Sample records for decontaminated salt solution

  1. Results of Analysis of Macrobatch 3 Decontaminated Salt Solution Coalescer from May 2010

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-18T23:59:59.000Z

    SRNL analyzed the Decontamination Salt Solution (DSS) coalescer from MCU by several analytical methods. This unit was removed from service in May 2010. The results of these analyses indicate that there is very little evidence of fouling via excessive solids, either from the leaching studies or X-Ray Diffraction (XRD) analysis.

  2. RESULTS OF ANALYSES OF MACROBATCH 3 DECONTAMINATED SALT SOLUTION (DSS) COALESCER AND PRE-FILTERS

    SciTech Connect (OSTI)

    Peters, T.; Fondeur, F.; Fink, S.

    2012-06-13T23:59:59.000Z

    SRNL analyzed the pre-filter and Decontamination Salt Solution (DSS) coalescer from MCU by several analytical methods. The results of these analyses indicate that overall there is light to moderate solids fouling of both the coalescer and pre-filter elements. The majority of the solids contain aluminum, sodium, silicon, and titanium, in oxide and/or hydroxide forms that we have noted before. The titanium is presumably precipitated from leached, dissolved monosodium titanate (MST) or fines from MST at ARP, and the quantity we find is significantly greater than in the past. A parallel report discusses potential causes for the increased leaching rate of MST, showing that increases in free hydroxide concentration of the feed solutions and of chemical cleaning solutions lead to faster leaching of titanium.

  3. Results Of Routine Strip Effluent Hold Tank And Decontaminated Salt Solution Hold Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 5 Operations

    SciTech Connect (OSTI)

    Peters, T. B.; Fondeur, F. F.

    2013-04-30T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the ''microbatches'' of Integrated Salt Disposition Project (ISDP) Salt Batch (''Macrobatch'') 5 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results indicate good decontamination performance within process design expectations. While the data set is sparse, the results of this set and the previous set of results for Macrobatch 4 samples indicate generally consistent operations. The DSSHT samples show continued presence of titanium, likely from leaching of the monosodium titanate in the Actinide Removal process (ARP).

  4. Waste Isolation Pilot Plant Salt Decontamination Testing

    SciTech Connect (OSTI)

    Rick Demmer; Stephen Reese

    2014-09-01T23:59:59.000Z

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  5. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, And Caustic Wash Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 4 Operations

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-10-25T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), and Caustic Wash Tank (CWT) samples from several of the ?microbatches? of Integrated Salt Disposition Project (ISDP) Salt Batch (?Macrobatch?) 4 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by inductively-coupled plasma emission spectroscopy (ICPES). Furthermore, samples from the CWT have been analyzed by a variety of methods to investigate a decline in the decontamination factor (DF) of the cesium observed at MCU. The results indicate good decontamination performance within process design expectations. While the data set is sparse, the results of this set and the previous set of results for Macrobatch 3 samples indicate generally consistent operations. There is no indication of a disruption in plutonium and strontium removal. The average cesium DF and concentration factor (CF) for samples obtained from Macrobatch 4 are slightly lower than for Macrobatch 3, but still well within operating parameters. The DSSHT samples show continued presence of titanium, likely from leaching of the monosodium titanate in Actinide Removal Process (ARP).

  6. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    SciTech Connect (OSTI)

    Peters, T. B.

    2014-01-02T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from the Interim Salt Disposition Project (ISDP) Salt Batch (“Macrobatch”) 6 have been analyzed for 238Pu, 90Sr, 137Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The Pu, Sr, and Cs results from the current Macrobatch 6 samples are similar to those from comparable samples in previous Macrobatch 5. In addition the SEHT and DSSHT heel samples (i.e. ‘preliminary’) have been analyzed and reported to meet NGS Demonstration Plan requirements. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous samples. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST has increased in ARP at the higher free hydroxide concentrations in the current feed.

  7. Results Of Routine Strip Effluent Hold Tank, Decontaminated Salt Solution Hold Tank, Caustic Wash Tank And Caustic Storage Tank Samples From Modular Caustic-Side Solvent Extraction Unit During Macrobatch 6 Operations

    SciTech Connect (OSTI)

    Peters, T. B.

    2013-10-01T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Caustic Storage Tank (CST) samples from several of the ''microbatches'' of Integrated Salt Disposition Project (ISDP) Salt Batch (''Macrobatch'') 6 have been analyzed for {sup 238}Pu, {sup 90}Sr, {sup 137}Cs, and by Inductively Coupled Plasma Emission Spectroscopy (ICPES). The results from the current microbatch samples are similar to those from comparable samples in Macrobatch 5. From a bulk chemical point of view, the ICPES results do not vary considerably between this and the previous macrobatch. The titanium results in the DSSHT samples continue to indicate the presence of Ti, when the feed material does not have detectable levels. This most likely indicates that leaching of Ti from MST in ARP continues to occur. Both the CST and CWT samples indicate that the target Free OH value of 0.03 has been surpassed. While at this time there is no indication that this has caused an operational problem, the CST should be adjusted into specification. The {sup 137}Cs results from the SRNL as well as F/H lab data indicate a potential decline in cesium decontamination factor. Further samples will be carefully monitored to investigate this.

  8. Electrochromic salts, solutions, and devices

    DOE Patents [OSTI]

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky,7,064,212 T. Mark (Los Alamos, NM)

    2006-06-20T23:59:59.000Z

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  9. Electrochromic Salts, Solutions, and Devices

    DOE Patents [OSTI]

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky, T. Mark (Los Alamos, NM)

    2008-10-14T23:59:59.000Z

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  10. Electrochromic Salts, Solutions, and Devices

    SciTech Connect (OSTI)

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky, T. Mark (Los Alamos, NM)

    2008-11-11T23:59:59.000Z

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  11. Method for preparing salt solutions having desired properties

    DOE Patents [OSTI]

    Ally, Moonis R. (Oak Ridge, TN); Braunstein, Jerry (Clinton, TN)

    1994-01-01T23:59:59.000Z

    The specification discloses a method for preparing salt solutions which exhibit desired thermodynamic properties. The method enables prediction of the value of the thermodynamic properties for single and multiple salt solutions over a wide range of conditions from activity data and constants which are independent of concentration and temperature. A particular application of the invention is in the control of salt solutions in a process to provide a salt solution which exhibits the desired properties.

  12. A laser-based solution to industrial decontamination problems

    SciTech Connect (OSTI)

    Edelson, M.C.; Pang, Ho-ming [Ames Lab., IA (United States); Ferguson, R.L. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

    1995-12-31T23:59:59.000Z

    The ability of lasers to deposit significant amounts of energy on surfaces located at large distances from the laser can be exploited to solve very difficult industrial problems. The Ames Laboratory has been working in partnership with Lockheed Martin Idaho Technologies (LMIT) to apply laser technologies to the decontamination of radioactively contaminated surfaces located in hostile environments. Many such applications exist within former USDOE and nuclear industry facilities. As opposed to laser coating removal systems, which are designed to ``strip`` relatively soft coatings from a substrate without damage to the substrate, the system being developed by Ames - LMIT is designed to remove contaminants that are embedded within the metal surface itself. The system generates irradiance levels sufficient to remove microns of metal from a surface and an off-gas system that prevents the redeposition of materials removed from the surface. Process control is assisted by monitoring the laser-generated plasma produced during laser surface ablation. Results achieved using this apparatus for various metal types will be presented along with a discussion of other potential industrial applications.

  13. ISOPAR L RELEASE RATES FROM SALTSTONE USING SIMULATED SALT SOLUTIONS

    SciTech Connect (OSTI)

    Zamecnik, J; Michael Bronikowski, M; Alex Cozzi, A; Russell Eibling, R; Charles Nash, C

    2008-07-31T23:59:59.000Z

    The Modular Caustic-Side Solvent Extraction (CSSX) Unit (MCU) and the Salt Waste Processing Facility (SWPF) will produce a Decontaminated Salt Solution (DSS) that will go to the Saltstone Production Facility (SPF). Recent information indicates that solvent entrainment in the DSS is larger than expected. The main concern is with Isopar{reg_sign} L, the diluent in the solvent mixture, and its flammability in the saltstone vault. If it is assumed that all the Isopar{reg_sign} L is released instantaneously into the vault from the curing grout before each subsequent pour, the Isopar{reg_sign} L in the vault headspace is well mixed, and each pour displaces an equivalent volume of headspace, the maximum concentration of Isopar{reg_sign} L in the DSS to assure 25% of the lower flammable limit is not exceeded has been determined to be about 4 ppm. The amount allowed would be higher if the release from grout were significantly less. The Savannah River National Laboratory was tasked with determining the release of Isopar{reg_sign} L from saltstone prepared with a simulated DSS with Isopar{reg_sign} L concentrations ranging from 50 to 200 mg/L in the salt fraction and with test temperatures ranging from ambient to 95 C. The results from the curing of the saltstone showed that the amount of Isopar{reg_sign} L released versus time can be treated as a percentage of initial amount present; there was no statistically significant dependence of the release rate on the initial concentration. The majority of the Isopar{reg_sign} L that was released over the test duration was released in the first few days. The release of Isopar{reg_sign} L begins immediately and the rate of release decreases over time. At higher temperatures the immediate release rate is larger than at lower temperatures. Initial curing temperature was found to be very important as slight variations during the first few hours or days had a significant effect on the amount of Isopar{reg_sign} L released. Short scoping tests at 95 C with solvent containing all components (Isopar{reg_sign} L, suppressor trioctylamine (TOA), and modifier Cs-7SB) except the BOBCalixC6 extractant released less Isopar{reg_sign} L than the tests run with Isopar{reg_sign} L/TOA. Based on these scoping tests, the Isopar{reg_sign} L releases reported herein are conservative. Isopar{reg_sign} L release was studied for a two-month period and average cumulative release rates were determined from three sets of tests each at 95 and 75 C and at ambient conditions. The overall average releases at were estimated for each temperature. For the 95 and 75 C data, at a 5% significance level, the hypothesis that the three test sets at each temperature had the same average percent release can be rejected, suggesting that there was a statistically significant difference among the three averages seen in the three experimental tests conducted. An upper confidence limit on the mean percent release required incorporation of variation from two sources: test-to-test variation as well as the variation within a test. An analysis of variance that relies on a random effects model was used to estimate the two variance components. The test-to-test variance and the within test (or residual) variance were both calculated. There is no indication of a statistically significant linear correlation between the percent Isopar{reg_sign} L release and the Isopar{reg_sign} L initial concentration. From the analysis of variance, upper confidence limits at confidences of 80-95% were calculated for the data at 95 and 75 C. The mean Isopar{reg_sign} L percent releases were 67.33% and 13.17% at 95 and 75 C, respectively.

  14. Molecular dynamics study of salt–solution interface: Solubility and surface charge of salt in water

    SciTech Connect (OSTI)

    Kobayashi, Kazuya; Liang, Yunfeng, E-mail: y-liang@earth.kumst.kyoto-u.ac.jp, E-mail: matsuoka@earth.kumst.kyoto-u.ac.jp; Matsuoka, Toshifumi, E-mail: y-liang@earth.kumst.kyoto-u.ac.jp, E-mail: matsuoka@earth.kumst.kyoto-u.ac.jp [Environment and Resource System Engineering, Kyoto University, Kyoto 615-8540 (Japan)] [Environment and Resource System Engineering, Kyoto University, Kyoto 615-8540 (Japan); Sakka, Tetsuo [Department of Energy and Hydrocarbon Chemistry, Kyoto University, Kyoto 615-8510 (Japan)] [Department of Energy and Hydrocarbon Chemistry, Kyoto University, Kyoto 615-8510 (Japan)

    2014-04-14T23:59:59.000Z

    The NaCl salt–solution interface often serves as an example of an uncharged surface. However, recent laser-Doppler electrophoresis has shown some evidence that the NaCl crystal is positively charged in its saturated solution. Using molecular dynamics (MD) simulations, we have investigated the NaCl salt–solution interface system, and calculated the solubility of the salt using the direct method and free energy calculations, which are kinetic and thermodynamic approaches, respectively. The direct method calculation uses a salt–solution combined system. When the system is equilibrated, the concentration in the solution area is the solubility. In the free energy calculation, we separately calculate the chemical potential of NaCl in two systems, the solid and the solution, using thermodynamic integration with MD simulations. When the chemical potential of NaCl in the solution phase is equal to the chemical potential of the solid phase, the concentration of the solution system is the solubility. The advantage of using two different methods is that the computational methods can be mutually verified. We found that a relatively good estimate of the solubility of the system can be obtained through comparison of the two methods. Furthermore, we found using microsecond time-scale MD simulations that the positively charged NaCl surface was induced by a combination of a sodium-rich surface and the orientation of the interfacial water molecules.

  15. Adding salt to an aqueous solution of t-butanol: Is hydrophobic association enhanced or reduced?

    E-Print Network [OSTI]

    Suter, Dieter

    Adding salt to an aqueous solution of t-butanol: Is hydrophobic association enhanced or reduced experiments on aqueous salt solutions of amphiphilic t-butanol by Bowron and Finney Phys. Rev. Lett. 89 in the presence of salt, as it would be expected for purely hydrophobic solutes. T. Ghosh et al., J. Phys. Chem. B

  16. Salt-stabilized globular protein structure in 7 M aqueous urea solution

    E-Print Network [OSTI]

    Wider, Gerhard

    1 Salt-stabilized globular protein structure in 7 M aqueous urea solution V. Dötsch,1 G. Wider, G Hochschule- Hönggerberg, CH-8093 Zürich, Switzerland Keywords Protein folding; Urea denaturation; Salt changing the solution conditions. In this paper we describe the influence of various salts or non

  17. Blending Of Radioactive Salt Solutions In Million Gallon Tanks

    SciTech Connect (OSTI)

    Leishear, Robert A.; Lee, Si Y.; Fowley, Mark D.; Poirier, Michael R.

    2012-12-10T23:59:59.000Z

    Research was completed at Savannah River National Laboratory (SRNL) to investigate processes related to the blending of radioactive, liquid waste, salt solutions in 4920 cubic meter, 25.9 meter diameter storage tanks. One process was the blending of large salt solution batches (up to 1135 ? 3028 cubic meters), using submerged centrifugal pumps. A second process was the disturbance of a settled layer of solids, or sludge, on the tank bottom. And a third investigated process was the settling rate of sludge solids if suspended into slurries by the blending pump. To investigate these processes, experiments, CFD models (computational fluid dynamics), and theory were applied. Experiments were performed using simulated, non-radioactive, salt solutions referred to as supernates, and a layer of settled solids referred to as sludge. Blending experiments were performed in a 2.44 meter diameter pilot scale tank, and flow rate measurements and settling tests were performed at both pilot scale and full scale. A summary of the research is presented here to demonstrate the adage that, ?One good experiment fixes a lot of good theory?. Experimental testing was required to benchmark CFD models, or the models would have been incorrectly used. In fact, CFD safety factors were established by this research to predict full-scale blending performance. CFD models were used to determine pump design requirements, predict blending times, and cut costs several million dollars by reducing the number of required blending pumps. This research contributed to DOE missions to permanently close the remaining 47 of 51 SRS waste storage tanks.

  18. Blending of Radioactive Salt Solutions in Million Gallon Tanks - 13002

    SciTech Connect (OSTI)

    Leishear, Robert A.; Lee, Si Y.; Fowley, Mark D.; Poirier, Michael R. [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)] [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)

    2013-07-01T23:59:59.000Z

    Research was completed at Savannah River National Laboratory (SRNL) to investigate processes related to the blending of radioactive, liquid waste, salt solutions in 4920 cubic meter, 25.9 meter diameter storage tanks. One process was the blending of large salt solution batches (up to 1135 - 3028 cubic meters), using submerged centrifugal pumps. A second process was the disturbance of a settled layer of solids, or sludge, on the tank bottom. And a third investigated process was the settling rate of sludge solids if suspended into slurries by the blending pump. To investigate these processes, experiments, CFD models (computational fluid dynamics), and theory were applied. Experiments were performed using simulated, non-radioactive, salt solutions referred to as supernates, and a layer of settled solids referred to as sludge. Blending experiments were performed in a 2.44 meter diameter pilot scale tank, and flow rate measurements and settling tests were performed at both pilot scale and full scale. A summary of the research is presented here to demonstrate the adage that, 'One good experiment fixes a lot of good theory'. Experimental testing was required to benchmark CFD models, or the models would have been incorrectly used. In fact, CFD safety factors were established by this research to predict full-scale blending performance. CFD models were used to determine pump design requirements, predict blending times, and cut costs several million dollars by reducing the number of required blending pumps. This research contributed to DOE missions to permanently close the remaining 47 of 51 SRS waste storage tanks. (authors)

  19. acid salt solutions: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  20. alkaline salt solution: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  1. alkaline salt solutions: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  2. Environmental decontamination

    SciTech Connect (OSTI)

    Cristy, G.A.; Jernigan, H.C. (eds.)

    1981-02-01T23:59:59.000Z

    The record of the proceedings of the workshop on environmental decontamination contains twenty-seven presentations. Emphasis is placed upon soil and surface decontamination, the decommissioning of nuclear facilities, and assessments of instrumentation and equipment used in decontamination. (DLS)

  3. Viscosity and Diffusion: Crowding and Salt Effects in Protein Solutions

    E-Print Network [OSTI]

    Marco Heinen; Fabio Zanini; Felix Roosen-Runge; Diana Fedunová; Fajun Zhang; Marcus Hennig; Tilo Seydel; Ralf Schweins; Michael Sztucki; Marián Antalík; Frank Schreiber; Gerhard Nägele

    2011-09-14T23:59:59.000Z

    We report on a joint experimental-theoretical study of collective diffusion in, and static shear viscosity of solutions of bovine serum albumin (BSA) proteins, focusing on the dependence on protein and salt concentration. Data obtained from dynamic light scattering and rheometric measurements are compared to theoretical calculations based on an analytically treatable spheroid model of BSA with isotropic screened Coulomb plus hard-sphere interactions. The only input to the dynamics calculations is the static structure factor obtained from a consistent theoretical fit to a concentration series of small-angle X-ray scattering (SAXS) data. This fit is based on an integral equation scheme that combines high accuracy with low computational cost. All experimentally probed dynamic and static properties are reproduced theoretically with an at least semi-quantitative accuracy. For lower protein concentration and low salinity, both theory and experiment show a maximum in the reduced viscosity, caused by the electrostatic repulsion of proteins. The validity range of a generalized Stokes-Einstein (GSE) relation connecting viscosity, collective diffusion coefficient, and osmotic compressibility, proposed by Kholodenko and Douglas [PRE 51, 1081 (1995)] is examined. Significant violation of the GSE relation is found, both in experimental data and in theoretical models, in semi-dilute systems at physiological salinity, and under low-salt conditions for arbitrary protein concentrations.

  4. Soil Washing Experiment for Decontamination of Contaminated NPP Soil

    SciTech Connect (OSTI)

    Son, J.K.; Kang, K.D.; Kim, K.D.; Ha, J.H.; Song, M.J. [Korea Hydro and Nuclear Power Company, P.O. Box 149, Yuseong, Daejeon, 305-600 (Korea, Republic of)

    2006-07-01T23:59:59.000Z

    The preliminary experiment was performed to obtain the operating conditions of soil washing decontamination process such as decontamination agent, decontamination temperature, decontamination time and ratio of soil and decontamination agent. To estimate decontamination efficiency, particle size of soil was classified into three categories; {>=} 2.0 mm, 2.0 {approx} 0.21 mm and {<=} 0.21 mm. Major target of this experiment was decontamination of Cs-137. The difference of decontamination efficiency using water and neutral salts as decontamination agent is not high. It is concluded that the best temperature of decontamination agent is normal temperature and the best decontamination time was about 60 minutes. And the best ratio of soil and decontamination agent is 1:10. In case of Cs decontamination for fine soils, the decontamination results using neutral salts such as Na{sub 2}CO{sub 3} and Na{sub 3}PO{sub 4} shows some limits while using strong acid such as sulfuric acid or hydrochloric acid shows high decontamination efficiency ({>=}90%). But we conclude that decontamination using strong acid is also inappropriate because of the insufficiency of decontamination efficiency for highly radioactive fine soils and the difficulty for treatment of secondary liquid waste. It is estimated that the best decontamination process is to use water as decontamination agent for particles which can be decontaminated to clearance level, after particle size separation. (authors)

  5. A Study of Novel Hexavalent Phosphazene Salts as Draw Solutes in Forward Osmosis

    SciTech Connect (OSTI)

    Mark L. Stone; Aaron D. Wilson; Mason K. Harrup; Frederick F. Stewart

    2013-03-01T23:59:59.000Z

    Two novel multi-valent salts based on phosphazene chemistry have been synthesized and characterized as forward osmosis (FO) draw solutes. Commercially obtained hexachlorocyclotriphosphazene was reacted with the sodium salt of 4-ethylhydroxybenzoate to yield hexa(4-ethylcarboxylatophenoxy)phosphazene. Hydrolysis, followed by and neutralization with NaOH or LiOH, of the resulting acidic moieties yielded water soluble sodium and lithium phosphazene salts, respectively. Degrees of dissociation were determined through osmometry over the range of 0.05-0.5 m, giving degrees of 3.08-4.95 per mole, suggesting a high osmotic potential. The Li salt was found to be more ionized in solution than the sodium salt, and this was reflected in FO experiments where the Li salt gave higher initial fluxes (~ 7 L/m2h) as compared to the sodium salt (~6 L/m2h) at identical 0.07 m draw solution concentrations at 30 °C. Longer term experiments revealed no detectable degradation of the salts; however some hydrolysis of the cellulose acetate membrane was observed, presumably due to the pH of the phosphazene salt draw solution (pH = ~8).

  6. Materials and methods for stabilizing nanoparticles in salt solutions

    DOE Patents [OSTI]

    Robinson, David Bruce; Zuckermann, Ronald; Buffleben, George M.

    2013-06-11T23:59:59.000Z

    Sequence-specific polymers are proving to be a powerful approach to assembly and manipulation of matter on the nanometer scale. Ligands that are peptoids, or sequence-specific N-functional glycine oligomers, allow precise and flexible control over the arrangement of binding groups, steric spacers, charge, and other functionality. We have synthesized short peptoids that can prevent the aggregation of gold nanoparticles in high-salt environments including divalent salt, and allow co-adsorption of a single DNA molecule. This degree of precision and versatility is likely to prove essential in bottom-up assembly of nanostructures and in biomedical applications of nanomaterials.

  7. Ion aggregation in high salt solutions: Ion network versus ion cluster

    SciTech Connect (OSTI)

    Kim, Seongheun; Kim, Heejae; Choi, Jun-Ho; Cho, Minhaeng, E-mail: mcho@korea.ac.kr [Department of Chemistry, Korea University, Seoul 136-713 (Korea, Republic of)

    2014-09-28T23:59:59.000Z

    The critical aggregation phenomena are ubiquitous in many self-assembling systems. Ions in high salt solutions could also spontaneously form larger ion aggregates, but their effects on hydrogen-bond structures in water have long been controversial. Here, carrying out molecular dynamics (MD) simulation studies of high salt solutions and comparing the MD simulation results with infrared absorption and pump-probe spectroscopy of O–D stretch mode of HDO in highly concentrated salt solutions and {sup 13}C-NMR chemical shift of S{sup 13}CN{sup ?} in KSCN solutions, we find evidence on the onset of ion aggregate and large-scale ion-ion network formation that concomitantly breaks water hydrogen-bond structure in certain salt solutions. Despite that these experimental results cannot provide direct evidence on the three-dimensional morphological structures of ion aggregates, they serve as reference data for verifying MD simulation methods. The MD results suggest that disrupted water hydrogen-bond network is intricately intertwined with ion-ion network. This further shows morphological variation of ion aggregate structures from ion cluster to ion network in high salt solutions that are interrelated to the onset of macroscopic aggregate formation and the water hydrogen-bond structure making and breaking processes induced by Hofmeister ions.

  8. A route to explain water anomalies from results on an aqueous solution of salt

    E-Print Network [OSTI]

    D. Corradini; M. Rovere; P. Gallo

    2010-03-26T23:59:59.000Z

    In this paper we investigate the possibility to detect the hypothesized liquid-liquid critical point of water in supercooled aqueous solutions of salts. Molecular dynamics computer simulations are conducted on bulk TIP4P water and on an aqueous solution of sodium chloride in TIP4P water, with concentration c = 0.67 mol/kg. The liquid-liquid critical point is found both in the bulk and in the solution. Its position in the thermodynamic plane shifts to higher temperature and lower pressure for the solution. Comparison with available experimental data allowed us to produce the phase diagrams of both bulk water and the aqueous solution as measurable in experiments. Given the position of the liquid-liquid critical point in the solution as obtained from our simulations, the experimental determination of the hypothesized liquid-liquid critical point of water in aqueous solutions of salts appears possible.

  9. Composition suitable for decontaminating a porous surface contaminated with cesium

    DOE Patents [OSTI]

    Kaminski, Michael D.; Finck, Martha R.; Mertz, Carol J.

    2010-06-15T23:59:59.000Z

    A method of decontaminating porous surfaces contaminated with water soluble radionuclides by contacting the contaminated porous surfaces with an ionic solution capable of solubilizing radionuclides present in the porous surfaces followed by contacting the solubilized radionuclides with a gel containing a radionuclide chelator to bind the radionuclides to the gel, and physically removing the gel from the porous surfaces. A dry mix is also disclosed of a cross-linked ionic polymer salt, a linear ionic polymer salt, a radionuclide chelator, and a gel formation controller present in the range of from 0% to about 40% by weight of the dry mix, wherein the ionic polymer salts are granular and the non cross-linked ionic polymer salt is present as a minor constituent.

  10. The Effect of Salt Stoichiometry on Protein-Salt Interactions Determined by Ternary Diffusion in Aqueous Solutions

    E-Print Network [OSTI]

    Annunziata, Onofrio

    The Effect of Salt Stoichiometry on Protein-Salt Interactions Determined by Ternary Diffusion of salt stoichiometry on the transport properties of lysozyme-salt aqueous mixtures. We find that the two cross-diffusion coefficients are very sensitive to salt stoichiometry. One of the cross

  11. An empirical correlation between the enthalpy of solution of aqueous salts and their ability to form hydrates

    SciTech Connect (OSTI)

    Pandelov, S.; Werhahn, Jasper C.; Pilles, Bert M.; Xantheas, Sotiris S.; Iglev, H.

    2010-09-30T23:59:59.000Z

    The ability of aqueous salt solutions to form hydrates by cooling them at ambient pressure is probed by infrared (IR) spectroscopy by examining the structure of the spectra in the hydrogen-bonding region (3,000 - 3,800 cm-1). A collection of 75 organic and inorganic salts in saturated solutions are examined. We have found a correlation between the enthalpy of solution of the salt and its ability to form a hydrate, namely that the salt’s enthalpy of solution is lower than the standard enthalpy of fusion of ice (6 kJ/mol). This observation can serve as an empirical rule that determines whether a salt will form a hydrate upon cooling from its aqueous solution.

  12. Water Dynamics in Salt Solutions Studied with Ultrafast Two-Dimensional Infrared (2D IR)

    E-Print Network [OSTI]

    Fayer, Michael D.

    Water Dynamics in Salt Solutions Studied with Ultrafast Two-Dimensional Infrared (2D IR RECEIVED ON FEBRUARY 3, 2009 C O N S P E C T U S Water is ubiquitous in nature, but it exists as pure water infrequently. From the ocean to biology, water molecules interact with a wide variety of dissolved species

  13. Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation

    SciTech Connect (OSTI)

    Morgan, Dane; Eapen, Jacob

    2013-10-01T23:59:59.000Z

    Recovery of actinides is an integral part of a closed nuclear fuel cycle. Pyrometallurgical nuclear fuel recycling processes have been developed in the past for recovering actinides from spent metallic and nitride fuels. The process is essentially to dissolve the spent fuel in a molten salt and then extract just the actinides for reuse in a reactor. Extraction is typically done through electrorefining, which involves electrochemical reduction of the dissolved actinides and plating onto a cathode. Knowledge of a number of basic thermokinetic properties of salts and salt-fuel mixtures is necessary for optimizing present and developing new approaches for pyrometallurgical waste processing. The properties of salt-fuel mixtures are presently being studied, but there are so many solutes and varying concentrations that direct experimental investigation is prohibitively time consuming and expensive (particularly for radioactive elements like Pu). Therefore, there is a need to reduce the number of required experiments through modeling of salt and salt-fuel mixture properties. This project will develop first-principles-based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. The focus of the proposed work is on property changes with higher concentrations (up to 5 mol%) of dissolved fuel components, where there is still very limited experimental data. The properties predicted with the modeling will be density, which is used to assess the amount of dissolved material in the salt; diffusion coefficients, which can control rates of material transport during separation; and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work will focus on La, Sr, and U, which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively. Studies will be performed using LiCl-KCl salt at the eutectic composition (58 mol% LiCl, 42 mol% KCl), which is used for treating spent EBR-II fuel. The same process being used for EBRII fuel is currently being studied for widespread international implementation. The methods will focus on first-principles and first- principles derived interatomic potential based simulations, primarily using molecular dynamics. Results will be validated against existing literature and parallel ongoing experimental efforts. The simulation results will be of value for interpreting experimental results, validating analytical models, and for optimizing waste separation by potentially developing new salt configurations and operating conditions.

  14. Electrochemical Recovery of Sodium Hydroxide from Alkaline Salt Solution

    SciTech Connect (OSTI)

    Hobbs, D.T. [Westinghouse Savannah River Company, AIKEN, SC (United States); Edwards, T.B.

    1996-10-01T23:59:59.000Z

    A statistically designed set of tests determined the effects of current density, temperature, and the concentrations of nitrate/nitrite, hydroxide and aluminate on the recovery of sodium as sodium hydroxide (caustic) from solutions simulating those produced from the Savannah River Site (SRS) In-Tank Precipitation process. These tests included low nitrate and nitrite concentrations which would be produced by electrolytic nitrate/nitrite destruction. The tests used a two compartment electrochemical cell with a Nafion Type 324 ion-exchange membrane. Caustic was successfully recovered from the waste solutions. Evaluation of the testing results indicated that the transport of sodium across the membrane was not significantly affected by any of the varied parameters. The observed variance in the sodium flux is attributed to experimental errors and variations in the performance characteristics of individual pieces of the organic-based Nafion membrane.Additional testing is recommended to determine the maximum current density, to evaluate the chemical durability of the organic membrane as a function of current density and to compare the durability and performance characteristics of the organic-based Nafion membrane with that of other commercially available organic membranes and the inorganic class of membranes under development by Ceramatec and PNNL.

