contains 13 Greater Confinement Disposal (GCD) boreholes, 16 narrow trenches, and 9 broader pits. With the exception of two active pits (P03 and P06), all trenches and pits in the 92-Acre Area had operational covers approximately 2.4 meters thick, at a minimum, in most areas when this project began. The units within the 92-Acre Area are grouped into the following six informal categories based on physical location

  8. Mineral-modeled ceramics for long-term storage of high-level nuclear wastes

    International Nuclear Information System (INIS)

    Vance, E.R.

    1980-01-01

    Over the past ten years, Penn State's Materials Research Laboratory has done extensive work on mineral-modeled ceramics for high-level nuclear waste storage. These ceramics are composed of several mineral analogues that form a monolithic polycrystalline aggregate. Mineral-modeling can be made in a similar fashion to nuclear waste glasses, and their naturally occurring analogues are known to last millions, and even billions, of years in hot, wet conditions. It is believed that such ceramics could reduce dispersal of radionuclides by leaching to a minimum

  9. Data analytics approach to create waste generation profiles for waste management and collection.

    Science.gov (United States)

    Niska, Harri; Serkkola, Ari

    2018-04-30

    Extensive monitoring data on waste generation is increasingly collected in order to implement cost-efficient and sustainable waste management operations. In addition, geospatial data from different registries of the society are opening for free usage. Novel data analytics approaches can be built on the top of the data to produce more detailed, and in-time waste generation information for the basis of waste management and collection. In this paper, a data-based approach based on the self-organizing map (SOM) and the k-means algorithm is developed for creating a set of waste generation type profiles. The approach is demonstrated using the extensive container-level waste weighting data collected in the metropolitan area of Helsinki, Finland. The results obtained highlight the potential of advanced data analytic approaches in producing more detailed waste generation information e.g. for the basis of tailored feedback services for waste producers and the planning and optimization of waste collection and recycling. Copyright © 2018 Elsevier Ltd. All rights reserved.

  10. Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs

    International Nuclear Information System (INIS)

    Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

    1982-09-01

    This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables

  11. The impact of industrial waste of Venezuelan marine water

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, Frank [Bechtel Corp., Gaithersburg, MD (United States); Guarino, Carmen [Guarino Engineers, Philadelphia, PA (United States); Arias, Marlene [Ministerio del Ambiente y Recursos Naturales Renovables, Caracas (Venezuela)

    1994-12-31

    The Puerto Cabello-Marron coastal area of Venezuela is an ideal location for industries that require large land areas, water, marine transportation, minimum habitation, cooling water, etc. However, mercury spills have produced concern in the entire coastal zone. The area was investigated and negative impacts were identified. Consequently, recommendations for waste water management were proceeded. 13 refs., 6 figs., 3 tabs.

  12. The impact of industrial waste of Venezuelan marine water

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, Frank [Bechtel Corp., Gaithersburg, MD (United States); Guarino, Carmen [Guarino Engineers, Philadelphia, PA (United States); Arias, Marlene [Ministerio del Ambiente y Recursos Naturales Renovables, Caracas (Venezuela)

    1993-12-31

    The Puerto Cabello-Marron coastal area of Venezuela is an ideal location for industries that require large land areas, water, marine transportation, minimum habitation, cooling water, etc. However, mercury spills have produced concern in the entire coastal zone. The area was investigated and negative impacts were identified. Consequently, recommendations for waste water management were proceeded. 13 refs., 6 figs., 3 tabs.

  13. Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes. Report number 3

    International Nuclear Information System (INIS)

    1981-01-01

    A discussion of the relative strengths and weaknesses of the alternative forms and recommendations for future program directions are presented in the body of this report. In addition to the relative ranking, the Peer Review Panel makes the following observations and recommendations: (1) Differences in overall performance of most of the uncoated waste forms are relatively small when compared under approximately equivalent conditions. (2) The increased scientific basis for this class of waste forms has not yet been sufficient to achieve reliably large improvements in waste form performance over the best borosilicate glasses. (3) The increased leach rates at elevated temperatures and the uncertainty regarding mechanisms of leaching under repository conditions continue to indicate that surface temperatures of waste canisters and especially any waste form-water interfaces should be restricted to less than 100 0 C, until more data is available to indicate otherwise. (4) Improvements are noteworthy, but there is still a need for adopting additional standardized tests, standard reference materials, common units and standardized methods of data presentation in the nuclear waste program. (5) Comparative data on leach rates in waters equilibrated with candidate rocks and potential geologic environments are almost non-existent and are essential to establish relevant long term extrapolation of waste form performance.(6) Understanding radiation damage effects on the microstructure and leaching mechanisms of polycrystalline ceramics is still insufficient to judge long term reliability of this class of waste forms. (7) More extensive data on rates and mechanisms of leaching of all waste forms under radiation and repository conditions are needed. (8) Additional studies of fundamental mechanisms controlling long term reliability of glass and alternative waste forms are strongly encouraged

  14. Liquid secondary waste: Waste form formulation and qualification

    Energy Technology Data Exchange (ETDEWEB)

    Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-31

    and water characteristic curves) were comparable to the properties measured on the Savannah River Site (SRS) Saltstone waste form. Future testing should include efforts to first; 1) determine the rate and amount of ammonia released during each unit operation of the treatment process to determine if additional ammonia management is required, then; 2) reduce the ammonia content of the ETF concentrated brine prior to solidification, making the waste more amenable to grouting, or 3) manage the release of ammonia during production and ongoing release during storage of the waste form, or 4) develop a lower pH process/waste form thereby precluding ammonia release.

  15. Enhancing phosphorus release from waste activated sludge containing ferric or aluminum phosphates by EDTA addition during anaerobic fermentation process.

    Science.gov (United States)

    Zou, Jinte; Zhang, Lili; Wang, Lin; Li, Yongmei

    2017-03-01

    The effect of ethylene diamine tetraacetic acid (EDTA) addition on phosphorus release from biosolids and phosphate precipitates during anaerobic fermentation was investigated. Meanwhile, the impact of EDTA addition on the anaerobic fermentation process was revealed. The results indicate that EDTA addition significantly enhanced the release of phosphorus from biosolids, ferric phosphate precipitate and aluminum phosphate precipitate during anaerobic fermentation, which is attributed to the complexation of metal ions and damage of cell membrane caused by EDTA. With the optimal EDTA addition of 19.5 mM (0.41 gEDTA/gSS), phosphorus release efficiency from biosolids was 82%, which was much higher than that (40%) without EDTA addition. Meanwhile, with 19.5 mM EDTA addition, almost all the phosphorus in ferric phosphate precipitate was released, while only 57% of phosphorus in aluminum phosphate precipitate was released. This indicates that phosphorus in ferric phosphate precipitate was much easier to be released than that in aluminum phosphate precipitate during anaerobic fermentation of sludge. In addition, proper EDTA addition facilitated the production of soluble total organic carbon and volatile fatty acids, as well as solid reduction during sludge fermentation, although methane production could be inhibited. Therefore, EDTA addition can be used as an alternative method for recovering phosphorus from waste activated sludge containing ferric or aluminum precipitates, as well as recovery of soluble carbon source. Copyright © 2016 Elsevier Ltd. All rights reserved.

  16. Waste water from dewatering of peat

    International Nuclear Information System (INIS)

    Ringqvist, L.; Bergner, K.; Olsson, Tommy; Bystroem, P.

    1991-01-01

    The influence of waste water from mechanical dewatering of peat was tested on two species of stream invertebrates. We compared the effects of waste water from peat without any chemical treatment, and waste water from peat where one of the following treatments of the peat had preceded dewatering; a: acidification combined with addition of the cationic polymer Zetag 78 FS40, b: addition of aluminium in combination with the anionic polymer Magnafloc E10, c: polymerisation of the peat by acidification and addition of ferrous chloride and hydrogen peroxide. Waste water from Al/Magnafloc and from the polymerisation treatments had a higher content of suspended matter and a higher oxygen demand than those of other treatments. Total metal content of the water from all treatments was higher than in water from non-treated peat. Survival and growth of nymphs of the mayfly Heptagenia fuscogrisa and the stonefly Nemoura cinerea were compared in waste water from the different treatments. In all tests, the waste water was diluted to 5% (volume) with unchlorinated tapwater and pH was between 7.0-8.0 in all treatments during the experiment. The nymphs were fed with birch leaves that had been incubated in natural stream water for one month. Under these conditions, we did not find any significant effect of waste water on either survival or growth of these two species

  17. SILVER RECYCLING FROM PHOTO-PROCESSING WASTE USING ELECTRODEPOSITION METHOD

    Directory of Open Access Journals (Sweden)

    Mochammad Feri Hadiyanto

    2010-06-01

    Full Text Available Silver electrodeposition of photo-processing waste and without addition of KCN 1,0 M has been studied for silver recycling. Photo procesing waste containing silver in form of [Ag(S2O32]3- was electrolysed at constant potential and faradic efficiency was determined at various of electrolysis times. Electrolysis of 100 mL photo processing waste without addition of KCN 1,0 M was carried out at constant potential 1.20 Volt, while electrolysis 100 mL photo procesing waste with addition of 10 mL KCN 1,0 M electrolysis was done at 1.30 Volt.The results showed that for silver electrodeposition from photo processing waste with addition of KCN 1,0 M was more favorable with faradic efficiency respectively were 93,16; 87,02; 74,74 and 78,35% for 30; 60; 90 and 120 minutes of electrolysis.   Keywords: Silver extraction, electrodeposition, photo-processing waste

  18. Speciation of organic carbon in Hanford waste storage tanks: Part 1

    International Nuclear Information System (INIS)

    Carlson, C.D.

    1997-02-01

    This report is the first in a series to report on speciation of organic carbon in Hanford waste storage tanks. The comparison of the existing total organic carbon with oxalate and limited analyses of other organic species (acetate, formate, and normal paraffin hydrocarbons [NPH]) are reported. All of the data have been previously reported by the Grout and Characterization programs; the information includes all of the publicly available data through October 1996. Oxalate data were reported for 33 tanks, TOC data were reported for 82 tanks, and both oxalate and TOC data were available for 27 tanks. Of these 27 tanks, seven were found to have greater than 80% of the TOC identified as oxalate: 241-BY-104, 241-BY-105, 241-BY-106, 241-BY-110, 241-S-109, and 241-SX-108. Eighty percent accountability has been tentatively established as a minimum goal of the Organic Safety Program for speciation of TOC. Accountability of TOC through speciation will allow more accurate estimate of the potential energy content of the wastes as currently stored. Of the remaining 19 tanks, seven had between 40 and 80% of the TOC identified as oxalate, and eleven had less than 35% of the TOC identified. Of these, only five tanks had segment results that were greater than 1% TOC, and none was above 2%. Since the cur-rent safety criterion outlined in the Safety Analysis is 4.5% TOC, it may be determined that the further analyses of these tank wastes are not necessary. If additional analyses are deemed necessary, minimal work may be required, possibly limited to ion chromatography (IC), ion pair chromatography and capillary zone electrophoresis (CZE). Additional speciation work is planned for this fiscal year in both the Organic Tanks Safety and Characterization programs. The Characterization program reports acetate and formate data in addition to the oxalate data for all the tank cores it processes

  19. Treatability study of absorbent polymer waste form for mixed waste treatment

    International Nuclear Information System (INIS)

    Herrmann, S. D.; Lehto, M. A.; Stewart, N. A.; Croft, A. D.; Kern, P. W.

    2000-01-01

    A treatability study was performed to develop and characterize an absorbent polymer waste form for application to low level (LLW) and mixed low level (MLLW) aqueous wastes at Argonne National Laboratory-West (ANL-W). In this study absorbent polymers proved effective at immobilizing aqueous liquid wastes in order to meet Land Disposal Restrictions for subsurface waste disposal. Treatment of aqueous waste with absorbent polymers provides an alternative to liquid waste solidification via high-shear mixing with clays and cements. Significant advantages of absorbent polymer use over clays and cements include ease of operations and waste volume minimization. Absorbent polymers do not require high-shear mixing as do clays and cements. Granulated absorbent polymer is poured into aqueous solutions and forms a gel which passes the paint filter test as a non-liquid. Pouring versus mixing of a solidification agent not only eliminates the need for a mixing station, but also lessens exposure to personnel and the potential for spread of contamination from treatment of radioactive wastes. Waste minimization is achieved as significantly less mass addition and volume increase is required of and results from absorbent polymer use than that of clays and cements. Operational ease and waste minimization translate into overall cost savings for LLW and MLLW treatment

  20. Long-term management USDOE transuranic waste

    International Nuclear Information System (INIS)

    Bennett, W.S.; Gilbert, K.V.; Lowrey, R.Y.

    1982-01-01

    Activities for permanent disposal of US DOE TRU waste are presently focused on newly generated and stored waste. The buried waste and contaminated soils pose no near term problem. Decisions on any possible actions for these wastes will be deferred until the newly generated and stored wastes are being placed into disposal on a routine basis. Several elements must be in place before such disposal can become routine. These elements consist of: a disposal facility; waste acceptance criteria; waste certification mechanisms; waste processing facilities; and a waste transportation system. Each of these elements has been the subject of considerable activity in the recent past. Progress and plans for each element are summarized. As of January 1981, DOE has 60,500 m 3 of waste classified as Transuranic waste (TRU) in retrievable storage, and projects that additional TRU waste will be generated at an average rate of 4500 m 3 per year for the next 10 years. Over 99% of this waste is contact handled, with the remainder being remote handled, i.e., surface radiation dose levels exceeding 200 mrem/h. An estimated 273,000 m 3 of TRU waste were placed in shallow land burial prior to establishment of the 1970 policy. In addition, large quantities of soil at DOE sites are contaminated with TRU elements due to disposal of liquid wastes and by contact of soil with solid, buried waste whose original containers are now badly degraded. Possibly as much as 10,000,000 m 3 of soil are contaminated above 10 nCi/gm. Less than 1,000,000 m 3 are estimated to be contaminated above 100 nCi/gm

  1. Minimum compliance topology optimization of shell–infill composites for additive manufacturing

    NARCIS (Netherlands)

    Wu, J.; Clausen, Anders; Sigmund, Ole

    2017-01-01

    Additively manufactured parts are often composed of two sub-structures, a solid shell forming their exterior and a porous infill occupying the interior. To account for this feature this paper presents a novel method for generating simultaneously optimized shell and infill in the context of

  2. Determination of composition of pozzolanic waste mixtures with optimized compressive strength

    Directory of Open Access Journals (Sweden)

    Nardi José Vidal

    2004-01-01

    Full Text Available The utilization of ceramic wastes with pozzolanic properties along with other compounds for obtaining new materials with cementating properties is an alternative for reducing the environmental pollution. The acceptance of these new products in the market demands minimal changes in mechanical properties according to its utilization. For a variable range of compositional intervals, attempts were made to establish limiting incorporation proportions that assure the achievement of minimum pre-established mechanical strength values in the final product. In this case minimum compressive strength value is 3,000 kPa. A simultaneous association of other properties is also possible.

  3. Waste disposal in the deep ocean: An overview

    International Nuclear Information System (INIS)

    O'Connor, T.P.; Kester, D.R.; Burt, W.V.; Capuzzo, J.M.; Park, P.K.; Duedall, I.W.