  15. Hydration structure of salt solutions from ab initio molecular dynamics

    SciTech Connect (OSTI)

    Bankura, Arindam; Carnevale, Vincenzo; Klein, Michael L. [Institute for Computational Molecular Science and Department of Chemistry, Temple University, Philadelphia, Pennsylvania 19122 (United States)

    2013-01-07T23:59:59.000Z

    The solvation structures of Na{sup +}, K{sup +}, and Cl{sup -} ions in aqueous solution have been investigated using density functional theory (DFT) based Car-Parrinello (CP) molecular dynamics (MD) simulations. CPMD trajectories were collected for systems containing three NaCl or KCl ion pairs solvated by 122 water molecules using three different but commonly employed density functionals (BLYP, HCTH, and PBE) with electron correlation treated at the level of the generalized gradient approximation (GGA). The effect of including dispersion forces was analyzed through the use of an empirical correction to the DFT-GGA scheme. Special attention was paid to the hydration characteristics, especially the structural properties of the first solvation shell of the ions, which was investigated through ion-water radial distribution functions, coordination numbers, and angular distribution functions. There are significant differences between the present results obtained from CPMD simulations and those provided by classical MD based on either the CHARMM force field or a polarizable model. Overall, the computed structural properties are in fair agreement with the available experimental results. In particular, the observed coordination numbers 5.0-5.5, 6.0-6.4, and 6.0-6.5 for Na{sup +}, K{sup +}, and Cl{sup -}, respectively, are consistent with X-ray and neutron scattering studies but differ somewhat from some of the many other recent computational studies of these important systems. Possible reasons for the differences are discussed.

  16. Aqueous Biphasic Systems Based on Salting-Out Polyethylene Glycol or Ionic Solutions: Strategies for Actinide or Fission Product Separations

    SciTech Connect (OSTI)

    Rogers, Robin D.; Gutowski, Keith E.; Griffin, Scott T.; Holbrey, John D.

    2004-03-29T23:59:59.000Z

    Aqueous biphasic systems can be formed by salting-out (with kosmotropic, waterstructuring salts) water soluble polymers (e.g., polyethylene glycol) or aqueous solutions of a wide range of hydrophilic ionic liquids based on imidazolium, pyridinium, phosphonium and ammonium cations. The use of these novel liquid/liquid biphases for separation of actinides or other fission products associated with nuclear wastes (e.g., pertechnetate salts) has been demonstrated and will be described in this presentation.

  17. Adding Salt to an Aqueous Solution of t-Butanol: Is Hydrophobic Association Enhanced or Reduced?

    E-Print Network [OSTI]

    Dietmar Paschek; Alfons Geiger; Momo Jeufack Herve; Dieter Suter

    2006-01-16T23:59:59.000Z

    Recent neutron scattering experiments on aqueous salt solutions of amphiphilic t-butanol by Bowron and Finney [Phys. Rev. Lett. {\\bf 89}, 215508 (2002); J. Chem. Phys. {\\bf 118}, 8357 (2003)] suggest the formation of t-butanol pairs, bridged by a chloride ion via ${O}-{H}...{Cl}^-$ hydrogen-bonds, and leading to a reduced number of intermolecular hydrophobic butanol-butanol contacts. Here we present a joint experimental/theoretical study on the same system, using a combination of molecular dynamics simulations and nuclear magnetic relaxation measurements. Both theory and experiment clearly support the more intuitive scenario of an enhanced number of hydrophobic contacts in the presence of the salt, as it would be expected for purely hydrophobic solutes [J. Phys. Chem. B {\\bf 107}, 612 (2003)]. Although our conclusions arrive at a structurally completely distinct scenario, the molecular dynamics simulation results are within the experimental errorbars of the Bowron and Finney work.

  18. Underground physics without underground labs: large detectors in solution-mined salt caverns

    E-Print Network [OSTI]

    Benjamin Monreal

    2014-09-30T23:59:59.000Z

    A number of current physics topics, including long-baseline neutrino physics, proton decay searches, and supernova neutrino searches, hope to someday construct huge (50 kiloton to megaton) particle detectors in shielded, underground sites. With today's practices, this requires the costly excavation and stabilization of large rooms in mines. In this paper, we propose utilizing the caverns created by the solution mining of salt. The challenge is that such caverns must be filled with pressurized fluid and do not admit human access. We sketch some possible methods of installing familiar detector technologies in a salt cavern under these constraints. Some of the detectors discussed are also suitable for deep-sea experiments, discussed briefly. These sketches appear challenging but feasible, and appear to force few major compromises on detector capabilities. This scheme offers avenues for enormous cost savings on future detector megaprojects.

  19. Effect of salt identity on the phase diagram for a globular protein in aqueous electrolyte solution

    E-Print Network [OSTI]

    Bostrom, Mathias; Tavares, Frederico W.; Ninham, Barry W.; Prausnitz, John M.

    2006-01-01T23:59:59.000Z

    or NaSCN. For all cases, salt concentration is 0.2 M. StableEFFECT OF SALT IDENTITY ON THE PHASE DIAGRAM FOR A GLOBULARcannot account for the effect of salt identity on the phase

  20. DNA decontamination: DNA-ExitusPlus in comparison with conventional reagents

    E-Print Network [OSTI]

    Cai, Long

    DNA decontamination: DNA-ExitusPlus in comparison with conventional reagents Here we present a completely new DNA decontamination reagent DNA-ExitusPlus. In comparison with conventional products, DNA solutions for effective DNA decontamination. DNA decontamination reagents use three different molecular prin

  1. Nuclear reactor cooling system decontamination reagent regeneration

    DOE Patents [OSTI]

    Anstine, Larry D. (San Jose, CA); James, Dean B. (Saratoga, CA); Melaika, Edward A. (Berkeley, CA); Peterson, Jr., John P. (Livermore, CA)

    1985-01-01T23:59:59.000Z

    An improved method for decontaminating the coolant system of water-cooled nuclear power reactors and for regenerating the decontamination solution. A small amount of one or more weak-acid organic complexing agents is added to the reactor coolant, and the pH is adjusted to form a decontamination solution which is circulated throughout the coolant system to dissolve metal oxides from the interior surfaces and complex the resulting metal ions and radionuclide ions. The coolant containing the complexed metal ions and radionuclide ions is passed through a strong-base anion exchange resin bed which has been presaturated with a solution containing the complexing agents in the same ratio and having the same pH as the decontamination solution. As the decontamination solution passes through the resin bed, metal-complexed anions are exchanged for the metal-ion-free anions on the bed, while metal-ion-free anions in the solution pass through the bed, thus removing the metal ions and regenerating the decontamination solution.

  2. The Effect of Salt on Protein Chemical Potential Determined by Ternary Diffusion in Aqueous Solutions

    E-Print Network [OSTI]

    Annunziata, Onofrio

    The Effect of Salt on Protein Chemical Potential Determined by Ternary Diffusion in Aqueous as a function of salt concentration, (b) compare the behavior of the protein chemical potential for the three salts, which we found to be consistent with the Hofmeister series, and (c) discuss our thermodynamic

  3. Decontamination n Sterilization

    E-Print Network [OSTI]

    Collins, Gary S.

    2.10 #12;Decontamination Definition n Sterilization The use of a physical or chemical procedure microorganisms but not all microbial forms (bacterial endospores) on inanimate objects. 2.10 Decontamination or destroying microorganisms. 2.10 Decontamination Definition #12;n Degree of microbial killing required n

  4. SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING

    SciTech Connect (OSTI)

    Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

    2011-01-12T23:59:59.000Z

    This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

  5. Reactive decontamination formulation

    DOE Patents [OSTI]

    Giletto, Anthony (College Station, TX); White, William (College Station, TX); Cisar, Alan J. (Cypress, TX); Hitchens, G. Duncan (Bryan, TX); Fyffe, James (Bryan, TX)

    2003-05-27T23:59:59.000Z

    The present invention provides a universal decontamination formulation and method for detoxifying chemical warfare agents (CWA's) and biological warfare agents (BWA's) without producing any toxic by-products, as well as, decontaminating surfaces that have come into contact with these agents. The formulation includes a sorbent material or gel, a peroxide source, a peroxide activator, and a compound containing a mixture of KHSO.sub.5, KHSO.sub.4 and K.sub.2 SO.sub.4. The formulation is self-decontaminating and once dried can easily be wiped from the surface being decontaminated. A method for decontaminating a surface exposed to chemical or biological agents is also disclosed.

  6. Protein-salt binding data from potentiometric titrations of lysozyme in aqueous solutions containing KCl

    SciTech Connect (OSTI)

    Engmann, J.; Blanch, H.W.; Prausnitz, J.M. [Univ. of California, Berkeley, CA (United States). Dept. of Chemical Engineering]|[Lawrence Berkeley National Lab., CA (United States). Chemical Sciences Div.

    1997-03-01T23:59:59.000Z

    An existing method for potentiometric titrations of proteins was improved, tested and applied to titrations of the enzyme hen-egg-white lysozyme in aqueous solutions containing KCl at ionic strengths from 0.1 M to 2.0 M at 25 C. Information about the protein`s net charge dependence on pH and ionic strength were obtained and salt binding numbers for the system were calculated using a linkage concept. For the pH range 2.5--11.5, the net charge slightly but distinctly increases with increasing ionic strength between 0.1 M and 2.0 M. The differences are most distinct in the pH region below 5. Above pH 11.35, the net charge decreases with increasing ionic strength. Preliminary calculation of binding numbers from titration curves at 0.1 M and 1.0 M showed selective association of chloride anions and expulsion of potassium ions at low pH. Ion-binding numbers from this work will be used to evaluate thermodynamic properties and to correlate crystallization or precipitation phase-equilibrium data in terms of a model based on the integral-equation theory of fluids which is currently under development.

  7. Decontamination & decommissioning focus area

    SciTech Connect (OSTI)

    NONE

    1996-08-01T23:59:59.000Z

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  8. Electroosmotic decontamination of concrete

    SciTech Connect (OSTI)

    Bostick, W.D.; Bush, S.A.; Marsh, G.C.; Henson, H.M. [Oak Ridge K-25 Site, TN (United States); Box, W.D.; Morgan, I.L. [Oak Ridge National Lab., TN (United States)

    1993-03-01T23:59:59.000Z

    A method is described for the electroosmotic decontamination of concrete surfaces, in which an electrical field is used to induce migration of ionic contaminants from porous concrete into an electrolyte solution that may be disposed of as a low-level liquid radioactive waste (LLRW); alternately, the contaminants from the solution can be sorbed onto anion exchange media in order to prevent contaminant buildup in the solution and to minimize the amount of LLRW generated. We have confirmed the removal of uranium (and infer the removal of {sup 99}Tc) from previously contaminated concrete surfaces. In a typical experimental configuration, a stainless steel mesh is placed in an electrolyte solution contained within a diked cell to serve as the negative electrode (cathode) and contaminant collection medium, respectively, and an existing metal penetration (e.g., piping, conduit, or rebar reinforcement within the concrete surface) serves as the positive electrode (anode) to complete the cell. Typically we have achieved 70 to >90% reductions in surface activity by applying <400 V and <1 A for 1--3 h (energy consumption of 0.4--12 kWh/ft{sup 2}).

  9. Decontamination of metals using chemical etching

    DOE Patents [OSTI]

    Lerch, Ronald E. (Kennewick, WA); Partridge, Jerry A. (Richland, WA)

    1980-01-01T23:59:59.000Z

    The invention relates to chemical etching process for reclaiming contaminated equipment wherein a reduction-oxidation system is included in a solution of nitric acid to contact the metal to be decontaminated and effect reduction of the reduction-oxidation system, and includes disposing a pair of electrodes in the reduced solution to permit passage of an electrical current between said electrodes and effect oxidation of the reduction-oxidation system to thereby regenerate the solution and provide decontaminated equipment that is essentially radioactive contamination-free.

  10. Gross decontamination experiment report

    SciTech Connect (OSTI)

    Mason, R.; Kinney, K.; Dettorre, J.; Gilbert, V.

    1983-07-01T23:59:59.000Z

    A Gross Decontamination Experiment was conducted on various levels and surfaces of the TMI - Unit 2 reactor building in March 1982. The polar crane, D-rings, missile shields, refueling canals, refueling bridges, equipment, and elevations 305' and 347'-6'' were flushed with low pressure water. Additionally, floor surfaces on elevation 305' and floor surfaces and major pieces of equipment on elevation 347'-6'' were sprayed with high pressure water. Selective surfaces were decontaminated with a mechanical scrubber and chemicals. Strippable coating was tested and evaluated on equipment and floor surfaces. The effectiveness, efficiency, and safety of several decontamination techniques were established for the large, complex decontamination effort. Various decontamination equipment was evaluated and its effectiveness was documented. Decontamination training and procedures were documented and evaluated, as were the support system and organization for the experiment.

  11. Equipment decontamination: A brief survey of the DOE complex

    SciTech Connect (OSTI)

    Conner, C.; Chamberlain, D.B; Chen, L.; Vandegrift, G.F.

    1995-03-01T23:59:59.000Z

    Deactivation at DOE facilities has left a tremendous amount of contaminated equipment behind. In-situ methods are needed to decontaminate the interiors of the equipment sufficiently to allow either free release or land disposal. A brief survey was completed of the DOE complex on their needs for equipment decontamination with in-situ technology to determine (1) the types of contamination problems within the DOE complex, (2) decontamination processes that are being used or are being developed within the DOE, and (3) the methods that are available to dispose of spent decontamination solutions. In addition, potential sites for testing decontamination methods were located. Based on the information obtained from these surveys, the Rocky Flats Plant and the Idaho National Engineering Laboratory appear to be best suited to complete the initial testing of the decontamination processes.

  12. Water purification using organic salts

    DOE Patents [OSTI]

    Currier, Robert P.

    2004-11-23T23:59:59.000Z

    Water purification using organic salts. Feed water is mixed with at least one organic salt at a temperature sufficiently low to form organic salt hydrate crystals and brine. The crystals are separated from the brine, rinsed, and melted to form an aqueous solution of organic salt. Some of the water is removed from the aqueous organic salt solution. The purified water is collected, and the remaining more concentrated aqueous organic salt solution is reused.

  13. Improved germination of pansy seed at high temperatures by priming with salt solutions

    E-Print Network [OSTI]

    Yoon, Beyoung-Han

    1995-01-01T23:59:59.000Z

    and nonprimed seeds. Pansy seeds (Viola x wittrockiana 'Majestic Giant Blue Shade' and 'Crystal Bowl Sky Blue') were primed with several salts and PEG 15,000 at - 1.0 and - 2.0 MPa, for 3, 6, or 9 days at 23 C. Total percent germination (G) of nonprimed seeds...

  14. Long lasting decontamination foam

    DOE Patents [OSTI]

    Demmer, Ricky L. (Idaho Falls, ID); Peterman, Dean R. (Idaho Falls, ID); Tripp, Julia L. (Pocatello, ID); Cooper, David C. (Idaho Falls, ID); Wright, Karen E. (Idaho Falls, ID)

    2010-12-07T23:59:59.000Z

    Compositions and methods for decontaminating surfaces are disclosed. More specifically, compositions and methods for decontamination using a composition capable of generating a long lasting foam are disclosed. Compositions may include a surfactant and gelatin and have a pH of less than about 6. Such compositions may further include affinity-shifting chemicals. Methods may include decontaminating a contaminated surface with a composition or a foam that may include a surfactant and gelatin and have a pH of less than about 6.

  15. Investigation on the coprecipitation of transuranium elements from alkaline solutions by the method of appearing reagents. Study of the effects of waste components on decontamination from Np(IV) and Pu(IV)

    SciTech Connect (OSTI)

    Bessonov, A.A.; Budantseva, N.A.; Gelis, A.V.; Nikonov, M.V.; Shilov, V.P. [Russian Academy of Sciences, Moscow (Russian Federation). Institute of Physical Chemistry

    1997-09-01T23:59:59.000Z

    The third stage of the study on the homogeneous coprecipitation of neptunium and plutonium from alkaline high-level radioactive waste solutions by the Method of Appearing Reagents has been completed. Alkaline radioactive wastes exist at the U.S. Department of Energy Hanford Site. The recent studies investigated the effects of neptunium chemical reductants, plutonium(IV) concentration, and the presence of bulk tank waste solution components on the decontamination from tetravalent neptunium and plutonium achieved by homogeneous coprecipitation. Data on neptunium reduction to its tetravalent state in alkaline solution of different NaOH concentrations are given. Eleven reductants were tested to find those most suited to remove neptunium, through chemical reduction, from alkaline solution by homogeneous coprecipitation. Hydrazine, VOSO{sub 4}, and Na{sub 2}S{sub 2}O{sub 4} were found to be the most effective reductants. The rates of reduction with these reductants were comparable with the kinetics of carrier formation. Solution decontamination factors of about 400 were attained for 10{sup -6}M neptunium. Coprecipitation of plutonium(IV) with carriers obtained as products of thermal hydrolysis, redox transformations, and catalytic decomposition of [Co(NH{sub 3}){sub 6}]{sup 3+}, [Fe(CN){sub 5}NO]{sup 2-}, Cr(NO{sub 3}){sub 3}, KMnO{sub 4}, and Li{sub 4}UO{sub 2}(O{sub 2}){sub 3} was studied and results are described. Under optimum conditions, a 100-fold decrease of plutonium concentration was possible with each of these reagents.

  16. Nuclear reactor cooling system decontamination reagent regeneration. [PWR; BWR

    DOE Patents [OSTI]

    Anstine, L.D.; James, D.B.; Melaika, E.A.; Peterson, J.P. Jr.

    1980-06-06T23:59:59.000Z

    An improved method for decontaminating the coolant system of water-cooled nuclear power reactors and for regenerating the decontamination solution is described. A small amount of one or more weak-acid organic complexing agents is added to the reactor coolant, and the pH is adjusted to form a decontamination solution which is circulated throughout the coolant system to dissolve metal oxides from the interior surfaces and complex the resulting metal ions and radionuclide ions. The coolant containing the complexed metal ions and radionuclide ions is passed through a strong-base anion exchange resin bed which has been presaturated with a solution containing the complexing agents in the same ratio and having the same pH as the decontamination solution. As the decontamination solution passes through the resin bed, metal-complexed anions are exchanged for the metal-ion-free anions on the bed, while metal-ion-free anions in the solution pass through the bed, thus removing the metal ions and regenerating the decontamination solution.

  17. Method for the decontamination of metallic surfaces

    DOE Patents [OSTI]

    Purohit, Ankur (Darien, IL); Kaminski, Michael D. (Lockport, IL); Nunez, Luis (Elmhurst, IL)

    2003-01-01T23:59:59.000Z

    A method of decontaminating a radioactively contaminated oxide on a surface. The radioactively contaminated oxide is contacted with a diphosphonic acid solution for a time sufficient to dissolve the oxide and subsequently produce a precipitate containing most of the radioactive values. Thereafter, the diphosphonic solution is separated from the precipitate. HEDPA is the preferred diphosphonic acid and oxidizing and reducing agents are used to initiate precipitation. SFS is the preferred reducing agent.

  18. Finite-Width Bundle is Most Stable in a Solution with Salt

    E-Print Network [OSTI]

    Takuya Saito; Kenichi Yoshikawa

    2010-04-21T23:59:59.000Z

    We applied the mean-field approach to a columnar bundle assembled by the parallel arrangement of stiff polyelectrolyte rods in a salt bath. The electrostatic potential can be divided into two regions: inside the bundle for condensed counter-ions, and outside the bundle for free small ions. To determine the distribution of condensed counter-ions inside the bundle, we use a local self-consistent condition that depends on the charge density, the electrostatic potential, and the net polarization. The results showed that, upon bundle formation, the electric charge of polyelectrolytes, even those inside the bundle, tend to survive in an inhomogeneous manner, and thus their width remains finite under thermal equilibrium because of the long-range effect of charge instability.

  19. Concentrating aqueous volatile fatty acid salt solutions using a tertiary amine mixture

    E-Print Network [OSTI]

    Gaskin, David J

    1997-01-01T23:59:59.000Z

    Lee (1993) has shown that tertiary amines are able to hics. extract water from low-concentration calcium acetate and sodium acetate solutions. This thesis extends the previous work to include calcium propionate and butyrate. Amine extraction may...

  20. The Breeding Blanket Interface (BBI): Recent results for the solid breeder and the aqueous salt solution blanket concepts

    SciTech Connect (OSTI)

    Clemmer, R.G.; Finn, P.A.; Greenwood, L.R.; Sze, D.K.; Bartlit, J.R.; Sherman, R.; Anderson, J.L.; Yoshida, H.; Naruse, Y.; Enoeda, M.; Okuno, K. (Argonne National Lab., IL (USA); Los Alamos National Lab., NM (USA); Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

    1989-10-01T23:59:59.000Z

    The Tritium Systems Test Assembly (TSTA) at Los Alamos is a full-scale facility dedicated to testing tritium processing for fusion reactors. We are involved in a study of adding a Breeder Blanket Interface (BBI) to the TSTA. The BBI is to test the processing required for the tritium output streams for the various fusion reactor breeder blankets. In the current phase of the study, we are evaluating the characteristics of the output from various breeding blankets types. Emphasis is placed on defining the output stream with respect to H/T ratio, impurity content, and radionuclide content. Reported herein is an assessment for two blanket concepts: solid breeder blanket (ceramic, Li{sub 2}O), and aqueous salt solution. 24 refs., 2 figs., 2 tabs.

  1. Oxidative Tritium Decontamination System

    DOE Patents [OSTI]

    Gentile, Charles A. (Plainsboro, NJ), Guttadora, Gregory L. (Highland Park, NJ), Parker, John J. (Medford, NJ)

    2006-02-07T23:59:59.000Z

    The Oxidative Tritium Decontamination System, OTDS, provides a method and apparatus for reduction of tritium surface contamination on various items. The OTDS employs ozone gas as oxidizing agent to convert elemental tritium to tritium oxide. Tritium oxide vapor and excess ozone gas is purged from the OTDS, for discharge to atmosphere or transport to further process. An effluent stream is subjected to a catalytic process for the decomposition of excess ozone to diatomic oxygen. One of two configurations of the OTDS is employed: dynamic apparatus equipped with agitation mechanism and large volumetric capacity for decontamination of light items, or static apparatus equipped with pressurization and evacuation capability for decontamination of heavier, delicate, and/or valuable items.

  2. Application of Ultrasonic for Decontamination of Contaminated Soil - 13142

    SciTech Connect (OSTI)

    Vasilyev, A.P. [JRC 'NIKIET', Moscow (Russian Federation)] [JRC 'NIKIET', Moscow (Russian Federation); Lebedev, N.M. [LLC 'Aleksandra-Plus', Vologda (Russian Federation)] [LLC 'Aleksandra-Plus', Vologda (Russian Federation); Savkin, A.E. [SUE SIA 'Radon', Moscow (Russian Federation)] [SUE SIA 'Radon', Moscow (Russian Federation)

    2013-07-01T23:59:59.000Z

    The trials of soil decontamination were carried out with the help of a pilot ultrasonic installation in different modes. The installation included a decontamination bath equipped with ultrasonic sources, a precipitator for solution purification from small particles (less than 80 micrometer), sorption filter for solution purification from radionuclides washing out from soil, a tank for decontamination solution, a pump for decontamination solution supply. The trials were carried out on artificially contaminated sand with specific activity of 4.5 10{sup 5} Bk/kg and really contaminated soil from Russian Scientific Center 'Kurchatovsky Institute' (RSC'KI') with specific activity of 2.9 10{sup 4} Bk/kg. It was established that application of ultrasonic intensify the process of soil reagent decontamination and increase its efficiency. The decontamination factor for the artificially contaminated soil was ?200 and for soil from RSC'KI' ?30. The flow-sheet diagram has been developed for the new installation as well as determined the main technological characteristics of the equipment. (authors)

  3. Anthrax Sampling and Decontamination: Technology Trade-Offs

    E-Print Network [OSTI]

    Price, Phillip N.

    2009-01-01T23:59:59.000Z

    6 Decontamination6.1 Decontamination Technologies . . . . . .6.2.4 Other anthrax decontamination experience 6.3 Selecting

  4. Decontaminating metal surfaces

    DOE Patents [OSTI]

    Childs, E.L.

    1984-01-23T23:59:59.000Z

    Radioactively contaminated surfaces can be electrolytically decontaminated with greatly increased efficiencies by using electrolytes containing higher than heretofore conventional amounts of nitrate, e.g., >600 g/1 of NaNO/sub 3/, or by using nitrate-containing electrolytes which are acidic, e.g., of a pH < 6.

  5. Mesoscale phenomena in solutions of 3-methylpyridine, heavy water, and an antagonistic salt

    E-Print Network [OSTI]

    Jan Leys; Deepa Subramanian; Eva Rodezno; Boualem Hammouda; Mikhail A. Anisimov

    2013-08-22T23:59:59.000Z

    We have investigated controversial issues regarding the mesoscale behavior of 3-methylpyridine (3MP), heavy water, and sodium tetraphenylborate (NaBPh4) solutions by combining results obtained from dynamic light scattering (DLS) and small-angle neutron scattering (SANS). We have addressed three questions: (i) what is the origin of the mesoscale inhomogeneities (order of 100 nm in size) manifested by the "slow mode" in DLS? (ii) Is the periodic structure observed from SANS an inherent property of this system? (iii) What is the universality class of critical behavior in this system? Our results confirm that the "slow mode" observed from DLS experiments corresponds to long-lived, highly stable mesoscale droplets (order of 100 nm in size), which occur only when the solute (3MP) is contaminated by hydrophobic impurities. SANS data confirm the presence of a periodic structure with a periodicity of about 10 nm. This periodic structure cannot be eliminated by nanopore filtration and thus is indeed an inherent solution property. The critical behavior of this system, in the range of concentration and temperatures investigated by DLS experiments, indicates that the criticality belongs to the universality class of the 3-dimensional Ising model.

  6. Precipitation-adsorption process for the decontamination of nuclear waste supernates

    DOE Patents [OSTI]

    Lee, Lien-Mow (North Augusta, SC); Kilpatrick, Lester L. (Aiken, SC)

    1984-01-01T23:59:59.000Z

    High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

  7. Precipitation-adsorption process for the decontamination of nuclear waste supernates

    DOE Patents [OSTI]

    Lee, L.M.; Kilpatrick, L.L.

    1982-05-19T23:59:59.000Z

    High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

  8. OSMOTIC COEFFICIENTS, SOLUBILITIES, AND DELIQUESCENCE RELATIONS IN MIXED AQUEOUS SALT SOLUTIONS AT ELEVATED TEMPERATURE

    SciTech Connect (OSTI)

    M.S. Gruszkiewicz; D.A. Palmer

    2006-02-22T23:59:59.000Z

    While thermodynamic properties of pure aqueous electrolytes are relatively well known at ambient temperature, there are far fewer data for binary systems extending to elevated temperatures and high concentrations. There is no general theoretically sound basis for prediction of the temperature dependence of ionic activities, and consequently temperature extrapolations based on ambient temperature data and empirical equations are uncertain and require empirical verification. Thermodynamic properties of mixed brines in a wide range of concentrations would enhance the understanding and precise modeling of the effects of deliquescence of initially dry solids in humid air in geological environments and in modeling the composition of waters during heating, cooling, evaporation or condensation processes. These conditions are of interest in the analysis of waters on metal surfaces at the proposed radioactive waste repository at Yucca Mountain, Nevada. The results obtained in this project will be useful for modeling the long-term evolution of the chemical environment, and this in turn is useful for the analysis of the corrosion of waste packages. In particular, there are few reliable experimental data available on the relationship between relative humidity and composition that reveals the eutonic points of the mixtures and the mixture deliquescence RH. The deliquescence RH for multicomponent mixtures is lower than that of pure component or binary solutions, but is not easy to predict quantitatively since the solutions are highly nonideal. In this work we used the ORNL low-temperature and high-temperature isopiestic facilities, capable of precise measurements of vapor pressure between ambient temperature and 250 C for determination of not only osmotic coefficients, but also solubilities and deliquescence points of aqueous mixed solutions in a range of temperatures. In addition to standard solutions of CaCl{sub 2}, LiCl, and NaCl used as references, precise direct-pressure measurements were also made at elevated temperatures. The project included multicomponent mixtures useful for verification of models, and a set of binary solutions with common ions (such as KNO{sub 3} + NaNO{sub 3}, KNO{sub 3} + Ca(NO{sub 3}){sub 2}, NaNO{sub 3} + Na{sub 2}SO{sub 4}, and KNO{sub 3} + K{sub 2}SO{sub 4}) needed for determination of the mixing parameters in the Pitzer ion-interaction model for mixtures. The results are compared with existing experimental results and model predictions.

  9. Process for preparing chemically modified micas for removal of cesium salts from aqueous solution

    DOE Patents [OSTI]

    Yates, Stephen Frederic (1539 S. Kennicott Dr., Arlington Heights, IL 60005); DeFilippi, Irene (208 E. Edgewood La., Palatine, IL 60067); Gaita, Romulus (6646 Davis Rd., Morton Grove, IL 60053); Clearfield, Abraham (Department of Chemistry, Texas A& M University, College Station, TX 77843); Bortun, Lyudmila (Department of Chemistry, Texas A& M University, College Station, TX 77843); Bortun, Anatoly (Department of Chemistry, Texas A& M University, College Station, TX 77843)

    2000-09-05T23:59:59.000Z

    A chemically modified mica composite formed by heating a trioctahedral mica in an aqueous solution of sodium chloride having a concentration of at least 1 mole/liter at a temperature greater than 180 degrees Centigrade for at least 20 hours, thereby replacing exchangeable ions in the mica with sodium. Formation is accomplished at temperatures and pressures which are easily accessed by industrial equipment. The reagent employed is inexpensive and non-hazardous, and generates a precipitate which is readily separated from the modified mica.

  10. Planning guidance for nuclear-power-plant decontamination. [PWR; BWR

    SciTech Connect (OSTI)

    Munson, L.F.; Divine, J.R.; Martin, J.B.

    1983-06-01T23:59:59.000Z

    Direct and indirect costs of decontamination are considered in the benefit-cost analysis. A generic form of the benefit-cost ratio is evaluated in monetary and nonmonetary terms, and values of dollar per man-rem are cited. Federal and state agencies that may have jurisiction over various aspects of decontamination and waste disposal activities are identified. Methods of decontamination, their general effectiveness, and the advantages and disadvantages of each are outlined. Dilute or concentrated chemical solutions are usually used in-situ to dissolve the contamination layer and a thin layer of the underlying substrate. Electrochemical techniques are generally limited to components but show high decontamination effectiveness with uniform corrosion. Mechanical agents are particularly appropriate for certain out-of-system surfaces and disassembled parts. These processes are catagorized and specific concerns are discussed. The treatment, storage, and disposal or discharge or discharge of liquid, gaseous, and solid wastes generated during the decontamination process are discussed. Radioactive and other hazardous chemical wastes are considered. The monitoring, treatment, and control of radioactive and nonradioactive effluents, from both routine operations and possible accidents, are discussed. Protecting the health and safety of personnel onsite during decontamination is of prime importance and should be considered in each facet of the decontamination process. The radiation protection philosophy of reducing exposure to levels as low as reasonably achievable should be stressed. These issues are discussed.

  11. Method for electrochemical decontamination of radioactive metal

    DOE Patents [OSTI]

    Ekechukwu, Amy A. (Augusta, GA)

    2008-06-10T23:59:59.000Z

    A decontamination method for stripping radionuclides from the surface of stainless steel or aluminum material comprising the steps of contacting the metal with a moderately acidic carbonate/bicarbonate electrolyte solution containing sodium or potassium ions and thereafter electrolytically removing the radionuclides from the surface of the metal whereby radionuclides are caused to be stripped off of the material without corrosion or etching of the material surface.

  12. Energy and entropy effects of counterions in salt-free colloidal solutions

    E-Print Network [OSTI]

    Chi-Lun Lee

    2012-02-08T23:59:59.000Z

    We use a shell model to study the counterion interactions in a colloidal solution. In this shell model, the counterions are restricted to move inside a spherical region about their host colloidal particle. In particular, we apply Monte Carlo simulations to derive the energy and entropy contributions of the effective colloidal interaction. Our result reveals an attractive electrostatic energy, which is overpowered by the osmotic repulsion among the counterions, as the latter can be well estimated by an ideal-gas approximation. We also provide an optional algorithm that enables counterion mixing between the two counterion clouds even when the clouds do not overlap. The residual mixing entropy of counterions gives a reduction in free energy that is comparable to the thermal fluctuation, suggesting a possible attractive mechanism between the colloidal particles under non-equilibrium condition.

  13. High-precision gigahertz-to-terahertz spectroscopy of aqueous salt solutions as a probe of the femtosecond-to-picosecond dynamics of liquid water

    E-Print Network [OSTI]

    Vinh, N Q; Allen, S James; George, D K; Rahmani, A J; Plaxco, Kevin W

    2015-01-01T23:59:59.000Z

    Because it is sensitive to fluctuations occurring over femtoseconds to picoseconds, gigahertz-to-terahertz dielectric relaxation spectroscopy can provide a valuable window into water's most rapid intermolecular motions. In response, we have built a vector network analyzer dielectric spectrometer capable of measuring absorbance and index of refraction in this frequency regime with unprecedented precision. Using this to determine the complex dielectric response of water and aqueous salt solutions from 5.9 GHz to 1.12 THz (which we provide in the SI), we have obtained strong new constraints on theories of water's collective dynamics. For example, while the salt-dependencies we observe for water's two slower relaxations (8 and 1 ps) are easily reconciled with suggestions that they arise due to rotations of fully and partially hydrogen bonded molecules, respectively, the salt-dependence of the fastest relaxation (180 fs) appears difficult to reconcile with its prior assignment to liberations of single hydrogen bon...

  14. A new equation of state of salt-free flexible-chain polyelectrolyte solution: phase equilibria and osmotic pressure

    E-Print Network [OSTI]

    Yu. A. Budkov; A. L. Kolesnikov; N. Georgi; E. A. Nogovitsyn; M. G. Kiselev

    2015-01-06T23:59:59.000Z

    We develop a first-principle equation of state of salt-free polyelectrolyte solution in the limit of infinitely long flexible polymer chains in the framework of a field-theoretical formalism beyond the linear Debye-Hueckel theory and predict a liquid-liquid phase separation induced by strong correlation attraction. As a reference system we choose a set of two independent ideal subsystems -- charged macromolecules immersed in a structureless oppositely charged background created by counterions (polymer one component plasma) and couterions immersed in oppositely charged background created by polymer chains (hard-core one component plasma). We calculate the excess free energy of polymer one component plasma in the framework of Modified Random Phase Approximation, whereas a contribution of charge densities fluctuations of neutralizing backgrounds we evaluate at the level of Gaussian approximation. We show that our theory is in a very good agreement with the results of Monte-Carlo and MD simulations for critical parameters of liquid-liquid phase separation and osmotic pressure in a wide range of monomer concentration above the critical point, respectively.

  15. The enhancement of xylose monomer and xylotriose degradation by inorganic salts in aqueous solutions at 180 C

    E-Print Network [OSTI]

    California at Riverside, University of

    compared to treatment with just pressurized hot water at the same temperature. Although the addition, and especially the latter, significantly increased xylose mono- mer and xylotriose degradation in water heated of these inorganic salts produced a significant drop in pH, the degradation rates with salts were much faster than

  16. ACTINIDE-SPECIFIC SEQUESTERING AGENTS AND DECONTAMINATION APPLICATIONS

    E-Print Network [OSTI]

    Smith, William L.

    2013-01-01T23:59:59.000Z

    SEQUESTERING AGENTS AND DECONTAMINATION APPLICATIONS WilliamSequestering Agents and Decontamination Applications by

  17. Persistence and decontamination of surrogate radioisotopes in a model drinking water distribution system

    SciTech Connect (OSTI)

    Szabo, Jeffrey G.; Impellitteri, Christopher A.; Govindaswamy, Shekar; Hall, John S.; (EPA); (Lakeshore)

    2010-01-12T23:59:59.000Z

    Contamination of a model drinking water system with surrogate radioisotopes was examined with respect to persistence on and decontamination of infrastructure surfaces. Cesium and cobalt chloride salts were used as surrogates for cesium-137 and cobalt-60. Studies were conducted in biofilm annular reactors containing heavily corroded iron surfaces formed under shear and constantly submerged in drinking water. Cesium was not detected on the corroded iron surface after equilibration with 10 and 100 mg L{sup -1} solutions of cesium chloride, but cobalt was detected on corroded iron coupons at both initial concentrations. The amount of adhered cobalt decreased over the next six weeks, but was still present when monitoring stopped. X-ray absorption near-edge spectroscopy (XANES) showed that adhered cobalt was in the III oxidation state. The adsorbed cobalt was strongly resistant to decontamination by various physicochemical methods. Simulated flushing, use of free chlorine and dilute ammonia were found to be ineffective whereas use of aggressive methods like 14.5 M ammonia and 0.36 M sulfuric acid removed 37 and 92% of the sorbed cobalt, respectively.

  18. DECONTAMINATION FACTORS AND FILTRATION FLUX IMPACT TO ARP AT REDUCED MST CONCENTRATION

    SciTech Connect (OSTI)

    Hobbs, D.

    2012-06-27T23:59:59.000Z

    Tank Farm and Closure Engineering is evaluating changes to the Actinide Removal Process facility operations to decrease the MST concentration from 0.4 g/L to 0.2 g/L and the contact time from 12 hours to between 6 and 8 hours. For this evaluation, SRNL reviewed previous datasets investigating the performance of MST at 0.2 g/L in salt solutions ranging from 4.5 to 7.5 M in sodium concentration. In general, reducing the MST concentration from 0.4 to 0.2 g/L and increasing the ionic strength from 4.5 to 7.5 M in sodium concentration will decrease the measured decontamination factors for plutonium, neptunium, uranium and strontium. The decontamination factors as well as single standard deviation values for each sorbate are reported. These values are applicable within the sorbate and sodium concentrations used in the experimental measurements. Decreasing the MST concentration in the ARP from 0.4 g/L to 0.2 g/L will produce an increase in the filter flux, and could lead to longer operating times between filter cleaning. The increase in flux is a function of a number of operating parameters, and is difficult to quantify. However, it is estimated that the reduction in MST could result in a reduction of filtration time of up to 20%.

  19. Ethidium Bromide: Disposal, Decontamination, and Destruction

    E-Print Network [OSTI]

    Jia, Songtao

    Ethidium Bromide: Disposal, Decontamination, and Destruction Procedure: 8.03 Created: 2 #12;Ethidium Bromide: Disposal, Decontamination, and Destruction Procedure: 8.03 Created: 2

  20. Uranium Enrichment Decontamination and Decommissioning Fund's...

    Office of Environmental Management (EM)

    Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2008 and 2007 Financial Statement Audit, OAS-FS-10-05 Uranium Enrichment Decontamination and...

  1. An evaluation of membrane materials for the treatment of highly concentrated suspended salt solutions in reverse osmosis and nanofiltration processes for desalination

    E-Print Network [OSTI]

    Hughes, Trenton Whiting

    2009-05-15T23:59:59.000Z

    of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2006 Major Subject: Civil Engineering AN EVALUATION OF MEMBRANE MATERIALS FOR THE TREATMENT OF HIGHLY... CONCENTRATED SUSPENDED SALT SOLUTIONS IN REVERSE OSMOSIS AND NANOFILTRATION PROCESSES FOR DESALINATION A Thesis by TRENTON WHITING HUGHES Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment...

  2. Cement-Lock for Decontaminating

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Cement-Lock® Technology for Decontaminating Dredged Estuarine Sediments Topical Report N O L O G Y I N S T I T U T E Cement-Lock Demo Plant Prepared by: Michael C. Mensinger GAS conducted as part of the overall program "Cement-Lock®1 Technology for Decontaminating Dredged Estuarine

  3. Fast Track Dredged Material Decontamination

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Fast Track Dredged Material Decontamination Demonstration for the Port of New York and New Jersey Department of Energy Brookhaven National Laboratory Fast Track Dredged Material Decontamination Demonstration .............................................................................. 3 3.3 Relation to the U.S. Army Corps of Engineers-New York District Dredged Material Management

  4. Integrated decontamination process for metals

    DOE Patents [OSTI]

    Snyder, Thomas S. (Oakmont, PA); Whitlow, Graham A. (Murrysville, PA)

    1991-01-01T23:59:59.000Z

    An integrated process for decontamination of metals, particularly metals that are used in the nuclear energy industry contaminated with radioactive material. The process combines the processes of electrorefining and melt refining to purify metals that can be decontaminated using either electrorefining or melt refining processes.

  5. Decontamination of the Shaft no.1 and cleaning container of 2. block NPP Paks

    SciTech Connect (OSTI)

    Bolcha, Jan; Mala, Zuzana [VUJE Trnava, Inc. (Slovakia); Tilky, Peter [NPP Paks PA Zrt. (Hungary)

    2007-07-01T23:59:59.000Z

    Available in abstract form only. Full text of publication follows: Meanwhile cleaning fuel assemblies on Paks NPP Unit 2. in 2003 year, the fuel assemblies were damaged, followed by contamination of cleaning container and operating shaft No. 1., in which was the container. As a part of the task - to restore operation NPP Paks, Unit 2, VUJE and.. realized decontamination of the wall of shaft prior to withdrawal of the defected fuel, decontamination of cleaning tank and in consequence decontamination of full shaft No. 1. Solution rest at finished conceptual decontamination proposal, fabrication of special purpose furnished, necessary documentation according to national legislative exigency. Real facilities on decontamination were examined on the stand and on shaft No. 1 in real conditions. This paper describes access method decontaminating procedure, applied facilities assigned on decontamination and present achievement results from decontamination shaft No. 1 realized in August 2006 and February 2007, respectively. Decontamination procedures were chosen on the base of experiments realized in laboratories VUJE and in Paks NPP. Laboratory experiments were realized on the sample of tube used for measurement of neutron flow, from NPP Paks, located in the shaft No.1 in time of event (INES-3). In NPP Paks were realized experiments on cover of cleaning container, which was in time of event situated on cleaning container. To compare decontaminated factors, the chemical and electrochemical procedures for decontamination were tested, and most effective practices were selected. Equipment ROS-740 can be used for the top part of the shaft decontamination. It allows high-pressure admission, rinse and chemical decontamination. Manipulator MAOS-170 is assigned for high-pressure admission of central part of the shaft. (authors)

  6. Condensation of Self-assembled Lyotropic Chromonic Liquid Crystal Sunset Yellow in Aqueous Solutions Crowded with Polyethylene glycol and Doped with Salt

    E-Print Network [OSTI]

    Heung-Shik Park; Shin-Woong Kang; Luana Tortora; Satyendra Kumar; Oleg D. Lavrentovich

    2011-04-06T23:59:59.000Z

    We use optical and fluorescence microscopy, densitometry, cryo-transmission electron microscopy (cryo-TEM), spectroscopy, and synchrotron X-ray scattering, to study the phase behavior of the reversible self-assembled chromonic aggregates of an anionic dye Sunset Yellow (SSY) in aqueous solutions crowded with an electrically neutral polymer polyethylene glycol (PEG) and doped with the salt NaCl. PEG causes the isotropic SSY solutions to condense into a liquid-crystalline region with a high concentration of SSY aggregates, coexisting with a PEG-rich isotropic (I) region. PEG added to the homogeneous nematic (N) phase causes separation into the coexisting N and I domains; the SSY concentration in the N domains is higher than the original concentration of PEG-free N phase. Finally, addition of PEG to the highly concentrated homogeneous N phase causes separation into the coexisting columnar hexagonal (C) phase and I phase. This behavior can be qualitatively explained by the depletion (excluded volume) effects that act at two different levels: at the level of aggregate assembly from monomers and short aggregates and at the level of inter-aggregate packing. We also show a strong effect of a monovalent salt NaCl on phase diagrams that is different for high and low concentrations of SSY. Upon the addition of salt, dilute I solutions of SSY show appearance of the condensed N domains, but the highly concentrated C phase transforms into a coexisting I and N domains. We suggest that the salt-induced screening of electric charges at the surface of chromonic aggregates leads to two different effects: (a) increase of the scission energy and the contour length of aggregates, and (b) decrease of the persistence length of SSY aggregates.

  7. Innovative Laser Ablation Technology for Surface Decontamination

    SciTech Connect (OSTI)

    Chen, Winston C. H.

    2003-06-01T23:59:59.000Z

    The objective of this project is to develop a novel laser ablation in liquid for surface decontamination. It aims to achieve more efficient surface decontamination without secondary contamination. Another aim is to make this surface decontamination technology becomes economically feasible for large scale decontamination.

  8. Actinide removal from spent salts

    DOE Patents [OSTI]

    Hsu, Peter C. (Pleasanton, CA); von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

    2002-01-01T23:59:59.000Z

    A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.

  9. Metals removal from spent salts

    DOE Patents [OSTI]

    Hsu, Peter C. (Pleasanton, CA); Von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Brummond, William A. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

    2002-01-01T23:59:59.000Z

    A method and apparatus for removing metal contaminants from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents may be added to precipitate the metal oxide and/or the metal as either metal oxide, metal hydroxide, or as a salt. The precipitated materials are filtered, dried and packaged for disposal as waste or can be immobilized as ceramic pellets. More than about 90% of the metals and mineral residues (ashes) present are removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be spray-dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 1.0 ppm of contaminants.

  10. Active Waste Materials Corrosion and Decontamination Tests

    SciTech Connect (OSTI)

    MJ Danielson; MR Elmore; SG Pitman

    2000-08-15T23:59:59.000Z

    Stainless steel alloys, 304L and 316L, were corrosion tested in representative radioactive samples of three actual Hanford tank waste solutions (Tanks AW-101, C-104, AN-107). Both the 304L and 316L exhibited good corrosion performance when immersed in boiling waste solutions. The maximum general corrosion rate was 0.015 mm/y (0.60 mils per year). Generally, the 304L had a slightly higher rate than the 316L. No localized attack was observed after 122 days of testing in the liquid phase, liquid/vapor phase, or vapor phase. Radioactive plate-out decontamination tests indicated that a 24-hour exposure to 1 {und M} HNO{sub 3} could remove about 99% of the radioactive components in the metal film when exposed to the C-104 and AN-107 solutions. The decontamination results are less certain for the AW-101 solution, since the initial contamination readings exceeded the capacity of the meter used for this test.

  11. Glovebox decontamination technology comparison

    SciTech Connect (OSTI)

    Quintana, D.M.; Rodriguez, J.B.; Cournoyer, M.E.

    1999-09-26T23:59:59.000Z

    Reconfiguration of the CMR Building and TA-55 Plutonium Facility for mission requirements will require the disposal or recycle of 200--300 gloveboxes or open front hoods. These gloveboxes and open front hoods must be decontaminated to meet discharge limits for Low Level Waste. Gloveboxes and open front hoods at CMR have been painted. One of the deliverables on this project is to identify the best method for stripping the paint from large numbers of gloveboxes. Four methods being considered are the following: conventional paint stripping, dry ice pellets, strippable coatings, and high pressure water technology. The advantages of each technology will be discussed. Last, cost comparisons between the technologies will be presented.

  12. Granulated decontamination formulations

    DOE Patents [OSTI]

    Tucker, Mark D. (Albuquerque, NM)

    2007-10-02T23:59:59.000Z

    A decontamination formulation and method of making that neutralizes the adverse health effects of both chemical and biological compounds, especially chemical warfare (CW) and biological warfare (BW) agents, and toxic industrial chemicals. The formulation provides solubilizing compounds that serve to effectively render the chemical and biological compounds, particularly CW and BW compounds, susceptible to attack, and at least one reactive compound that serves to attack (and detoxify or kill) the compound. The formulation includes at least one solubilizing agent, a reactive compound, a sorbent additive, and water. A highly adsorbent sorbent additive (e.g., amorphous silica, sorbitol, mannitol, etc.) is used to "dry out" one or more liquid ingredients into a dry, free-flowing powder that has an extended shelf life, and is more convenient to handle and mix in the field.

  13. Development of a Model to Compare Emergency Chemical Decontamination Methods

    E-Print Network [OSTI]

    Bradley, Richard N; Huff, Ester N

    2008-01-01T23:59:59.000Z

    Emergency Chemical Decontamination Methods Richard N.the clothing even after decontamination. Additionally, whileon the skin before decontamination, we found significant

  14. UV Decontamination of MDA Reagents for Single Cell Genomics

    E-Print Network [OSTI]

    Lee, Janey

    2011-01-01T23:59:59.000Z

    UV Decontamination of MDA Reagents for Single Cell Genomicsof California. UV Decontamination of MDA Reagents for Singleand highly efficient decontamination method of MDA reagents

  15. Impact of Decontamination Therapy on Ultrasound Visualization of Ingested Pills

    E-Print Network [OSTI]

    Bothwell, Jason; Skinner, Carl; Della-Giustina, David; Kang, Christopher; Cookman, Laura; Laselle, Brooks

    2014-01-01T23:59:59.000Z

    R esearch Impact of Decontamination Therapy on Ultrasoundused for gastric decontamination on examiners’ ability toet al Impact of Decontamination Therapy often required to

  16. Large-bore pipe decontamination

    SciTech Connect (OSTI)

    Ebadian, M.A.

    1998-01-01T23:59:59.000Z

    The decontamination and decommissioning (D and D) of 1200 buildings within the US Department of Energy-Office of Environmental Management (DOE-EM) Complex will require the disposition of miles of pipe. The disposition of large-bore pipe, in particular, presents difficulties in the area of decontamination and characterization. The pipe is potentially contaminated internally as well as externally. This situation requires a system capable of decontaminating and characterizing both the inside and outside of the pipe. Current decontamination and characterization systems are not designed for application to this geometry, making the direct disposal of piping systems necessary in many cases. The pipe often creates voids in the disposal cell, which requires the pipe to be cut in half or filled with a grout material. These methods are labor intensive and costly to perform on large volumes of pipe. Direct disposal does not take advantage of recycling, which could provide monetary dividends. To facilitate the decontamination and characterization of large-bore piping and thereby reduce the volume of piping required for disposal, a detailed analysis will be conducted to document the pipe remediation problem set; determine potential technologies to solve this remediation problem set; design and laboratory test potential decontamination and characterization technologies; fabricate a prototype system; provide a cost-benefit analysis of the proposed system; and transfer the technology to industry. This report summarizes the activities performed during fiscal year 1997 and describes the planned activities for fiscal year 1998. Accomplishments for FY97 include the development of the applicable and relevant and appropriate regulations, the screening of decontamination and characterization technologies, and the selection and initial design of the decontamination system.

  17. Efficacy of a solution-based approach for making sodalite waste forms for an oxide reduction salt utilized in the reprocessing of used uranium oxide fuel

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Riley, Brian J.; Pierce, David A.; Frank, Steven M.; Matyáš, Josef; Burns, Carolyne A.

    2015-04-01T23:59:59.000Z

    This paper describes the various approaches attempted to make solution-derived sodalite with a LiCl-Li2O oxide reduction salt used to dissolve used uranium oxide fuel so the uranium can be recovered and recycled. The approaches include modified sol-gel and solutionbased synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3- SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2Omore »and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions in the crystalline product (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt but that the incorporation of Li into the sodalite is low.« less

  18. Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Used in the Reprocessing of Used Uranium Oxide Fuel

    SciTech Connect (OSTI)

    Brian J. Riley; David A. Pierce; Steven M. Frank; Josef Matyas; Carolyne A. Burns

    2014-09-01T23:59:59.000Z

    This paper describes the various approaches attempted to make solution-derived sodalite with a LiCl-Li2O oxide reduction salt used to dissolve used uranium oxide fuel so the uranium can be recovered and recycled. The approaches include modified sol-gel and solutionbased synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3- SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2O and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions in the crystalline product (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt but that the incorporation of Li into the sodalite is low.

  19. Microstructure and corrosion behavior of die-cast AM60B magnesium alloys in a complex salt solution: A slow positron beam study

    SciTech Connect (OSTI)

    Liu, Y.F. [Wuhan University] [Wuhan University; Qin, Q.L. [Wuhan University] [Wuhan University; Yang, W. [Wuhan University] [Wuhan University; Wen, W. [University of Kentucky] [University of Kentucky; Zhai, T. [University of Kentucky] [University of Kentucky; Yu, B. [University of Alberta] [University of Alberta; Liu, D.Y. [University of Alberta] [University of Alberta; Luo, A. [GM Research and Development Center] [GM Research and Development Center; Song, GuangLing [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    The microstructure and corrosion behavior of high pressure die-cast (HPDC) and super vacuum die-cast (SVDC) AM60B magnesium alloys were investigated in a complex salt solution using slow positron beam technique and potentiodynamic polarization tests. The experiments revealed that a CaCO3 film was formed on the surface of the alloys and that the rate of CaCO3 formation for the SVDC alloy with immersion time was slower than that of the HPDC alloy. The larger volume fraction of b-phase in the skin layer of the SVDC alloy than that of the HPDC alloy was responsible for the better corrosion resistance.

  20. Electrostatic self-energy of a partially formed spherical shell in salt solution: application to stability of tethered and fluid shells -- viruses and vesicles

    E-Print Network [OSTI]

    Anze Losdorfer Bozic; Antonio Siber; Rudolf Podgornik

    2011-04-24T23:59:59.000Z

    We investigate the electrostatics of a partially formed, charged spherical shell in a salt solution. We solve the problem numerically at the Poisson-Boltzmann level and analytically in the Debye-Huckel regime. From the results on energetics of partially formed shells we examine the stability of tethered (crystalline) and fluid shells towards rupture. We clearly delineate different regimes of stability towards rupture, where, for fluid shells, we also include the effects of bending elasticity of the shells. Our analysis shows how charging of the shell induces its instability towards rupture but also provides insight regarding growth of charged shells.

  1. Ion Partitioning at the liquid/vapor interface of a multi-component alkali halide solution: A model for aqueous sea salt aerosols

    E-Print Network [OSTI]

    Ghosal, Sutapa

    2009-01-01T23:59:59.000Z

    A model for aqueous sea salt aerosols Sutapa Ghosal, 1species associated with sea salt ice and aerosols has beena minor component in sea salt, which has a Br – /Cl – molar

  2. Health physics and industrial hygiene aspects of decontamination as a precursor to decontamination

    SciTech Connect (OSTI)

    Card, C.J.; Hoenes, G.R.; Munson, L.F.; Halseth, G.A.

    1982-06-01T23:59:59.000Z

    The Pacific Northwest Laboratory is conducting a comprehensive study of the impacts, benefits and effects of decontamination as a precursor to decommissioning for the US Nuclear Regulatory Commission. The program deals primarily with chemical cleaning of light-water reactor (LWR) systems that will not be returned to operation. A major section of this study defines the health physics and industrial hygiene and safety concerns during decontamination operations. The primary health physics concerns include providing adequate protection for workers from radiation sources which are transported by the decontamination processes, estimating and limiting radioactive effluents to the environment and maintaining operations in accordance with the ALARA philosophy. Locating and identifying the areas of contamination and measuring the radiation exposure rates throughout the reactor primary system are fundamental to implementing these health physics goals. The principal industrial hygiene and safety concerns stem from the fact that a nuclear power plant is being converted for a time to a chemical plant which will contain large volumes of chemical solutions.

  3. Development of decontamination procedures for beef trimmings

    E-Print Network [OSTI]

    Ebeling, Christine Suzanne

    2001-01-01T23:59:59.000Z

    in the decontamination of beef trimmings without adversely effecting ground beef shelf-life and flavor attributes....

  4. Decontamination of the Curium Source Fabrication Facility

    SciTech Connect (OSTI)

    Schaich, R.W.

    1982-01-01T23:59:59.000Z

    The Curium Source Fabrication Facility (CSFF) at Oak Ridge National Laboratory (ORNL) was decontaminated to acceptable contamination levels for maintenance activities, using standard decontamination techniques. Solid- and liquid-waste volumes were controlled to minimize discharge to the ORNL Waste Systems. This program required two years of decontamination effort at a total cost of $580K.

  5. Decontaminating Human Judgments by Removing Sequential Dependencies

    E-Print Network [OSTI]

    Mozer, Michael C.

    Decontaminating Human Judgments by Removing Sequential Dependencies Michael C. Mozer, Harold, and thereby decontaminate a series of ratings to obtain more meaningful human judgments. In our formulation, decontamination is fun- damentally a problem of inferring latent states (internal sensations) which, be- cause

  6. Blind Pilot Decontamination Ralf R. Mller

    E-Print Network [OSTI]

    Müller, Ralf R.

    Blind Pilot Decontamination Ralf R. Müller Institute for Digital Communications Friedrich and interference. Ralf Müller (FAU) 14-Mar-2013 2 / 16 #12;Introduction Pilot (De-)Contamination For T transmit estimation. Ralf Müller (FAU) 14-Mar-2013 3 / 16 #12;Introduction Pilot (De-)Contamination For T transmit

  7. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    care facility-based decontamination of victims exposed tofirst undergoing field decontamination. This article reviewsfacility-based decontamination, including regulatory

  8. Commercializationof Dredged-Material Decontamination

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Commercializationof Dredged- Material Decontamination Technologies Keitb U?Jones isa senior Keith375,000 mdmmnentalm@m*ng m3 of dredged material per year. The need to develop public-priuate p r o g r assessmentsand dredged materialmanagemart. He istbe tecbnfcalprogram managerfor tbe WRM NXm Harbor Sediment

  9. Pipe and hose decontamination apparatus

    SciTech Connect (OSTI)

    Fowler, D.E.

    1985-03-12T23:59:59.000Z

    A pipe and hose decontamination apparatus is disclosed using freshly filtered high pressure Freon solvent in an integrated closed loop to remove radioactive particles or other contaminants from items having a long cylindrical geometry such as hoses, pipes, cables and the like. The pipe and hose decontamination apparatus comprises a chamber capable of accomodating a long cylindrical work piece to be decontaminated. The chamber has a downward sloped bottom draining to a solvent holding tank. An entrance zone, a cleaning zone and an exit drying zone are defined within the chamber by removable partitions having slotted rubber gaskets in their centers. The entrance and exit drying zones contain a horizontally mounted cylindrical housing which supports in combination a plurality of slotted rubber gaskets and circular brushes to initiate mechanical decontamination. Solvent is delivered at high pressure to a spray ring located in the cleaning zone having a plurality of nozzles surrounding the work piece. The solvent drains into a solvent holding tank located below the nozzles and means are provided for circulating the solvent to and from a solvent cleaning, distilling and filter unit.

  10. Surface Decontamination of System Components in Uranium Conversion Plant at KAERI

    SciTech Connect (OSTI)

    Choi, W. K.; Kim, K. N.; Won, H. J.; Jung, C. H.; Oh, W. Z.

    2003-02-25T23:59:59.000Z

    A chemical decontamination process using nitric acid solution was selected as in-situ technology for recycle or release with authorization of a large amount of metallic waste including process system components such as tanks, piping, etc., which is generated by dismantling a retired uranium conversion plant at Korea Atomic Energy Research Institute (KAERI). The applicability of nitric acid solution for surface decontamination of metallic wastes contaminated with uranium compounds was evaluated through the basic research on the dissolution of UO2 and ammonium uranyl carbonate (AUC) powder. Decontamination performance was verified by using the specimens contaminated with such uranium compounds as UO2 and AUC taken from the uranium conversion plant. Dissolution rate of UO2 powder is notably enhanced by the addition of H2O2 as an oxidant even in the condition of a low concentration of nitric acid and low temperature compared with those in a nitric acid solution without H2O2. AUC powders dissolve easily in nitric acid solutions until the solution pH attains about 2.5 {approx} 3. Above that solution pH, however, the uranium concentration in the solution is lowered drastically by precipitation as a form of U3(NH3)4O9 . 5H2O. Decontamination performance tests for the specimens contaminated with UO2 and AUC were quite successful with the application of decontamination conditions obtained through the basic studies on the dissolution of UO2 and AUC powders.

  11. Uranium enrichment decontamination and decommissioning fund

    SciTech Connect (OSTI)

    NONE

    1994-12-31T23:59:59.000Z

    One of the most challenging issues facing the Department of Energy`s Office of Environmental Management is the cleanup of the three gaseous diffusion plants. In October 1992, Congress passed the Energy Policy Act of 1992 and established the Uranium Enrichment Decontamination and Decommissioning Fund to accomplish this task. This mission is being undertaken in an environmentally and financially responsible way by: devising cost-effective technical solutions; producing realistic life-cycle cost estimates, based on practical assumptions and thorough analysis; generating coherent long-term plans which are based on risk assessments, land use, and input from stakeholders; and, showing near-term progress in the cleanup of the gaseous diffusion facilities at Oak Ridge.