    1985-01-01

    Incineration at sea, industrial and sewage waste disposal in the surface mixing zone, and disposal of low-level nuclear wastes, obsolete munitions, and nerve gas onto the seafloor have been the main uses of the deep sea for waste management. In 1981 the wastes disposed of in the deep sea consisted of 48 X 10/sup 4/ t of liquid industrial wastes and 2 X 10/sup 4/ t of sewage sludge by the United States; 1.5 X 10/sup 4/ t (solids) of sewage sludge by the Federal Republic of German; 5300 t of liquid industrial wastes by Denmark; 99 t of solid industrial wastes by the United Kingdom; and 9400 t of low-level radioactive wastes by several European countries. Also in 1981 at-sea incineration of slightly more than 10/sup 5/ t of organic wastes from Belgium, France, the Federal Republic of Germany, the Netherlands, Norway, Sweden, and the United Kingdom was carried out in the North Sea. Unique oceanographic features of the deep sea include its large dilution capacity; the long residence time of deep-sea water (on the order of 10/sup 2/ y); low biological productivity in the surface water of the open ocean (≅50 g m/sup -2/ of carbon per year); the existence of an oxygen minimum zone at several hundred meters deep in the mid-latitudes; and the abyssal-clay regions showing sedimentary records of tens of millions of years of slow, uninterrupted deposition of fine-grained clay. Any deep-sea waste disposal strategy must take into account oceanic processes and current scientific knowledge in order to attain a safe solution that will last for centuries

  4. The Vital Minimum Amount of Drinking Water Required in Ecuador

    Directory of Open Access Journals (Sweden)

    Andrés Martínez Moscoso

    2018-02-01

    Full Text Available In 2017, the government of Ecuador established the minimum quantity of water required to be provided for free by drinking water utilities. Ecuador recognized the access to water as a fundamental human right because it guarantees the good living, known as “Sumak kawsay”, an indigenous Andean concept, in the Ecuadorian Constitution. This represents a novel approach to water rights in the world, as it is the first attempt to establish a minimum quantity of water under a constitutional guarantee by legislation, rather than regulation or judicial decision. However, this novel legislative approach raises the question of how this minimum amount of free water will impact the most vulnerable members of the Ecuadorian community. This paper provides the results of the first comprehensive research of the minimum required water provision in Ecuador. In order to measure the impact on the income of households, we built a methodology integrating: doctrinaire analyses, normative studies, and economic analyses. According to the Ecuadorian legislation, over-consumption of raw water generates additional costs that must be paid by water companies to the central government. In that regard, there is an inevitable relationship between the efficiency of the service and those additional costs. Efficiency, on this case, is the capacity of water companies (public or private to provide water services at an adequate price, observing the following parameters: quantity, quality and sufficiency. Our research found that with this legislation in three Ecuadorian local governments (Cuenca, Gualaceo and Suscal, the most vulnerable households (i.e., low-income and/or indigenous households will be affected the most. This means that and those families will spend the most part of their income on water services otherwise they would have to reduce their water consumption.

  5. Presence of potentially critical substances in waste paper

    DEFF Research Database (Denmark)

    Pivnenko, Kostyantyn; Eriksson, Eva; Astrup, Thomas Fruergaard

    2013-01-01

    the process itself as well as the quality or functionality of the final product. Such additives may be re-introduced to the paper production process once waste paper is recycled, leading to their accumulation and spreading in newly manufactured paper and board products. This study aimed at identification...... of the critical additives potentially present in paper products and quantification of a selected group of additives (Mineral Oil Hydrocarbons) in waste paper and board source segregated from Danish municipal solid waste....

  6. Waste processing options

    International Nuclear Information System (INIS)

    Turney, J.; Miller, A.; Leventhal, L.; Naughton, M.

    1985-01-01

    Decontamination of components, facilities and sites is becoming an increasingly significant source of low-level waste. Another source, of potentially greater magnitude, is the decommissioning of nuclear reactor facilities. According to DOE, there are about 15 operating reactors that will be candidates for decommissioning by the end of the century. In addition, there are reactors such as Humboldt Bay, Dresden 1, and Indian Point, Unit 1, which have been shut down prior to their design life. Chemical decontamination of components and systems is a frequently used technique in controlling nuclear plant radiation exposure, and is especially useful during decommissioning. However, many of the solutions used pose a chemical or biological hazard, in addition to being radioactively contaminated. These hazards, if not ameliorated, may prohibit their disposal. Recent regulations, such as 10CFR Part 61(2), are focusing more attention on the non-radioactive aspects of radioactive waste. 10CFR Part 61 and the existing burial site licenses prohibit burial of waste which is chemically reactive, explosive under ambient conditions, produces toxic gases, vapors or fumes, or is pyrophoric. Additionally, the Barnwell license restricts organic chemicals which may affect the migration of radionuclides from the burial site. The NRC is studying additional restrictions on a class of these chemicals called chelating agents

  7. Repository waste-handling operations, 1998

    International Nuclear Information System (INIS)

    Cottam, A.E.; Connell, L.

    1986-04-01

    The Civilian Radioactive Waste Management Program Mission Plan and the Generic Requirements for a Mined Geologic Disposal System state that beginning in 1998, commercial spent fuel not exceeding 70,000 metric tons of heavy metal, or a quantity of solidified high-level radioactive waste resulting from the reprocessing of such a quantity of spent fuel, will be shipped to a deep geologic repository for permanent storage. The development of a waste-handling system that can process 3000 metric tons of heavy metal annually will require the adoption of a fully automated approach. The safety and minimum exposure of personnel will be the prime goals of the repository waste handling system. A man-out-of-the-loop approach will be used in all operations including the receipt of spent fuel in shipping casks, the inspection and unloading of the spent fuel into automated hot-cell facilities, the disassembly of spent fuel assemblies, the consolidation of fuel rods, and the packaging of fuel rods into heavy-walled site-specific containers. These containers are designed to contain the radionuclides for up to 1000 years. The ability of a repository to handle more than 6000 pressurized water reactor spent-fuel rods per day on a production basis for approximately a 23-year period will require that a systems approach be adopted that combines space-age technology, robotics, and sophisticated automated computerized equipment. New advanced inspection techniques, maintenance by robots, and safety will be key factors in the design, construction, and licensing of a repository waste-handling facility for 1998

  8. Impact of long-lived radionuclides on waste classification for fusion

    International Nuclear Information System (INIS)

    Maninger, R.C.

    1985-01-01

    A major goal for commercial applications of fusion reactors is to minimize radioactive wastes and to dispose of them by near-surface burial. There currently are no regulations specifically applicable to fusion wastes but those in force for fission wastes furnish a framework for expected fusion regulations. This paper recommends that all nuclides with half-lives greater than five years be assigned concentration limits as done in 10CFR61 for fission wastes. The paper gives approximate limits for all the significant long half-life sources of gamma radiation in the currently known periodic table. In the absence of working fusion reactors, computer models must be used to estimate the expected actual concentrations of radioactive nuclides. These estimates are needed to guide design parameters to achieve minimum radioactivity in fusion reactors. It is believed that the computer models and nuclear reaction libraries must be much more comprehensive than ordinarily used today to do activation calculations

  9. Glasses and nuclear waste vitrification

    International Nuclear Information System (INIS)

    Ojovan, Michael I.

    2012-01-01

    Glass is an amorphous solid material which behaves like an isotropic crystal. Atomic structure of glass lacks long-range order but possesses short and most probably medium range order. Compared to crystalline materials of the same composition glasses are metastable materials however crystallisation processes are kinetically impeded within times which typically exceed the age of universe. The physical and chemical durability of glasses combined with their high tolerance to compositional changes makes glasses irreplaceable when hazardous waste needs immobilisation for safe long-term storage, transportation and consequent disposal. Immobilisation of radioactive waste in glassy materials using vitrification has been used successfully for several decades. Nuclear waste vitrification is attractive because of its flexibility, the large number of elements which can be incorporated in the glass, its high corrosion durability and the reduced volume of the resulting wasteform. Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro- and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation when the final glassy material can be in form of a glass composite material. Both borosilicate and phosphate glasses are currently used to immobilise nuclear wastes. In addition to relatively homogeneous glasses novel glass composite materials are used to immobilise problematic waste streams. (author)

  10. Technology applications for radioactive waste minimization

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1994-01-01

    The nuclear power industry has achieved one of the most successful examples of waste minimization. The annual volume of low-level radioactive waste shipped for disposal per reactor has decreased to approximately one-fifth the volume about a decade ago. In addition, the curie content of the total waste shipped for disposal has decreased. This paper will discuss the regulatory drivers and economic factors for waste minimization and describe the application of technologies for achieving waste minimization for low-level radioactive waste with examples from the nuclear power industry

  11. Cementation of wastes with boric acid

    International Nuclear Information System (INIS)

    Tello, Cledola C.O.; Haucz, Maria Judite A.; Alves, Lilian J.L.; Oliveira, Arno H.

    2000-01-01

    In nuclear power plants (PWR) are generated wastes, such as concentrate, which comes from the evaporation of liquid radioactive wastes, and spent resins. Both have boron in their composition. The cementation process is one of the options to solidify these wastes, but the boron has a negative effect on the setting of the cement mixture. In this paper are presented the experiments that are being carried out in order to overcome this problem and also to improve the efficiency of the process. Simulated wastes were cemented using additives (clays, admixtures etc.). In the process and product is being evaluated the effect of the amount, type and addition order of the materials. The mixtures were selected in accordance with their workability and incorporated waste. The solidified products are monolithic without free water with a good mechanical resistance. (author)

  12. Combustion of Waste Wood. Second phase of the collaboration project on waste wood combustion

    International Nuclear Information System (INIS)

    Andersson, Annika; Andersson, Christer; Eriksson, Jan; Hemstroem, Bengt; Jungstedt, Jenny; Kling, Aasa; Bahr, Bo von; Ekvall, Annika; Eskilsson, David; Tullin, Claes; Harnevie, Henrik; Sieurin, Jan; Keihaes, Juha; Mueller, Christian; Berg, Magnus; Wikman, Karin

    2003-08-01

    Combustion of waste wood has during the last decade increased dramatically and this has resulted in a number of Swedish plants using this fuel, e.g. Handeloe P11 (Norrkoeping) and ldbaecken P3 (Nykoeping), and yet other plants that are under construction (e.g. Nynaeshamn). The experience from these plants are that waste wood combustion results in a number of operational problems. To some extent these problems are different compared with the problems related to combustion of other biofuels but the situation is not directly comparable to waste incinerators. The problems are mainly related to slagging and fouling of heat exchanger surfaces and accelerated corrosion at relatively low temperature compared to the situation for ordinary biofuels. In some cases an increase in the emissions of specific substances can also result in difficulties to fulfil the EC-directive on waste combustion. Within previous projects the main problems related to combustion of waste wood have been identified and to some extent the cause of these problems has been clarified. One result of this reported investigation is a deeper understanding of the actual causes of these problems. However, the most important result is a number of recommendations for different measures on how to achieve disturbance-free combustion of waste wood. These recommendations actually summarises the most important possible solutions on how to achieve a disturbance-free operation and a lower maintenance cost for boilers combusting waste wood and can thereby be regarded as a short summery of the whole project: 1) Improving fuel quality by Improved sorting at the source and Sieving of the fuel -> Reducing the amount of metals and chlorine and Separation of fines and thereby reducing the amount of metals. 2) Combustion modifications by Avoiding reducing conditions at the heat exchanger surfaces -> Minimising slagging, fouling and corrosion. 3) Additives or co-combustion by Addition of sulphur with the fuel; Injection of

  13. Big Area Additive Manufacturing of High Performance Bonded NdFeB Magnets

    Science.gov (United States)

    Li, Ling; Tirado, Angelica; Nlebedim, I. C.; Rios, Orlando; Post, Brian; Kunc, Vlastimil; Lowden, R. R.; Lara-Curzio, Edgar; Fredette, Robert; Ormerod, John; Lograsso, Thomas A.; Paranthaman, M. Parans

    2016-10-01

    Additive manufacturing allows for the production of complex parts with minimum material waste, offering an effective technique for fabricating permanent magnets which frequently involve critical rare earth elements. In this report, we demonstrate a novel method - Big Area Additive Manufacturing (BAAM) - to fabricate isotropic near-net-shape NdFeB bonded magnets with magnetic and mechanical properties comparable or better than those of traditional injection molded magnets. The starting polymer magnet composite pellets consist of 65 vol% isotropic NdFeB powder and 35 vol% polyamide (Nylon-12). The density of the final BAAM magnet product reached 4.8 g/cm3, and the room temperature magnetic properties are: intrinsic coercivity Hci = 688.4 kA/m, remanence Br = 0.51 T, and energy product (BH)max = 43.49 kJ/m3 (5.47 MGOe). In addition, tensile tests performed on four dog-bone shaped specimens yielded an average ultimate tensile strength of 6.60 MPa and an average failure strain of 4.18%. Scanning electron microscopy images of the fracture surfaces indicate that the failure is primarily related to the debonding of the magnetic particles from the polymer binder. The present method significantly simplifies manufacturing of near-net-shape bonded magnets, enables efficient use of rare earth elements thus contributing towards enriching the supply of critical materials.

  14. Effect of sugarcane waste in the control of interrill erosion

    Directory of Open Access Journals (Sweden)

    Wander Cardoso Valim

    2016-06-01

    Full Text Available The cultivation of sugarcane uses different cropping systems that result in varying quantities of crop waste, this may influence soil erosion. The objective of this study was to evaluate the loss of soil and water, the infiltration rate, and soil surface roughness in an area cultivated with sugarcane (Saccharum spp.. Six treatments with different levels of plant waste were evaluated: sugarcane without plant waste; sugarcane with 4.0 Mg ha-1 of waste; sugarcane with 8.0 Mg ha-1 of waste; sugarcane with 12.0 Mg ha-1 of waste; sugarcane with 16.0 Mg ha-1 of waste; and burned sugarcane. The treatments were arranged in a randomized block design with four replications, totalling 24 experimental plots. As soil depth increased, there is reduction in macroporosity, total soil porosity, organic carbon content, mean geometric diameter and weighted mean diameter of the soil aggregates, whereas the bulk density of the soil displays the opposite trend. The presence of sugarcane waste on the soil surface increases the time required for the initiation of surface runoff. Sugarcane waste does not alter soil surface roughness, and at the minimum amount of waste administered (4 Mg ha-1 reduces losses of soil and water and increases the infiltration rate. The lack of soil surface coverage after harvesting the sugarcane contributes to soil and water loss, and reduces the rate of stable infiltration of water into the soil.

  15. Modifications to an existing waste containment structure at Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    Paez-Restrepo, A.; Darby, J.W.