  12. Precipitation of jarosite-type double salts from spent acid solutions from a chemical coal cleaning process

    SciTech Connect (OSTI)

    Norton, G.

    1990-09-21T23:59:59.000Z

    The precipitation of jarosite compounds to remove Na, K, Fe, and SO{sub 4}{sup 2{minus}} impurities from spent acid solutions from a chemical coal cleaning process was studied. Simple heating of model solutions containing Fe{sub 2}(SO{sub 4}){sub 3}, Na{sub 2}SO{sub 4}, and K{sub 2}SO{sub 4} caused jarosite (KFe{sub 3}(SO{sub 4}){sub 2}(OH){sub 6}) to form preferentially to natrojarosite (NaFe{sub 3}(SO{sub 4}){sub 2}(OH){sub 6}). Virtually all of the K, about 90% of the Fe, and about 30% of the SO{sub 4}{sup 2{minus}} could be precipitated from those solutions at 95{degree}C, while little or no Na was removed. However, simple heating of model solutions containing only Fe{sub 2}(SO{sub 4}){sub 3} and Na{sub 2}SO{sub 4} up to 95{degree}C for {le}12 hours produced low yields of jarosite compounds, and the Fe concentration in the solution had to be increased to avoid the formation of undesirable Fe compounds. Precipitate yields could be increased dramatically in model solutions of Na{sub 2}SO{sub 4}/Fe{sub 2}(SO{sub 4}){sub 3} containing excess Fe by using either CaCO{sub 3}, Ca(OH){sub 2}, or ZnO to neutralize H{sub 2}SO{sub 4} released during hydrolysis of the Fe{sub 2}(SO{sub 4}){sub 3} and during the precipitation reactions. Results obtained from the studies with model solutions were applied to spent acids produced during laboratory countercurrent washing of coal which had been leached with a molten NaOH/KOH mixture. Results indicated that jarosite compounds can be precipitated effectively from spent acid solutions by heating for 6 hours at 80{degree}C while maintaining a pH of about 1.5 using CaCO{sub 3}.

  13. Foam and gel methods for the decontamination of metallic surfaces

    DOE Patents [OSTI]

    Nunez, Luis; Kaminski, Michael Donald

    2007-01-23T23:59:59.000Z

    Decontamination of nuclear facilities is necessary to reduce the radiation field during normal operations and decommissioning of complex equipment. In this invention, we discuss gel and foam based diphosphonic acid (HEDPA) chemical solutions that are unique in that these solutions can be applied at room temperature; provide protection to the base metal for continued applications of the equipment; and reduce the final waste form production to one step. The HEDPA gels and foams are formulated with benign chemicals, including various solvents, such as ionic liquids and reducing and complexing agents such as hydroxamic acids, and formaldehyde sulfoxylate. Gel and foam based HEDPA processes allow for decontamination of difficult to reach surfaces that are unmanageable with traditional aqueous process methods. Also, the gel and foam components are optimized to maximize the dissolution rate and assist in the chemical transformation of the gel and foam to a stable waste form.

  14. New Waste Calcining Facility Non-Radioactive Process Decontamination

    SciTech Connect (OSTI)

    Swenson, Michael C.

    2001-09-30T23:59:59.000Z

    This report documents the results of a test of the New Calcining Facility (NWCF) process decontamination system. The decontamination system test occurred in December 1981, during non-radioactive testing of the NWCF. The purpose of the decontamination system test was to identify equipment whose design prevented effective calcine removal and decontamination. Effective equipment decontamination was essential to reduce radiation fields for in-cell work after radioactive processing began. The decontamination system test began with a pre-decontamination inspection of the equipment. The pre- decontamination inspection documented the initial condition and cleanliness of the equipment. It provided a basis for judging the effectiveness of the decontamination. The decontamination consisted of a series of equipment flushes using nitric acid and water. A post-decontamination equipment inspection determined the effectiveness of the decontamination. The pre-decontamination and post-decontamination equipment inspections were documented with photographs. The decontamination system was effective in removing calcine from most of the NWCF equipment as evidenced by little visible calcine residue in the equipment after decontamination. The decontamination test identified four areas where the decontamination system required improvement. These included the Calciner off-gas line, Cyclone off-gas line, fluidizing air line, and the Calciner baffle plates. Physical modifications to enhance decontamination were made to those areas, resulting in an effective NWCF decontamination system.

  15. New Waste Calcining Facility Non-radioactive Process Decontamination

    SciTech Connect (OSTI)

    Swenson, Michael Clair

    2001-09-01T23:59:59.000Z

    This report documents the results of a test of the New Calcining Facility (NWCF) process decontamination system. The decontamination system test occurred in December 1981, during non-radioactive testing of the NWCF. The purpose of the decontamination system test was to identify equipment whose design prevented effective calcine removal and decontamination. Effective equipment decontamination was essential to reduce radiation fields for in-cell work after radioactive processing began. The decontamination system test began with a pre-decontamination inspection of the equipment. The pre-decontamination inspection documented the initial condition and cleanliness of the equipment. It provided a basis for judging the effectiveness of the decontamination. The decontamination consisted of a series of equipment flushes using nitric acid and water. A post-decontamination equipment inspection determined the effectiveness of the decontamination. The pre-decontamination and post-decontamination equipment inspections were documented with hotographs. The decontamination system was effective in removing calcine from most of the NWCF equipment as evidenced by little visible calcine residue in the equipment after decontamination. The decontamination test identified four areas where the decontamination system required improvement. These included the Calciner off-gas line, Cyclone off-gas line, fluidizing air line, and the Calciner baffle plates. Physical modifications to enhance decontamination were made to those areas, resulting in an effective NWCF decontamination system.

  16. Voltammetry and conductivity of a polyether-pyridinium room temperature molten salt electrolyte and of its polymer electrolyte solutions in polydimethylsiloxane

    SciTech Connect (OSTI)

    Pyati, R.; Murray, R.W. [Univ. of North Carolina, Chapel Hill, NC (United States)

    1996-02-01T23:59:59.000Z

    This report describes the synthesis, microelectrode voltammetry, and ionic conductivity of a new room temperature molten salt N-(methoxy(ethoxy){sub 2}ethyl)pyridinium p-toluene sulfonate (abbreviated as[Py(E{sub 3}M){sup +}][Tos{sup {minus}}]) and of its solution in a hydroxy-terminated polydimethylsiloxane. Both ionically conductive liquids (conductivity = 1 {times} 10{sup {minus}4} {Omega}{sup {minus}1} cm{sup {minus}1}) exhibit voltammetric potential windows of about 1.5 V. The negative potential limit is determined by the reduction of the [Py(E{sub 3}M){sup +}] pyridinium species, with subsequent radical coupling to form a voltammetrically observed viologen dimer. The estimated diffusivities of the [Py(E{sub 3}M){sup +}] species, of a diethyleneglycol-tailed ferrocene redox solute studied, and by application of Nernst-Einstein relation to the ionic charge carriers, all lie in the 10{sup {minus}7} to 10{sup {minus}8} cm{sup 2}/s range. Viscosities and glass transition thermal observations are reported as is the fit of the temperature dependencies of ionic conductivity in [Py(E{sub 3}M){sup +}][Tos{sup {minus}}] and in [Py(E{sub 3}M){sup +}][TOS{sup {minus}}]/PDMS mixtures to Vogel-Tamman-Fulcher predictions.

  17. Salt Concentration Differences Alter Membrane Resistance in Reverse Electrodialysis Stacks

    E-Print Network [OSTI]

    Salt Concentration Differences Alter Membrane Resistance in Reverse Electrodialysis Stacks Geoffrey is usually measured by immersing the membrane in a salt solution at a single, fixed concentration. While salt resistance of the membranes separating different salt concentration solutions has implications for modeling

  18. Electrokinetic decontamination of concrete

    SciTech Connect (OSTI)

    Lomasney, H.L.; SenGupta, A.K.; Yachmenev, V.

    1996-12-31T23:59:59.000Z

    ELECTROSORB Electrokinetic Extraction Technology, developed by ISOTRON Corp., offers a cost-effective approach to treating contaminated concrete. Heavy metals/radionuclides trapped in concrete can be extracted using this process if they are chemically solubilized; solubilizers used are citric acid alone and a mixture of citric and nitric acids. A DC electric field is applied across the contaminated concrete to electrokinetically transport the solubilized contaminants from the concrete pores to a collector on the concrete surface. The collector is an extraction pad laid on the surface. The pad provides confinement for a planar electrode and solubilizer solution; it is operated under a vacuum to hold the pad against the concrete surface. Operation requires little attendance, reducing the workers` health hazards. The process incorporates a mechanism for recycling the solubilizer solution. A field demonstration of the process took place in Building 21 of DOE`s Mound facility in Miamisburg, OH, over 12 days in June 1996. The thorium species present in this building`s concrete floors included ThO{sub 2} and thorium oxalate. The nitric acid was found to facilitate Th extraction.

  19. Initiation of nuclear reactions under laser irradiation of Au nanoparticles in the aqueous solution of Uranium salt

    E-Print Network [OSTI]

    A. V. Simakin; G. A. Shafeev

    2009-11-29T23:59:59.000Z

    Laser exposure of suspension of either gold or palladium nanoparticles in aqueous solutions of UO2Cl2 of natural isotope abundance was experimentally studied. Picosecond Nd:YAG lasers at peak power from 1011 to 1013 W/cm2 at the wavelength of 1064 and 355 nm were used as well as a visible-range Cu vapor laser at peak power of 1010 W/cm2. The composition of colloidal solutions before and after laser exposure was analyzed using atomic absorption and gamma spectroscopy between 0.06 and 1 MeV range of photon energy. A real-time gamma-spectroscopy was used to characterize the kinetics of nuclear reactions during laser exposure. It was found that laser exposure initiated nuclear reactions involving both 238U and 235U nuclei via different channels in H2O and D2O. The influence of saturation of both the liquid and nanoparticles by gaseous H2 and D2 on the kinetics of nuclear transformations was found. Possible mechanisms of observed processes are discussed.

  20. SOLUTIONS

    E-Print Network [OSTI]

    2012-07-04T23:59:59.000Z

    MA 162 - Quiz 5 (20 minutes). SOLUTIONS. The solutions I present are not necessarily the only solutions. As long as you give a correct method of solving a ...

  1. Decontamination of a canyon crane at the Savannah River Plant

    SciTech Connect (OSTI)

    Stevenson, D A; Moore, D B; Bowers, J W; Brown, D L

    1985-01-01T23:59:59.000Z

    Decontamination of the crane is reviewed in terms of the health physics aspects, controls during decontamination efforts, and the resultant radiation exposure rates for decontamination efforts. 17 figs., (ACR)

  2. Nitrogen Atmospheric Pressure Post Discharges for Surface Biological Decontamination inside

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Nitrogen Atmospheric Pressure Post Discharges for Surface Biological Decontamination inside Small) (PET) capillary tubes of different shapes and lengths and decontamination of flow tubes, both for several years at the Orsay Plasma Lab. Its biological decontamination efficiency has been demonstrated

  3. UV Decontamination of MDA Reagents for Single Cell Genomics

    E-Print Network [OSTI]

    Lee, Janey

    2011-01-01T23:59:59.000Z

    UV Decontamination of MDA Reagents for Single Cell GenomicsUV Decontamination of MDA Reagents for Single Cell Genomicsdisplacement amplification (MDA), which can generate

  4. TREATABILITY STUDIES USED TO TEST FOR EXOTHERMIC REACTIONS OF PLUTONIUM DECONTAMINATION CHEMICALS

    SciTech Connect (OSTI)

    EWALT, J.R.

    2005-06-06T23:59:59.000Z

    Fluor Hanford is decommissioning the Plutonium Finishing Plant (PFP) at the Hanford site in Eastern Washington. Aggressive chemicals are commonly used to remove transuranic contaminants from process equipment to allow disposal as low level waste. Chemicals being considered for decontamination of gloveboxes in PFP include cerium(IV) nitrate in a nitric acid solution, and proprietary commercial solutions that include acids, degreasers, and sequestering agents. Fluor's decontamination procedure involves application of chemical solutions as a spray on the contaminated surfaces, followed by a wipe-down with rags. This process effectively transfers the transuranic materials to the decontamination liquids, which are then absorbed by rags and packaged for disposal as TRU waste. Concerns regarding the safety of this procedure developed following a fire at Rocky Flats in 2003. The fire occurred in a glovebox that had been treated with cerium nitrate, which is one of the decontamination chemicals that Fluor Hanford has proposed to use. The investigation of the event was hampered by the copious use of chemicals and water to extinguish the fire, and was not conclusive regarding the cause. However, the reviewers noted that rags were found in the glovebox, suggesting that the combination of rags and chemicals may have contributed to the fire. With that uncertainty, Fluor began an investigation into the potential for fire when using the chemicals and materials in the decontamination process. The focus of this work has been to develop a disposal strategy that will provide a chemically stable waste form at expected Hanford waste storage temperatures. Treatability tests under CERCLA were used to assess the use of certain chemicals and wipes during the decontamination process. Chemicals being considered for decontamination of gloveboxes at PFP include cerium (IV) nitrate in a nitric acid solution, and proprietary commercial solutions as RadPro{trademark} that include acids, degreasers, and sequestering agents. As part of the treatability study, Fluor and the Pacific Northwest National Laboratory (PNNL) personnel have evaluated the potential for self-heating and exothermic reactions in the residual decontamination materials. Exothermic reactions that release significant heat and off-gas have been discovered for both the cerium nitrate, as seen in a fire at Rocky Flats, and proprietary solutions developed for decontamination purposes. From the treatability studies, certain limiting conditions have been defined that will aid in assuring safe operations and waste packaging during the decommissioning process.

  5. INTEGRATED VERTICAL AND OVERHEAD DECONTAMINATION SYSTEM

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    1999-01-01T23:59:59.000Z

    This report summarizes the activities performed during FY98 and describes the planned activities for FY99. Accomplishments for FY98 include identifying and selecting decontamination, the screening of potential characterization technologies, development of minimum performance factors for the decontamination technology, and development and identification of Applicable, Relevant and Appropriate Regulations (ARARs).

  6. Decontamination formulation with additive for enhanced mold remediation

    DOE Patents [OSTI]

    Tucker, Mark D. (Albuquerque, NM); Irvine, Kevin (Huntsville, AL); Berger, Paul (Rome, NY); Comstock, Robert (Bel Air, MD)

    2010-02-16T23:59:59.000Z

    Decontamination formulations with an additive for enhancing mold remediation. The formulations include a solubilizing agent (e.g., a cationic surfactant), a reactive compound (e.g., hydrogen peroxide), a carbonate or bicarbonate salt, a water-soluble bleaching activator (e.g., propylene glycol diacetate or glycerol diacetate), a mold remediation enhancer containing Fe or Mn, and water. The concentration of Fe.sup.2+ or Mn.sup.2+ ions in the aqueous mixture is in the range of about 0.0001% to about 0.001%. The enhanced formulations can be delivered, for example, as a foam, spray, liquid, fog, mist, or aerosol for neutralization of chemical compounds, and for killing certain biological compounds or agents and mold spores, on contaminated surfaces and materials.

  7. Fundamental Properties of Salts

    SciTech Connect (OSTI)

    Toni Y Gutknecht; Guy L Fredrickson

    2012-11-01T23:59:59.000Z

    Thermal properties of molten salt systems are of interest to electrorefining operations, pertaining to both the Fuel Cycle Research & Development Program (FCR&D) and Spent Fuel Treatment Mission, currently being pursued by the Department of Energy (DOE). The phase stability of molten salts in an electrorefiner may be adversely impacted by the build-up of fission products in the electrolyte. Potential situations that need to be avoided, during electrorefining operations, include (i) fissile elements build up in the salt that might approach the criticality limits specified for the vessel, (ii) electrolyte freezing at the operating temperature of the electrorefiner due to changes in the liquidus temperature, and (iii) phase separation (non-homogenous solution). The stability (and homogeneity) of the phases can be monitored by studying the thermal characteristics of the molten salts as a function of impurity concentration. Simulated salt compositions consisting of the selected rare earth and alkaline earth chlorides, with a eutectic mixture of LiCl-KCl as the carrier electrolyte, were studied to determine the melting points (thermal characteristics) using a Differential Scanning Calorimeter (DSC). The experimental data were used to model the liquidus temperature. On the basis of the this data, it became possible to predict a spent fuel treatment processing scenario under which electrorefining could no longer be performed as a result of increasing liquidus temperatures of the electrolyte.

  8. Tree Decontamination with Temporary Immunity Paola Flocchini1

    E-Print Network [OSTI]

    Mans, Bernard

    Tree Decontamination with Temporary Immunity Paola Flocchini1 , Bernard Mans2 , and Nicola Santoro3, a network site will continuously attempt to spread the virus to all its neighbours. The decontamination, called cleaners, avoiding any recontamination of decontaminated areas. A cleaner is able to decontaminate

  9. Decontamination of large horizontal concrete surfaces outdoors

    SciTech Connect (OSTI)

    Barbier, M.M.; Chester, C.V.

    1980-01-01T23:59:59.000Z

    A study is being conducted of the resources and planning that would be required to clean up an extensive contamination of the outdoor environment. As part of this study, an assessment of the fleet of machines needed for decontaminating large outdoor surfaces of horizontal concrete will be attempted. The operations required are described. The performance of applicable existing equipment is analyzed in terms of area cleaned per unit time, and the comprehensive cost of decontamination per unit area is derived. Shielded equipment for measuring directional radiation and continuously monitoring decontamination work are described. Shielding of drivers' cabs and remote control vehicles is addressed.

  10. The feasibility study of hot cell decontamination by the PFC spray method

    SciTech Connect (OSTI)

    Hui-Jun Won; Chong-Hun Jung; Jei-Kwon Moon [Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yuseong-Gu, Daejeon, 305-353 (Korea, Republic of)

    2008-01-15T23:59:59.000Z

    The characteristics of per-fluorocarbon compounds (PFC) are colorless, non-toxic, easily vaporized and nonflammable. Also, some of them are liquids of a high density, low surface tension, low latent heat and low specific heat. These particular chemical and physical properties of fluoro-organic compounds permit their use in very different fields such as electronics, medicine, tribology, nuclear and material science. The Sonatol process was developed under a contract with the DOE. The Sonatol process uses an ultrasonic agitation in a PFC solution that contains a fluorinated surfactant to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. They applied the Sonatol process to the decontamination of a heterogeneous legacy Pu-238 waste that exhibited an excessive hydrogen gas generation, which prevents a transportation of such a waste to a Waste Isolation Pilot Plant. Korea Atomic Energy Research Institute (KAERI) is developing dry decontamination technologies applicable to a decontamination of a highly radioactive area loosely contaminated with radioactive particles. This contamination has occurred as a result of an examination of a post-irradiated material or the development of the DUPIC process. The dry decontamination technologies developed are the carbon dioxide pellet spray method and the PFC spray method. As a part of the project, PFC ultrasonic decontamination technology was developed in 2004. The PFC spray decontamination method which is based on the test results of the PFC ultrasonic method has been under development since 2005. The developed PFC spray decontamination equipment consists of four modules (spray, collection, filtration and distillation). Vacuum cup of the collection module gathers the contaminated PFC solution, then the solution is moved to the filtration module and it is recycled. After a multiple recycling of the spent PFC solution, it is purified in the distillation module. A performance test on each module was executed and the results have been reported. A combined test of the four modules, however, has not been performed as yet. The main objective of the present study is to demonstrate the feasibility of the full PFC spray decontamination process. Decontamination of the inside of the IMEF hot cell by the PFC spray method was also performed. PFC spray decontamination process was demonstrated by using a surrogate wall contaminated with Eu{sub 2}O{sub 3} powder. The spray pressure was 41 kgf/cm{sup 2}, the orifice diameter was 0.2 mm and the spray velocity was 0.2 L/min. And, the decontaminated area was 100 cm{sup 2}. From previous test results, we found that the decontamination factor of the PFC spray method was in the range from 9.6 to 62.4. When the decontamination efficiency of Co-60 was high, then the decontamination efficiency of Cs-137 was also high. As the surface roughness of the specimen increased, the PFC spray decontamination efficiency decreased. Inferring from the previous results, the surface of the surrogate wall was cleaned by the PFC spray method. The vacuum cup of the collection module operated well and gathered more than 99 % of the PFC solution. Also, filtration and distillation modules operated well. All the filtered PFC solution flowed to the storage chamber where some of the PFC solution was distilled. The coolant of the distillation module was a dry ice. And, the recycled solution was transferred to the spray module by a high pressure pump. To evaluate the PFC spray decontamination efficiency, a smear device was fabricated and operated by a manipulator. Before and after decontamination, a smear test was performed. The tested area was 100 cm{sup 2} and the radioactivity was estimated indirectly by measuring the radioactivity of the filter paper. The average decontamination factor was in the range between 10 and 15. One application time was 2 minutes. The sprayed PFC solution was collected by the vacuum cup and it was stored in the collection equipment. After the termination of the decontamination test, th

  11. Decontamination formulation with sorbent additive

    DOE Patents [OSTI]

    Tucker; Mark D. (Albuquerque, NM), Comstock; Robert H. (Gardendale, AL)

    2007-10-16T23:59:59.000Z

    A decontamination formulation and method of making that neutralizes the adverse health effects of both chemical and biological compounds, especially chemical warfare (CW) and biological warfare (BW) agents, and toxic industrial chemicals. The formulation provides solubilizing compounds that serve to effectively render the chemical and biological compounds, particularly CW and BW compounds, susceptible to attack, and at least one reactive compound that serves to attack (and detoxify or kill) the compound. The formulation includes at least one solubilizing agent, a reactive compound, a bleaching activator, a sorbent additive, and water. The highly adsorbent, water-soluble sorbent additive (e.g., sorbitol or mannitol) is used to "dry out" one or more liquid ingredients, such as the liquid bleaching activator (e.g., propylene glycol diacetate or glycerol diacetate) and convert the activator into a dry, free-flowing powder that has an extended shelf life, and is more convenient to handle and mix in the field.

  12. LABORATORY OPTIMIZATION TESTS OF TECHNETIUM DECONTAMINATION OF HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE OFF-GAS CONDENSATE SIMULANT

    SciTech Connect (OSTI)

    Taylor-Pashow, K.; Nash, C.; McCabe, D.

    2014-09-29T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task examines the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in greatest abundance in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are low but are also expected to be in measurable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, {sup 241}Pu, and {sup 241}Am. These are present due to their partial volatility and some entrainment in the off-gas system. This report discusses results of optimized {sup 99}Tc decontamination testing of the simulant. Testing examined use of inorganic reducing agents for {sup 99}Tc. Testing focused on minimizing the quantity of sorbents/reactants added, and minimizing mixing time to reach the decontamination targets in this simulant formulation. Stannous chloride and ferrous sulfate were tested as reducing agents to determine the minimum needed to convert soluble pertechnetate to the insoluble technetium dioxide. The reducing agents were tried with and without sorbents.

  13. Urban Decontamination Experience at Pripyat Ukraine - 13526

    SciTech Connect (OSTI)

    Paskevych, Sergiy [Institute for Safety Problems of Nuclear Power Plants, National Academy of Sciences of Ukraine, 36 a Kirova str. Chornobyl, Kiev region, 07200 (Ukraine)] [Institute for Safety Problems of Nuclear Power Plants, National Academy of Sciences of Ukraine, 36 a Kirova str. Chornobyl, Kiev region, 07200 (Ukraine); Voropay, Dmitry [Federal State Unitary Enterprise 'Russian State Center of Inventory and Registration and Real Estate - Federal Bureau of Technical Inventory', 37-2 Bernadsky Prospekt, Moscow Russia 119415 (Russian Federation)] [Federal State Unitary Enterprise 'Russian State Center of Inventory and Registration and Real Estate - Federal Bureau of Technical Inventory', 37-2 Bernadsky Prospekt, Moscow Russia 119415 (Russian Federation); Schmieman, Eric [Battelle Memorial Institute, PO Box 999 MSIN K6-90, Richland, WA 99352 (United States)] [Battelle Memorial Institute, PO Box 999 MSIN K6-90, Richland, WA 99352 (United States)

    2013-07-01T23:59:59.000Z

    This paper describes the efficiency of radioactive decontamination activities of the urban landscape in the town of Pripyat, Ukraine. Different methods of treatment for various urban infrastructure and different radioactive contaminants are assessed. Long term changes in the radiation condition of decontaminated urban landscapes are evaluated: 1. Decontamination of the urban system requires the simultaneous application of multiple methods including mechanical, chemical, and biological. 2. If a large area has been contaminated, decontamination of local areas of a temporary nature. Over time, there is a repeated contamination of these sites due to wind transport from neighboring areas. 3. Involvement of earth-moving equipment and removal of top soil by industrial method achieves 20-fold reduction in the level of contamination by radioactive substances, but it leads to large amounts of waste (up to 1500 tons per hectare), and leads to the re-contamination of treated areas due to scatter when loading, transport pollutants on the wheels of vehicles, etc.. (authors)

  14. Salt Frost Deterioration in Concrete Pavement --Causes and Mitigation

    E-Print Network [OSTI]

    Salt Frost Deterioration in Concrete Pavement --Causes and Mitigation Zhichao Liu, Will Hansen and special effects such as surface tension and osmotic effect (salt solution). ·Below the nucleation the surface contains a salt solution, pore suction attracts surface liquid and additional ice growth may

  15. SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092

    SciTech Connect (OSTI)

    Oji, L.; Martin, K.; Hobbs, D.

    2012-01-03T23:59:59.000Z

    Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate and crystalline silicotitanate laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both strontium-85 and cesium-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor for strontium-85 with monosodium titanate impregnated filter membrane cartridges measured 26, representing 96% strontium-85 removal efficiency. On the other hand, the strontium-85 instantaneous decontamination factor with co-sintered active monosodium titanate cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the monosodium titanate impregnated membrane cartridges and crystalline silicotitanate impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active monosodium titanate cartridges and co-sintered active crystalline silicotitanate cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of cesium-137 with co-sintered crystalline silicotitanate cartridges. Tests results with crystalline silicotitanate impregnated membrane cartridges for cesium-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating monosodium titanate and crystalline silicotitanate sorbents into membranes represent a promising method for the semicontinuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

  16. Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Washington, A. L. II

    2013-08-08T23:59:59.000Z

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

  17. Solution

    E-Print Network [OSTI]

    2011-09-09T23:59:59.000Z

    Solution: We're looking for the presale cost of the shirt, so let x be the price of ... The sale price is $10 and we've called the presale price x, so we need to solve.

  18. Decontamination trade study for the Light Duty Utility Arm

    SciTech Connect (OSTI)

    Rieck, R.H.

    1994-09-29T23:59:59.000Z

    Various methods were evaluated for decontaminating the Light Duty Utility Arm (LDUA). Physical capabilities of each method were compared with the constraints and requirements for the LDUA Decontamination System. Costs were compared and a referred alternative was chosen.

  19. DECONTAMINATION AND BENEFICIAL USE OF DREDGED MATERIALS.

    SciTech Connect (OSTI)

    STERN, E.A.; LODGE, J.; JONES, K.W.; CLESCERI, N.L.; FENG, H.; DOUGLAS, W.S.

    2000-12-03T23:59:59.000Z

    Our group is leading a large-sale demonstration of dredged material decontamination technologies for the New York/New Jersey Harbor. The goal of the project is to assemble a complete system for economic transformation of contaminated dredged material into an environmentally-benign material used in the manufacture of a variety of beneficial use products. This requires the integration of scientific, engineering, business, and policy issues on matters that include basic knowledge of sediment properties, contaminant distribution visualization, sediment toxicity, dredging and dewatering techniques, decontamination technologies, and product manufacturing technologies and marketing. A summary of the present status of the system demonstrations including the use of both existing and new manufacturing facilities is given here. These decontamination systems should serve as a model for use in dredged material management plans of regions other than NY/NJ Harbor, such as Long Island Sound, where new approaches to the handling of contaminated sediments are desirable.

  20. Uranium enrichment decontamination and decommissioning fund, 1995 report

    SciTech Connect (OSTI)

    NONE

    1996-11-01T23:59:59.000Z

    This report describes strategies for the decontamination and decommissioning of gaseous diffusion plants. Progress in remedial action activities are discussed.

  1. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    SciTech Connect (OSTI)

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-02-25T23:59:59.000Z

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

  2. Role of alkyl alcohol on viscosity of silica-based chemical gels for decontamination of highly radioactive nuclear facilities

    SciTech Connect (OSTI)

    Choi, B. S.; Yoon, S. B.; Jung, C. H.; Lee, K. W.; Moon, J. K. [Div. of Decontamination and Decommissioning Technology Development, Korea Atomic Energy Research Inst., Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2012-07-01T23:59:59.000Z

    Silica-based chemical gel for the decontamination of nuclear facilities was prepared by using fumed silica as a viscosifier, a 0.5 M Ce (IV) solution dissolved in concentrated nitric acid as a chemical decontamination agent, and tripropylene glycol butyl ether (TPGBE) as a co-viscosifier. A new effective strategy for the preparation of the chemical gel was investigated by introducing the alkyl alcohols as organic solvents to effectively dissolve the co-viscosifier. The mixture solution of the co-viscosifier and alkyl alcohols was more effective in the control of viscosity than that of the co-viscosifier only in gel. Here, the alkyl alcohols played a key role as an effective dissolution solvent for the co-viscosifier in the preparation of the chemical gel, resulting in a reducing of the amount of the co-viscosifier and gel time compared with that of the chemical gel prepared without the alkyl alcohols. It was considered that the alkyl alcohols contributed to the effective dissolution of the co-viscosifier as well as the homogeneous mixing in the formation of the gel, while the co-viscosifier in an aqueous media of the chemical decontamination agent solution showed a lower solubility. The decontamination efficiency of the chemical gels prepared in this work using a multi-channel analyzer (MCA) showed a high decontamination efficiency of over ca. 94% and ca. 92% for Co-60 and Cs-137 contaminated on surface of the stainless steel 304, respectively. (authors)

  3. SEDIMENT DECONTAMINATION TREATMENT TRAIN: COMMERCIAL-SCALE DEMONSTRATION

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    1 SEDIMENT DECONTAMINATION TREATMENT TRAIN: COMMERCIAL-SCALE DEMONSTRATION FOR THE PORT OF NEW YORK Dredging Seminar Louisville, Kentucky - May 15-20, 1999 ABSTRACT Decontamination and beneficial use York and New Jersey. We describe here a regional contaminated sediment decontamination program

  4. Decontamination of Mutually Contaminated Models Gilles Blanchard Clayton Scott

    E-Print Network [OSTI]

    Kaski, Samuel

    Decontamination of Mutually Contaminated Models Gilles Blanchard Clayton Scott Universit¨at Potsdam distributions are nonseparable and po- tentially quite complex. We develop a pro- cedure for decontamination technique for "decontamination" of the contaminated models. In particular, we show that under the sufficient

  5. Research Article Decontamination of Surfaces Exposed to Carbon-Based

    E-Print Network [OSTI]

    Vaziri, Ashkan

    Research Article Decontamination of Surfaces Exposed to Carbon-Based Nanotubes and Nanomaterials nanomaterial-specific decontamination guidelines. In this paper, we propose and investigate a potential method for surface decontamination of carbon-based nanomaterials using solvent cleaning and wipes. The results show

  6. Worker Protection Standard: Decontamination Frederick M. Fishel2

    E-Print Network [OSTI]

    Watson, Craig A.

    PI-116 Worker Protection Standard: Decontamination Supplies 1 Frederick M. Fishel2 1. This document Basic responsibilities Employers of pesticide handlers must make sure that decontamination supplies. Employers must make sure that decontamination supplies for washing off pesticide residues are provided

  7. Network Decontamination with Temporal Immunity by Cellular Automata

    E-Print Network [OSTI]

    Flocchini, Paola

    Network Decontamination with Temporal Immunity by Cellular Automata Yassine Daadaa, Paola Flocchini,flocchin,zaguia}@site.uottawa.ca Abstract. Network decontamination (or disinfection) is a widely stud- ied problem in distributed computing to decontaminate the whole network. In the vast literature a variety of as- sumptions are made on the power

  8. Decontamination of 2-chloroethyl ethylsulfide using titanate nanoscrolls

    E-Print Network [OSTI]

    Qin, Lu-Chang

    Decontamination of 2-chloroethyl ethylsulfide using titanate nanoscrolls Alfred Kleinhammes a of TiO2 nanocrystals, are tested as reactive sorbent for chemical warfare agent (CWA) decontamination as a decontaminant for CWAs. Ó 2005 Elsevier B.V. All rights reserved. Hydrolysis reactions have shown promising

  9. Decontamination of Hypercubes by Mobile Agents Paola Flocchini

    E-Print Network [OSTI]

    Flocchini, Paola

    Decontamination of Hypercubes by Mobile Agents Paola Flocchini Miao Jun Huang Flaminia L. Luccio Abstract In this paper we consider the decontamination problem in a hypercube network of size n. The nodes of the network are assumed to be contaminated and they have to be decontaminated by a sufficient number of agents

  10. Treatment methods for spent decontamination electrolyte produced in the ABB Atom electrochemical decontamination process ELDECON

    E-Print Network [OSTI]

    Carlsson, Charlotta Elisabeth

    1995-01-01T23:59:59.000Z

    One of ABB Atom's methods under development, ELDECON, is an electrochemical process for decontamination of components used in nuclear power plants. ELDECON removes radioactive species while producing small amounts of waste. However, the waste sludge...

  11. Decontamination and decommissioning focus area. Technology summary

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities.

  12. INTEGRATED VERTICAL AND OVERHEAD DECONTAMINATION (IVOD) SYSTEM

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    2001-01-01T23:59:59.000Z

    The deactivation and decommissioning of 1200 buildings within the U.S. Department of Energy-Office of Environmental Management complex will require the disposition of a large quantity of contaminated concrete and metal surfaces. It has been estimated that 23 million cubic meters of concrete and over 600,000 tons of metal will need disposition. The disposition of such large quantities of material presents difficulties in the area of decontamination and characterization. The final disposition of this large amount of material will take time and money as well as risk to the D&D work force. A single automated system that would decontaminate and characterize surfaces in one step would not only reduce the schedule and decrease cost during D&D operations but would also protect the D&D workers from unnecessary exposures to contaminated surfaces. This report summarizes the activities performed during FY00 and describes the planned activities for FY01. Accomplishments for FY00 include the following: Development and field-testing of characterization system; Completion of Title III design of deployment platform and decontamination unit; In-house testing of deployment platform and decontamination unit; Completion of system integration design; Identification of deployment site; and Completion of test plan document for deployment of IVOD at Rancho Seco nuclear power facility.

  13. Statistical sampling method for releasing decontaminated vehicles

    SciTech Connect (OSTI)

    Lively, J.W.; Ware, J.A. [Rust Geotech, Grand Junction, CO (United States)

    1996-06-01T23:59:59.000Z

    Earth moving vehicles (e.g., dump trucks, belly dumps) commonly haul radiologically contaminated materials from a site being remediated to a disposal site. Traditionally, each vehicle must be surveyed before being released. The logistical difficulties of implementing the traditional approach on a large scale demand that an alternative be devised. A statistical method (MIL-STD-105E, {open_quotes}Sampling Procedures and Tables for Inspection by Attributes{close_quotes}) for assessing product quality from a continuous process was adapted to the vehicle decontamination process. This method produced a sampling scheme that automatically compensates and accommodates fluctuating batch sizes and changing conditions without the need to modify or rectify the sampling scheme in the field. Vehicles are randomly selected (sampled) upon completion of the decontamination process to be surveyed for residual radioactive surface contamination. The frequency of sampling is based on the expected number of vehicles passing through the decontamination process in a given period and the confidence level desired. This process has been successfully used for 1 year at the former uranium mill site in Monticello, Utah (a CERCLA regulated clean-up site). The method forces improvement in the quality of the decontamination process and results in a lower likelihood that vehicles exceeding the surface contamination standards are offered for survey. Implementation of this statistical sampling method on Monticello Projects has resulted in more efficient processing of vehicles through decontamination and radiological release, saved hundreds of hours of processing time, provided a high level of confidence that release limits are met, and improved the radiological cleanliness of vehicles leaving the controlled site.

  14. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

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

  15. DECONTAMINATION OF PLUTONIUM FOR FLUORIDE AND CHLORIDE DURING OXALATE PRECIPITATION, FILTRATION AND CALCINATION PROCESSES

    SciTech Connect (OSTI)

    Kyser, E.

    2012-07-25T23:59:59.000Z

    Due to analytical limitations for the determination of fluoride (F) and chloride (Cl) in a previous anion exchange study, an additional study of the decontamination of Pu from F and Cl by oxalate precipitation, filtration and calcination was performed. Anion product solution from the previous impurity study was precipitated as an oxalate, filtered, and calcined to produce an oxide for analysis by pyrohydrolysis for total Cl and F. Analysis of samples from this experiment achieved the purity specification for Cl and F for the proposed AFS-2 process. Decontamination factors (DF's) for the overall process (including anion exchange) achieved a DF of {approx}5000 for F and a DF of {approx}100 for Cl. Similar experiments where both HF and HCl were spiked into the anion product solution to a {approx}5000 {micro}g /g Pu concentration showed a DF of 5 for F and a DF of 35 for Cl across the combined precipitation-filtration-calcination process steps.

  16. OPERATIONS REVIEW OF THE SAVANNAH RIVER SITE INTEGRATED SALT DISPOSITION PROCESS - 11327

    SciTech Connect (OSTI)

    Peters, T.; Poirier, M.; Fondeur, F.; Fink, S.; Brown, S.; Geeting, M.

    2011-02-07T23:59:59.000Z

    The Savannah River Site (SRS) is removing liquid radioactive waste from its Tank Farm. To treat waste streams that are low in Cs-137, Sr-90, and actinides, SRS developed the Actinide Removal Process and implemented the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). The Actinide Removal Process contacts salt solution with monosodium titanate to sorb strontium and select actinides. After monosodium titanate contact, the resulting slurry is filtered to remove the monosodium titanate (and sorbed strontium and actinides) and entrained sludge. The filtrate is transferred to the MCU for further treatment to remove cesium. The solid particulates removed by the filter are concentrated to {approx} 5 wt %, washed to reduce the sodium concentration, and transferred to the Defense Waste Processing Facility for vitrification. The CSSX process extracts the cesium from the radioactive waste using a customized solvent to produce a Decontaminated Salt Solution (DSS), and strips and concentrates the cesium from the solvent with dilute nitric acid. The DSS is incorporated in grout while the strip acid solution is transferred to the Defense Waste Processing Facility for vitrification. The facilities began radiological processing in April 2008 and started processing of the third campaign ('MarcoBatch 3') of waste in June 2010. Campaigns to date have processed {approx}1.2 million gallons of dissolved saltcake. Savannah River National Laboratory (SRNL) personnel performed tests using actual radioactive samples for each waste batch prior to processing. Testing included monosodium titanate sorption of strontium and actinides followed by CSSX batch contact tests to verify expected cesium mass transfer. This paper describes the tests conducted and compares results from facility operations. The results include strontium, plutonium, and cesium removal, cesium concentration, and organic entrainment and recovery data. Additionally, the poster describes lessons learned during operation of the facility.

  17. THE USE OF A TREATABILITY STUDY TO INVESTIGATE THE POTENTIAL FOR SELF HEATING & EXOTHERMIC REACTIONS IN DECONTAMINATION MATERIALS AT PFP

    SciTech Connect (OSTI)

    HOPKINS, A.M.

    2005-02-23T23:59:59.000Z

    Cerium Nitrate has been proposed for use in the decontamination of plutonium contaminated equipment at the Plutonium Finishing Plant (PFP) located on the Hanford Nuclear Reservation in eastern Washington. A Treatability Study was conducted to determine the validity of this decontamination technology in terms of meeting its performance goals and to understand the risks associated with the use of Cerium Nitrate under the conditions found at the PFP. Fluor Hanford is beginning the decommissioning of the PFP at the Hanford site. Aggressive chemicals are commonly used to remove transuranic contaminants from process equipment to allow disposal as low level waste. Chemicals being considered for decontamination of gloveboxes in PFP include cerium (IV) nitrate in a nitric acid solution, and proprietary commercial solutions that include acids, degreasers, and sequestering agents. Fluor's decontamination procedure involves application of the chemicals, followed by a wipe-down of the contaminated surfaces with rags. This process effectively transfers the decontamination liquids containing the transuranic materials to the rags, which can then be readily packaged for disposal as TRU waste. As part of a treatability study, Fluor Hanford and the Pacific Northwest National Laboratory (PNNL) have evaluated the potential for self-heating and exothermic reactions in the residual decontamination materials and the waste packages. Laboratory analyses and thermal-hydraulic modeling reveal a significant self-heating risk for cerium nitrate solutions when used with cotton rags. Exothermic reactions that release significant heat and off-gas have been discovered for cerium nitrate at higher temperatures. From these studies, limiting conditions have been defined to assure safe operations and waste packaging.

  18. Decontamination system study for the Tank Waste Retrieval System

    SciTech Connect (OSTI)

    Reutzel, T.; Manhardt, J.

    1994-05-01T23:59:59.000Z

    This report summarizes the findings of the Idaho National Engineering Laboratory`s decontamination study in support of the Tank Waste Retrieval System (TWRS) development program. Problems associated with waste stored in existing single shell tanks are discussed as well as the justification for the TWRS program. The TWRS requires a decontamination system. The subsystems of the TWRS are discussed, and a list of assumptions pertinent to the TWRS decontamination system were developed. This information was used to develop the functional and operational requirements of the TWRS decontamination system. The requirements were combined with a comprehensive review of currently available decontamination techniques to produced a set of evaluation criteria. The cleaning technologies and techniques were evaluated, and the CO{sub 2} blasting decontamination technique was chosen as the best technology for the TWRS.

  19. Decontamination and dismantlement of Plant 7 at Fernald

    SciTech Connect (OSTI)

    Albertin, M.; Borgman, T.; Zebick, B.

    1994-11-07T23:59:59.000Z

    Decontamination and dismantlement (D&D) tasks have been successfully completed on Plant 7 at the Fernald Environmental Management Project. The seven story facility was radiologically, chemically, and biologically contaminated. The work involved the D&D work beginning with safe shutdown and gross decontamination, and ended with removal of the structural steel. A series of lessons learned were gained which include use of explosives, bidding tactics, safe shutdown, building decontamination and lockdown, use of seam climbers, etc.

  20. Development of decontamination techniques for decommissioning commercial nuclear power plants

    SciTech Connect (OSTI)

    Ishikura, T.; Miwa, T.; Onozawa, T.; Ohtsuka, H. [Nuclear Power Engineering Corp., Tokyo (Japan). Plant and Components Dept.; Ishigure, K. [Univ. of Tokyo (Japan). Dept. of Quantum Engineering and System Science

    1993-12-31T23:59:59.000Z

    NUPEC has been developing various techniques to safely and efficiently decommission large commercial nuclear power plants. The development work, referred to as the verification tests, has been performed since 1982. The verification tests on decontamination techniques have focused on the reduction of both occupational radiation exposure and radioactive waste volume. Experiments on various decontamination methods have been carried out. Prospects of applying efficient decontamination techniques to commercial nuclear power plant decommissioning are bright due to the experimental results.

  1. SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION-EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATIONS-12092

    SciTech Connect (OSTI)

    Oji, L.; Martin, K.; Hobbs, D.

    2011-11-10T23:59:59.000Z

    Experimental results for the selective removal of strontium and cesium from simulated waste solutions with monosodium titanate (MST) and crystalline silicotitanate (CST) laden filter cartridges are presented. In these proof-of-principle tests, effective uptake of both Sr-85 and Cs-137 were observed using ion-exchangers in this filter cartridge configuration. At low salt simulant conditions, the instantaneous decontamination factor (D{sub F}) for Sr-85 with MST impregnated filter membrane cartridges measured 26, representing 96% Sr-85 removal efficiency. On the other hand, the Sr-85 instantaneous D{sub F} with co-sintered active MST cartridges measured 40 or 98% Sr-85 removal efficiency. Strontium-85 removal with the MST impregnated membrane cartridges and CST impregnated membrane cartridges, placed in series arrangement, produced an instantaneous decontamination factor of 41 compared to an instantaneous decontamination factor of 368 for strontium-85 with co-sintered active MST cartridges and co-sintered active CST cartridges placed in series. Overall, polyethylene co-sintered active titanates cartridges performed as well as titanate impregnated filter membrane cartridges in the uptake of strontium. At low ionic strength conditions, there was a significant uptake of Cs-137 with co-sintered CST cartridges. Tests results with CST impregnated membrane cartridges for Cs-137 decontamination are currently being re-evaluated. Based on these preliminary findings we conclude that incorporating MST and CST sorbents into membranes represent a promising method for the semi-continuous removal of radioisotopes of strontium and cesium from nuclear waste solutions.

  2. Recovery and survival of nontuberculous mycobacteria under various growth and decontamination conditions

    E-Print Network [OSTI]

    Falkinham, Joseph

    Recovery and survival of nontuberculous mycobacteria under various growth and decontamination. 1984. Recovery and survival of nontuberculous mycobacteria under various growth and decontamination. intracellulare, and M. scrofulaceum (MAIS) complex was evaluated after various soi1 and water decontamination

  3. Contaminated concrete: Occurrence and emerging technologies for DOE decontamination

    SciTech Connect (OSTI)

    Dickerson, K.S.; Wilson-Nichols, M.J. [Oak Ridge National Lab., Grand Junction, CO (United States); Morris, M.I. [Oak Ridge National Lab., TN (United States)

    1995-08-01T23:59:59.000Z

    The goals of the Facility Deactivation, Decommissioning, and Material Disposition Focus Area, sponsored by the US Department of Energy (DOE) Office of Technology Development, are to select, demonstrate, test, and evaluate an integrated set of technologies tailored to provide a complete solution to specific problems posed by deactivation, decontamination, and decommissioning, (D&D). In response to these goals, technical task plan (TTP) OR152002, entitled Accelerated Testing of Concrete Decontamination Methods, was submitted by Oak Ridge National Laboratory. This report describes the results from the initial project tasks, which focused on the nature and extent of contaminated concrete, emerging candidate technologies, and matching of emerging technologies to concrete problems. Existing information was used to describe the nature and extent of contamination (technology logic diagrams, data bases, and the open literature). To supplement this information, personnel at various DOE sites were interviewed, providing a broad perspective of concrete contamination. Because characterization is in the initial stage at many sites, complete information is not available. Assimilation of available information into one location is helpful in identifying potential areas of concern in the future. The most frequently occurring radiological contaminants within the DOE complex are {sup 137}Cs, {sup 238}U (and it daughters), and {sup 60}Co, followed closely by {sup 90}Sr and tritium, which account for {minus}30% of the total occurrence. Twenty-four percent of the contaminants were listed as unknown, indicating a lack of characterization information, and 24% were listed as other contaminants (over 100 isotopes) with less than 1% occurrence per isotope.

  4. Calixarene crown ether solvent composition and use thereof for extraction of cesium from alkaline waste solutions

    DOE Patents [OSTI]

    Moyer, Bruce A. (Oak Ridge, TN); Sachleben, Richard A. (Knoxville, TN); Bonnesen, Peter V. (Knoxville, TN); Presley, Derek J. (Ooltewah, TN)

    2001-01-01T23:59:59.000Z

    A solvent composition and corresponding method for extracting cesium (Cs) from aqueous neutral and alkaline solutions containing Cs and perhaps other competing metal ions is described. The method entails contacting an aqueous Cs-containing solution with a solvent consisting of a specific class of lipophilic calix[4]arene-crown ether extractants dissolved in a hydrocarbon-based diluent containing a specific class of alkyl-aromatic ether alcohols as modifiers. The cesium values are subsequently recovered from the extractant, and the solvent subsequently recycled, by contacting the Cs-containing organic solution with an aqueous stripping solution. This combined extraction and stripping method is especially useful as a process for removal of the radionuclide cesium-137 from highly alkaline waste solutions which are also very concentrated in sodium and potassium. No pre-treatment of the waste solution is necessary, and the cesium can be recovered using a safe and inexpensive stripping process using water, dilute (millimolar) acid solutions, or dilute (millimolar) salt solutions. An important application for this invention would be treatment of alkaline nuclear tank wastes. Alternatively, the invention could be applied to decontamination of acidic reprocessing wastes containing cesium-137.

  5. Salt never calls itself sweet.

    E-Print Network [OSTI]

    Baliga, Ragavendra R; Narula, Jagat

    2009-01-01T23:59:59.000Z

    54. 11. Frohlich ED. The role of salt in hypertension: theblockade, diuretics, and salt restriction for the managementa low- sodium high-potassium salt in hypertensive patients

  6. Molten salt electrolyte separator

    DOE Patents [OSTI]

    Kaun, Thomas D. (New Lenox, IL)

    1996-01-01T23:59:59.000Z

    A molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication.

  7. Decontamination formulations for disinfection and sterilization

    DOE Patents [OSTI]

    Tucker, Mark D. (Albuquerque, NM); Engler, Daniel E. (Albuquerque, NM)

    2007-09-18T23:59:59.000Z

    Aqueous decontamination formulations that neutralize biological pathogens for disinfection and sterilization applications. Examples of suitable applications include disinfection of food processing equipment, disinfection of areas containing livestock, mold remediation, sterilization of medical instruments and direct disinfection of food surfaces, such as beef carcasses. The formulations include at least one reactive compound, bleaching activator, inorganic base, and water. The formulations can be packaged as a two-part kit system, and can have a pH value in the range of 7-8.

  8. Laser Decontamination of Metals | The Ames Laboratory

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOEThe Bonneville PowerCherries 82981-1cnHigh SchoolIn12electron 9 5 - -/e),,sandLaser Decontamination of Metals

  9. Retrospective salt tectonics

    SciTech Connect (OSTI)

    Jackson, M.P.A. [Univ. of Texas, Austin, TX (United States)

    1996-12-31T23:59:59.000Z

    The conceptual breakthroughs in understanding salt tectonics can be recognized by reviewing the history of salt tectonics, which divides naturally into three parts: the pioneering era, the fluid era, and the brittle era. The pioneering era (1856-1933) featured the search for a general hypothesis of salt diapirism, initially dominated by bizarre, erroneous notions of igneous activity, residual islands, in situ crystallization, osmotic pressures, and expansive crystallization. Gradually data from oil exploration constrained speculation. The effects of buoyancy versus orogeny were debated, contact relations were characterized, salt glaciers were discovered, and the concepts of downbuilding and differential loading were proposed as diapiric mechanisms. The fluid era (1933-{approximately}1989) was dominated by the view that salt tectonics resulted from Rayleigh-Taylor instabilities in which a dense fluid overburden having negligible yield strength sinks into a less dense fluid salt layer, displacing it upward. Density contrasts, viscosity contrasts, and dominant wavelengths were emphasized, whereas strength and faulting of the overburden were ignored. During this era, palinspastic reconstructions were attempted; salt upwelling below thin overburdens was recognized; internal structures of mined diapirs were discovered; peripheral sinks, turtle structures, and diapir families were comprehended; flow laws for dry salt were formulated; and contractional belts on divergent margins and allochthonous salt sheets were recognized. The 1970s revealed the basic driving force of salt allochthons, intrasalt minibasins, finite strains in diapirs, the possibility of thermal convection in salt, direct measurement of salt glacial flow stimulated by rainfall, and the internal structure of convecting evaporites and salt glaciers. The 1980`s revealed salt rollers, subtle traps, flow laws for damp salt, salt canopies, and mushroom diapirs.

  10. SELECTIVE REMOVAL OF STRONTIUM AND CESIUM FROM SIMULATED WASTE SOLUTION WITH TITANATE ION EXCHANGERS IN A FILTER CARTRIDGE CONFIGURATION

    SciTech Connect (OSTI)

    Oji, L.; Martin, K.; Hobbs, D.

    2011-05-26T23:59:59.000Z

    This report describes experimental results for the selective removal of strontium and cesium from simulated waste solutions using monosodium titanate (MST) and crystalline silicotitanate (CST)-laden filter cartridges. Four types of ion exchange cartridge media (CST and MST designed by both 3M and POROX{reg_sign}) were evaluated. In these proof-of-principle tests effective uptake of both Sr-85 and Cs-137 was observed. However, the experiments were not performed long enough to determine the saturation levels or breakthrough curve for each filter cartridge. POREX{reg_sign} MST cartridges, which by design were based on co-sintering of the active titanates with polyethylene particles, seem to perform as well as the 3M-designed MST cartridges (impregnated filter membrane design) in the uptake of strontium. At low salt simulant conditions (0.29 M Na{sup +}), the instantaneous decontamination factor (D{sub F}) for Sr-85 with the 3M-design MST cartridge measured 26, representing the removal of 96% of the Sr-85. On the other hand, the Sr-85 instantaneous D{sub F} with the POREX{reg_sign} design MST cartridge measured 40 or 98% removal of the Sr-85. Strontium removal with the 3M-design MST and CST cartridges placed in series filter arrangement produced an instantaneous decontamination factor of 41 or 97.6% removal compared to an instantaneous decontamination factor of 368 or 99.7% removal of the strontium with the POREX{reg_sign} MST and CST cartridge design placed in series. At high salt simulant conditions (5.6 M Na{sup +}), strontium removal with 3M-designed MST cartridge only and with 3M-designed MST and CST cartridges operated in a series configuration were identical. The instantaneous decontamination factor and the strontium removal efficiency, under the above configuration, averaged 8.6 and 88%, respectively. There were no POREX{reg_sign} cartridge experiments using the higher ionic strength simulant solution. At low salt simulant conditions, the uptake of Cs-137 with POREX{reg_sign} CST cartridge out performed the 3M-designed CST cartridges. The POREX{reg_sign} CST cartridge, with a Cs-137 instantaneous decontamination factor of 55 and a Cs-137 removal efficiency of 98% does meet the Cs-137 decontamination goals in the low salt simulant liquor. The Cs-137 removal with 3M-designed CST cartridge produced a decontamination factor of 2 or 49% removal efficiency. The Cs-137 performance graph for the 3M-designed CST cartridge showed an early cessation in the uptake of cesium-137. This behavior was not observed with the POREX{reg_sign} CST cartridges. No Cs-137 uptake tests were performed with the POREX{reg_sign} CST cartridges at high salt simulant conditions. The 3M-designed CST cartridges, with an instantaneous Cs-137 decontamination factor of less than 3 and a Cs-137 removal efficiency of less than 50% failed to meet the Cs-137 decontamination goals in both the low and high salt simulant liquors. This poor performance in the uptake of Cs-137 by the 3M CST cartridges may be attributed to fabrication flaws for the 3M-designed CST cartridges. The reduced number of CST membrane wraps per cartridge during the cartridge design phase, from 3-whole wraps to about 1.5, may have contributed to Cs-137 laden simulant channeling/by-pass which led to the poor performance in terms of Cs-137 sorption characteristics for the 3M designed CST cartridges. The grinding of CST ion exchange materials, to reduce the particle size distribution and thus enhance their easy incorporation into the filter membranes and the co-sintering of MST with polyethylene particles, did not adversely affect the sorption kinetics of both CST and MST in the uptake of Cs-137 and Sr-85, respectively. In general, the POREX{reg_sign} based cartridges showed more resistance to simulant flow through the filter cartridges as evidenced by higher pressure differences across the cartridges. Based on these findings they conclude that incorporating MST and CST sorbents into filter membranes represent a promising method for the semi-continuous removal of radioisotopes of strontium a

  11. Dependence of DNA persistence length on ionic strength of solutions with monovalent and divalent salts: a joint theory-experiment study

    E-Print Network [OSTI]

    Brunet, Annaël; Salomé, Laurence; Rousseau, Philippe; Destainville, Nicolas; Manghi, Manoel

    2015-01-01T23:59:59.000Z

    Using high-throughput Tethered Particle Motion single molecule experiments, the double-stranded DNA persistence length, $L_p$, is measured in solutions with Na$^+$ and Mg$^{2+}$ ions of various ionic strengths, $I$. Several theoretical equations for $L_p(I)$ are fitted to the experimental data, but no decisive theory is found which fits all the $L_p$ values for the two ion valencies. Properly extracted from the particle trajectory using simulations, $L_p$ varies from 30~nm to 55~nm, and is compared to previous experimental results. For the Na$^+$ only case, $L_p$ is an increasing concave function of $I^{-1}$, well fitted by Manning's electrostatic stretching approach, but not by classical Odjik-Skolnick-Fixman theories with or without counter-ion condensation. With added Mg$^{2+}$ ions, $L_p$ shows a marked decrease at low $I$, interpreted as an ion-ion correlation effect, with an almost linear law in $I^{-1}$, fitted by a proposed variational approach.

  12. Laboratory Scoping Tests Of Decontamination Of Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    SciTech Connect (OSTI)

    Taylor-Pashow, Kathryn M.; Nash, Charles A.; Crawford, Charles L.; McCabe, Daniel J.; Wilmarth, William R.

    2014-01-21T23:59:59.000Z

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable de-coupled operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste. This LAW Off-Gas Condensate stream contains components that are volatile at melter temperatures and are problematic for the glass waste form. Because this stream recycles within WTP, these components accumulate in the Condensate stream, exacerbating their impact on the number of LAW glass containers that must be produced. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and diverting the stream reduces the halides in the recycled Condensate and is a key outcome of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, identifying a disposition path becomes vitally important. This task seeks to examine the potential treatment of this stream to remove radionuclides and subsequently disposition the decontaminated stream elsewhere, such as the Effluent Treatment Facility (ETF), for example. The treatment process envisioned is very similar to that used for the Actinide Removal Process (ARP) that has been operating for years at the Savannah River Site (SRS), and focuses on using mature radionuclide removal technologies that are also compatible with longterm tank storage and immobilization methods. For this new application, testing is needed to demonstrate acceptable treatment sorbents and precipitating agents and measure decontamination factors for additional radionuclides in this unique waste stream. The origin of this LAW Off-Gas Condensate stream will be the liquids from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover. The soluble components are expected to be mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet and will not be available until the WTP begins operation, but a simulant has been produced based on models, calculations, and comparison with pilot-scale tests. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Off-Gas Condensate stream is Technetium-99 ({sup 99}Tc). Technetium will not be removed from the aqueous waste in the Hanford WTP, and will primarily end up immobilized in the LAW glass by repeated recycle of the off-gas condensate into the LAW melter. Other radionuclides that are also expected to be in appreciable concentration in the LAW Off-Gas Condensate are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. This report discusses results of preliminary radionuclide decontamination testing of the simulant. Testing examined use of Monosodium Titanate (MST) to remove {sup 90}Sr and actinides, inorganic reducing agents for {sup 99}Tc, and zeolites for {sup 137}Cs. Test results indicate that excellent removal of {sup 99}Tc was achieved using Sn(II)Cl{sub 2} as a reductant, coupled with sorption onto hydroxyapatite, even in the presence of air and at room temperature. This process was very effective at neutral pH, with a Decontamination Factor (DF) >577 in two hours. It was less effective at alkaline pH. Conversely, removal of the cesium was more effective at alka

  13. Decontamination and decommissioning of the Kerr-McGee Cimarron Plutonium Fuel Plant

    SciTech Connect (OSTI)

    Not Available

    1994-05-01T23:59:59.000Z

    This final report is a summary of the events that completes the decontamination and decommissioning of the Cimarron Corporation`s Mixed Oxides Fuel Plant (formally Sequoyah Fuels Corporation and formerly Kerr-McGee Nuclear Corporation - all three wholly owned subsidiaries of the Kerr-McGee Corporation). Included are details dealing with tooling and procedures for performing the unique tasks of disassembly decontamination and/or disposal. That material which could not be economically decontaminated was volume reduced by disassembly and/or compacted for disposal. The contaminated waste cleaning solutions were processed through filtration and ion exchange for release or solidified with cement for L.S.A. waste disposal. The L.S.A. waste was compacted, and stabilized as required in drums for burial in an approved burial facility. T.R.U. waste packaging and shipping was completed by the end of July 1987. This material was shipped to the Hanford, Washington site for disposal. The personnel protection and monitoring measures and procedures are discussed along with the results of exposure data of operating personnel. The shipping containers for both T.R.U. and L.S.A. waste are described. The results of the decommissioning operations are reported in six reports. The personnel protection and monitoring measures and procedures are contained and discussed along with the results of exposure data of operating personnel in this final report.