    1992-01-01

    The Niagara Falls Storage Site (NFSS), located near Lewiston, New York, is an interim waste containment facility for low-level radioactive waste. The facility was completed in 1986 and is managed for the Department of Energy (DOE) by Bechtel National, Inc. (BNI) as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). The waste containment structure (WCS) at NFSS is approximately 297 m (975 ft) long and 137 m (450 ft) wide and reaches a maximum height of 10.4 m (34 ft). The peripheral slopes rise at an angle of 3:1 (h:v) for a width of about 16.8 m (55 ft), where the inclination decreases to 7.5%. The apex of the pile is higher at the south end, sloping about 1.2 m (4 ft) to the north. The interim layered cap consists of 0.9 m (3 ft) of clay overlain by 0.45 m (1.5 ft) of topsoil. The uppermost 15 cm (6 in.) of soil was loosely compacted to permit the development of a grass cover. In the summer of 1991, approximately 2,677 m 3 (3,500 yd 3 ) of additional contaminated soil and material in temporary storage elsewhere at NFSS was incorporated into the WCS. To accommodate the waste, a portion of the cap roughly centered with the pile [including 0.45 m (1.5 ft) of topsoil and 0.6 m (2 ft) of clay cap] was removed from an area 99 m (325 ft) long and 58.5 m (192 ft) wide, leaving a minimum of 0.3 m (I ft) of clay over the old waste as a radiation and radon barrier. The newly incorporated waste forms a layer 0.6 m (2 ft) thick, replacing the clay portion of the excavated cap. The waste is contained laterally by the old cap and sealed by a new cap, which also consists of 0.9 m (3 ft) of compacted clay and 0.45 m (1.5 ft) of topsoil. A transition zone about 6.1 m (20 ft) wide feathers the new cap to the old cap (see Fig. 3). Except for the uppermost 10.5 to 15.2 cm (4 to 6 in.) of vegetated topsoil, the excavated cap materials were stockpiled and reused in constructing the new cap. Additional material required to complete cap construction was imported from

  16. Geology of high-level nuclear waste disposal: an introduction

    International Nuclear Information System (INIS)

    Roxbugh, I.S.

    1987-01-01

    Hazardous waste is produced by the nuclear fuel cycle from mining and milling of uranium ore, refinement and enrichment, reactor use, and during reprocessing of spent fuel. Waste can be classified according to origin, physical state, and levels of radioactivity and radiotoxicity. The method of the long-term waste disposal is based on the degree of the hazard and the length of time (1000 years to millions of years) for the waste to become safe. The International Atomic Energy Agency (IAEA) has classified radioactive waste into five categories (I-V) based on the amount of radioactivity and heat output of the waste. The text is concerned mainly with the two most hazardous categories (I and II). Disposal at various geological sites using proven mining, engineering, and deep drilling techniques has been proposed and studied. An ideal geological repository would have (1) minimum ground water movement, (2) geochemical and mineralogical properties to retard or immobilize the effects of the nuclear waste from reaching the biosphere, (3) thermochemical properties to allow for heat loading without damage, and (4) structural strength for the operational period. Types of geological environments (both undersea and on land) include evaporites, crystalline rocks, and argillaceous deposits. European and North American case histories are described, and there is a glossary and an extensive list of references in this concise review

  17. Effect of porcelain polishing addition of waste in properties blocks ceramic; Efeito da adicao do residuo de polimento de porcelanato nas propriedades de blocos ceramicos

    Energy Technology Data Exchange (ETDEWEB)

    Santana, G.L.; Barbosa Neto, M.C.; Campos, L.F.; Macedo, D.A; Dutra, R.P.S., E-mail: geovanalira1@gmail.com [Universidade Federal da Paraiba (UFPB), PB (Brazil)

    2016-07-01

    This work has as objective the study of the technological properties of ceramic blocks with addition of residue porcelain polishing. The test samples are produced with clay base, where the waste is introduced in concentrations of 10% and 20% by mass, to evaluate its influence on the properties of the ceramic block. All these materials were characterized by determining their chemical composition (XRF) and X-ray diffraction Sintering was performed at temperatures of 850 ° C, 950 ° C and 1100 ° C with a heating rate of 2 ° C / me and 60 minutes of landing. After this, there was obtained the technological properties of the samples such as: Loss on fire, the burning linear shrinkage, water absorption, porosity and density, as well as, mechanical strength properties through the flexural strength test. The results show that the addition of waste influenced both the technological properties, the mechanical properties evaluated in this study. (author)

  18. Waste processing by pyrolysis; Posibilidades de la pirolisis en el tratamiento de los residuos

    Energy Technology Data Exchange (ETDEWEB)

    Elias, X.

    2002-07-01

    The present work starts reminding the beginnings of pyrolysis and its applications. Nevertheless the Directive 2000/76/CE talks about it and gasification calling them intermediate systems for waste to energy. Of all it, the conclusions is that both gasification and particularly pyrolysis alone cannot solve the environmental challenges that the treatment of the present waste supposes. Thus it is precise to refer to a larger set of technologies. Of the industrial applications it is inferred that both gasification and pyrolysis generate a minimum amount of gases, in comparison with the conventional incineration, so they are more advanced technologies of treatment. Pyrolysis allows a larger treatment of waste because, depending on an organic/inorganic relation present in the waste, provides a better fitting to the treatment. (Author)

  19. Solid waste workers and livelihood strategies in Greater Port-au-Prince, Haiti

    International Nuclear Information System (INIS)

    Noel, Claudel

    2010-01-01

    The solid waste management industry in Haiti is comprised of a formal and an informal sector. Many basic activities in the solid waste management sector are being carried out within the context of profound poverty, which exposes the failure of the socioeconomic and political system to provide sufficient job opportunities for the urban population. This paper examines the involvement of workers in the solid waste management industry in Greater Port-au-Prince and the implications for livelihood strategies. The findings revealed that the Greater Port-au-Prince solid waste management system is very inclusive with respect to age, while highly segregated with regard to gender. In terms of earning capacity, the results showed that workers hired by the State agencies were the most economically vulnerable group as more than 50% of them fell below the official nominal minimum wage. This paper calls for better salary scales and work compensation for the solid waste workers.

  20. Mixed waste study, Lawrence Livermore National Laboratory Hazardous Waste Management facilities

    International Nuclear Information System (INIS)

    1990-11-01

    This document addresses the generation and storage of mixed waste at Lawrence Livermore National Laboratory (LLNL) from 1984 to 1990. Additionally, an estimate of remaining storage capacity based on the current inventory of low-level mixed waste and an approximation of current generation rates is provided. Section 2 of this study presents a narrative description of Environmental Protection Agency (EPA) and Department of Energy (DOE) requirements as they apply to mixed waste in storage at LLNL's Hazardous Waste Management (HWM) facilities. Based on information collected from the HWM non-TRU radioactive waste database, Section 3 presents a data consolidation -- by year of storage, location, LLNL generator, EPA code, and DHS code -- of the quantities of low-level mixed waste in storage. Related figures provide the distribution of mixed waste according to each of these variables. A historical review follows in Section 4. The trends in type and quantity of mixed waste managed by HWM during the past five years are delineated and graphically illustrated. Section 5 provides an estimate of remaining low-level mixed waste storage capacity at HWM. The estimate of remaining mixed waste storage capacity is based on operational storage capacity of HWM facilities and the volume of all waste currently in storage. An estimate of the time remaining to reach maximum storage capacity is based on waste generation rates inferred from the HWM database and recent HWM documents. 14 refs., 18 figs., 9 tabs

  1. Strategy Study on Treatment and Disposal of the Radioactive Graphite Waste of HTR

    International Nuclear Information System (INIS)

    Li Junfeng; Ma Tao; Wang Jianlong

    2014-01-01

    The possible options to change HTGR spent fuel into an acceptable form for repository disposal were discussed. The progresses of physical, chemical, and electrochemical separation of graphite from the HTGR fuel elements were reviewed. The advantages and disadvantages of each method were listed out. The total waste volume of each method was compared. The preferred option depends on the waste acceptance criteria for the repository, availability of low level waste disposal for graphite, overall economics, and overall risks. The minimum processing that yields an acceptable waste form also gives the lowest costs as well as the simplest process and the least risk. The options that could be used for treating HTGR spent fuels were listed out. The strategy for treating HTGR spent fuels and the packages needed for repository were discussed. (author)

  2. Extended producer responsibility for consumer waste: the gap between economic theory and implementation.

    Science.gov (United States)

    Dubois, Maarten

    2012-09-01

    Although economic theory supports the use of extended producer responsibility (EPR) to stimulate prevention and recycling of waste, EPR systems implemented in Europe are often criticized as a result of weak incentives for prevention and green product design. Using a stylized economic model, this article evaluates the efficiency of European EPR systems. The model reveals that the introduction of static collection targets creates a gap between theory and implementation. Static targets lead to inefficient market outcomes and weak incentives for prevention and green product design. The minimum collection targets should be complemented with a tax on producers for the non-collected waste fraction. Because such a tax internalizes the cost of waste disposal, more efficient price signals will lead to better incentives for waste management in a complex and dynamic market.

  3. Hazardous Waste Code Determination for First/Second-Stage Sludge Waste Stream (IDCs 001, 002, 800)

    International Nuclear Information System (INIS)

    Arbon, R.E.

    2001-01-01

    This document, Hazardous Waste Code Determination for the First/Second-Stage Sludge Waste Stream, summarizes the efforts performed at the Idaho National Engineering and Environmental Laboratory (INEEL) to make a hazardous waste code determination on Item Description Codes (IDCs) 001, 002, and 800 drums. This characterization effort included a thorough review of acceptable knowledge (AK), physical characterization, waste form sampling, chemical analyses, and headspace gas data. This effort included an assessment of pre-Waste Analysis Plan (WAP) solidified sampling and analysis data (referred to as preliminary data). Seventy-five First/Second-Stage Sludge Drums, provided in Table 1-1, have been subjected to core sampling and analysis using the requirements defined in the Quality Assurance Program Plan (QAPP). Based on WAP defined statistical reduction, of preliminary data, a sample size of five was calculated. That is, five additional drums should be core sampled and analyzed. A total of seven drums were sampled, analyzed, and validated in compliance with the WAP criteria. The pre-WAP data (taken under the QAPP) correlated very well with the WAP compliant drum data. As a result, no additional sampling is required. Based upon the information summarized in this document, an accurate hazardous waste determination has been made for the First/Second-Stage Sludge Waste Stream

  4. Studying soil organic carbon in Mediterranean soils. Different techniques and the effects of land management and use, climatic and topographic conditions, organic waste addition

    Science.gov (United States)

    Lozano-García, Beatriz; Parras-Alcántara, Luis

    2014-05-01

    Soil organic carbon (SOC) is an important component of global carbon cycle, and the changes of its accumulation and decomposition directly affect terrestrial ecosystem carbon storage and global carbon balance. The ability of soil to store SOC depends to a great extent on climate and some soil properties, in addition to the cultivation system in agricultural soils. Soils in Mediterranean areas are very poor in organic matter and are exposed to progressive degradation processes. Therefore, a lot of actions are conducted to improve soil quality and hence mitigate the negative environmental and agronomic limitations of these soils. Improved cultivation systems (conversion of cropland to pastoral and forest lands, conventional tillage to conservation tillage, no manure use to regular addition of manure) have been introduced in recent years, increasing the contents in SOC and therefore, enhancing the soil quality, reducing soil erosion and degradation, improving surface water quality and increasing soil productivity. Moreover, the organic waste addition to the soils is especially useful in Mediterranean regions, where the return of organic matter to soil not only does it help soils store SOC and improve soil structure and soil fertility but also it allows to reuse a wide range of agro-industrial wastes.

  5. Low-level radioactive waste treatment technology. Low-level radioactive waste management handbook series

    International Nuclear Information System (INIS)

    1984-07-01

    Each generator of low-level radioactive waste must consider three sequential questions: (1) can the waste in its as-generated form be packaged and shipped to a disposal facility; (2) will the packaged waste be acceptable for disposal; and (3) if so, is it cost effective to dispose of the waste in its as-generated form. These questions are aimed at determining if the waste form, physical and chemical characteristics, and radionuclide content collectively are suitable for shipment and disposal in a cost-effective manner. If not, the waste management procedures will involve processing operations in addition to collection, segregation, packaging, shipment, and disposal. This handbook addresses methods of treating and conditioning low-level radioactive waste for shipment and disposal. A framework is provided for selection of cost-effective waste-processing options for generic categories of low-level radioactive waste. The handbook is intended as a decision-making guide that identifies types of information required to evaluate options, methods of evaluation, and limitations associated with selection of any of the processing options

  6. Recycling slaughterhouse waste into fertilizer: how do pyrolysis temperature and biomass additions affect phosphorus availability and chemistry?

    Science.gov (United States)

    Zwetsloot, Marie J; Lehmann, Johannes; Solomon, Dawit

    2015-01-01

    Pyrolysis of slaughterhouse waste could promote more sustainable phosphorus (P) usage through the development of alternative P fertilizers. This study investigated how pyrolysis temperature (220, 350, 550 and 750 °C), rendering before pyrolysis, and wood or corn biomass additions affect P chemistry in bone char, plant availability, and its potential as P fertilizer. Linear combination fitting of synchrotron-based X-ray absorption near edge structure spectra demonstrated that higher pyrolysis temperatures decreased the fit with organic P references, but increased the fit with a hydroxyapatite (HA) reference, used as an indicator of high calcium phosphate (CaP) crystallinity. The fit to the HA reference increased from 0% to 69% in bone with meat residue and from 20% to 95% in rendered bone. Biomass additions to the bone with meat residue reduced the fit to the HA reference by 83% for wood and 95% for corn, and additions to rendered bone by 37% for wood. No detectable aromatic P forms were generated by pyrolysis. High CaP crystallinity was correlated with low water-extractable P, but high formic acid-extractable P indicative of high plant availability. Bone char supplied available P which was only 24% lower than Triple Superphosphate fertilizer and two- to five-fold higher than rock phosphate. Pyrolysis temperature and biomass additions can be used to design P fertilizer characteristics of bone char through changing CaP crystallinity that optimize P availability to plants. © 2014 Society of Chemical Industry.

  7. Mixed Waste Management Facility

    International Nuclear Information System (INIS)

    Brummond, W.; Celeste, J.; Steenhoven, J.

    1993-08-01

    The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE

  8. Optimization of waste management in the EG with the aid of systems analysis methods

    International Nuclear Information System (INIS)

    Braun, H.W.M.; Ditterich, K.; Schneider, J.

    1974-01-01

    The problems of waste management range from their production when they must be collected to transport, conditioning etc., and, finally, to safe disposal. Until recently, the subsystems in waste management had for the most part been treated empirically and separately. In this paper, all subsystems are considered and related to each other with systems analysis methods. In this way the complex problem including the initial and end values can be optimized with regard to a maximum of security and reliability and a minimum of cost and environmental load. The annex contains a simplified example for the treatment of waste mangement by methods of systems analysis. (orig./AK) [de

  9. Hazardous waste management plan, Savannah River Plant

    International Nuclear Information System (INIS)

    Phifer, M.A.

    1984-06-01

    All SRP waste storage, disposal, and recycling facilities that have received hazardous waste, low-level radioactive hazardous waste (mixed waste) or process waste since 1980 have been evaluated by EPA standards. Generally the waste storage areas meet all applicable standards. However, additional storage facilities currently estimated at $2 million and waste disposal facilities currently estimated at $20 million will be required for proper management of stored waste. The majority of the disposal facilities are unlined earthen basins that receive hazardous or process wastes and have or have the potential to contaminate groundwater. To come into compliance with the groundwater standards the influents to the basins will be treated or discontinued, the basins will be decommissioned, groundwater monitoring will be conducted, and remedial actions will be taken as necessary. The costs associated with these basin actions are not completely defined and will increase from present estimates. A major cost which has not been resolved is associated with the disposal of the sludge produced from the treatment plants and basin decommissioning. The Low-Level Radioactive Burial Ground which is also a disposal facility has received mixed waste; however, it does not meet the standards for hazardous waste landfills. In order to properly handle mixed wastes additional storage facilities currently estimated at $500,000 will be provided and options for permanent disposal will be investigated

  10. Techniques for site investigations for underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1985-01-01

    The report provides a more detailed description of the capabilities and applications of the various earth science investigation techniques outlined in the IAEA Technical Reports Series Nos. 177, 215 and 216. These methods are generally appropriate during at least one of the stages of the assessment or selection of a site for any type of waste disposal facility, in shallow ground or in deep geological formations. This report is addressed to technical authorities responsible for or involved in planning, approving, executing and reviewing national waste disposal programmes. It may also help administrative authorities in this field to select appropriate techniques for obtaining the majority of the required information at minimum cost

  11. Substance Flow Analysis of Wastes Containing Polybrominated Diphenyl Ethers

    DEFF Research Database (Denmark)

    Vyzinkarova, Dana; Brunner, Paul H.