  14. 1 Research review paper 2 Metabolic reengineering invoked by microbial systems to decontaminate aluminum

    E-Print Network [OSTI]

    Appanna, Vasu

    by microbial systems to decontaminate aluminum: 3 Implications for bioremediation technologies 4 ChristopherQ1

  15. Long-term decontamination engineering study. Volume 1

    SciTech Connect (OSTI)

    Geuther, W.J.

    1995-04-03T23:59:59.000Z

    This report was prepared by Westinghouse Hanford Company (WHC) with technical and cost estimating support from Pacific Northwest Laboratories (PNL) and Parsons Environmental Services, Inc. (Parsons). This engineering study evaluates the requirements and alternatives for decontamination/treatment of contaminated equipment at the Hanford Site. The purpose of this study is to determine the decontamination/treatment strategy that best supports the Hanford Site environmental restoration mission. It describes the potential waste streams requiring treatment or decontamination, develops the alternatives under consideration establishes the criteria for comparison, evaluates the alternatives, and draws conclusions (i.e., the optimum strategy for decontamination). Although two primary alternatives are discussed, this study does identify other alternatives that may warrant additional study. hanford Site solid waste management program activities include storage, special processing, decontamination/treatment, and disposal facilities. This study focuses on the decontamination/treatment processes (e.g., waste decontamination, size reduction, immobilization, and packaging) that support the environmental restoration mission at the Hanford Site.

  16. Preconceptual design of the gas-phase decontamination demonstration cart

    SciTech Connect (OSTI)

    Munday, E.B.

    1993-12-01T23:59:59.000Z

    Removal of uranium deposits from the interior surfaces of gaseous diffusion equipment will be a major portion of the overall multibillion dollar effort to decontaminate and decommission the gaseous diffusion plants. Long-term low-temperature (LTLT) gas-phase decontamination is being developed at the K-25 Site as an in situ decontamination process that is expected to significantly lower the decontamination costs, reduce worker exposure to radioactive materials, and reduce safeguard concerns. This report documents the preconceptual design of the process equipment that is necessary to conduct a full-scale demonstration of the LTLT method in accordance with the process steps listed above. The process equipment and method proposed in this report are not intended to represent a full-scale production campaign design and operation, since the gas evacuation, gas charging, and off-gas handling systems that would be cost effective in a production campaign are not cost effective for a first-time demonstration. However, the design presented here is expected to be applicable to special decontamination projects beyond the demonstration, which could include the Deposit Recovery Program. The equipment will therefore be sized to a 200 ft size 1 converter (plus a substantial conservative design margin), which is the largest item of interest for gas phase decontamination in the Deposit Recovery Program. The decontamination equipment will allow recovery of the UF{sub 6}, which is generated from the reaction of ClF{sub 3} with the uranium deposits, by use of NaF traps.

  17. Decision Analysis System for Selection of Appropriate Decontamination Technologies

    SciTech Connect (OSTI)

    Ebadian, M.A.; Boudreaux, J.F.; Chinta, S.; Zanakis, S.H.

    1998-01-01T23:59:59.000Z

    The principal objective for designing Decision Analysis System for Decontamination (DASD) is to support DOE-EM's endeavor to employ the most efficient and effective technologies for treating radiologically contaminated surfaces while minimizing personnel and environmental risks. DASD will provide a tool for environmental decision makers to improve the quality, consistency, and efficacy of their technology selection decisions. The system will facilitate methodical comparisons between innovative and baseline decontamination technologies and aid in identifying the most suitable technologies for performing surface decontamination at DOE environmental restoration sites.

  18. Decontamination Technologies, Task 3, Urban Remediation and Response Project

    SciTech Connect (OSTI)

    Heiser,J.; Sullivan, T.

    2009-06-30T23:59:59.000Z

    In the aftermath of a Radiological Dispersal Device (RDD, also known as a dirty bomb) it will be necessary to remediate the site including building exteriors and interiors, equipment, pavement, vehicles, personal items etc. Remediation will remove or reduce radioactive contamination from the area using a combination of removing and disposing of many assets (including possible demolition of buildings), decontaminating and returning to service other assets, and fixing in place or leaving in place contamination that is deemed 'acceptable'. The later will require setting acceptable dose standards, which will require negotiation with all involved parties and a balance of risk and cost to benefit. To accomplish the first two, disposal or decontamination, a combination of technologies will be deployed that can be loosely classified as: Decontamination; Equipment removal and size reduction; and Demolition. This report will deal only with the decontamination technologies that will be used to return assets to service or to reduce waste disposal. It will not discuss demolition, size reduction or removal technologies or equipment (e.g., backhoe mounted rams, rock splitter, paving breakers and chipping hammers, etc.). As defined by the DOE (1994), decontamination is removal of radiological contamination from the surfaces of facilities and equipment. Expertise in this field comes primarily from the operation and decommissioning of DOE and commercial nuclear facilities as well as a small amount of ongoing research and development closely related to RDD decontamination. Information related to decontamination of fields, buildings, and public spaces resulting from the Goiania and Chernobyl incidents were also reviewed and provide some meaningful insight into decontamination at major urban areas. In order to proceed with decontamination, the item being processed needs to have an intrinsic value that exceeds the cost of the cleaning and justifies the exposure of any workers during the decontamination process(es). In the case of an entire building, the value may be obvious; it's costly to replace the structure. For a smaller item such as a vehicle or painting, the cost versus benefit of decontamination needs to be evaluated. This will be determined on a case by case basis and again is beyond the scope of this report, although some thoughts on decontamination of unique, personal and high value items are given. But, this is clearly an area that starting discussions and negotiations early on will greatly benefit both the economics and timeliness of the clean up. In addition, high value assets might benefit from pre-event protection such as protective coatings or HEPA filtered rooms to prevent contaminated outside air from entering the room (e.g., an art museum).

  19. Radioactive hot cell access hole decontamination machine

    DOE Patents [OSTI]

    Simpson, William E. (Richland, WA)

    1982-01-01T23:59:59.000Z

    Radioactive hot cell access hole decontamination machine. A mobile housing has an opening large enough to encircle the access hole and has a shielding door, with a door opening and closing mechanism, for uncovering and covering the opening. The housing contains a shaft which has an apparatus for rotating the shaft and a device for independently translating the shaft from the housing through the opening and access hole into the hot cell chamber. A properly sized cylindrical pig containing wire brushes and cloth or other disks, with an arrangement for releasably attaching it to the end of the shaft, circumferentially cleans the access hole wall of radioactive contamination and thereafter detaches from the shaft to fall into the hot cell chamber.

  20. Development of high temperature transport technology for LiCl-KCl eutectic salt in pyroprocessing

    SciTech Connect (OSTI)

    Lee, Sung Ho; Lee, Hansoo; Kim, In Tae; Kim, Jeong-Guk [Korea Atomic Energy Research Institute, 1045 Daedeok-daaro, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

    2013-07-01T23:59:59.000Z

    The development of high-temperature transport technologies for molten salt is a prerequisite and a key issue in the industrialization of pyro-reprocessing for advanced fuel cycle scenarios. The solution of a molten salt centrifugal pump was discarded because of the high corrosion power of a high temperature molten salt, so the suction pump solution was selected. An apparatus for salt transport experiments by suction was designed and tested using LiC-KCl eutectic salt. The experimental results of lab-scale molten salt transport by suction showed a 99.5% transport rate (ratio of transported salt to total salt) under a vacuum range of 100 mtorr - 10 torr at 500 Celsius degrees. The suction system has been integrated to the PRIDE (pyroprocessing integrated inactive demonstration) facility that is a demonstrator using non-irradiated materials (natural uranium and surrogate materials). The performance of the suction pump for the transport of molten salts has been confirmed.

  1. Strippable coating used for the TMI-2 reactor building decontamination

    SciTech Connect (OSTI)

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

    1984-01-01T23:59:59.000Z

    Strippable coating material used in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, thermal stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation and heating of the coating did not produce any apparent physical changes in the coating to 1 x 10/sup 8/ rad and 100/sup 0/C; however, gas generation of H/sub 2/, CO, CO/sub 2/ was observed in both cases. Biodegradation of the coating occurred readily in soils as indicated by monitoring CO/sub 2/ produced from microbial respiration. These test results indicate that strippable coating radwaste would have to be stabilized to meet the requirements for Class B waste outlined in 10 CFR Part 61 and the NRC Draft Technical Position on Waste Form.

  2. The EPRI DFDX Chemical Decontamination Process

    SciTech Connect (OSTI)

    Bushart, S.; Wood, C. J.; Bradbury, D.; Elder, G.

    2003-02-25T23:59:59.000Z

    Decommissioning of retired nuclear plants and components demands the proper management of the process, both for economic reasons and for retaining public confidence in the continued use of nuclear power for electricity generation. The cost and ease of management of radioactively contaminated components can be greatly assisted by the application of decontamination technology. EPRI initiated a program of research and development work in collaboration with Bradtec, which has led to the ''EPRI DFD'' (Decontamination for Decommissioning) Process. The Process has been patented and licensed to six companies worldwide. The purpose of this process is to achieve efficient removal of radioactivity with minimum waste from retired nuclear components and plant systems. The process uses dilute fluoroboric acid with controlled oxidation potential. By removing all the outer scale and a thin layer of base metal from the surfaces, contamination can in many cases be reduced below the levels required to allow clearance (free-release) or recycle to form new components for the nuclear industry. This reduces the need for on-site storage or burial of large amounts of contaminated material at low level radioactive disposal facilities. An additional benefit is that residual radiation fields can be reduced by a large factor, which reduces the worker radiation exposure associated with decommissioning. Furthermore, this dose rate reduction improves the viability of early dismantlement following plant closure, as opposed to waiting for a prolonged period for radioactive decay to occur. The results obtained in early applications of the EPRI DFD process demonstrated the benefits of taking this approach (reference 1).

  3. Surface Decontamination Using Laser Ablation Process - 12032

    SciTech Connect (OSTI)

    Moggia, Fabrice; Lecardonnel, Xavier; Damerval, Frederique [AREVA, Back End Business Group, Clean Up Business Unit (France)

    2012-07-01T23:59:59.000Z

    A new decontamination method has been investigated and used during two demonstration stages by the Clean-Up Business Unit of AREVA. This new method is based on the use of a Laser beam to remove the contaminants present on a base metal surface. In this paper will be presented the type of Laser used during those tests but also information regarding the efficiency obtained on non-contaminated (simulated contamination) and contaminated samples (from the CEA and La Hague facilities). Regarding the contaminated samples, in the first case, the contamination was a quite thick oxide layer. In the second case, most of the contamination was trapped in dust and thin grease layer. Some information such as scanning electron microscopy (SEM), X-Ray scattering spectroscopy and decontamination factors (DF) will be provided in this paper. Laser technology appears to be an interesting one for the future of the D and D applications. As shown in this paper, the results in terms of efficiency are really promising and in many cases, higher than those obtained with conventional techniques. One of the most important advantages is that all those results have been obtained with no generation of secondary wastes such as abrasives, chemicals, or disks... Moreover, as mentioned in introduction, the Laser ablation process can be defined as a 'dry' process. This technology does not produce any liquid waste (as it can be the case with chemical process or HP water process...). Finally, the addition of a vacuum system allows to trap the contamination onto filters and thus avoiding any dissemination in the room where the process takes place. The next step is going to be a commercial use in 2012 in one of the La Hague buildings. (authors)

  4. Impact of Salt Purity on Interfacial Water Organization Revealed by Conventional and Heterodyne-Detected Vibrational Sum Frequency

    E-Print Network [OSTI]

    Impact of Salt Purity on Interfacial Water Organization Revealed by Conventional and Heterodyne of the chosen salts and their solutions. This is true not only for the ACS grade salts but also vibrational sum frequency generation (VSFG) and heterodyne-detected VSFG (HD-VSFG) spectroscopy that salt

  5. Le Thorium Molten Salt Reactor : Au del du MSBR

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Le Thorium Molten Salt Reactor : Au delà du MSBR L. Mathieu, D. Heuer, A. Billebaud, R. Brissot, C réflexion est menée afin de trou- ver des solutions et ainsi d'aboutir au concept du Thorium Mol- ten Salt optimale du minerai d'uranium ou de thorium, une conception résistante à la prolifération, une meilleur

  6. Dosimetry using silver salts

    DOE Patents [OSTI]

    Warner, Benjamin P. (Los Alamos, NM)

    2003-06-24T23:59:59.000Z

    The present invention provides a method for detecting ionizing radiation. Exposure of silver salt AgX to ionizing radiation results in the partial reduction of the salt to a mixture of silver salt and silver metal. The mixture is further reduced by a reducing agent, which causes the production of acid (HX) and the oxidized form of the reducing agent (R). Detection of HX indicates that the silver salt has been exposed to ionizing radiation. The oxidized form of the reducing agent (R) may also be detected. The invention also includes dosimeters employing the above method for detecting ionizing radiation.

  7. Enhanced toxic cloud knockdown spray system for decontamination applications

    DOE Patents [OSTI]

    Betty, Rita G. (Rio Rancho, NM); Tucker, Mark D. (Albuquerque, NM); Brockmann, John E. (Albuquerque, NM); Lucero, Daniel A. (Albuquerque, NM); Levin, Bruce L. (Tijeras, NM); Leonard, Jonathan (Albuquerque, NM)

    2011-09-06T23:59:59.000Z

    Methods and systems for knockdown and neutralization of toxic clouds of aerosolized chemical or biological warfare (CBW) agents and toxic industrial chemicals using a non-toxic, non-corrosive aqueous decontamination formulation.

  8. Modification of the Decontamination Facility at the Kruemmel NPP - 13451

    SciTech Connect (OSTI)

    Klute, Stefan; Kupke, Peter [Siempelkamp Nukleartechnik GmbH Am Taubenfeld 25/1, 69123 Heidelberg (Germany)] [Siempelkamp Nukleartechnik GmbH Am Taubenfeld 25/1, 69123 Heidelberg (Germany)

    2013-07-01T23:59:59.000Z

    In February 2009, Siempelkamp Nukleartechnik GmbH was awarded the contract for the design, manufacture, delivery and construction of a new Decontamination Facility in the controlled area for Kruemmel NPP. The new decontamination equipment has been installed according to the state of art of Kruemmel NPP. The existing space required the following modification, retrofitting and reconstruction works: - Demounting of the existing installation: to create space for the new facility it was necessary to dismantle the old facility. The concrete walls and ceilings were cut into sizes of no more than 400 kg for ease of handling. This enabled decontamination so largest possible amount could be released for recycling. All steel parts were cut into sizes fitting for iron-barred boxes, respecting the requirement to render the parts decontaminable and releasable. - Reconstructing a decontamination facility: Reconstruction of a decontamination box with separate air lock as access area for the decontamination of components and assemblies was conducted using pressurized air with abrasives (glass beads or steel shots). The walls were equipped with sound protection, the inner walls were welded gap-free to prevent the emergence of interstices and were equipped with changeable wear and tear curtains. Abrasive processing unit positioned underneath the dry blasting box adjacent to the two discharge hoppers. A switch has been installed for the separation of the glass beads and the steel shot. The glass beads are directed into a 200 l drum for the disposal. The steel shot was cleaned using a separator. The cleaned steel shot was routed via transportation devices to the storage container, making it available for further blasting operations. A decontamination box with separate air lock as access area for the decontamination of components and assemblies using high pressure water technology was provided by new construction. Water pressures between 160 bar and 800 bar can be selected. The inner walls are welded gap-free and all rough edges are rounded off. All wetted parts are steel grade 1.4301 or higher. In an extension to the high pressure water decontamination box, 2 ultrasonic ponds and one washing station for small components as provide by new construction. A long pond with 3.25 m length for the decontamination of large components (e.g. turbine blades, pump rotors, driving rods) was installed. For the handling heavy components, a 2 t crane was installed. New construction of a mechanical effluent treatment facility including oil separator was connected to the existing effluent storage tank provided by the customer. One exhaust air filtration system is provided for each decontamination box, with the following requirements. The exhaust air is sent back to the room (recirculated air system). Dry blasting box including raw separator with dust collection in 200 l drum, filter for suspended particles; High pressure water decontamination box and wet area with water separator, pre-separator, filter for suspended particles. Installation of a steel platform at building height +12.85 above the decontamination boxes + 8.50 m for the erection of the high pressure water facilities, the recirculating air filter system, the air compressor and the respiratory air supply unit. The aforementioned components are placed on the steel platform and have been encased in a sound-lowering and accessible manner. New construction of the entire E and C technology for the TU system including modification of the supply lines from the switch gear. All devices are to be operated automatically. Dry blasting box, high pressure water decontamination box and wet area are designed to guarantee a unitary 'exterior view' of the decontamination facility. (authors)

  9. Decontamination of water using nitrate selective ion exchange resin

    DOE Patents [OSTI]

    Lockridge, J.E.; Fritz, J.S.

    1990-07-31T23:59:59.000Z

    A method for nitrate decontamination of water which involves passing the water through a bed of alkyl phosphonium anion exchange resin which has pendant alkyl groups of C[sub 3] or larger.

  10. abrasive decontamination operating: Topics by E-print Network

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

    n Radiation 2.10 Decontamination Methods 12;n Types n Moist - steam n Dry n Incineration *The most effective method Collins, Gary S. 4 Abrasion of flat rotating shapes...

  11. Decontamination of water using nitrate selective ion exchange resin

    DOE Patents [OSTI]

    Lockridge, James E. (Ames, IA); Fritz, James S. (Ames, IA)

    1990-07-31T23:59:59.000Z

    A method for nitrate decontamination of water which involves passing the water through a bed of alkyl phosphonium anion exchange resin which has pendant alkyl groups of C.sub.3 or larger.

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

    SciTech Connect (OSTI)

    NONE

    1994-09-01T23:59:59.000Z

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

  13. NOVEL SALTS OF GRAPHITE AND A BORON NITRIDE SALT

    E-Print Network [OSTI]

    Bartlett, Neil

    2011-01-01T23:59:59.000Z

    ~ i\\f'{y AND DOCUMENTS SECTION NOVEL SALTS OF GRAPHITE ANDA BORON NITRIDE SALT Neil Bartlett, R. N. Biagioni, B. W.privately owned rights. Novel Salts of Graphite and a Boron

  14. Molecular dynamics simulations of the effects of salts on the aggregation properties of benzene in water.

    SciTech Connect (OSTI)

    Smith, P. E.

    2003-07-16T23:59:59.000Z

    The specific aims of the project were: to provide an atomic level description of the interactions between benzene, water and ions in solutions. To determine the degree of association between two benzene molecules in aqueous and salt solutions. To investigate the structure and dynamics of the interface between benzene and water or salt solution.

  15. Demonstration recommendations for accelerated testing of concrete decontamination methods

    SciTech Connect (OSTI)

    Dickerson, K.S.; Ally, M.R.; Brown, C.H.; Morris, M.I.; Wilson-Nichols, M.J.

    1995-12-01T23:59:59.000Z

    A large number of aging US Department of Energy (DOE) surplus facilities located throughout the US require deactivation, decontamination, and decommissioning. Although several technologies are available commercially for concrete decontamination, emerging technologies with potential to reduce secondary waste and minimize the impact and risk to workers and the environment are needed. In response to these needs, the Accelerated Testing of Concrete Decontamination Methods project team described the nature and extent of contaminated concrete within the DOE complex and identified applicable emerging technologies. Existing information used to describe the nature and extent of contaminated concrete indicates that the most frequently occurring radiological contaminants are {sup 137}Cs, {sup 238}U (and its daughters), {sup 60}Co, {sup 90}Sr, and tritium. The total area of radionuclide-contaminated concrete within the DOE complex is estimated to be in the range of 7.9 {times} 10{sup 8} ft{sup 2}or approximately 18,000 acres. Concrete decontamination problems were matched with emerging technologies to recommend demonstrations considered to provide the most benefit to decontamination of concrete within the DOE complex. Emerging technologies with the most potential benefit were biological decontamination, electro-hydraulic scabbling, electrokinetics, and microwave scabbling.

  16. Anthrax Sampling and Decontamination: Technology Trade-Offs

    SciTech Connect (OSTI)

    Price, Phillip N.; Hamachi, Kristina; McWilliams, Jennifer; Sohn, Michael D.

    2008-09-12T23:59:59.000Z

    The goal of this project was to answer the following questions concerning response to a future anthrax release (or suspected release) in a building: 1. Based on past experience, what rules of thumb can be determined concerning: (a) the amount of sampling that may be needed to determine the extent of contamination within a given building; (b) what portions of a building should be sampled; (c) the cost per square foot to decontaminate a given type of building using a given method; (d) the time required to prepare for, and perform, decontamination; (e) the effectiveness of a given decontamination method in a given type of building? 2. Based on past experience, what resources will be spent on evaluating the extent of contamination, performing decontamination, and assessing the effectiveness of the decontamination in abuilding of a given type and size? 3. What are the trade-offs between cost, time, and effectiveness for the various sampling plans, sampling methods, and decontamination methods that have been used in the past?

  17. Hybrid Molten Salt Reactor (HMSR) System Study

    SciTech Connect (OSTI)

    Woolley, Robert D [PPPL; Miller, Laurence F [PPPL

    2014-04-01T23:59:59.000Z

    Can the hybrid system combination of (1) a critical fission Molten Salt Reactor (MSR) having a thermal spectrum and a high Conversion Ratio (CR) with (2) an external source of high energy neutrons provide an attractive solution to the world's expanding demand for energy? The present study indicates the answer is an emphatic yes.

  18. Fracture of porous materials induced by crystallization of salt

    E-Print Network [OSTI]

    Katzoff, Golda Y

    2006-01-01T23:59:59.000Z

    The penetration of salt into porous materials is known to have deleterious effects, often resulting in fracture. The damage process begins with a saline solution penetrating the porous network by way of capillary action. ...

  19. Molten salt electrolyte separator

    DOE Patents [OSTI]

    Kaun, T.D.

    1996-07-09T23:59:59.000Z

    The patent describes a molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication. 5 figs.

  20. Unusual Salt Stability in Highly Charged Diblock Co-polypeptide Hydrogels

    E-Print Network [OSTI]

    Breedveld, Victor

    Unusual Salt Stability in Highly Charged Diblock Co-polypeptide Hydrogels Andrew P. Nowak, Victor of poly(L-lysine HBr) or poly(L-glutamic acid sodium salt), and helical, hydrophobic segments of poly as low as 0.25 wt %, stability in salt or buffer solutions was found to be only achieved at moderately

  1. Hydrotropic salt promotes anionic surfactant self-assembly into vesicles and ultralong fibers

    E-Print Network [OSTI]

    Huang, Jianbin

    Hydrotropic salt promotes anionic surfactant self-assembly into vesicles and ultralong fibers November 2011 Available online 6 December 2011 Keywords: Surfactant self-assembly Hydrotropic salt Fiber dodecylbenzene sulfo- nate, SDBS) and a hydrotropic salt (benzylamine hydrochloride, BzCl) in aqueous solution

  2. A LARGE SCALE CONTINUUM-DISCRETE NUMERICAL MODELLING: APPLICATION TO OVERBURDEN DAMAGE OF A SALT CAVERN

    E-Print Network [OSTI]

    Boyer, Edmond

    A LARGE SCALE CONTINUUM-DISCRETE NUMERICAL MODELLING: APPLICATION TO OVERBURDEN DAMAGE OF A SALT damage on top of an underground solution mining, an in-situ experiment is undertaken above a salt cavity in the Lorraine region (NE of France). The overburden overlying the salt cavity is characterized by a competent

  3. Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives

    SciTech Connect (OSTI)

    Elder, H.H.

    2001-07-11T23:59:59.000Z

    The HLW salt waste (salt cake and supernate) now stored at the SRS must be treated to remove insoluble sludge solids and reduce the soluble concentration of radioactive cesium radioactive strontium and transuranic contaminants (principally Pu and Np). These treatments will enable the salt solution to be processed for disposal as saltstone, a solid low-level waste.

  4. Mobile workstation for decontamination and decommissioning operations

    SciTech Connect (OSTI)

    Whittaker, W.L.; Osborn, J.F.; Thompson, B.R. [Carnegie-Mellon Univ., Pittsburgh, PA (United States). Robotics Inst.

    1993-10-01T23:59:59.000Z

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The project has three phases. In this the first phase, an existing teleoperated worksystem, the Remote Work Vehicle (developed for use in the Three Mile Island Unit 2 Reactor Building basement), was enhanced for telerobotic performance of several D&D operations. Its ability to perform these operations was then assessed through a series of tests in a mockup facility that contained generic structures and equipment similar to those that D&D work machines will encounter in DOE facilities. Building upon the knowledge gained through those tests and evaluations, a next generation mobile worksystem, the RWV II, and a more advanced controller will be designed, integrated and tested in the second phase, which is scheduled for completion in January 1995. The third phase of the project will involve testing of the RWV II in the real DOE facility.

  5. Kit systems for granulated decontamination formulations

    DOE Patents [OSTI]

    Tucker, Mark D. (Albuquerque, NM)

    2010-07-06T23:59:59.000Z

    A decontamination formulation and method of making that neutralizes the adverse health effects of both chemical and biological compounds, especially chemical warfare (CW) and biological warfare (BW) agents, and toxic industrial chemicals. The formulation provides solubilizing compounds that serve to effectively render the chemical and biological compounds, particularly CW and BW compounds, susceptible to attack, and at least one reactive compound that serves to attack (and detoxify or kill) the compound. The formulation includes at least one solubilizing agent, a reactive compound, a sorbent additive, and water. A highly adsorbent sorbent additive (e.g., amorphous silica, sorbitol, mannitol, etc.) is used to "dry out" one or more liquid ingredients into a dry, free-flowing powder that has an extended shelf life, and is more convenient to handle and mix in the field. The formulation can be pre-mixed and pre-packaged as a multi-part kit system, where one or more of the parts are packaged in a powdered, granulated form for ease of handling and mixing in the field.

  6. A simplified model of decontamination by BWR steam suppression pools

    SciTech Connect (OSTI)

    Powers, D.A.

    1997-05-01T23:59:59.000Z

    Phenomena that can decontaminate aerosol-laden gases sparging through steam suppression pools of boiling water reactors during reactor accidents are described. Uncertainties in aerosol properties, aerosol behavior within gas bubbles, and bubble behavior in plumes affect predictions of decontamination by steam suppression pools. Uncertainties in the boundary and initial conditions that are dictated by the progression of severe reactor accidents and that will affect predictions of decontamination by steam suppression pools are discussed. Ten parameters that characterize boundary and initial condition uncertainties, nine parameters that characterize aerosol property and behavior uncertainties, and eleven parameters that characterize uncertainties in the behavior of bubbles in steam suppression pools are identified. Ranges for the values of these parameters and subjective probability distributions for parametric values within the ranges are defined. These uncertain parameters are used in Monte Carlo uncertainty analyses to develop uncertainty distributions for the decontamination that can be achieved by steam suppression pools and the size distribution of aerosols that do emerge from such pools. A simplified model of decontamination by steam suppression pools is developed by correlating features of the uncertainty distributions for total decontamination factor, DF(total), mean size of emerging aerosol particles, d{sub p}, and the standard deviation of the emerging aerosol size distribution, {sigma}, with pool depth, H. Correlations of the median values of the uncertainty distributions are suggested as the best estimate of decontamination by suppression pools. Correlations of the 10 percentile and 90 percentile values of the uncertainty distributions characterize the uncertainty in the best estimates. 295 refs., 121 figs., 113 tabs.

  7. On-Site Decontamination System for Liquid Low Level Radioactive Waste - 13010

    SciTech Connect (OSTI)

    OSMANLIOGLU, Ahmet Erdal [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)] [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)

    2013-07-01T23:59:59.000Z

    This study is based on an evaluation of purification methods for liquid low-level radioactive waste (LLLW) by using natural zeolite. Generally the volume of liquid low-level waste is relatively large and the specific activity is rather low when compared to other radioactive waste types. In this study, a pilot scale column was used with natural zeolite as an ion exchanger media. Decontamination and minimization of LLLW especially at the generation site decrease operational cost in waste management operations. Portable pilot scale column was constructed for decontamination of LLW on site. Effect of temperature on the radionuclide adsorption of the zeolite was determined to optimize the waste solution temperature for the plant scale operations. In addition, effect of pH on the radionuclide uptake of the zeolite column was determined to optimize the waste solution pH for the plant scale operations. The advantages of this method used for the processing of LLLW are discussed in this paper. (authors)

  8. MERCURY CONTAMINATED MATERIAL DECONTAMINATION METHODS: INVESTIGATION AND ASSESSMENT

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    2001-01-01T23:59:59.000Z

    Over the years mercury has been recognized as having serious impacts on human health and the environment. This recognition has led to numerous studies that deal with the properties of various mercury forms, the development of methods to quantify and speciate the forms, fate and transport, toxicology studies, and the development of site remediation and decontamination technologies. This report reviews several critical areas that will be used in developing technologies for cleaning mercury from mercury-contaminated surfaces of metals and porous materials found in many DOE facilities. The technologies used for decontamination of water and mixed wastes (solid) are specifically discussed. Many technologies that have recently appeared in the literature are included in the report. Current surface decontamination processes have been reviewed, and the limitations of these technologies for mercury decontamination are discussed. Based on the currently available technologies and the processes published recently in the literature, several processes, including strippable coatings, chemical cleaning with iodine/iodide lixiviant, chemisorbing surface wipes with forager sponge and grafted cotton, and surface/pore fixation through amalgamation or stabilization, have been identified as potential techniques for decontamination of mercury-contaminated metal and porous surfaces. Their potential merits and applicability are discussed. Finally, two processes, strippable coatings and chemical cleaning with iodine/iodide lixiviant, were experimentally investigated in Phase II of this project.

  9. A review of plant decontamination methods: 1988 Update: Final report

    SciTech Connect (OSTI)

    Remark, J.F.

    1989-01-01T23:59:59.000Z

    This document updates the state-of-the-art in decontamination technology since the publication of the previous review (EPRI NP- 1128) in May 1981. A brief description of the corrosion-film characteristics is presented as well as corrosion film differences between a BWR and PWR. The generation transportation, activation, and deposition of the radioisotopes found throughout the reactor coolant system is also discussed. Successful, well executed, decontamination campaigns are always preceded by meticulous planning and careful procedure preparation which include contingency operations. The Decontamination Planning and Preparation Section describes the technical planning steps as well as the methodology that should be followed in order to select the optimum decontamination technique for a specific application. A review of a number of the decontamination methods commercialized since 1980 is presented. The basic mechanism for each process is described as well as specific applications of the technology in the fields. Where possible, results obtained in the field are presented. The information was obtained from industry vendors as well as personnel at the plant locations that have utilized the technology. 72 refs., 5 tabs.

  10. Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part A, Decontamination and Decommissioning

    SciTech Connect (OSTI)

    Not Available

    1993-09-01T23:59:59.000Z

    This report documents activities of decontamination and decommissioning at ORNL. Topics discussed include general problems, waste types, containment, robotics automation and decontamination processes.

  11. Amine salts of nitroazoles

    DOE Patents [OSTI]

    Kienyin Lee; Stinecipher, M.M.

    1993-10-26T23:59:59.000Z

    Compositions of matter, a method of providing chemical energy by burning said compositions, and methods of making said compositions are described. These compositions are amine salts of nitroazoles. 1 figure.

  12. Technology needs for decommissioning and decontamination

    SciTech Connect (OSTI)

    Bundy, R.D.; Kennerly, J.M.

    1993-12-01T23:59:59.000Z

    This report summarizes the current view of the most important decontamination and decommissioning (D & D) technology needs for the US Department of Energy facilities for which the D & D programs are the responsibility of Martin Marietta Energy Systems, Inc. The source of information used in this assessment was a survey of the D & D program managers at each facility. A summary of needs presented in earlier surveys of site needs in approximate priority order was supplied to each site as a starting point to stimulate thinking. This document reflects a brief initial assessment of ongoing needs; these needs will change as plans for D & D are finalized, some of the technical problems are solved through successful development programs, and new ideas for D and D technologies appear. Thus, this assessment should be updated and upgraded periodically, perhaps, annually. This assessment differs from others that have been made in that it directly and solely reflects the perceived need for new technology by key personnel in the D & D programs at the various facilities and does not attempt to consider the likelihood that these technologies can be successfully developed. Thus, this list of technology needs also does not consider the cost, time, and effort required to develop the desired technologies. An R & D program must include studies that have a reasonable chance for success as well as those for which there is a high need. Other studies that considered the cost and probability of successful development as well as the need for new technology are documented. However, the need for new technology may be diluted in such studies; this document focuses only on the need for new technology as currently perceived by those actually charged with accomplishing D & D.

  13. Brine flow in heated geologic salt.

    SciTech Connect (OSTI)

    Kuhlman, Kristopher L.; Malama, Bwalya

    2013-03-01T23:59:59.000Z

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

  14. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    radiological exposures may also present first to healthcare facilities.facility-based decontamination of victims exposed to chemical, biological, and radiologicalfacility-based decontamination of victims exposed to chemical, biological, and radiological

  15. An Unsupervised Decontamination Procedure For Improving The Reliability Of Human Judgments

    E-Print Network [OSTI]

    Mozer, Michael C.

    An Unsupervised Decontamination Procedure For Improving The Reliability Of Human Judgments Michael decontaminate a series of ratings to obtain more mean- ingful human judgments. In our formulation, the problem

  16. Method for decontamination of radioactive metal surfaces

    DOE Patents [OSTI]

    Bray, L.A.

    1996-08-13T23:59:59.000Z

    Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

  17. Method for decontamination of radioactive metal surfaces

    DOE Patents [OSTI]

    Bray, Lane A. (Richland, WA)

    1996-01-01T23:59:59.000Z

    Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

  18. Testing and evaluation of electrokinetic decontamination of concrete

    SciTech Connect (OSTI)

    DePaoli, D.W.; Harris, M.T.; Ally, M.R. [Oak Ridge National Lab., TN (United States). Chemical Technology Div.] [and others

    1996-10-01T23:59:59.000Z

    The goals and objectives of the technical task plan (TTP) are to (1) describe the nature and extent of concrete contamination within the Department of Energy (DOE) complex and emerging and commercial technologies applicable to these problems; (2) to match technologies to the concrete problems and recommend up to four demonstrations; (3) to initiate recommended demonstrations; and (4) to continue investigation and evaluation of the application of electrokinetic decontamination processes to concrete. This document presents findings of experimental and theoretical studies of the electrokinetic decontamination (EK) process and their implications for field demonstrations. This effort is an extension of the work performed under TTP 142005, ``Electroosmotic Concrete Decontamination. The goals of this task were to determine the applicability of EK for treating contaminated concrete and, if warranted, to evaluate EK as a potential technology for demonstration. 62 refs.

  19. Systems analysis of decontamination options for civilian vehicles.

    SciTech Connect (OSTI)

    Foltz, Greg W.; Hoette, Trisha Marie

    2010-11-01T23:59:59.000Z

    The objective of this project, which was supported by the Department of Homeland Security (DHS) Science and Technology Directorate (S&T) Chemical and Biological Division (CBD), was to investigate options for the decontamination of the exteriors and interiors of vehicles in the civilian setting in order to restore those vehicles to normal use following the release of a highly toxic chemical. The decontamination of vehicles is especially challenging because they often contain sensitive electronic equipment, multiple materials some of which strongly adsorb chemical agents, and in the case of aircraft, have very rigid material compatibility requirements (i.e., they cannot be exposed to reagents that may cause even minor corrosion). A systems analysis approach was taken examine existing and future civilian vehicle decontamination capabilities.

  20. Decontamination of Dredged Material from The Port of New York and New Jersey

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Decontamination of Dredged Material from The Port of New York and New Jersey .K.W. Jones Brookhaven copyrightcoveringthispaper. #12;Decontamination of Dredged Material from The Port of New York and New Jersey K. W. Jones the dredging operations required for the efficient operation of the Port. Decontamination and beneficial reuse

  1. Comparison of Different Decontaminant Delivery Methods for Sterilizing1 Unoccupied Commercial Airliner Cabins2

    E-Print Network [OSTI]

    Chen, Qingyan "Yan"

    1 Comparison of Different Decontaminant Delivery Methods for Sterilizing1 Unoccupied Commercial as a tool and vaporized hydrogen12 peroxide (VHP) as an exem plary decontaminant and Geobacillus efficacy data from the literature. The th ree decontaminant delivery19 methods were (1) to supply the mixed

  2. Process for decontaminating radioactive liquids using a calcium cyanamide-containing composition. [Patent application

    DOE Patents [OSTI]

    Silver, G.L.

    1980-09-24T23:59:59.000Z

    The present invention provides a process for decontaminating a radioactive liquid containing a radioactive element capable of forming a hydroxide. This process includes the steps of contacting the radioactive liquid with a decontaminating composition and separating the resulting radioactive sludge from the resulting liquid. The decontaminating composition contains calcium cyanamide.

  3. Journal of Hazardous Materials 85 (2001) 127143 Dredged material decontamination demonstration

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    2001-01-01T23:59:59.000Z

    Journal of Hazardous Materials 85 (2001) 127­143 Dredged material decontamination demonstration component of an overall management plan can be the application of a decontamination technology followed material; Decontamination; Beneficial use; Commercialization; NY/NJ Harbor Corresponding author. Tel.: +1

  4. Introduction and Case Studies The Ratio Plot Under Homogeneity and the Decontaminated Turing

    E-Print Network [OSTI]

    Boehning, Dankmar

    Outline Introduction and Case Studies The Ratio Plot Under Homogeneity and the Decontaminated Introduction and Case Studies The Ratio Plot Under Homogeneity and the Decontaminated Turing The Ratio Plot The Ratio Plot Under Homogeneity and the Decontaminated Turing The Ratio Plot and Structured Heterogeneity

  5. Decontamination and demolition of a former plutonium processing facility`s process exhaust system, firescreen, and filter plenum buildings

    SciTech Connect (OSTI)

    LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

    1996-03-01T23:59:59.000Z

    The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-2 1). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases.

  6. Decontamination and demolition of a former plutonium processing facility`s process exhaust system, firescreen, and filter plenum buildings

    SciTech Connect (OSTI)

    LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

    1996-04-01T23:59:59.000Z

    The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-21). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases.

  7. Phase diagram of mechanically stretched DNA: The salt effect

    E-Print Network [OSTI]

    Amar Singh; Navin Singh

    2014-09-05T23:59:59.000Z

    The cations, in form of salt, present in the solution containing DNA play a crucial role in the opening of two strands of DNA. We use a simple non linear model and investigate the role of these cations on the mechanical unzipping of DNA. The Hamiltonian is modified to incoporate the solvent effect and the cations present in the solution. We calculate the melting temperature as well as the critical force that is required to unzip the DNA molecule as a function of salt concentration of the solution. The phase diagrams are found to be in close agreement with the experimental phase diagrams.

  8. Gas releases from salt

    SciTech Connect (OSTI)

    Ehgartner, B.; Neal, J.; Hinkebein, T.

    1998-06-01T23:59:59.000Z

    The occurrence of gas in salt mines and caverns has presented some serious problems to facility operators. Salt mines have long experienced sudden, usually unexpected expulsions of gas and salt from a production face, commonly known as outbursts. Outbursts can release over one million cubic feet of methane and fractured salt, and are responsible for the lives of numerous miners and explosions. Equipment, production time, and even entire mines have been lost due to outbursts. An outburst creates a cornucopian shaped hole that can reach heights of several hundred feet. The potential occurrence of outbursts must be factored into mine design and mining methods. In caverns, the occurrence of outbursts and steady infiltration of gas into stored product can effect the quality of the product, particularly over the long-term, and in some cases renders the product unusable as is or difficult to transport. Gas has also been known to collect in the roof traps of caverns resulting in safety and operational concerns. The intent of this paper is to summarize the existing knowledge on gas releases from salt. The compiled information can provide a better understanding of the phenomena and gain insight into the causative mechanisms that, once established, can help mitigate the variety of problems associated with gas releases from salt. Outbursts, as documented in mines, are discussed first. This is followed by a discussion of the relatively slow gas infiltration into stored crude oil, as observed and modeled in the caverns of the US Strategic Petroleum Reserve. A model that predicts outburst pressure kicks in caverns is also discussed.

  9. COMPARING DETECTION METHODS OF AFLATOXIN AND EXPLORING AFLATOXIN DECONTAMINATION METHODS

    E-Print Network [OSTI]

    Ray, David

    DECONTAMINATION METHODS Pages in Study: 81 Candidate for Degree of Master of Science Ethanol fermentation if aflatoxin concentrated in the distilled ethanol and/or dry distillers grain end-products. Alliquots of fermented mash, distilled ethanol, stillage, and dry distillers grain (DDG) were analyzed via LC

  10. Atmospheric-pressure plasma decontamination/sterilization chamber

    DOE Patents [OSTI]

    Herrmann, Hans W. (Los Alamos, NM); Selwyn, Gary S. (Los Alamos, NM)

    2001-01-01T23:59:59.000Z

    An atmospheric-pressure plasma decontamination/sterilization chamber is described. The apparatus is useful for decontaminating sensitive equipment and materials, such as electronics, optics and national treasures, which have been contaminated with chemical and/or biological warfare agents, such as anthrax, mustard blistering agent, VX nerve gas, and the like. There is currently no acceptable procedure for decontaminating such equipment. The apparatus may also be used for sterilization in the medical and food industries. Items to be decontaminated or sterilized are supported inside the chamber. Reactive gases containing atomic and metastable oxygen species are generated by an atmospheric-pressure plasma discharge in a He/O.sub.2 mixture and directed into the region of these items resulting in chemical reaction between the reactive species and organic substances. This reaction typically kills and/or neutralizes the contamination without damaging most equipment and materials. The plasma gases are recirculated through a closed-loop system to minimize the loss of helium and the possibility of escape of aerosolized harmful substances.

  11. Ris-R-1029(EN) Mechanical decontamination tests in

    E-Print Network [OSTI]

    Risø-R-1029(EN) Mechanical decontamination tests in areas affected by the Chernobyl accident J of one of the houses was replaced with a new roof. This reduced the Chernobyl related dose rate by 10;3 Contents 1 Introduction 7 1.1 The Chernobyl Accident 7 1.2 The Contamination of Novozybkov district 8 1

  12. Chemical decontamination technical resources at Los Alamos National Laboratory (2008)

    SciTech Connect (OSTI)

    Moore, Murray E [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    This document supplies information resources for a person seeking to create planning or pre-planning documents for chemical decontamination operations. A building decontamination plan can be separated into four different sections: Pre-planning, Characterization, Decontamination (Initial response and also complete cleanup), and Clearance. Of the identified Los Alamos resources, they can be matched with these four sections: Pre-planning -- Dave Seidel, EO-EPP, Emergency Planning and Preparedness; David DeCroix and Bruce Letellier, D-3, Computational fluids modeling of structures; Murray E. Moore, RP-2, Aerosol sampling and ventilation engineering. Characterization (this can include development projects) -- Beth Perry, IAT-3, Nuclear Counterterrorism Response (SNIPER database); Fernando Garzon, MPA-11, Sensors and Electrochemical Devices (development); George Havrilla, C-CDE, Chemical Diagnostics and Engineering; Kristen McCabe, B-7, Biosecurity and Public Health. Decontamination -- Adam Stively, EO-ER, Emergency Response; Dina Matz, IHS-IP, Industrial hygiene; Don Hickmott, EES-6, Chemical cleanup. Clearance (validation) -- Larry Ticknor, CCS-6, Statistical Sciences.

  13. Controlled black liquor viscosity reduction through salting-in

    SciTech Connect (OSTI)

    Roberts, J.E.; Khan, S.A.; Spontak, R.J. [North Carolina State Univ., Raleigh, NC (United States)] [North Carolina State Univ., Raleigh, NC (United States)

    1996-08-01T23:59:59.000Z

    Black liquor viscosity increases exponentially with solids content and therefore causes processing problems for the paper industry by being a limiting factor in the Kraft pulp process. This study investigates a new approach for achieving viscosity reduction by salting-in black liquor through the addition of thiocyanate salts. These salts generally increase the solubility of the polymer constituents in black liquor, leading to a decrease in its viscosity. Several thiocyanate salts capable of reducing liquor viscosity by more than two orders of magnitude have been identified, with viscosity reduction greatest at high solids content. Salting-in of black liquor depends on the cation paired with the thiocyanate anion, as well as on solution pH and temperature. Comparative studies reveal the most effective viscosity-reducing agent of the series examined and that lignin plays an important role in the viscosity behavior of both unmodified and salted-in black liquor at high solids concentrations. These experimental findings are interpreted in terms of the underlying principles that describe salting-in and how it affects aqueous solution structure.

  14. Decontamination Processes for Restorative Operations and as a Precursor to Decommissioning: A Literature Review

    SciTech Connect (OSTI)

    Nelson, J. L.; Divine, J. R.

    1981-05-01T23:59:59.000Z

    Pacific Northwest Laboratory (PNL) conducted an comprehensive literature review of actual reactor decontamination processes that are currently available. In general, any decontamination process should be based on the following criteria: effectiveness, efficiency, safety, and waste production. The information that was collected and analyzed has been divided into three major categories of decontamination: chemical, mechanical, and electrochemical. Chemical methods can be further classified as either low-concentration, singlestep processes or high-concentration, single- or multistep processes. Numerous chemical decontamination methods are detailed. Mechanical decontamination methods are usually restricted to the removal of a contaminated surface layer, whlch limits their versatility; several mechanical decontamination methods are described. Electrochemical decontamination. is both fast and easily controlled, and numerous processes that have been used in industry for many years are discussed. Information obtained from this work is tabulated in Appendix A for easy access, and a bibliography and a glossary have been provided.

  15. The Thorium Molten Salt Reactor : Moving on from the MSBR

    E-Print Network [OSTI]

    L. Mathieu; D. Heuer; R. Brissot; C. Le Brun; E. Liatard; J. M. Loiseaux; O. Méplan; E. Merle-Lucotte; A. Nuttin; J. Wilson; C. Garzenne; D. Lecarpentier; E. Walle; the GEDEPEON Collaboration

    2005-06-02T23:59:59.000Z

    A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered. A reflection is carried out anew in view of finding innovative solutions leading to the Thorium Molten Salt Reactor concept. Several main constraints are established and serve as guides to parametric evaluations. These then give an understanding of the influence of important core parameters on the reactor's operation. The aim of this paper is to discuss this vast research domain and to single out the Molten Salt Reactor configurations that deserve further evaluation.

  16. The Estimation of Salt and Molasses in Mixed Feeds

    E-Print Network [OSTI]

    Fraps, G. S. (George Stronach)

    1931-01-01T23:59:59.000Z

    . THE ESTIMATION OF SALT The method described in Bulletin 271 referred to above, consists briefly in extracting the salt from 5.55 gm. of the feed with about 200 cc. water, purifying the extract by means of carbon black or lead acetate, making up to 200 cc... described in this publication is based upon the method of E. R. Theis, published in the Chemist-Analyst, No. 41, 1924, and consists in extracting the salt with a solution of picric acid, neutral- izing with calcium carbonate, and titrating an aliquot...

  17. The Thorium Molten Salt Reactor Moving on from the MSBR

    E-Print Network [OSTI]

    Mathieu, L; Brissot, R; Le Brun, C; Liatard, E; Loiseaux, J M; Méplan, O; Merle-Lucotte, E; Nuttin, A; Wilson, J; Garzenne, C; Lecarpentier, D; Walle, E

    2006-01-01T23:59:59.000Z

    A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered. A reflection is carried out anew in view of finding innovative solutions leading to the Thorium Molten Salt Reactor concept. Several main constraints are established and serve as guides to parametric evaluations. These then give an understanding of the influence of important core parameters on the reactor's operation. The aim of this paper is to discuss this vast research domain and to single out the Molten Salt Reactor configurations that deserve further evaluation.

  18. RECHARGEABLE MOLTEN-SALT CELLS

    E-Print Network [OSTI]

    Cairns, Elton J.

    2013-01-01T23:59:59.000Z

    KC! /FeS 2 cell lithium-silicon magnesium oxide molten-saltmolten-salt cells Na/Na glass/Na:z.Sn-S cell Na/NazO•xA!Symposium on Molten Salts, Physical Electrochemistry

  19. Process for cesium decontamination and immobilization

    DOE Patents [OSTI]

    Komarneni, Sridhar (Altoona, PA); Roy, Rustum (State College, PA)

    1989-01-01T23:59:59.000Z

    Cesium can be selectively recovered from a nuclear waste solution containing cesium together with other metal ions by contact with a modified phlogopite which is a hydrated, sodium phlogopite mica. Once the cesium has entered the modified phlogopite it is fixed and can be safely stored for long periods of time.

  20. Process for cesium decontamination and immobilization

    DOE Patents [OSTI]

    Komarneni, S.; Roy, R.

    1988-04-25T23:59:59.000Z

    Cesium can be selectively recovered from a nuclear waste solution containing cesium together with other metal ions by contact with a modified phlogopite which is a hydrated, sodium phlogopite mica. Once the cesium has entered the modified phlogopite it is fixed and can be safely stored for long periods of time. 6 figs., 2 tabs.

  1. APPLICATIONS OF SALT IN ELECTROFISHING

    E-Print Network [OSTI]

    APPLICATIONS OF SALT IN ELECTROFISHING iNlarine Biological Laboratory LIB55.A.K.Y WOODS HOLE, MASS OF SALT IN ELECTROFISHING By Robert E . Lennon and Phillip S . Parker Fishery Research Biologists Leetown. Electric fisliliiK. 2. Salt. i. Farker, Phillip Slieridaii, 192t>- .joiut author, ii. Title. ( Series : IT

  2. Improved Saltstone Facilities Restart Operations | Department...

    Office of Environmental Management (EM)

    to provide a new and more reliable system to process larger amounts of decontaminated salt solution needed for future tank closure operations. Saltstone processs and disposes of...

  3. Decontamination analysis of the NUWAX-83 accident site using DECON

    SciTech Connect (OSTI)

    Tawil, J.J.

    1983-11-01T23:59:59.000Z

    This report presents an analysis of the site restoration options for the NUWAX-83 site, at which an exercise was conducted involving a simulated nuclear weapons accident. This analysis was performed using a computer program deveoped by Pacific Northwest Laboratory. The computer program, called DECON, was designed to assist personnel engaged in the planning of decontamination activities. The many features of DECON that are used in this report demonstrate its potential usefulness as a site restoration planning tool. Strategies that are analyzed with DECON include: (1) employing a Quick-Vac option, under which selected surfaces are vacuumed before they can be rained on; (2) protecting surfaces against precipitation; (3) prohibiting specific operations on selected surfaces; (4) requiring specific methods to be used on selected surfaces; (5) evaluating the trade-off between cleanup standards and decontamination costs; and (6) varying of the cleanup standards according to expected exposure to surface.

  4. Membership Probability via Control Field Colour-Magnitude Decontamination

    E-Print Network [OSTI]

    Corradi, Wagner J B; Santos, Joao F C

    2009-01-01T23:59:59.000Z

    The open clusters fundamental physical parameters are important tools to understand the formation and evolution of the Galactic disk and as grounding tests for star formation and evolution models. However only a small fraction of the known open clusters in the Milky Way has precise determination of distance, reddening, age, metallicity, radial velocity and proper motion. One of the major problems in determining these parameters lies on the difficulty to separate cluster members from field stars and to assign membership. We propose a decontamination method by employing 2MASS data in the encircling region of the clusters NGC1981, NGC2516, NGC6494 and M11. We present a decontaminated CMD of these objects showing the membership probabilities and structural parameters as derived from King profile fitting.

  5. Testing of a portable ultrahigh pressure water decontamination system (UHPWDS)

    SciTech Connect (OSTI)

    Lovell, A.; Dahlby, J.

    1996-02-01T23:59:59.000Z

    This report describes the tests done with a portable ultrahigh pressure water decontamination system (UHPWDS) on highly radioactively contaminated surfaces. A small unit was purchased, modified, and used for in-situ decontamination to change the waste level of the contaminated box from transuranic (TRU) waste to low- level waste (LLW). Low-level waste is less costly by as much as a factor of five or more if compared with TRU waste when handling, storage, and disposal are considered. The portable unit we tested is commercially available and requires minimal utilities for operation. We describe the UHPWDS unit itself, a procedure for its use, the results of the testing we did, and conclusions including positive and negative aspects of the UHPWDS.

  6. Development of simulated contamination (SIMCON) and miscellaneous decontamination scoping tests

    SciTech Connect (OSTI)

    Demmer, R.L.

    1994-01-01T23:59:59.000Z

    This report details the development of a method of simulating ICPP type contamination (SIMCON) with surrogate, nonradioactive materials and some miscellaneous testing and results that were completed using SIMCON. An analysis of historical ICPP decontamination samples is given, along with the justification relating SIMCON to this historical data. Some SIMCON testing of the following methods are given as miscellaneous examples: water rinse, water ultrasonic, cerric nitrate, CO{sub 2} snowflake blasting, nitrogen ``Cryogenic`` blasting and strippable coating removal.

  7. Proceedings: Decommissioning, Decontamination, ALARA, and Worker Safety Workshop

    SciTech Connect (OSTI)

    None

    2000-09-01T23:59:59.000Z

    This workshop on decontamination, ALARA, and worker safety was the sixth in a series initiated by EPRI to aid utility personnel in assessing the technologies for decommissioning nuclear power plants. The workshop focused on specific aspects of decommissioning related to the management of worker radiation exposure and safety. The information presented will help individual utilities assess benefits of programs in these areas for their projects, including their potential to reduce decommissioning costs.

  8. Assessment of strippable coatings for decontamination and decommissioning

    SciTech Connect (OSTI)

    Ebadian, M.A.

    1998-01-01T23:59:59.000Z

    Strippable or temporary coatings were developed to assist in the decontamination of the Three Mile Island (TMI-2) reactor. These coatings have become a viable option during the decontamination and decommissioning (D and D) of both US Department of Energy (DOE) and commercial nuclear facilities to remove or fix loose contamination on both vertical and horizontal surfaces. A variety of strippable coatings are available to D and D professionals. However, these products exhibit a wide range of performance criteria and uses. The Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU) was commissioned to perform a 2-year investigation into strippable coatings. This investigation was divided into four parts: (1) identification of commercially available strippable coating products; (2) survey of D and D professionals to determine current uses of these coatings and performance criteria; (3) design and implementation of a non-radiological testing program to evaluate the physical properties of these coatings; and (4) design and implementation of a radiological testing program to determine decontamination factors and effects of exposure to ionizing radiation. Activities during fiscal year 1997 are described.

  9. Decontamination and decommissioning of the Mayaguez (Puerto Rico) facility

    SciTech Connect (OSTI)

    Jackson, P.K.; Freemerman, R.L. [Bechtel National, Inc., Oak Ridge, TN (United States)

    1989-11-01T23:59:59.000Z

    On February 6, 1987 the US Department of Energy (DOE) awarded the final phase of the decontamination and decommissioning of the nuclear and reactor facilities at the Center for Energy and Environmental Research (CEER), in Mayaguez, Puerto Rico. Bechtel National, Inc., was made the decontamination and decommissioning (D and D) contractor. The goal of the project was to enable DOE to proceed with release of the CEER facility for use by the University of Puerto Rico, who was the operator. This presentation describes that project and lesson learned during its progress. The CEER facility was established in 1957 as the Puerto Rico Nuclear Center, a part of the Atoms for Peace Program. It was a nuclear training and research institution with emphasis on the needs of Latin America. It originally consisted of a 1-megawatt Materials Testing Reactor (MTR), support facilities and research laboratories. After eleven years of operation the MTR was shutdown and defueled. A 2-megawatt TRIGA reactor was installed in 1972 and operated until 1976, when it woo was shutdown. Other radioactive facilities at the center included a 10-watt homogeneous L-77 training reactor, a natural uranium graphite-moderated subcritical assembly, a 200KV particle accelerator, and a 15,000 Ci Co-60 irradiation facility. Support facilities included radiochemistry laboratories, counting rooms and two hot cells. As the emphasis shifted to non-nuclear energy technology a name change resulted in the CEER designation, and plans were started for the decontamination and decommissioning effort.

  10. Predicting viscosities of aqueous salt mixtures

    SciTech Connect (OSTI)

    Zaltash, A.; Ally, M.R.

    1992-01-01T23:59:59.000Z

    Viscosity plays an important role in quantifying heat and mass transfer rates as depicted in theoretical and semi-empirical correlations. In practical problems where extreme temperatures and solute concentrations are encountered, viscosity data is usually unavailable. At these conditions, no dependable correlation appears to exist in the literature. This paper uses the hole type model to predict the viscosity of aqueous electrolytes containing single and mixed salts up to the molten salt regime. This model needs two parameters which can be evaluated from sparse data. For LiBr/water and (Li, K, na) NO[sub 3]/water mixtures, it is shown that the agreement between predicted and experimental values is very good over wide temperature and concentration ranges. The deviation between these two values was found to be less than 9%.

  11. Predicting viscosities of aqueous salt mixtures

    SciTech Connect (OSTI)

    Zaltash, A.; Ally, M.R.

    1992-12-01T23:59:59.000Z

    Viscosity plays an important role in quantifying heat and mass transfer rates as depicted in theoretical and semi-empirical correlations. In practical problems where extreme temperatures and solute concentrations are encountered, viscosity data is usually unavailable. At these conditions, no dependable correlation appears to exist in the literature. This paper uses the hole type model to predict the viscosity of aqueous electrolytes containing single and mixed salts up to the molten salt regime. This model needs two parameters which can be evaluated from sparse data. For LiBr/water and (Li, K, na) NO{sub 3}/water mixtures, it is shown that the agreement between predicted and experimental values is very good over wide temperature and concentration ranges. The deviation between these two values was found to be less than 9%.

  12. Program management plan for the Molten Salt Reactor Experiment Remediation Project at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-09-01T23:59:59.000Z

    The primary mission of the Molten Salt Reactor Experiment (MSRE) Remediation Project is to effectively implement the risk-reduction strategies and technical plans to stabilize and prevent further migration of uranium within the MSRE facility, remove the uranium and fuel salts from the system, and dispose of the fuel and flush salts by storage in appropriate depositories to bring the facility to a surveillance and maintenance condition before decontamination and decommissioning. This Project Management Plan (PMP) for the MSRE Remediation Project details project purpose; technical objectives, milestones, and cost objectives; work plan; work breakdown structure (WBS); schedule; management organization and responsibilities; project management performance measurement planning, and control; conduct of operations; configuration management; environmental, safety, and health compliance; quality assurance; operational readiness reviews; and training.

  13. FULL SCALE SEDIMENT DECONTAMINATION APPLICATIONS NEW YORK/NEW JERSEY HARBOR

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    -development of impacted waterways, ports and harbors, and adjacent brownfield communities. Besides its application that would benefit from a sediment decontamination program include brownfield, aquatic Superfund

  14. EIS-0329: Proposed Construction, Operation, Decontamination/Decommissioning of Depleted Uranium Hexafluoride Conversion Facilities

    Broader source: Energy.gov [DOE]

    This EIS analyzes DOE's proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky.

  15. Health care facility-based decontamination of victims exposed to chemical, biological, and radiological materials

    E-Print Network [OSTI]

    Koenig, Kristi L MD

    2008-01-01T23:59:59.000Z

    contaminants, and management of contaminated materials andmanagement, triage, surveillance, decontamination procedures and materials,from the body, and management of contaminated materials and

  16. Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Haghighi, M. H.; Szozda, R. M.; Jugan, M. R.

    2002-02-26T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR), south of the Oak Ridge National Laboratory (ORNL) main plant across Haw Ridge in Melton Valley. The MSRE was run by ORNL to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503 (Figure 1). The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed t o cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. As a result of the S&M program, it was discovered in 1994 that gaseous uranium (233U/232U) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 was generated when radiolysis of the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine.Some of the free fluorine combined with uranium fluorides (UF4) in the salt to form UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE.

  17. Electrolyte salts for nonaqueous electrolytes

    DOE Patents [OSTI]

    Amine, Khalil; Zhang, Zhengcheng; Chen, Zonghai

    2012-10-09T23:59:59.000Z

    Metal complex salts may be used in lithium ion batteries. Such metal complex salts not only perform as an electrolyte salt in a lithium ion batteries with high solubility and conductivity, but also can act as redox shuttles that provide overcharge protection of individual cells in a battery pack and/or as electrolyte additives to provide other mechanisms to provide overcharge protection to lithium ion batteries. The metal complex salts have at least one aromatic ring. The aromatic moiety may be reversibly oxidized/reduced at a potential slightly higher than the working potential of the positive electrode in the lithium ion battery. The metal complex salts may also be known as overcharge protection salts.