    2013-01-01

    materials. Therefore, end-of-life (EOL) plastic materials used for construction must be separated and properly treated, for example, in a state-of-the-art municipal solid waste (MSW) incinerator. In the case of cOctaBDE, the main flows are waste electrical and electronic equipment (WEEE) and, possibly......The present article examines flows and stocks of Stockholm Convention regulated pollutants, commercial penta- and octabrominated diphenyl ether (cPentaBDE, cOctaBDE), on a city level. The goals are to (1) identify sources, pathways, and sinks of these compounds in the city of Vienna, (2) determine...... the fractions that reach final sinks, and (3) develop recommendations for waste management to ensure their minimum recycling and maximum transfer to appropriate final sinks. By means of substance flow analysis (SFA) and scenario analysis, it was found that the key flows of cPentaBDE stem from construction...

  12. Site Specific Waste Management Instructions for loading and shipment of category 3 investigation derived waste to ERDF

    International Nuclear Information System (INIS)

    Corriveau, C.E.; Wolf, D.M.

    1996-08-01

    This Site Specific Waste Management Instruction (SSWMI) provides guidance for management of containerized investigation-derived waste being loaded and transported to the Environmental Restoration Disposal Facility. The SSWMI outlines the waste management practices that will be performed in the field to implement federal, state, and US Department of Energy requirements. Additional guidance for waste packaging, marking, labeling and shipping is provided (US DOT rules in 49 CFR have precedence)

  13. Experimental Determination and Thermodynamic Modeling of Electrical Conductivity of SRS Waste Tank Supernate

    Energy Technology Data Exchange (ETDEWEB)

    Pike, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Reboul, S. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-06-01

    SRS High Level Waste Tank Farm personnel rely on conductivity probes for detection of incipient overflow conditions in waste tanks. Minimal information is available concerning the sensitivity that must be achieved such that that liquid detection is assured. Overly sensitive electronics results in numerous nuisance alarms for these safety-related instruments. In order to determine the minimum sensitivity required of the probe, Tank Farm Engineering personnel need adequate conductivity data to improve the existing designs. Little or no measurements of liquid waste conductivity exist; however, the liquid phase of the waste consists of inorganic electrolytes for which the conductivity may be calculated. Savannah River Remediation (SRR) Tank Farm Facility Engineering requested SRNL to determine the conductivity of the supernate resident in SRS waste Tank 40 experimentally as well as computationally. In addition, SRNL was requested to develop a correlation, if possible, that would be generally applicable to liquid waste resident in SRS waste tanks. A waste sample from Tank 40 was analyzed for composition and electrical conductivity as shown in Table 4-6, Table 4-7, and Table 4-9. The conductivity for undiluted Tank 40 sample was 0.087 S/cm. The accuracy of OLI Analyzer™ was determined using available literature data. Overall, 95% of computed estimates of electrical conductivity are within ±15% of literature values for component concentrations from 0 to 15 M and temperatures from 0 to 125 °C. Though the computational results are generally in good agreement with the measured data, a small portion of literature data deviates as much as ±76%. A simplified model was created that can be used readily to estimate electrical conductivity of waste solution in computer spreadsheets. The variability of this simplified approach deviates up to 140% from measured values. Generally, this model can be applied to estimate the conductivity within a factor of two. The comparison of the

  14. Low level waste disposal

    International Nuclear Information System (INIS)

    Barthoux, A.

    1985-01-01

    Final disposal of low level wastes has been carried out for 15 years on the shallow land disposal of the Manche in the north west of France. Final participant in the nuclear energy cycle, ANDRA has set up a new waste management system from the production center (organization of the waste collection) to the disposal site including the setting up of a transport network, the development of assessment, additional conditioning, interim storage, the management of the disposal center, records of the location and characteristics of the disposed wastes, site selection surveys for future disposals and a public information Department. 80 000 waste packages representing a volume of 20 000 m 3 are thus managed and disposed of each year on the shallow land disposal. The disposal of low level wastes is carried out according to their category and activity level: - in tumuli for very low level wastes, - in monoliths, a concrete structure, of the packaging does not provide enough protection against radioactivity [fr

  15. Permanganate Treatment of Savannah River Site Simulant Wastes for Strontium and Actinide Removal

    International Nuclear Information System (INIS)

    Wilmarth, W.R.

    2003-01-01

    This study examined the use of sodium permanganate and strontium nitrate to remove the actinides and radio-strontium from Savannah River Site (SRS) waste supernate. We examined the quantities of chemical feed reagents along with increased mixing and the excess of organic reductant. Additionally, we examined two processing schemes including that applicable to either the Salt Waste Processing Facility or the Alpha Removal Process (ARP) (5.6 M sodium ion concentration) conditions and the conditions for an In-Tank application (7.5 M sodium ion concentration). Our results support the following conclusions: The process met minimum required decontamination factors (DFs) within the tested parameter sets for strontium and plutonium in both the ARP and In-Tank application. The strontium DFs far exceeded the required values within the tested parameter sets. Within the ARP application, the use of peroxide as the reductant for permanganate produced higher plutonium DFs than the use of sodium formate. Reductant concentration and degree of mixing strongly influenced radionuclide decontamination. In the formate application under the ARP process, increasing the reductant concentration and mixing energy resulted in higher Sr and Pu decontamination

  16. Analysis of low-level wastes. Review of hazardous waste regulations and identification of radioactive mixed wastes. Final report

    International Nuclear Information System (INIS)

    Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.; Piciulo, P.L.

    1985-12-01

    Regulations governing the management and disposal of hazardous wastes have been promulgated by the US Environmental Protection Agency under authority of the Resource Conservation and Recovery Act. These were reviewed and compared with the available information on the properties and characteristics of low-level radioactive wastes (LLW). In addition, a survey was carried out to establish a data base on the nature and composition of LLW in order to determine whether some LLW streams could also be considered hazardous as defined in 40 CFR Part 261. For the survey, an attempt was made to obtain data on the greatest volume of LLW; hence, as many large LLW generators as possible were contacted. The list of 238 generators contacted was based on information obtained from NRC and other sources. The data base was compiled from completed questionnaires which were returned by 97 reactor and non-reactor facilities. The waste volumes reported by these respondents corresponded to approximately 29% of all LLW disposed of in 1984. The analysis of the survey results indicated that three broad categories of LLW may be radioactive mixed wastes. They include: waste containing organic liquids, disposed of by all types of generators; wastes containing lead metal, i.e., discarded shielding or lead containers; wastes containing chromates, i.e., nuclear power plant process wastes where chromates are used as corrosion inhibitors. Certain wastes, specific to particular generators, were identified as potential mixed wastes as well. 8 figs., 48 tabs

  17. Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program

    International Nuclear Information System (INIS)

    Clark, C. Jr.; Hunt-Davenport, L.D.; Cofer, G.H.

    1995-03-01

    This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency's (EPA's) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created

  18. Underage drinking: does the minimum age drinking law offer enough protection?

    Science.gov (United States)

    Green, Rivka; Jason, Hannah; Ganz, Debora

    2015-05-01

    Underage drinking is a significant problem in the US. It is responsible for several thousand mortalities and fatalities each year, both among minors and other members of society. Additionally, underage alcohol consumption produces a severe economic burden in the US. Introduction to alcohol in youth poses serious long-term risks for adolescents, including occupational, educational, and psychosocial impairments, and increases the risk for developing alcohol abuse disorders in adulthood. In order to address and mitigate this problem, the US has set a minimum age drinking law of 21 in all 50 states, and has implemented several supplementary laws limiting the possession and consumption of alcohol. Though these laws have successfully reduced underage drinking, several additional strategies are noteworthy, including preventative and intervention efforts incorporating environmental, individual, communal, and parental factors. The following literature review describes these concepts as they relate to underage drinking laws in the US. Directions for future research, interventions, and ongoing challenges related to the minimum drinking age in the US are also discussed.

  19. Understanding the Minimum Wage: Issues and Answers.

    Science.gov (United States)

    Employment Policies Inst. Foundation, Washington, DC.

    This booklet, which is designed to clarify facts regarding the minimum wage's impact on marketplace economics, contains a total of 31 questions and answers pertaining to the following topics: relationship between minimum wages and poverty; impacts of changes in the minimum wage on welfare reform; and possible effects of changes in the minimum wage…

  20. Youth minimum wages and youth employment

    NARCIS (Netherlands)

    Marimpi, Maria; Koning, Pierre

    2018-01-01

    This paper performs a cross-country level analysis on the impact of the level of specific youth minimum wages on the labor market performance of young individuals. We use information on the use and level of youth minimum wages, as compared to the level of adult minimum wages as well as to the median

  1. Concentrated energy addition for active drag reduction in hypersonic flow regime

    Science.gov (United States)

    Ashwin Ganesh, M.; John, Bibin

    2018-01-01

    Numerical optimization of hypersonic drag reduction technique based on concentrated energy addition is presented in this study. A reduction in wave drag is realized through concentrated energy addition in the hypersonic flowfield upstream of the blunt body. For the exhaustive optimization presented in this study, an in-house high precision inviscid flow solver has been developed. Studies focused on the identification of "optimum energy addition location" have revealed the existence of multiple minimum drag points. The wave drag coefficient is observed to drop from 0.85 to 0.45 when 50 Watts of energy is added to an energy bubble of 1 mm radius located at 74.7 mm upstream of the stagnation point. A direct proportionality has been identified between energy bubble size and wave drag coefficient. Dependence of drag coefficient on the upstream added energy magnitude is also revealed. Of the observed multiple minimum drag points, the energy deposition point (EDP) that offers minimum wave drag just after a sharp drop in drag is proposed as the most optimum energy addition location.

  2. Discretization of space and time: determining the values of minimum length and minimum time

    OpenAIRE

    Roatta , Luca

    2017-01-01

    Assuming that space and time can only have discrete values, we obtain the expression of the minimum length and the minimum time interval. These values are found to be exactly coincident with the Planck's length and the Planck's time but for the presence of h instead of ħ .

  3. Minimum wage development in the Russian Federation

    OpenAIRE

    Bolsheva, Anna

    2012-01-01

    The aim of this paper is to analyze the effectiveness of the minimum wage policy at the national level in Russia and its impact on living standards in the country. The analysis showed that the national minimum wage in Russia does not serve its original purpose of protecting the lowest wage earners and has no substantial effect on poverty reduction. The national subsistence minimum is too low and cannot be considered an adequate criterion for the setting of the minimum wage. The minimum wage d...

  4. Summary of Uranium Solubility Studies in Concrete Waste Forms and Vadose Zone Environments

    Energy Technology Data Exchange (ETDEWEB)

    Golovich, Elizabeth C.; Wellman, Dawn M.; Serne, R. Jeffrey; Bovaird, Chase C.

    2011-09-30

    One of the methods being considered for safely disposing of Category 3 low-level radioactive wastes is to encase the waste in concrete. Concrete encasement would contain and isolate the waste packages from the hydrologic environment and act as an intrusion barrier. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages in concrete. These concrete-encased waste stacks are expected to vary in size with maximum dimensions of 6.4 m long, 2.7 m wide, and 4 m high. The waste stacks are expected to have a surrounding minimum thickness of 15 cm of concrete encasement. These concrete-encased waste packages are expected to withstand environmental exposure (solar radiation, temperature variations, and precipitation) until an interim soil cover or permanent closure cover is installed and to remain largely intact thereafter. Any failure of concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. This report presents the results of investigations elucidating the uranium mineral phases controlling the long-term fate of uranium within concrete waste forms and the solubility of these phases in concrete pore waters and alkaline, circum-neutral vadose zone environments.

  5. Separate collection of plastic waste, better than technical sorting from municipal solid waste?

    Science.gov (United States)

    Feil, Alexander; Pretz, Thomas; Jansen, Michael; Thoden van Velzen, Eggo U

    2017-02-01

    The politically preferred solution to fulfil legal recycling demands is often implementing separate collection systems. However, experience shows their limitations, particularly in urban centres with a high population density. In response to the European Union landfill directive, mechanical biological waste treatment plants have been installed all over Europe. This technology makes it possible to retrieve plastic waste from municipal solid waste. Operators of mechanical biological waste treatment plants, both in Germany and the Netherlands, have started to change their mechanical separation processes to additionally produce plastic pre-concentrates. Results from mechanical biological waste treatment and separate collection of post-consumer packaging waste will be presented and compared. They prove that both the yield and the quality of plastic waste provided as feedstock for the production of secondary plastic raw material are largely comparable. An economic assessment shows which conditions for a technical sorting plant are economically attractive in comparison to separate collection systems. It is, however, unlikely that plastic recycling will ever reach cost neutrality.

  6. French regulations and waste management

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1985-01-01

    The authors describe the organization and the role of safety authorities in France in matter of waste management. They precise the French policy in waste storage and treatment: basic objectives, optimization of waste management. The safety requirements are based upon the barrier principle. Safety requirements about waste conditioning and waste disposal are mentioned. In addition to the safety analysis and studies described above, the Protection and Nuclear Safety Institute assists the ministerial authorities in the drafting of ''basic safety rules (RFS)'', laying down safety objectives. Appendix 1 and Appendix 2 deal with safety aspects in spent fuel storage and in transportation of radioactive materials [fr

  7. Fernald waste management and disposition

    International Nuclear Information System (INIS)

    West, M.L.; Fisher, L.A.; Frost, M.L.; Rast, D.M.

    1995-01-01

    Historically waste management within the Department of Energy complex has evolved around the operating principle of packaging waste generated and storing until a later date. In many cases wastes were delivered to onsite waste management organizations with little or no traceability to origin of generation. Sites then stored their waste for later disposition offsite or onsite burial. While the wastes were stored, sites incurred additional labor costs for maintaining, inspecting and repackaging containers and capital costs for storage warehouses. Increased costs, combined with the inherent safety hazards associated with storage of hazardous material make these practices less attractive. This paper will describe the methods used at the Department of Energy's Fernald site by the Waste Programs Management Division to integrate with other site divisions to plan in situ waste characterization prior to removal. This information was utilized to evaluate and select disposal options and then to package and ship removed wastes without storage

  8. Aerobic Microbial Respiration In Oceanic Oxygen Minimum Zones

    DEFF Research Database (Denmark)

    Kalvelage, Tim; Lavik, Gaute; Jensen, Marlene Mark

    2015-01-01

    Oxygen minimum zones are major sites of fixed nitrogen loss in the ocean. Recent studies have highlighted the importance of anaerobic ammonium oxidation, anammox, in pelagic nitrogen removal. Sources of ammonium for the anammox reaction, however, remain controversial, as heterotrophic denitrifica......Oxygen minimum zones are major sites of fixed nitrogen loss in the ocean. Recent studies have highlighted the importance of anaerobic ammonium oxidation, anammox, in pelagic nitrogen removal. Sources of ammonium for the anammox reaction, however, remain controversial, as heterotrophic...... denitrification and alternative anaerobic pathways of organic matter remineralization cannot account for the ammonium requirements of reported anammox rates. Here, we explore the significance of microaerobic respiration as a source of ammonium during organic matter degradation in the oxygen-deficient waters off...... Namibia and Peru. Experiments with additions of double-labelled oxygen revealed high aerobic activity in the upper OMZs, likely controlled by surface organic matter export. Consistently observed oxygen consumption in samples retrieved throughout the lower OMZs hints at efficient exploitation of vertically...

  9. Minimum emittance of three-bend achromats

    International Nuclear Information System (INIS)

    Li Xiaoyu; Xu Gang

    2012-01-01

    The calculation of the minimum emittance of three-bend achromats (TBAs) made by Mathematical software can ignore the actual magnets lattice in the matching condition of dispersion function in phase space. The minimum scaling factors of two kinds of widely used TBA lattices are obtained. Then the relationship between the lengths and the radii of the three dipoles in TBA is obtained and so is the minimum scaling factor, when the TBA lattice achieves its minimum emittance. The procedure of analysis and the results can be widely used in achromats lattices, because the calculation is not restricted by the actual lattice. (authors)

  10. Determination of performance criteria for high-level solidified nuclear waste from the commercial nuclear fuel cycle: a probabilistic safety analysis

    International Nuclear Information System (INIS)

    Heckman, R.A.

    1978-01-01

    To minimize the radiological risk from the operation of a waste management system for the safe disposal of high-level waste, performance characteristics of the solidified waste form must be specified. The minimum waste form characteristics that must be specified are the radionuclide volatilization fraction, airborne particulate dispersion fraction, and the aqueous dissolution characteristics. The results indicate that the pre-emplacement environs are more limiting in establishing the waste form performance criteria than the post-emplacement environs. The actual values of expected risk are sensitive to modeling assumptions and data base uncertainties. The transportation step appears to be the most limiting in determining the required performance characteristics

  11. Designing testing service at baristand industri Medan’s liquid waste laboratory

    Science.gov (United States)

    Kusumawaty, Dewi; Napitupulu, Humala L.; Sembiring, Meilita T.

    2018-03-01

    Baristand Industri Medan is a technical implementation unit under the Industrial and Research and Development Agency, the Ministry of Industry. One of the services often used in Baristand Industri Medan is liquid waste testing service. The company set the standard of service is nine working days for testing services. At 2015, 89.66% on testing services liquid waste does not meet the specified standard of services company because of many samples accumulated. The purpose of this research is designing online services to schedule the coming the liquid waste sample. The method used is designing an information system that consists of model design, output design, input design, database design and technology design. The results of designing information system of testing liquid waste online consist of three pages are pages to the customer, the recipient samples and laboratory. From the simulation results with scheduled samples, then the standard services a minimum of nine working days can be reached.

  12. Value Addition to Sulfate Waste Pickle Liquor of Steel Industry Using Hydrometallurgical Processes

    Science.gov (United States)

    Agrawal, Archana; Sahu, K. K.

    2009-12-01

    The solvent extraction of concentrated acid was investigated from sulfate waste pickle liquors using Cyanex 923 (trialkylphosphine oxide (TRPO); manufactured by Cytec Industries Inc., Woodland Park, NJ; provided by Cyanamid Canada Inc. (Markham, Canada)) as an extractant. The effect of various parameters was studied such as extractant concentration, organic-to-aqueous phase ratio, temperature. and retention time on acid extraction from the waste pickle liquor to the organic phase, After the saturation of the organic phase with sulfuric acid, stripping studies were performed to back-extract the pure acid into the aqueous phase. The raffinate of the solvent extraction process that contains both ferrous and ferric iron as well as trace impurities was subjected to oxidation and hydrothermal treatment to precipitate iron with a well-defined pseudo-cubic morphology and a high coercivity value that renders it suitable for high-grade ferrite production.

  13. Waste minimization assessment procedure

    International Nuclear Information System (INIS)

    Kellythorne, L.L.

    1993-01-01

    Perry Nuclear Power Plant began developing a waste minimization plan early in 1991. In March of 1991 the plan was documented following a similar format to that described in the EPA Waste Minimization Opportunity Assessment Manual. Initial implementation involved obtaining management's commitment to support a waste minimization effort. The primary assessment goal was to identify all hazardous waste streams and to evaluate those streams for minimization opportunities. As implementation of the plan proceeded, non-hazardous waste streams routinely generated in large volumes were also evaluated for minimization opportunities. The next step included collection of process and facility data which would be useful in helping the facility accomplish its assessment goals. This paper describes the resources that were used and which were most valuable in identifying both the hazardous and non-hazardous waste streams that existed on site. For each material identified as a waste stream, additional information regarding the materials use, manufacturer, EPA hazardous waste number and DOT hazard class was also gathered. Once waste streams were evaluated for potential source reduction, recycling, re-use, re-sale, or burning for heat recovery, with disposal as the last viable alternative

  14. Thermogravimetric analysis of the co-pyrolysis of paper sludge and municipal solid waste

    International Nuclear Information System (INIS)

    Fang, Shiwen; Yu, Zhaosheng; Lin, Yousheng; Hu, Shanchao; Liao, Yanfen; Ma, Xiaoqian

    2015-01-01

    Highlights: • The co-pyrolysis of municipal solid waste, paper sludge and the blends was studied. • The reactivity of paper sludge could be improved by blending municipal solid waste. • The FWO and KAS methods were used to calculate activation energy. • The average activation energy was the minimum by blending 50% paper sludge. - Abstract: The pyrolysis characteristics of municipal solid waste (MSW), paper sludge (PS) and their blends were studied through a thermogravimetric simultaneous thermal analyzer from room temperature to 1000 °C. Meanwhile their kinetics were studied by Flynn–Wall–Ozawa (FWO) and Kissinger–Akahira–Sunose (KAS) methods. The mass proportions of PS in the blends were 10%, 30%, 50%, 70%, 90%, respectively and the experiments were carried out at different heating rates (30, 40 and 50 °C/min). The initial temperature of MSW was lower than that of PS and the terminated temperature was higher than PS. The comprehensive characteristic index decreased progressively along with the decrease of the MSW proportion. The values of average activation energies calculated by FWO and KAS methods were highly consistent. The average activation energy reached the minimum number, 96.7 kJ/mol by KAS and 11.56 kJ/mol by FWO, with the proportion of PS was 50%

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

    International Nuclear Information System (INIS)

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

    2011-01-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-08-12

    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

  17. Tracking mixed waste from environmental restoration through waste management for the Federal Facility Compliance Act

    International Nuclear Information System (INIS)

    Isbell, D.; Tolbert-Smith, M.; MacDonell, M.; Peterson, J.

    1994-01-01

    The Federal Facility Compliance Act required the US Department of Energy (DOE) to prepare an inventory report that presents comprehensive information on mixed wastes. Additional documents, such as site treatment plans, were also required of facilities with mixed waste. For a number of reasons, not all DOE mixed waste sites are able to provide detailed characterization and planning data at this time. Thus, an effort is currently under way to develop a reporting format that will permit mixed waste information across the DOE complex to be tracked as it becomes available

  18. Waste Minimization Measurement and Progress Reporting

    International Nuclear Information System (INIS)

    Stone, K.A.

    1995-01-01

    Westinghouse Savannah River Company is implementing productivity improvement concepts into the Waste Minimization Program by focusing on the positive initiatives taken to reduce waste generation at the Savannah River Site. Previous performance measures, based only on waste generation rates, proved to be an ineffective metric for measuring performance and promoting continuous improvements within the Program. Impacts of mission changes and non-routine operations impeded development of baseline waste generation rates and often negated waste generation trending reports. A system was developed to quantify, document and track innovative activities that impact waste volume and radioactivity/toxicity reductions. This system coupled with Management-driven waste disposal avoidance goals is proving to be a powerful tool to promote waste minimization awareness and the implementation of waste reduction initiatives. Measurement of waste not generated, in addition to waste generated, increases the credibility of the Waste Minimization Program, improves sharing of success stories, and supports development of regulatory and management reports

  19. WASTE HANDLING BUILDING SHIELD WALL ANALYSIS

    International Nuclear Information System (INIS)

    Padula, D.

    2000-01-01

    The scope of this analysis is to estimate the shielding wall, ceiling or equivalent door thicknesses that will be required in the Waste Handling Building to maintain the radiation doses to personnel within acceptable limits. The shielding thickness calculated is the minimum required to meet administrative limits, and not necessarily what will be recommended for the final design. The preliminary evaluations will identify the areas which have the greatest impact on mechanical and facility design concepts. The objective is to provide the design teams with the necessary information to assure an efficient and effective design

  20. Renewable municipal waste barometer - EurObserv'ER - November 2014

    International Nuclear Information System (INIS)

    2014-11-01

    EurObserv'ER reckons that the energy recovered from renewable municipal waste incineration that takes into account the organic part (cartons, kitchen waste, etc.) increased slightly in 2013 (by 0.7% over 2012), giving output of about 8.7 Mtoe. Heat sales to district heating networks stepped up conspicuously in 2013, as synergy between the incineration plants and the heating networks improved. Heat output increased 7.8% over 2012 to reach 2.4 Mtoe, while electricity output remained stable at 18.7 TWh. This development demonstrates the increased energy efficiency of the incineration plants that is stimulated by European legislation, primarily through the transposition of the framework directive on waste (2008/98/EC) that encourages operators to optimize the energy efficiency of their plants, primarily by looking for new outlets for heat production. The Directive stipulates that the incinerators can only be classed as waste-to- energy recovery units if they meet minimum yield criteria, which in the case of plant constructed since 31 December 2008 must be at least equal to 65%. The energy efficiency of those constructed prior to 2008 must be at least 60%. If these criteria are not met, the waste incineration process will not be recognized as treatment eligible for waste ranking as imposed by the directive

  1. An analysis of repository waste-handling operations

    International Nuclear Information System (INIS)

    Dennis, A.W.

    1990-09-01

    This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs

  2. Health and safety training for hazardous waste site activities at Oak Ridge National Laboratory: Implementation of OSHA 29 CFR 1910.120(e)

    International Nuclear Information System (INIS)

    White, D.A.

    1988-01-01

    Among the requirements set forth by the interim final rule, 29 CFR Part 1910.120, promulgated by the Occupational Safety and Health Administration (OSHA) in response to the Superfund Amendments and Reauthorization Act of 1986 (SARA), are specific provisions for health and safety training of employees involved in hazardous waste operations. These training provisions require a minimum of 40 hours of initial instruction off the site for employees involved in corrective operations and cleanup activities at hazardous waste sites. A less detailed training requirement of 24 hours is specified for employees working in more routine treatment, storage, and disposal activities. Managers and supervisors who are directly responsible for or who supervise employees engaged in hazardous waste operations must complete 8 additional hours of training related to management of hazardous waste site activities. Consistent with the intent of 29 CFR 1910.120, a training program has been developed at Oak Ridge National Laboratory (ORNL) to comply with the need to protect the safety and health of hazardous waste workers. All hourly requirements specified in the interim final rule are met by a comprehensive program structure involving three stages of training. This paper will outline and discuss the content of each of these stages of the program. The involvement of various ORNL organizations in facilitating the training will be highlighted. Implementation strategies will be discussed as well as progress made to date

  3. Management of radioactive wastes - an overview of the Indian programme

    International Nuclear Information System (INIS)

    Thomas, K.T.; Sunder Rajan, N.S.; Balu, K.; Khan, A.A.

    1977-01-01

    An overview of the management of radioactive wastes with particular reference to the Indian Nuclear Programme is presented. The initial design philosophy of the radwaste management system is discussed in relation to accepting a calculated, minimum discharge of radioactivity to the environment. A brief report of the operational experience with the low and intermediate level radwaste systems is given. Factors that influence the review of the present philosophy for future adoption are presented. Some methods being developed for decreasing release of the radioactivity to the environment are discussed. Among techniques considered are solar evaporation, delay and decay of fission rare gases from power reactors and concentration and storage of Kr 85 from fuel reprocessing plants. Problems in the management of high level and alph-bearing wastes are discussed with particular reference to the nature of the waste generated and the policy under implementation for their management. The matrices, solidification processes, modes of interim storage and criteria for selection of site for ultimate dispensation of the solidified high level wastes in geological formations are described. An approach towards the solution of the probelm of management of alpha-bearing waste is also presented

  4. Permeability test and slope stability analysis of municipal solid waste in Jiangcungou Landfill, Shaanxi, China.

    Science.gov (United States)

    Yang, Rong; Xu, Zengguang; Chai, Junrui; Qin, Yuan; Li, Yanlong

    2016-07-01

    With the rapid increase of city waste, landfills have become a major method to deals with municipal solid waste. Thus, the safety of landfills has become a valuable research topic. In this paper, Jiangcungou Landfill, located in Shaanxi, China, was investigated and its slope stability was analyzed. Laboratory tests were used to obtain permeability coefficients of municipal solid waste. Based on the results, the distribution of leachate and stability in the landfill was computed and analyzed. These results showed: the range of permeability coefficient was from 1.0 × 10(-7) cm sec(-1) to 6.0 × 10(-3) cm sec(-1) on basis of laboratory test and some parameters of similar landfills. Owing to the existence of intermediate cover layers in the landfill, the perched water level appeared in the landfill with heavy rain. Moreover, the waste was filled with leachate in the top layer, and the range of leachate level was from 2 m to 5 m in depth under the waste surface in other layers. The closer it gets to the surface of landfill, the higher the perched water level of leachate. It is indicated that the minimum safety factors were 1.516 and 0.958 for winter and summer, respectively. Additionally, the slope failure may occur in summer. The research of seepage and stability in landfills may provide a less costly way to reduce accidents. Landslides often occur in the Jiangcungou Landfill because of the high leachate level. Some measures should be implemented to reduce the leachate level. This paper investigated seepage and slope stability of landfills by numerical methods. These results may provide the basis for increasing stability of landfills.

  5. WRAP Module 1 sampling strategy and waste characterization alternatives study

    Energy Technology Data Exchange (ETDEWEB)

    Bergeson, C.L.

    1994-09-30

    The Waste Receiving and Processing Module 1 Facility is designed to examine, process, certify, and ship drums and boxes of solid wastes that have a surface dose equivalent of less than 200 mrem/h. These wastes will include low-level and transuranic wastes that are retrievably stored in the 200 Area burial grounds and facilities in addition to newly generated wastes. Certification of retrievably stored wastes processing in WRAP 1 is required to meet the waste acceptance criteria for onsite treatment and disposal of low-level waste and mixed low-level waste and the Waste Isolation Pilot Plant Waste Acceptance Criteria for the disposal of TRU waste. In addition, these wastes will need to be certified for packaging in TRUPACT-II shipping containers. Characterization of the retrievably stored waste is needed to support the certification process. Characterization data will be obtained from historical records, process knowledge, nondestructive examination nondestructive assay, visual inspection of the waste, head-gas sampling, and analysis of samples taken from the waste containers. Sample characterization refers to the method or methods that are used to test waste samples for specific analytes. The focus of this study is the sample characterization needed to accurately identify the hazardous and radioactive constituents present in the retrieved wastes that will be processed in WRAP 1. In addition, some sampling and characterization will be required to support NDA calculations and to provide an over-check for the characterization of newly generated wastes. This study results in the baseline definition of WRAP 1 sampling and analysis requirements and identifies alternative methods to meet these requirements in an efficient and economical manner.

  6. WRAP Module 1 sampling strategy and waste characterization alternatives study

    International Nuclear Information System (INIS)

    Bergeson, C.L.

    1994-01-01

    The Waste Receiving and Processing Module 1 Facility is designed to examine, process, certify, and ship drums and boxes of solid wastes that have a surface dose equivalent of less than 200 mrem/h. These wastes will include low-level and transuranic wastes that are retrievably stored in the 200 Area burial grounds and facilities in addition to newly generated wastes. Certification of retrievably stored wastes processing in WRAP 1 is required to meet the waste acceptance criteria for onsite treatment and disposal of low-level waste and mixed low-level waste and the Waste Isolation Pilot Plant Waste Acceptance Criteria for the disposal of TRU waste. In addition, these wastes will need to be certified for packaging in TRUPACT-II shipping containers. Characterization of the retrievably stored waste is needed to support the certification process. Characterization data will be obtained from historical records, process knowledge, nondestructive examination nondestructive assay, visual inspection of the waste, head-gas sampling, and analysis of samples taken from the waste containers. Sample characterization refers to the method or methods that are used to test waste samples for specific analytes. The focus of this study is the sample characterization needed to accurately identify the hazardous and radioactive constituents present in the retrieved wastes that will be processed in WRAP 1. In addition, some sampling and characterization will be required to support NDA calculations and to provide an over-check for the characterization of newly generated wastes. This study results in the baseline definition of WRAP 1 sampling and analysis requirements and identifies alternative methods to meet these requirements in an efficient and economical manner

  7. Generation of electronic waste in India: Current scenario, dilemmas ...

    African Journals Online (AJOL)

    This paper tries to quantify the amount of E-waste generated in India with the related stakeholder involvement. Electronic waste (E-waste) or waste electrical and electronic equipments (WEEE), which is relatively a recent addition to the hazardous waste stream, is drawing rapid attention across the globe as the quantity ...

  8. 30 CFR 57.19021 - Minimum rope strength.

    Science.gov (United States)

    2010-07-01

    ... feet: Minimum Value=Static Load×(7.0−0.001L) For rope lengths 3,000 feet or greater: Minimum Value=Static Load×4.0. (b) Friction drum ropes. For rope lengths less than 4,000 feet: Minimum Value=Static Load×(7.0−0.0005L) For rope lengths 4,000 feet or greater: Minimum Value=Static Load×5.0. (c) Tail...

  9. 30 CFR 56.19021 - Minimum rope strength.

    Science.gov (United States)

    2010-07-01

    ... feet: Minimum Value=Static Load×(7.0-0.001L) For rope lengths 3,000 feet or greater: Minimum Value=Static Load×4.0 (b) Friction drum ropes. For rope lengths less than 4,000 feet: Minimum Value=Static Load×(7.0-0.0005L) For rope lengths 4,000 feet or greater: Minimum Value=Static Load×5.0 (c) Tail ropes...

  10. Low-level radioactive wastes: Their treatment, handling, disposal

    Energy Technology Data Exchange (ETDEWEB)

    Straub, Conrad P [Robert A. Taft Sanitary Engineering Center, Radiological Health Research Activities, Cincinnati, OH(United States)

    1964-07-01

    The release of low level wastes may result in some radiation exposure to man and his surroundings. This book describes techniques of handling, treatment, and disposal of low-level wastes aimed at keeping radiation exposure to a practicable minimum. In this context, wastes are considered low level if they are released into the environment without subsequent control. This book is concerned with practices relating only to continuous operations and not to accidental releases of radioactive materials. It is written by use for those interested in low level waste disposal problems and particularly for the health physicist concerned with these problems in the field. It should be helpful also to water and sewage works personnel concerned with the efficiency of water and sewage treatment processes for the removal of radioactive materials; the personnel engaged in design, construction, licensing, and operation of treatment facilities; and to student of nuclear technology. After an introduction the following areas are discussed: sources, quantities and composition of radioactive wastes; collection, sampling and measurement; direct discharge to the water, soil and air environment; air cleaning; removal of radioactivity by water-treatment processes and biological processes; treatment on site by chemical precipitation , ion exchange and absorption, electrodialysis, solvent extraction and other methods; treatment on site including evaporation and storage; handling and treatment of solid wastes; public health implications. Appendices include a glossary; standards for protection against radiation; federal radiation council radiation protection guidance for federal agencies; site selection criteria for nuclear energy facilities.

  11. VULNERABILITY OF MOUNTAIN RIVERS TO WASTE DUMPING FROM NEAMT COUNTY, ROMANIA

    Directory of Open Access Journals (Sweden)

    FLORIN-CONSTANTIN MIHAI

    2012-11-01

    Full Text Available Lack of waste management facilities from mountain region often lead to uncontrolled disposal of waste on river banks polluting the local environment and damaging the tourism potential. Geographical conditions influences the distribution of human settlements which are located along the rivers and its tributaries. This paper aims to estimate the amounts of household waste generated and uncollected disposed into mountain rivers, taking into account several factors such as:proximity of rivers to the human settlements, the morphology of villages, length of river that crosses the locality(built up areas, local population, the access to waste collection services and waste management infrastructure. Vulnerability of rivers to illegal dumping is performed using GIS techniques, highlighting the localities pressure on rivers in close proximity. For this purpose, it developed a calculation model for estimation the amounts of waste (kg that are dumped on a river section (m that crosses a locality (village or it is in close proximity. This estimation is based on the “principle of proximity and minimum effort” it can be applied in any mountainous region that are lacking or partially access to waste collection services. It is an assessment tool of mountain rivers vulnerability to waste dumping,taking into account the geographical and demographic conditions of the study area. Also the current dysfunctions are analyzed based on field observations.

  12. Test plan for buried waste containment system materials

    International Nuclear Information System (INIS)

    Weidner, J.; Shaw, P.

    1997-03-01

    The objectives of the FY 1997 barrier material work at the Idaho National Engineering and Environmental Laboratory are to (1) select a waste barrier material and verify that it is compatible with the Buried Waste Containment System Process, and (2) determine if, and how, the Buried Waste Containment System emplacement process affects the material properties and performance (on proof of principle scale). This test plan describes a set of measurements and procedures used to validate a waste barrier material for the Buried Waste Containment System. A latex modified proprietary cement manufactured by CTS Cement Manufacturing Company will be tested. Emplacement properties required for the Buried Waste Containment System process are: slump between 8 and 10 in., set time between 15 and 30 minutes, compressive strength at set of 20 psi minimum, and set temperature less than 100 degrees C. Durability properties include resistance to degradation from carbonate, sulfate, and waste-site soil leachates. A set of baseline barrier material properties will be determined to provide a data base for comparison with the barrier materials when tested in the field. The measurements include permeability, petrographic analysis to determine separation and/or segregation of mix components, and a set of mechanical properties. The measurements will be repeated on specimens from the field test material. The data will be used to determine if the Buried Waste Containment System equipment changes the material. The emplacement properties will be determined using standard laboratory procedures and instruments. Durability of the barrier material will be evaluated by determining the effect of carbonate, sulfate, and waste-site soil leachates on the compressive strength of the barrier material. The baseline properties will be determined using standard ASTM procedures. 9 refs., 1 fig., 2 tabs

  13. Hanford Waste Transfer Planning and Control - 13465

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

    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)

  14. Hospital wastes management containing in radioactive refusals

    International Nuclear Information System (INIS)

    Campi, F.

    1999-01-01

    In large hospitals, featuring a nuclear medicine department, diagnostic examinations and metabolic therapies are performed using an amount of radio drugs per day averaging around some hundreds mCi. Part of these drugs are disposed in the conventional patient related waste and collected within the hospital itself. Before directing the wastes to the disposal, it is necessary verify that they do not contain radioactive materials. This article refers a study on the possibility to perform this verification by means of an automatic radio-metric system, in order to improve the efficiency, the speed and the safety of the control. Measures devoted to determined the minimum detectable activities for the main radionuclides used in the hospitals have been executed, and it has been designed a comprehensive device able to operate automatically, and unattended by any operator, the selection of radioactive refusals [it

  15. Use of waste materials in rubber matrix

    Directory of Open Access Journals (Sweden)

    Pajtášová Mariana

    2018-01-01

    Full Text Available The presented paper deals with the use of waste materials as ecological fillers into rubber matrix. Waste materials were used as partial replacement of the commercial filler – carbon black, designated as N339. These prepared rubber compounds were characterized on the basis of the rheology and vulcanization characteristics – minimum torque (ML, maximum torque (MH, optimum time of vulcanization (t(c90, processing safety of compound (ts, rate coefficient of vulcanization (Rv. In the case of the prepared vulcanizates, physical-mechanical properties (tensile strength, tensibility and hardness and dynamic-mechanical properties (storage modulus, loss modulus, loss angle tan δ were investigated. Using the dependency of loss angle on temperature, the selected properties for tyre tread vulcanizates were evaluated, including traction on snow and ice, traction on the wet surface and rolling resistance.

  16. Waste management, waste resource facilities and waste conversion processes

    International Nuclear Information System (INIS)

    Demirbas, Ayhan

    2011-01-01

    In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

  17. 30 CFR 77.1431 - Minimum rope strength.

    Science.gov (United States)

    2010-07-01

    ... feet: Minimum Value=Static Load×(7.0−0.001L) For rope lengths 3,000 feet or greater: Minimum Value=Static Load×4.0 (b) Friction drum ropes. For rope lengths less than 4,000 feet: Minimum Value=Static Load×(7.0−0.0005L) For rope lengths 4,000 feet or greater: Minimum Value=Static Load×5.0 (c) Tail ropes...

  18. Waste Acceptance System Requirements document (WASRD)

    International Nuclear Information System (INIS)

    1993-01-01

    This Waste Acceptance System Requirements document (WA-SRD) describes the functions to be performed and the technical requirements for a Waste Acceptance System for accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) into the Civilian Radioactive Waste Management System (CRWMS). This revision of the WA-SRD addresses the requirements for the acceptance of HLW. This revision has been developed as a top priority document to permit DOE's Office of Environmental Restoration and Waste Management (EM) to commence waste qualification runs at the Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) in a timely manner. Additionally, this revision of the WA-SRD includes the requirements from the Physical System Requirements -- Accept Waste document for the acceptance of SNF. A subsequent revision will fully address requirements relative to the acceptance of SNF

  19. Ferrocyanide Safety Project: Comparison of actual and simulated ferrocyanide waste properties

    International Nuclear Information System (INIS)

    Scheele, R.D.; Burger, L.L.; Sell, R.L.; Bredt, P.R.; Barrington, R.J.

    1994-09-01

    In the 1950s, additional high-level radioactive waste storage capacity was needed to accommodate the wastes that would result from the production of recovery of additional nuclear defense materials. To provide this additional waste storage capacity, the Hanford Site operating contractor developed a process to decontaminate aqueous wastes by precipitating radiocesium as an alkali nickel ferrocyanide; this process allowed disposal of the aqueous waste. The radiocesium scavenging process as developed was used to decontaminate (1) first-cycle bismuth phosphate (BiPO 4 ) wastes, (2) acidic wastes resulting from uranium recovery operations, and (3) the supernate from neutralized uranium recovery wastes. The radiocesium scavenging process was often coupled with other scavenging processes to remove radiostrontium and radiocobalt. Because all defense materials recovery processes used nitric acid solutions, all of the wastes contained nitrate, which is a strong oxidizer. The variety of wastes treated, and the occasional coupling of radiostrontium and radiocobalt scavenging processes with the radiocesium scavenging process, resulted in ferrocyanide-bearing wastes having many different compositions. In this report, we compare selected physical, chemical, and radiochemical properties measured for Tanks C-109 and C-112 wastes and selected physical and chemical properties of simulated ferrocyanide wastes to assess the representativeness of stimulants prepared by WHC

  20. Proceedings of the 3. International conference on waste management in the chemical and petrochemical industries. Volume 1 and 2.

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Francisco F; Pereira Filho, Francisco A; Almeida, Sergio A.S. [eds.

    1994-12-31

    To produce without pollution is today a mandate for the preservation of our society. To produce cleaner means to conserve energy and natural resources, to reduce the use of toxic substances, to invest in the evolution of products and production processes towards a minimum of residues. The Third International Conference on Waste Minimization in the Chemical and Petrochemical Industries addresses these challenging questions regarding waste minimization

  1. Proceedings of the 3. International conference on waste management in the chemical and petrochemical industries. Volume 1 and 2.

    Energy Technology Data Exchange (ETDEWEB)

    Lima, Francisco F.; Pereira Filho, Francisco A.; Almeida, Sergio A.S. [eds.

    1993-12-31

    To produce without pollution is today a mandate for the preservation of our society. To produce cleaner means to conserve energy and natural resources, to reduce the use of toxic substances, to invest in the evolution of products and production processes towards a minimum of residues. The Third International Conference on Waste Minimization in the Chemical and Petrochemical Industries addresses these challenging questions regarding waste minimization

  2. Closed Fuel Cycle Waste Treatment Strategy

    Energy Technology Data Exchange (ETDEWEB)

    Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Collins, E. D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crum, J. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, S. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Garn, T. G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gombert, D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Maio, V. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Matyas, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nenoff, T. M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, G. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thallapally, P. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, J. H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-02-01

    This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form

  3. Multi-period fuzzy mean-semi variance portfolio selection problem with transaction cost and minimum transaction lots using genetic algorithm

    Directory of Open Access Journals (Sweden)

    Mohammad Ali Barati

    2016-04-01

    Full Text Available Multi-period models of portfolio selection have been developed in the literature with respect to certain assumptions. In this study, for the first time, the portfolio selection problem has been modeled based on mean-semi variance with transaction cost and minimum transaction lots considering functional constraints and fuzzy parameters. Functional constraints such as transaction cost and minimum transaction lots were included. In addition, the returns on assets parameters were considered as trapezoidal fuzzy numbers. An efficient genetic algorithm (GA was designed, results were analyzed using numerical instances and sensitivity analysis were executed. In the numerical study, the problem was solved based on the presence or absence of each mode of constraints including transaction costs and minimum transaction lots. In addition, with the use of sensitivity analysis, the results of the model were presented with the variations of minimum expected rate of programming periods.

  4. A Phosphate Minimum in the Oxygen Minimum Zone (OMZ) off Peru

    Science.gov (United States)

    Paulmier, A.; Giraud, M.; Sudre, J.; Jonca, J.; Leon, V.; Moron, O.; Dewitte, B.; Lavik, G.; Grasse, P.; Frank, M.; Stramma, L.; Garcon, V.

    2016-02-01

    The Oxygen Minimum Zone (OMZ) off Peru is known to be associated with the advection of Equatorial SubSurface Waters (ESSW), rich in nutrients and poor in oxygen, through the Peru-Chile UnderCurrent (PCUC), but this circulation remains to be refined within the OMZ. During the Pelágico cruise in November-December 2010, measurements of phosphate revealed the presence of a phosphate minimum (Pmin) in various hydrographic stations, which could not be explained so far and could be associated with a specific water mass. This Pmin, localized at a relatively constant layer ( 20minimum with a mean vertical phosphate decrease of 0.6 µM but highly variable between 0.1 and 2.2 µM. In average, these Pmin are associated with a predominant mixing of SubTropical Under- and Surface Waters (STUW and STSW: 20 and 40%, respectively) within ESSW ( 25%), complemented evenly by overlying (ESW, TSW: 8%) and underlying waters (AAIW, SPDW: 7%). The hypotheses and mechanisms leading to the Pmin formation in the OMZ are further explored and discussed, considering the physical regional contribution associated with various circulation pathways ventilating the OMZ and the local biogeochemical contribution including the potential diazotrophic activity.

  5. Nuclear waste incineration technology status

    International Nuclear Information System (INIS)

    Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

    1981-01-01

    The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance

  6. Nuclear waste incineration technology status

    Energy Technology Data Exchange (ETDEWEB)

    Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

    1981-07-15

    The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

  7. Economic and ecologic considerations for bidding procedures and contracting for bio-waste fermentation plants; Oekonomische und oekologische Gesichtspunkte bei Ausschreibung und Vergabe von Bioabfallvergaerungsanlagen

    Energy Technology Data Exchange (ETDEWEB)

    Raussen, Thomas; Lootsma, Auke [Witzenhausen-Institut fuer Abfall, Umwelt und Energie GmbH, Witzenhausen (Germany); Oldhafer, Nils [umwelttechnik und ingenieure GmbH, Hannvoer (Germany)

    2013-07-01

    The use of the energetic and mass potentials of biological wastes in an integrated fermentation and composting plant needs extensive conceptual and planning activities. The call for tenders for the construction of plants is an EU-wide open procedure. Public waste management organizations are interested to receive profitable solutions with reliable operation and minimized ecological impacts. The minimum requirements and technical aspects are defined by the public waste management organizations.

  8. The acid digestion process for radioactive waste: The radioactive waste management series. Volume II

    International Nuclear Information System (INIS)

    Cecille, L.; Simon, R.

    1983-01-01

    This volume focuses on the acid digestion process for the treatment of alpha combustible solid waste by presenting detailed performance figures for the principal sub-assemblies of the Alona pilot plant, Belgium. Experience gained from the operation of the US RADTU plant, the only other acid digestion pilot plant, is also summarized, and the performances of these two plants compared. In addition, the research and development programmes carried out or supported by the Commission of the European Communities are reviewed, and details of an alternative to acid digestion for waste contamination described. Topics considered include review of the treatment of actinides-bearing radioactive wastes; alpha waste arisings in fuel fabrication; Alona Demonstration Facility for the acid digestion process at Eurochemic Mol (Belgium); the treatment of alpha waste at Eurochemic by acid digestion-feed pretreatment and plutonium recovery; US experience with acid digestion of combustible transuranic waste; and The European Communities R and D actions on alpha waste

  9. Microbiological effects of olive mill waste addition to substrates for Pleurotus pulmonarius cultivation

    NARCIS (Netherlands)

    Soler-Rivas, C.; Garcia-Rosado, A.; Polonia, I.; Junca-Blanch, G.; Marin, F.R.; Wichers, H.J.

    2006-01-01

    When olive mill wastes (OMWs) and vegetation waters (VWs) obtained during the manufacture of olive oil were added as substrate supplements for the cultivation of Pleurotus pulmonarius the material modified growth of the mushroom and the endemic microbiota of the substrate, in particular the

  10. Waste Isolation Pilot Plant remote-handled transuranic waste disposal strategy

    International Nuclear Information System (INIS)

    1995-01-01

    The remote-handled transuranic (RH-TRU) waste disposal strategy described in this report identifies the process for ensuring that cost-effective initial disposal of RH-TRU waste will begin in Fiscal Year 2002. The strategy also provides a long-term approach for ensuring the efficient and sustained disposal of RH-TRU waste during the operating life of WIPP. Because Oak Ridge National Laboratory stores about 85 percent of the current inventory, the strategy is to assess the effectiveness of modifying their facilities to package waste, rather than constructing new facilities. In addition, the strategy involves identification of ways to prepare waste at other sites to supplement waste from Oak Ridge National Laboratory. DOE will also evaluate alternative packagings, modes of transportation, and waste emplacement configurations, and will select preferred alternatives to ensure initial disposal as scheduled. The long-term strategy provides a systemwide planning approach that will allow sustained disposal of RH-TRU waste during the operating life of WIPP. The DOE's approach is to consider the three relevant systems -- the waste management system at the generator/storage sites, the transportation system, and the WIPP disposal system -- and to evaluate the system components individually and in aggregate against criteria for improving system performance. To ensure full implementation, in Fiscal Years 1996 and 1997 DOE will: (1) decide whether existing facilities at Oak Ridge National Laboratory or new facilities to package and certify waste are necessary; (2) select the optimal packaging and mode of transportation for initial disposal; and (3) select an optimal disposal configuration to ensure that the allowable limits of RH-TRU waste can be disposed. These decisions will be used to identify funding requirements for the three relevant systems and schedules for implementation to ensure that the goal of initial disposal is met

  11. Process for remediation of plastic waste

    Science.gov (United States)

    Pol, Vilas G [Westmont, IL; Thiyagarajan, Pappannan [Germantown, MD

    2012-04-10

    A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically egg-shaped and spherical-shaped solid carbons. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

  12. Application of EPA regulations to low-level radioactive waste

    International Nuclear Information System (INIS)

    Bowerman, B.S.; Piciulo, P.L.

    1985-01-01

    The survey reported here was conducted with the intent of identifying categories of low-level radioactive wastes which would be classified under EPA regulations 40 CFR Part 261 as hazardous due to the chemical properties of the waste. Three waste types are identified under these criteria as potential radioactive mixed wastes: wastes containing organic liquids; wastes containing lead metal; and wastes containing chromium. The survey also indicated that certain wastes, specific to particular generators, may also be radioactive mixed wastes. Ultimately, the responsibility for determining whether a facility's wastes are mixed wastes rest with the generator. However, the uncertainties as to which regulations are applicable, and the fact that no legal definition of mixed wastes exists, make such a determination difficult. In addition to identifying mixed wastes, appropriate methods for the management of mixed wastes must be defined. In an ongoing study, BNL is evaluating options for the management of mixed wastes. These options will include segregation, substitution, and treatments to reduce or eliminate chemical hazards associated with the wastes listed above. The impacts of the EPA regulations governing hazardous wastes on radioactive mixed waste cannot be assessed in detail until the applicability of these regulations is agreed upon. This issue is still being discussed by EPA and NRC and should be resolved in the near future. Areas of waste management which may affect generators of mixed wastes include: monitoring/tracking of wastes before shipment; chemical testing of wastes; permits for treatment of storage of wastes; and additional packaging requirements. 3 refs., 1 fig., 2 tabs

  13. A comparison of minimum dietary diversity in Bangladesh in 2011 and 2014.

    Science.gov (United States)

    Blackstone, Sarah; Sanghvi, Tina

    2018-04-16

    Improving infant and young child feeding practices is critical for improving growth and reducing child mortality and morbidity. This paper aims to compare predictors of minimum dietary diversity, an important indicator of adequate complementary feeding practices, in Bangladesh in 2011 and 2014. The 2011 and 2014 Bangladesh Demographic and Health Survey were used to examine predictors of minimum dietary diversity among 6-23 months. An additional analysis was conducted for the 18-23-month group, because a significant increase in meeting minimum dietary diversity recommendations was seen in this age group only. Factors found to be associated with practices were compared across time points. In 2011, minimum dietary diversity was 23.8% and increased to 28.8% in 2014. Among children 18-23 months, in 2011, minimum dietary diversity was 32.5% and increased to 42.8% in 2014. Among all children, wealth, education, exposure to media, and antenatal care were significant predictors of dietary diversity. In the 18-23-month age group, significant predictors in 2011 were wealth and decision making. In 2014, significant predictors were education and exposure to media. Demographic trends indicated a significant increase in education and exposure to media between 2011 and 2014. As these were significant for minimum dietary diversity in 2014 overall and for 18-23 months, they might be important targets of future interventions, specifically utilizing media channels and tailoring special strategies for women with low education and limited exposure to media. © 2018 John Wiley & Sons Ltd.

  14. Defense transuranic waste program strategy document

    International Nuclear Information System (INIS)

    1982-07-01

    This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment

  15. The characterization of cement waste form for final disposal of decommissioning concrete wastes

    International Nuclear Information System (INIS)

    Lee, Yoon-ji; Lee, Ki-Won; Min, Byung-Youn; Hwang, Doo-Seong; Moon, Jei-Kwon

    2015-01-01

    Highlights: • Decommissioning concrete waste recycling and disposal. • Compressive strength of cement waste form. • Characteristic of thermal resistance and leaching of cement waste form. - Abstract: In Korea, the decontamination and decommissioning of KRR-1, 2 at KAERI have been under way. The decommissioning of the KRR-2 was finished completely by 2011, whereas the decommissioning of KRR-1 is currently underway. A large quantity of slightly contaminated concrete waste has been generated from the decommissioning projects. The concrete wastes, 83ea of 200 L drums, and 41ea of 4 m 3 containers, were generated in the decommissioning projects. The conditioning of concrete waste is needed for final disposal. Concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled with a void space after concrete rubble pre-placement into 200 L drums. Thus, this research developed an optimizing mixing ratio of concrete waste, water, and cement, and evaluated the characteristics of a cement waste form to meet the requirements specified in the disposal site specific waste acceptance criteria. The results obtained from a compressive strength test, leaching test, and thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested as an optimized mixing ratio of 75:15:10. In addition, the compressive strength of the cement waste form was satisfied, including a fine powder up to a maximum of 40 wt% in concrete debris waste of about 75%. According to the scale-up test, the mixing ratio of concrete waste, water, and cement is 75:10:15, which meets the satisfied compressive strength because of an increase in the particle size in the waste

  16. Heat Melt Compaction as an Effective Treatment for Eliminating Microorganisms from Solid Waste

    Science.gov (United States)

    Hummerick, Mary P.; Strayer, Richard F.; McCoy, Lashelle E.; Richards, Jeffrey T.; Ruby, Anna Maria; Wheeler, Ray; Fisher, John

    2013-01-01

    One of the technologies being tested at Ames Research Center as part of the logistics and repurposing project is heat melt compaction (HMC) of solid waste to reduce volume, remove water and render a biologically stable and safe product. Studies at Kennedy Space Center have focused on the efficacy of the heat melt compaction process for killing microorganisms in waste and specific compacter operation protocols, i.e., time and temperature required to achieve a sterile, stable product. The work. reported here includes a controlled study to examine the survival and potential re-growth of specific microorganisms over a 6-month period of storage after heating and compaction. Before heating and compaction, ersatz solid wastes were inoculated with Bacillus amyloliquefaciens and Rhodotorula mucilaginosa, previously isolated from recovered space shuttle mission food and packaging waste. Compacted HMC tiles were sampled for microbiological analysis at time points between 0 and 180 days of storage in a controlled environment chamber. In addition, biological indicator strips containing spores of Bacillus atrophaeus and Geobacillus stearothermophilus were imbedded in trash to assess the efficacy of the HMC process to achieve sterilization. Analysis of several tiles compacted at 180deg C for times of 40 minutes to over 2 hours detected organisms in all tile samples with the exception of one exposed to 180deg C for approximately 2 hours. Neither of the inoculated organisms was recovered, and the biological indicator strips were negative for growth in all tiles indicating at least local sterilization of tile areas. The findings suggest that minimum time/temperature combination is required for complete sterilization. Microbial analysis of tiles processed at lower temperatures from 130deg C-150deg C at varying times will be discussed, as well as analysis of the bacteria and fungi present on the compactor hardware as a result of exposure to the waste and the surrounding environment

  17. Big Area Additive Manufacturing of High Performance Bonded NdFeB Magnets.

    Science.gov (United States)

    Li, Ling; Tirado, Angelica; Nlebedim, I C; Rios, Orlando; Post, Brian; Kunc, Vlastimil; Lowden, R R; Lara-Curzio, Edgar; Fredette, Robert; Ormerod, John; Lograsso, Thomas A; Paranthaman, M Parans

    2016-10-31

    Additive manufacturing allows for the production of complex parts with minimum material waste, offering an effective technique for fabricating permanent magnets which frequently involve critical rare earth elements. In this report, we demonstrate a novel method - Big Area Additive Manufacturing (BAAM) - to fabricate isotropic near-net-shape NdFeB bonded magnets with magnetic and mechanical properties comparable or better than those of traditional injection molded magnets. The starting polymer magnet composite pellets consist of 65 vol% isotropic NdFeB powder and 35 vol% polyamide (Nylon-12). The density of the final BAAM magnet product reached 4.8 g/cm 3 , and the room temperature magnetic properties are: intrinsic coercivity H ci  = 688.4 kA/m, remanence B r  = 0.51 T, and energy product (BH) max  = 43.49 kJ/m 3 (5.47 MGOe). In addition, tensile tests performed on four dog-bone shaped specimens yielded an average ultimate tensile strength of 6.60 MPa and an average failure strain of 4.18%. Scanning electron microscopy images of the fracture surfaces indicate that the failure is primarily related to the debonding of the magnetic particles from the polymer binder. The present method significantly simplifies manufacturing of near-net-shape bonded magnets, enables efficient use of rare earth elements thus contributing towards enriching the supply of critical materials.

  18. Global recycling - waste trafficking in disguise?

    DEFF Research Database (Denmark)

    Kamuk, Bettina; Hansen, Jens Aage

    2007-01-01

    Recycling is used as cover for illegal exporting of hazardous wastes (waste trafficking). This happens in spite of international conventions and codes of good conduct. Additional rules and recommendations are suggested to initiatiate local and national action and compliance with international...

  19. Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)

    Energy Technology Data Exchange (ETDEWEB)

    1980-10-01

    Since 1970, solid waste with TRU or U-233 contamination in excess of 10 ..mu..Ci per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact.

  20. Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)

    International Nuclear Information System (INIS)

    1980-10-01

    Since 1970, solid waste with TRU or U-233 contamination in excess of 10 μCi per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact

  1. Electrochemical/Pyrometallurgical Waste Stream Processing and Waste Form Fabrication

    Energy Technology Data Exchange (ETDEWEB)

    Steven Frank; Hwan Seo Park; Yung Zun Cho; William Ebert; Brian Riley

    2015-07-01

    This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.

  2. Electrochemical probing of high-level radioactive waste tanks containing washed sludge and precipitates

    International Nuclear Information System (INIS)

    Bickford, D.F.; Congdon, J.W.; Oblath, S.B.

    1987-01-01

    At the U.S. Department of Energy's Savannah River Plant, corrosion of carbon steel storage tanks containing alkaline, high-level radioactive waste is controlled by specification of limits on waste composition and temperature. Processes for the preparation of waste for final disposal will result in waste with low corrosion inhibitor concentrations and, in some cases, high aromatic organic concentrations, neither of which are characteristic of previous operations. Laboratory tests, conducted to determine minimum corrosion inhibitor levels indicated pitting of carbon steel near the waterline for proposed storage conditions. In situ electrochemical measurements of full-scale radioactive process demonstrations have been conducted to assess the validity of laboratory tests. Probes included pH, Eh (potential relative to a standard hydrogen electrode), tank potential, and alloy coupons. In situ results are compared to those of the laboratory tests, with particular regard given to simulated solution composition

  3. Waste statistics 2004

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-07

    The 2004 reporting to the ISAG comprises 394 plants owned by 256 enterprises. In 2003, reports covered 403 plants owned by 273 enterprises. Waste generation in 2004 is compared to targets for 2008 in the government's Waste Strategy 2005-2008. The following summarises waste generation in 2004: 1) In 2004, total reported waste arisings amounted to 13,359,000 tonnes, which is 745,000 tonnes, or 6 per cent, more than in 2003. 2) If amounts of residues from coal-fired power plants are excluded from statistics, waste arisings in 2004 were 12,179,000 tonnes, which is a 9 per cent increase from 2003. 3) If amounts of residues from coal-fired power plants and waste from the building and construction sector are excluded from statistics, total waste generation in 2004 amounted to 7,684,000 tonnes, which is 328,000 tonnes, or 4 per cent, more than in 2002. In other words, there has been an increase in total waste arisings, if residues and waste from building and construction are excluded. Waste from the building and construction sector is more sensitive to economic change than most other waste. 4) The total rate of recycling was 65 per cent. The 2008 target for recycling is 65 per cent. The rate of recycling in 2003 was also 65 per cent. 5) The total amount of waste led to incineration amounted to 26 per cent, plus an additional 1 per cent left in temporary storage to be incinerated at a later time. The 2008 target for incineration is 26 per cent. These are the same percentage figures as applied to incineration and storage in 2003. 6) The total amount of waste led to landfills amounted to 8 per cent, which is one percentage point better than the overall landfill target of a maximum of 9 per cent landfilling in 2008. Also in 2003, 8 per cent of the waste was landfilled. 7) The targets for treatment of waste from individual sectors are still not being met: too little waste from households and the service sector is being recycled, and too much waste from industry is being

  4. Seasonal characterization of municipal solid waste (MSW) in the city of Chihuahua, Mexico

    International Nuclear Information System (INIS)

    Gomez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

    2009-01-01

    Management of municipal solid waste (MSW) has become a significant environmental problem, especially in fast-growing cities. The amount of waste generated increases each year and this makes it difficult to create solutions which due to the increase in waste generation year after year and having to identify a solution that will have minimum impact on the environment. To determine the most sustainable waste management strategy for Chihuahua, it is first necessary to identify the nature and composition of the city's urban waste. The MSW composition varied considerably depending on many factors, the time of year is one of them. Therefore, as part of our attempt to implement an integral waste management system in the city of Chihuahua, we conducted a study of the characteristics of MSW composition for the different seasons. This paper analyzes and compares the findings of the study of the characterization and the generation of solid waste from households at three different socio-economic levels in the city over three periods (April and August, 2006 and January, 2007). The average weight of waste generated in Chihuahua, taking into account all three seasons, was 0.592 kg capita -1 day -1 . Our results show that the lowest income groups generated the least amount of waste. We also found that less waste was generated during the winter season. The breakdown for the composition of the waste shows that organic waste accounts for the largest proportion (45%), followed by paper (17%) and others (16%).

  5. Seasonal characterization of municipal solid waste (MSW) in the city of Chihuahua, Mexico.

    Science.gov (United States)

    Gómez, Guadalupe; Meneses, Montserrat; Ballinas, Lourdes; Castells, Francesc

    2009-07-01

    Management of municipal solid waste (MSW) has become a significant environmental problem, especially in fast-growing cities. The amount of waste generated increases each year and this makes it difficult to create solutions which due to the increase in waste generation year after year and having to identify a solution that will have minimum impact on the environment. To determine the most sustainable waste management strategy for Chihuahua, it is first necessary to identify the nature and composition of the city's urban waste. The MSW composition varied considerably depending on many factors, the time of year is one of them. Therefore, as part of our attempt to implement an integral waste management system in the city of Chihuahua, we conducted a study of the characteristics of MSW composition for the different seasons. This paper analyzes and compares the findings of the study of the characterization and the generation of solid waste from households at three different socio-economic levels in the city over three periods (April and August, 2006 and January, 2007). The average weight of waste generated in Chihuahua, taking into account all three seasons, was 0.592 kg capita(-1) day(-1). Our results show that the lowest income groups generated the least amount of waste. We also found that less waste was generated during the winter season. The breakdown for the composition of the waste shows that organic waste accounts for the largest proportion (45%), followed by paper (17%) and others (16%).

  6. Hazardous-waste analysis plan for LLNL operations

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, R.S.

    1982-02-12

    The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste.

  7. Hazardous-waste analysis plan for LLNL operations

    International Nuclear Information System (INIS)

    Roberts, R.S.

    1982-01-01

    The Lawrence Livermore National Laboratory is involved in many facets of research ranging from nuclear weapons research to advanced Biomedical studies. Approximately 80% of all programs at LLNL generate hazardous waste in one form or another. Aside from producing waste from industrial type operations (oils, solvents, bottom sludges, etc.) many unique and toxic wastes are generated such as phosgene, dioxin (TCDD), radioactive wastes and high explosives. One key to any successful waste management program must address the following: proper identification of the waste, safe handling procedures and proper storage containers and areas. This section of the Waste Management Plan will address methodologies used for the Analysis of Hazardous Waste. In addition to the wastes defined in 40 CFR 261, LLNL and Site 300 also generate radioactive waste not specifically covered by RCRA. However, for completeness, the Waste Analysis Plan will address all hazardous waste

  8. Evaluation of a radioactive concrete waste form recovered from an ocean dumpsite

    International Nuclear Information System (INIS)

    Colombo, P.; Neilson, R.M. Jr.

    1982-01-01

    Little dissolution of the concrete waste form in the ocean environment occurred as evidenced by a maximum waste package weight loss of approximately 5%. Water loss through evaporation during curing and dissolution of calcium hydroxide in disposal or inaccuracy of the initial weighing are believed to be responsible for the apparent weight loss. A conservative estimate that assumes a constant 0.33%/yr weight loss due solely to cement-phase dissolution predicts that it would require a minimum of 300 years in this environment before the concrete waste form would lose its integrity. The measured compression strength of the concrete waste form is in the range expected for concrete formulations. This indicates the absence of appreciable attack which is also supported by the observation that negligible deterioration of the waste form surface has occurred. The concrete waste form contained Cs-137, Cs-134, and Co-60. Based on the assumed initial Cs-137 distribution in the waste form, a bulk leach rate for this radionuclide of 2.4x10 -3 g/(cm 2 -day) was calculated. This corresponds to an average fractional activity loss rate of 3.7x10 -2 per year (neglecting decay). 7 figures, 1 table

  9. Konrad transport study: Safety analysis of the transportation of radioactive waste to the Konrad waste disposal site

    International Nuclear Information System (INIS)

    Lange, F.; Gruendler, D.; Schwarz, G.

    1992-05-01

    For the purpose of the study the anticipated waste transport volume and the waste properties were analysed in detail. This included information on the transport containers, waste product properties, activity inventories and local dose rates of the waste packages being transported. The envisaged practical implementation, i.e. the transport arrangements including shunting operations at the Braunschweig marshalling yard and the Beddingen interchange station, were also included. The two shipping scenarios 100% transportation by rail and 80% transportation by rail, 20% by road, which could be considered to bound the real conditions, were analysed. The relevant transport regulations contain the requirements to be met by the transport of shipping units carrying radioactive waste. In addition, the ''Konrad preliminary waste acceptance criteria'' contain activity limits for waste packages being disposed of in conjunction with further requirements relating to the properties of waste products and waste containers. (orig./DG)

  10. A brief analysis and description of transuranic wastes in the subsurface disposal area of the radioactive waste management complex at INEL

    International Nuclear Information System (INIS)

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

    1991-02-01

    This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area during the period 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and special-case wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and makes recommendations for future efforts at waste characterization. 20 refs., 3 figs., 17 tabs

  11. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Seki, Shuji.

    1992-01-01

    Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

  12. A comparative assessment of alternative waste management procedures for selected reprocessing wastes

    International Nuclear Information System (INIS)

    Hickford, G.E.; Plews, M.J.

    1983-07-01

    This report, which has been prepared by Associated Nuclear Services for the Department of the Environment, presents the results of a study and comparative assessment of management procedures for low and intermediate level solid waste streams arising from current and future fuel reprocessing operations on the Sellafield site. The characteristics and origins of the wastes under study are discussed and a reference waste inventory is presented, based on published information. Waste management strategy in the UK and its implications for waste conditioning, packaging and disposal are discussed. Wastes currently arising which are not suitable for Drigg burial or sea dumping are stored in an untreated form. Work is in hand to provide additional and improved disposal facilities which will accommodate all the waste streams under study. For each waste stream viable procedures are identified for further assessment. The procedures comprise a series of on-site operations-recovery from storage, pre-treatment, treatment, encapsulation, and packaging, prior to storage or disposal of the conditioned waste form. Assessments and comparisons of each procedure for each waste are presented. These address various process, operational, economic, radiological and general safety factors. The results are presented in a series of tables with supporting text. For the majority of wastes direct encapsulation with minimal treatment appears to be a viable procedure. Occupational exposure and general safety are not identified as significant factors governing the choice of procedures. The conditioned wastes meet the general requirements for safe handling during storage and transportation. The less active wastes suitable for disposal by currently available routes meet the appropriate disposal criteria. It is not possible to consider in detail the suitability for disposal of the more active wastes for which disposal facilities are not yet available. (Author)

  13. Thermo-economic optimization of Regenerative Organic Rankine Cycle for waste heat recovery applications

    International Nuclear Information System (INIS)

    Imran, Muhammad; Park, Byung Sik; Kim, Hyouck Ju; Lee, Dong Hyun; Usman, Muhammad; Heo, Manki

    2014-01-01

    Highlights: • Thermo-economic optimization of regenerative ORC is performed. • Optimization is performed using multi objective genetic algorithm. • Objective function is maximum cycle efficiency and minimum specific investment. • Evaporation pressure, pinch point and superheat are decision variables. • Sensitivity analysis is performed to investigate effect of decision variables. - Abstract: Organic Rankine Cycle (ORC) is low grade and waste heat conversion technology. The current article deal with the thermo-economic optimization of basic ORC and regenerative ORC for waste heat recovery applications under constant heat source condition. Thermal efficiency and specific investment cost of basic ORC, single stage regenerative and double stage regenerative ORC has been optimized by using Non-dominated Sorting Genetic Algorithm-II (NSGA-II). Maximum thermal efficiency and minimum specific investment cost were selected as objective functions and relative increase in thermal efficiency and cost has been analyzed taking the basic ORC as base case. The constraint set consist of evaporation pressure, superheat, pinch point temperature difference in evaporator and condenser. The optimization was performed for five different working fluids. The optimization result show that R245fa is best working under considered conditions and basic ORC has low specific investment cost and thermal efficiency compared to regenerative ORC. R245fa is low boiling organic fluid, which has high degree of thermal stability and compatible with common construction materials of ORC. The average increase in thermal efficiency from basic ORC to single stage regenerative ORC was 1.01% with an additional cost of 187 $/kW while from basic ORC to double stage regenerative ORC was 1.45% with an average increase in cost of 297 $/kW. The sensitivity analysis was also performed to investigate the effect of operating conditions which show that evaporation pressure has promising effect on thermal

  14. Additive to clay drilling muds

    Energy Technology Data Exchange (ETDEWEB)

    Voytenko, V.S.; Nekrasova, V.B.; Nikitinskiy, E.L.; Ponomarev, V.N.

    1984-01-01

    The purpose of the invention is to improve the lubricating and strengthening properties of clay drilling muds. This goal is achieved because the lubricating and strengthening additive used is waste from the pulp and paper industry at the stage of reprocessing crude sulfate soap into phytosterol.

  15. The additivity of radionuclide and chemical risk estimates in performance evaluation of mixed-waste sites

    International Nuclear Information System (INIS)

    Till, J.E.; Meyer, K.R.

    1990-01-01

    Methods for assessing radioactive waste sites that contain chemical constituents are in the formative stages. In evaluating these sites, a key concern will be the hazard to personnel involved in cleanup work and to the general population. This paper focuses on what we have learned from pathway analysis and risk assessment about providing a combined estimate of risk from exposure to both chemicals and radionuclides. Quantitative radiation risk assessment involves a high degree of uncertainty. Chemical risk assessment generally does not provide quantitative results. Thus, it is not currently possible to develop a useful, quantitative combined risk assessment for mixed-waste sites

  16. Packaging radioactive wastes for geologic disposal

    International Nuclear Information System (INIS)

    Benton, H.A.

    1996-01-01

    The M ampersand O contractor for the DOE Office of Civilian Radioactive Waste Management is developing designs of waste packages that will contain the spent nuclear fuel assemblies from commercial and Navy reactor plants and various civilian and government research reactor plants, as well as high-level wastes vitrified in glass. The safe and cost effective disposal of the large and growing stockpile of nuclear waste is of national concern and has generated political and technical debate. This paper addresses the technical aspects of disposing of these wastes in large and robust waste packages. The paper discusses the evolution of waste package design and describes the current concepts. In addition, the engineering and regulatory issues that have governed the development are summarized and the expected performance in meeting the requirements are discussed

  17. How it is possible to build a national system for decommissioning waste management without site nor waste liberation: the case of France

    International Nuclear Information System (INIS)

    Averous, Jeremie; Chapalain, Estelle

    2003-01-01

    Past experience in decommissioning in France has shown that a national system has to be put in place to deal with decommissioning, waste elimination and site cleaning up activities in order to allow a consistent, safe, transparent and industrially applicable management of these matters. A system founded on successive lines of defence has been put into enforcement, which does not involve any site nor waste liberation, as it is considered that the criteria associated are always prone to discussion and contradiction. This system is based on the following concepts: - 'nuclear waste', waste prone to have been contaminated or activated, is segregated from 'conventional waste' using a system involving successive lines of defence, and hence, building a very high level of confidence that no 'nuclear waste' will be eliminated without control in conventional waste eliminators or recycling facilities; - 'nuclear waste' is eliminated in dedicated facilities or repositories, or in conventional facilities under the condition of a special authorization based on a radiological impact study and a public inquiry; - a global safety evaluation of the nuclear site is conducted after decommissioning in order to define possible use restrictions. In all cases, minimum restrictions will be put into enforcement in urbanization plans to ensure sufficient precaution when planning future uses of the ground or the building. This paper describes this global system in detail and shows that its inherent consistency allows it to be easily applicable by operators while achieving a high level of safety and confidence. It is now widely accepted by stakeholders. The French Nuclear Safety Authority is now working to apply this methodology more widely to other nuclear practices like the waste management from medical, research and industrial activities, or from past or remediation activities. (authors)

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

    International Nuclear Information System (INIS)

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

    1991-08-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-08-01

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

  20. 40 CFR 60.2065 - What should I include in my waste management plan?

    Science.gov (United States)

    2010-07-01

    ... Management Plan § 60.2065 What should I include in my waste management plan? A waste management plan must... additional waste management measures and implement those measures the source considers practical and feasible, considering the effectiveness of waste management measures already in place, the costs of additional measures...