  18. Decontamination Process of Internal Part Pipes - 13442

    SciTech Connect (OSTI)

    Ladet, X.; Sozet, O.; Cabanillas, P.; Macia, G. [STMI, Site de MARCOULE - Batiment 423 - 30204 Bagnols-sur-Ceze (France)] [STMI, Site de MARCOULE - Batiment 423 - 30204 Bagnols-sur-Ceze (France); Moggia, F.; Damerval, F. [STMI, 1 route de la Noue 91196 - Gif-sur-Yvette (France)] [STMI, 1 route de la Noue 91196 - Gif-sur-Yvette (France)

    2013-07-01T23:59:59.000Z

    The Marcoule Site, created in 1955 is one of the first nuclear sites in France. It combines the activities of the Research Centre of the French Atomic Energy Commission (CEA) and AREVA industrial operations. Today, a large part of the operations on this site consists of the cleaning and the dismantling of nuclear Installations, once the end of their life cycle has been reached. An example can be the reprocessing plant UP1. This unit, started in 1958 has been stopped in 1997 and its dismantling started quickly thereafter. Technical challenges of the UP1 dismantling are mainly linked to a very high risk of exposure due to a large variety of contaminated equipments and residuals of fission products, potential sources of irradiation. The dismantling of Hall 71 is a typical example of such challenge. This paper will present a solution developed by AREVA Clean-Up business unit, in collaboration with COFIM Industry, to remove contamination incrusted inside the pipes before starting the cutting operations, thus reducing irradiation risk. (authors)

  19. Water Dynamics in Divalent and Monovalent Concentrated Salt Chiara H. Giammanco, Daryl B. Wong, and Michael D. Fayer*

    E-Print Network [OSTI]

    Fayer, Michael D.

    Water Dynamics in Divalent and Monovalent Concentrated Salt Solutions Chiara H. Giammanco, Daryl B, United States ABSTRACT: Water hydrogen bond dynamics in concentrated salt solutions are studied using causes a shift in absorption frequency relative to that of the OD stretch absorption in bulk pure water

  20. Batteries using molten salt electrolyte

    DOE Patents [OSTI]

    Guidotti, Ronald A. (Albuquerque, NM)

    2003-04-08T23:59:59.000Z

    An electrolyte system suitable for a molten salt electrolyte battery is described where the electrolyte system is a molten nitrate compound, an organic compound containing dissolved lithium salts, or a 1-ethyl-3-methlyimidazolium salt with a melting temperature between approximately room temperature and approximately 250.degree. C. With a compatible anode and cathode, the electrolyte system is utilized in a battery as a power source suitable for oil/gas borehole applications and in heat sensors.

  1. Influence of Permian salt dissolution on distribution of shallow Niobrara gas fields, eastern Colorado

    SciTech Connect (OSTI)

    Oldham, D.W.; Smosna, R.A. [West Virginia Univ., Morgantown, WV (United States)

    1996-06-01T23:59:59.000Z

    Subsurface analysis of Permian salt and related strata in the shallow Niobrara gas area on the eastern flank of the Denver basin reveals that the location of faulted anticlines which produce gas from porous chalk is related to the occurrence of six Nippewalla Group (Leonardian) salt zones. Salt distribution is controlled by the configuration of evaporate basins during the Leonardian, truncation at a sub-Jurassic unconformity (which has completely removed Guadalupian salts), and post-Jurassic subsurface dissolution. Significant dissolution took place in response to Laramide orogeny and subsequent eastward regional groundwater flow within the Lyons (Cedar Hills) Sandstone aquifer. Initially, dissolution occurred along a regional facies change from sandstone to salt. Solution collapse allowed for cross-formational flow and removal of younger salts. Shallow Niobrara gas fields are situated above salt outliers or along regionally updip salt edges. No significant Niobrara production exists in areas where salt is absent. Structural relief across fields is related to Leonardian thickness variations, rather than subsalt offset. Seismic data reveal abrupt Leonardian thinning at the regionally updip limit of Eckley field, which has produced over 33 BCFG. Thickness of residual salt may be important in controlling the amount of gas trapped within the Niobrara. Where thick salts are preserved, structural relief is greater, the gas-water transition zone is thicker, and gas saturation is higher at the crests of faulted anticlines.

  2. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, I.D.; Poris, J.; Huggins, R.A.

    1980-07-18T23:59:59.000Z

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400 to 500/sup 0/C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell which may be operated at temperatures between about 100 to 170/sup 0/C. The cell is comprised of an electrolyte, which preferably includes lithium nitrate, and a lithium or lithium alloy electrode.

  3. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, Ian D. (Menlo Park, CA); Poris, Jaime (Portola Valley, CA); Huggins, Robert A. (Stanford, CA)

    1982-02-09T23:59:59.000Z

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  4. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, Ian D. (Menlo Park, CA); Poris, Jaime (Portola Valley, CA); Huggins, Robert A. (Stanford, CA)

    1983-01-01T23:59:59.000Z

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  5. Salt Repository Research,

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What's PossibleRadiation Protection245C Unlimited ReleaseWelcome ton6 th US/German Workshop on Salt

  6. Salt Selected (FINAL)

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of Scienceand Requirements RecentlyElectronicResourcesjobsJuly throughR EMaterialsSafety,andWHY SALT

  7. A microfluidic platform for pharmaceutical salt screening Michael R. Thorson,a

    E-Print Network [OSTI]

    Kenis, Paul J. A.

    A microfluidic platform for pharmaceutical salt screening Michael R. Thorson,a Sachit Goyal platform comprised of 48 wells to screen for pharmaceutical salts. Solutions of pharmaceutical parent spectra. Two drugs, naproxen (acid) and ephedrine (base), were used for validation of the platform

  8. Sandia National Laboratories: Molten Salt

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

    receiver technology is attractive because it can cost-effectively capture and store heat at higher ... Molten Nitrate Salt Initial Flow Testing is a Tremendous Success On...

  9. PROPERTIES AND BEHAVIOR OF 238PU RELEVANT TO DECONTAMINATION OF BUILDING 235-F

    SciTech Connect (OSTI)

    Duncan, A.; Kane, M.

    2009-11-24T23:59:59.000Z

    This report was prepared to document the physical, chemical and radiological properties of plutonium oxide materials that were processed in the Plutonium Fuel Form Facility (PuFF) in building 235-F at the Savannah River Plant (now known as the Savannah River Site) in the late 1970s and early 1980s. An understanding of these properties is needed to support current project planning for the safe and effective decontamination and deactivation (D&D) of PuFF. The PuFF mission was production of heat sources to power Radioisotope Thermoelectric Generators (RTGs) used in space craft. The specification for the PuO{sub 2} used to fabricate the heat sources required that the isotopic content of the plutonium be 83 {+-} 1% Pu-238 due to its high decay heat of 0.57 W/g. The high specific activity of Pu-238 (17.1 Ci/g) due to alpha decay makes this material very difficult to manage. The production process produced micron-sized particles which proved difficult to contain during operations, creating personnel contamination concerns and resulting in the expenditure of significant resources to decontaminate spaces after loss of material containment. This report examines high {sup 238}Pu-content material properties relevant to the D&D of PuFF. These relevant properties are those that contribute to the mobility of the material. Physical properties which produce or maintain small particle size work to increase particle mobility. Early workers with {sup 238}PuO{sub 2} felt that, unlike most small particles, Pu-238 oxide particles would not naturally agglomerate to form larger, less mobile particles. It was thought that the heat generated by the particles would prevent water molecules from binding to the particle surface. Particles covered with bound water tend to agglomerate more easily. However, it is now understood that the self-heating effect is not sufficient to prevent adsorption of water on particle surfaces and thus would not prevent agglomeration of particles. Operational experience at PuFF indicates that the Pu-238 contamination was observed to move along surfaces and through High Efficiency Particulate Air (HEPA) filters over time. Recent research into the phenomenon known as alpha recoil offers a potential explanation for this observed behavior. Momentum is conserved when an alpha particle is ejected from a Pu-238 atom due to radioactive decay. Consequently, the entire particle of which that Pu-238 atom is a constituent experiences a movement similar to the recoil of a gun when a bullet is ejected. Furthermore, the particle often fractures in response to Pu-238 atom disintegration (yielding an alpha particle), with a small particle fragment also being ejected in order to conserve momentum. This process results in the continuous size reduction and transport of particles containing Pu-238 atoms, thus explaining movement of contamination along surfaces and through HEPA filters. A better understanding of the thermal behavior of {sup 238}PuO{sub 2} particles is needed to inform the planning process for the PuFF D&D project at the 235-F facility. There has been a concern that the surface temperature of individual particles may be high enough to cause problems with decontamination equipment and materials as a result of heat generation due to radioactive decay. A calculation under conservative assumptions shows that the surface temperature of particles less than about 100 {micro}m diameter is not appreciably above ambient. Since most particles in PuFF are on order of 1 {micro}m in diameter, the effect of particle surface temperature on decontamination equipment and materials is expected to be minimal. The result of this calculation also indicates that thermal imaging, which has been under consideration as a method to monitor the progress of system decontamination efforts would not likely be effective. The use of strippable coating was suggested as a possible alternative to other decontamination techniques. One particular system (i.e., Decon Gel 1101) may offer significant advantages over conventional liquid decontamination solut

  10. Salt-induced collapse and reexpansion of highly charged flexible polyelectrolytes

    E-Print Network [OSTI]

    Pai-Yi Hsiao; Erik Luijten

    2006-10-05T23:59:59.000Z

    We study the salt-dependent conformations of dilute flexible polyelectrolytes in solution via computer simulations. Low concentrations of multivalent salt induce the known conformational collapse of individual polyelectrolyte chains, but as the salt concentration is increased further this is followed by a reexpansion. We explicitly demonstrate that multivalent counterions can overcompensate the bare charge of the chain in the reexpansion regime. Both the degree of reexpansion and the occurrence of overcharging sensitively depend on ion size. Our findings are relevant for a wide range of salt-induced complexation phenomena.

  11. Feasibility of gas-phase decontamination of gaseous diffusion equipment

    SciTech Connect (OSTI)

    Munday, E.B.; Simmons, D.W.

    1993-02-01T23:59:59.000Z

    The five buildings at the K-25 Site formerly involved in the gaseous diffusion process contain 5000 gaseous diffusion stages as well as support facilities that are internally contaminated with uranium deposits. The gaseous diffusion facilities located at the Portsmouth Gaseous Diffusion Plant and the Paducah Gaseous Diffusion Plant also contain similar equipment and will eventually close. The decontamination of these facilities will require the most cost-effective technology consistent with the criticality, health physics, industrial hygiene, and environmental concerns; the technology must keep exposures to hazardous substances to levels as low as reasonably achievable (ALARA). This report documents recent laboratory experiments that were conducted to determine the feasibility of gas-phase decontamination of the internal surfaces of the gaseous diffusion equipment that is contaminated with uranium deposits. A gaseous fluorinating agent is used to fluorinate the solid uranium deposits to gaseous uranium hexafluoride (UF[sub 6]), which can be recovered by chemical trapping or freezing. The lab results regarding the feasibility of the gas-phase process are encouraging. These results especially showed promise for a novel decontamination approach called the long-term, low-temperature (LTLT) process. In the LTLT process: The equipment is rendered leak tight, evacuated, leak tested, and pretreated, charged with chlorine trifluoride (ClF[sub 3]) to subatmospheric pressure, left for an extended period, possibly > 4 months, while processing other items. Then the UF[sub 6] and other gases are evacuated. The UF[sub 6] is recovered by chemical trapping. The lab results demonstrated that ClF[sub 3] gas at subatmospheric pressure and at [approx] 75[degree]F is capable of volatilizing heavy deposits of uranyl fluoride from copper metal surfaces sufficiently that the remaining radioactive emissions are below limits.

  12. Feasibility of gas-phase decontamination of gaseous diffusion equipment

    SciTech Connect (OSTI)

    Munday, E.B.; Simmons, D.W.

    1993-02-01T23:59:59.000Z

    The five buildings at the K-25 Site formerly involved in the gaseous diffusion process contain 5000 gaseous diffusion stages as well as support facilities that are internally contaminated with uranium deposits. The gaseous diffusion facilities located at the Portsmouth Gaseous Diffusion Plant and the Paducah Gaseous Diffusion Plant also contain similar equipment and will eventually close. The decontamination of these facilities will require the most cost-effective technology consistent with the criticality, health physics, industrial hygiene, and environmental concerns; the technology must keep exposures to hazardous substances to levels as low as reasonably achievable (ALARA). This report documents recent laboratory experiments that were conducted to determine the feasibility of gas-phase decontamination of the internal surfaces of the gaseous diffusion equipment that is contaminated with uranium deposits. A gaseous fluorinating agent is used to fluorinate the solid uranium deposits to gaseous uranium hexafluoride (UF{sub 6}), which can be recovered by chemical trapping or freezing. The lab results regarding the feasibility of the gas-phase process are encouraging. These results especially showed promise for a novel decontamination approach called the long-term, low-temperature (LTLT) process. In the LTLT process: The equipment is rendered leak tight, evacuated, leak tested, and pretreated, charged with chlorine trifluoride (ClF{sub 3}) to subatmospheric pressure, left for an extended period, possibly > 4 months, while processing other items. Then the UF{sub 6} and other gases are evacuated. The UF{sub 6} is recovered by chemical trapping. The lab results demonstrated that ClF{sub 3} gas at subatmospheric pressure and at {approx} 75{degree}F is capable of volatilizing heavy deposits of uranyl fluoride from copper metal surfaces sufficiently that the remaining radioactive emissions are below limits.

  13. Unit decontamination and dismantlement (D&D) costs

    SciTech Connect (OSTI)

    Folga, S.; Swanston, R.; Davis, M. [Argonne National Lab., IL (United States); Janke, R.J. [USDOE Fernald Area Office, OH (United States)

    1996-03-01T23:59:59.000Z

    A series of relationships have been developed for estimating unit decontamination and dismantlement (D&D) costs for a number of building types which may be applied in the absence of other data to obtain rough order-of-magnitude (ROM) cost estimates for D&D activities. The relationships were developed using unit D&D costs for a number of building structure types at the Department of Energy Fernald site. These unit costs into account the level of radioactive contamination as well as the, building size.

  14. EIS-0082-S2: Savannah River Site Salt Processing, Savannah River Site, Aiken, South Carolina

    Broader source: Energy.gov [DOE]

    This SEIS evaluates the potential environmental impacts of alternatives for separating the high-activity fraction from the low-activity fraction of the high-level radioactive waste salt solutions...

  15. Damage in porous media due to salt crystallization

    E-Print Network [OSTI]

    Noushine Shahidzadeh-Bonn; Julie Desarnaud; François Bertrand; Xavier Chateau; Daniel Bonn

    2010-07-13T23:59:59.000Z

    We investigate the origins of salt damage in sandstones for the two most common salts: sodium chloride and sulfate. The results show that the observed difference in damage between the two salts is directly related to the kinetics of crystallization and the interfacial properties of the salt solutions and crystals with respect to the stone. We show that, for sodium sulfate, the existence of hydrated and anhydrous crystals and specifically their dissolution and crystallization kinetics are responsible for the damage. Using magnetic resonance imaging and optical microscopy we show that when water imbibes sodium sulfate contaminated sandstones, followed by drying at room temperature, large damage occurs in regions where pores are fully filled with salts. After partial dissolution, anhydrous sodium sulfate salt present in these regions gives rise to a very rapid growth of the hydrated phase of sulfate in the form of clusters that form on or close to the remaining anhydrous microcrystals. The rapid growth of these clusters generates stresses in excess of the tensile strength of the stone leading to the damage. Sodium chloride only forms anhydrous crystals that consequently do not cause damage in the experiments.

  16. 112 STERN ET AL. Decontamination and BeneficialUse of Dredged Materials

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    112 STERN ET AL. Decontamination and BeneficialUse of Dredged Materials E. A. STERN! U. S";.. ABSTRACT: Our group is leading a large-sale demonstration of dredged material decontamination technologies transformation of contaminated dredged material into an environmentally-benign material used in the manufacture

  17. RIS-M-2472 FORCED DECONTAMINATION OF FISSION PRODUCTS DEPOSITED ON

    E-Print Network [OSTI]

    a serious reactor accident. Areas of special concern are cities where the collective dose might be high, DECONTAMINATION, FISSION, PROD- UCTS, REACTOR ACCIDENTS, REMEDIAL ACTION, REVIEWS, ROADS, SURFACE CLEANING-550-1067-9 ISSN 0418-6435 Risø Repro 1985 #12;CONTENTS Paqe 1. INTRODUCTION 5 2. DECONTAMINATION PRINCIPLES 6 2

  18. Decontamination and Management of Human Remains Following Incidents of Hazardous Chemical Release

    SciTech Connect (OSTI)

    Hauschild, Veronique [U.S. Army Public Health Command; Watson, Annetta Paule [ORNL; Bock, Robert Eldon [ORNL

    2012-01-01T23:59:59.000Z

    Abstract Objective: To provide specific procedural guidance and resources for identification, assessment, control, and mitigation of compounds that may contaminate human remains resulting from chemical attack or release. Design: A detailed technical, policy, and regulatory review is summarized. Setting: Guidance is suitable for civilian or military settings where human remains potentially contaminated with hazardous chemicals may be present. Settings would include sites of transportation accidents, natural disasters, terrorist or military operations, mortuary affairs or medical examiner processing and decontamination points, and similar. Patients, Participants: While recommended procedures have not been validated with actual human remains, guidance has been developed from data characterizing controlled experiments with fabrics, materiel, and laboratory animals. Main Outcome Measure(s): Presentation of logic and specific procedures for remains management, protection and decontamination of mortuary affairs personnel, as well as decision criteria for determining when remains are sufficiently decontaminated so as to pose no chemical health hazard. Results: Established procedures and existing equipment/materiel available for decontamination and verification provide appropriate and reasonable means to mitigate chemical hazards from remains. Extensive characterization of issues related to remains decontamination indicates that supra-lethal concentrations of liquid chemical warfare agent VX may prove difficult to decontaminate and verify in a timely fashion. Specialized personnel can and should be called upon to assist with monitoring necessary to clear decontaminated remains for transport and processing. Conclusions: Once appropriate decontamination and verification have been accomplished, normal procedures for remains processing and transport to the decedent s family and the continental United States can be followed.

  19. Decontamination systems information and research program. Quarterly report, January 1--March 31, 1997

    SciTech Connect (OSTI)

    NONE

    1997-12-31T23:59:59.000Z

    Progress reports are given on the following projects: (A) Subsurface contaminants, containment and remediation: 1.1 Characteristic evaluation of grout barriers in grout testing chamber; 1.2 Development of standard test protocols and barrier design models for desiccation barriers; 1.3 Development of standard test protocols and barrier design models for in-situ formed barriers -- technical support; 1.4 Laboratory studies and field testing at the DOE/RMI Extrusion Plant (Ashtabula, Ohio); 1.5 Use of drained enhanced soil flushing for contaminants removal; (B) Mixed waste characterization, treatment and disposal: Analysis of the Vortec cyclone melting system for remediation of PCB contaminated soils using computational fluid dynamics; (C) Decontamination and decommissioning: 3.1 Production and evaluation of biosorbents and cleaning solutions for use in D and D; 3.2 Use of Spintek centrifugal membrane technology and sorbents/cleaning solutions in the D and D of DOE facilities; (D) Cross-cutting innovative technologies: 4.1 Use of centrifugal membrane technology with novel membranes to treat hazardous/radioactive wastes; 4.2 Environmental pollution control devices based on novel forms of carbon; 4.3 Design of rotating membrane filtration system for remediation technologies; and (E) Outreach: Small business technical based support.

  20. Plant salt-tolerance mechanisms

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01T23:59:59.000Z

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selectionmore »and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.« less

  1. Plant salt-tolerance mechanisms

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01T23:59:59.000Z

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selection and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.

  2. Decontamination of Savannah River Plant H-Area hot-canyon crane

    SciTech Connect (OSTI)

    Rankin, W N; Sims, J R

    1985-01-01T23:59:59.000Z

    Decontamination techniques applicable to the remotely operated bridge cranes in canyon buildings at the Savannah River Plant (SRP) were identified and were evaluated in laboratory-scale tests. High pressure Freon blasting was found to be the most attractive process available for this application. Strippable coatings were selected as an alternative technique in selected applications. The ability of high pressure Freon blasting plus two strippable coatings (Quadcoat 100 and Alara 1146) to remove the type of contamination expected on SRP cranes was demonstrated in laboratory-scale tests. Quadrex HPS was given a contract to decontaminate the H-Area hot canyon crane. Decontamination operations were successfully carried out within the specified time-frame window. The radiation level goals specified by SRP were met and decontamination was accomplished with 85% less personnel exposure than estimated by SRP before the job started. This reduction is attributed to the increased efficiency of the new decontamination techniques used. 6 refs., 1 tab.

  3. Characterization of bedded salt for storage caverns -- A case study from the Midland Basin, Texas

    SciTech Connect (OSTI)

    Hovorka, Susan D.; Nava, Robin

    2000-06-13T23:59:59.000Z

    The geometry of Permian bedding salt in the Midland Basin is a product of interaction between depositional facies and postdepositional modification by salt dissolution. Mapping high-frequency cycle patterns in cross section and map view using wireline logs documents the salt geometry. Geologically based interpretation of depositional and dissolution processes provides a powerful tool for mapping and geometry of salt to assess the suitability of sites for development of solution-mined storage caverns. In addition, this process-based description of salt geometry complements existing data about the evolution of one of the best-known sedimentary basins in the world, and can serve as a genetic model to assist in interpreting other salts.

  4. Sediment Decontamination For Navigational And Environmental Restoration In NY/NJ Harbor Case Study: Passaic River, New Jersey

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Sediment Decontamination For Navigational And Environmental Restoration In NY/NJ Harbor ­ Case compounds. Decontamination of these sediments is one tool that can be used to cope with the problems posed decontamination technologies in near- commercial scale projects during the 2004-2005time period. We stress

  5. Independent Oversight Assessment, Salt Waste Processing Facility...

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

    Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department...

  6. Sandia National Laboratories: molten salt test loop

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

    molten salt test loop Sandia-AREVA Commission Solar ThermalMolten Salt Energy-Storage Demonstration On May 21, 2014, in Capabilities, Concentrating Solar Power, Energy, Energy...

  7. Decontamination and decommissioning surveillance and maintenance report for FY 1991

    SciTech Connect (OSTI)

    Gunter, David B.; Burwinkle, T. W.; Cannon, T. R.; Ford, M. K.; Holder, Jr., L.; Clotfelter, O. K.; Faulkner, R. L.; Smith, D. L.; Wooten, H. O.

    1991-12-01T23:59:59.000Z

    The Decontamination and Decommissioning (D D) Program has three distinct phases: (1) surveillance and maintenance (S M); (2) decontamination and removal of hazardous materials and equipment (which DOE Headquarters in Washington, D.C., calls Phase I of remediation); and (3) decommissioning and ultimate disposal, regulatory compliance monitoring, and property transfer (which DOE Headquarters calls Phase II of remediation). A large part of D D is devoted to S M at each of the sites. Our S M activities, which are performed on facilities awaiting decommissioning, are designed to minimize potential hazards to human health and the environment by: ensuring adequate containment of residual radioactive and hazardous materials; and, providing physical safety and security controls to minimize potential hazards to on-site personnel and the general public. Typically, we classify maintenance activities as either routine or special (major repairs). Routine maintenance includes such activities as painting, cleaning, vegetation control, minor structural repairs, filter changes, and building system(s) checks. Special maintenance includes Occupational Safety and Health Act facility upgrades, roof repairs, and equipment overhaul. Surveillance activities include inspections, radiological measurements, reporting, records maintenance, and security (as required) for controlling and monitoring access to facilities. This report summarizes out FY 1991 S M activities for the Tennessee plant sites, which include the K-25 Site, the Gas Centrifuge facilities, ORNL, and the Y-12 Plant.

  8. Determination of vapor-liquid equilibrium data and decontamination factors needed for the development of evaporator technology for use in volume reduction of radioactive waste streams

    SciTech Connect (OSTI)

    Betts, S.E. [California Univ., Santa Barbara, CA (United States)

    1993-10-01T23:59:59.000Z

    A program is currently in progress at Argonne National Laboratory to evaluate and develop evaporator technology for concentrating radioactive waste streams. By concentrating radioactive waste streams, disposal costs can be significantly reduced. To effectively reduce the volume of waste, the evaporator must achieve high decontamination factors so that the distillate is sufficiently free of radioactive material. One technology that shows a great deal of potential for this application is being developed by LICON, Inc. In this program, Argonne plans to apply LICON`s evaporator designs to the processing of radioactive solutions. Concepts that need to be incorporated into the design of the evaporator include, criticality safety, remote operation and maintenance, and materials of construction. To design an effective process for concentrating waste streams, both solubility and vapor-liquid equilibrium data are needed. The key issue, however, is the high decontamination factors that have been demonstrated by this equipment. Two major contributions were made to this project. First, a literature survey was completed to obtain available solubility and vapor-liquid equilibrium data. Some vapor-liquid data necessary for the project but not available in the literature was obtained experimentally. Second, the decontamination factor for the evaporator was determined using neutron activation analysis (NAA).

  9. The in-situ decontamination of sand and gravel aquifers by chemically enhanced solubilization of multiple-compound DNAPLs with surfactant solutions: Phase 1 -- Laboratory and pilot field-scale testing and Phase 2 -- Solubilization test and partitioning and interwell tracer tests. Final report

    SciTech Connect (OSTI)

    NONE

    1997-10-24T23:59:59.000Z

    Laboratory, numerical simulation, and field studies have been conducted to assess the potential use of micellar-surfactant solutions to solubilize chlorinated solvents contaminating sand and gravel aquifers. Ninety-nine surfactants were screened for their ability to solubilize trichloroethene (TCE), perchloroethylene (PCE), and carbon tetrachloride (CTET). The field test was conducted in the alluvial aquifer which is located 20 to 30 meters beneath a vapor degreasing operation at Paducah Gaseous Diffusion Plant. This aquifer has become contaminated with TCE due to leakage of perhaps 40,000 liters of TCE, which has generated a plume of dissolved TCE extending throughout an area of approximately 3 km{sup 2} in the aquifer. Most of the TCE is believed to be present in the overlying lacustrine deposits and in the aquifer itself as a dense, non-aqueous phase liquid, or DNAPL. The objective of the field test was to assess the efficacy of the surfactant for in situ TCE solubilization. Although the test demonstrated that sorbitan monooleate was unsuitable as a solubilizer in this aquifer, the single-well test was demonstrated to be a viable method for the in situ testing of surfactants or cosolvents prior to proceeding to full-scale remediation.

  10. Decontamination and size reduction of plutonium contaminated process exhaust ductwork and glove boxes

    SciTech Connect (OSTI)

    LaFrate, P.; Elliott, J.; Valasquez, M.

    1996-11-15T23:59:59.000Z

    The Los Alamos National Laboratory (LANL) Decommissioning Program has decontaminated and demolished two filter plenum buildings at Technical Area 21 (TA-21). During the project a former hot cell was retrofitted to perform decontamination and size reduction of highly Pu contaminated process exhaust (1,100 ft) and gloveboxes. Pu-238/239 concentrations were as high a 1 Ci per linear foot and averaged approximately 1 mCi/ft. The Project decontamination objective was to reduce the plutonium contamination on surfaces below transuranic levels. If possible, metal surfaces were decontaminated further to meet Science and Ecology Group (SEG) waste classification guidelines to enable the metal to be recycled at their facility in oak Ridge, Tennessee. Project surface contamination acceptance criteria for low-level radioactive waste (LLRW), transuranic waste, and SEG waste acceptance criteria will be presented. Ninety percent of all radioactive waste for the project was characterized as LLRW. Twenty percent of this material was shipped to SEG. Process exhaust and glove boxes were brought to the project decontamination area, an old hot cell in Building 4 North. This paper focuses on process exhaust and glovebox decontamination methodology, size reduction techniques, waste characterization, airborne contamination monitoring, engineering controls, worker protection, lessons learned, and waste minimization. Decontamination objectives are discussed in detail.

  11. BYU Salt Lake Center Financial Aid Program

    E-Print Network [OSTI]

    Martinez, Tony R.

    BYU Salt Lake Center Financial Aid Program 2011 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  12. BYU Salt Lake Center Financial Aid Program

    E-Print Network [OSTI]

    Olsen Jr., Dan R.

    BYU Salt Lake Center Financial Aid Program 2013 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  13. BYU Salt Lake Center Financial Aid Program

    E-Print Network [OSTI]

    Hart, Gus

    BYU Salt Lake Center Financial Aid Program 2014 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  14. BYU Salt Lake Center Financial Aid Program

    E-Print Network [OSTI]

    Hart, Gus

    BYU Salt Lake Center Financial Aid Program 2012 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  15. Results From The Salt Disposition Project Next Generation Solvent Demonstration Plan

    SciTech Connect (OSTI)

    Peters, T. B.; Fondeur, F. F.; Taylor-Pashow, K. M.L.

    2014-04-02T23:59:59.000Z

    Strip Effluent Hold Tank (SEHT), Decontaminated Salt Solution Hold Tank (DSSHT), Caustic Wash Tank (CWT) and Solvent Hold Tank (SHT) samples were taken throughout the Next Generation Solvent (NGS) Demonstration Plan. These samples were analyzed and the results are reported. SHT: The solvent behaved as expected, with no bulk changes in the composition over time, with the exception of the TOA and TiDG. The TiDG depletion is higher than expected, and consideration must be taken on the required rate of replenishment. Monthly sampling of the SHT is warranted. If possible, additional SHT samples for TiDG analysis (only) would help SRNL refine the TiDG degradation model. CWT: The CWT samples show the expected behavior in terms of bulk chemistry. The 137Cs deposited into the CWT varies somewhat, but generally appears to be lower than during operations with the BOBCalix solvent. While a few minor organic components were noted to be present in the Preliminary sample, at this time these are thought to be artifacts of the sample preparation or may be due to the preceding solvent superwash. DSSHT: The DSSHT samples show the predicted bulk chemistry, although they point towards significant dilution at the front end of the Demonstration. The 137Cs levels in the DSSHT are much lower than during the BOBCalix operations, which is the expected observation. SEHT: The SEHT samples represent the most different output of all four of the outputs from MCU. While the bulk chemistry is as expected, something is causing the pH of the SEHT to be higher than what would be predicted from a pure stream of 0.01 M boric acid. There are several possible different reasons for this, and SRNL is in the process of investigating. Other than the pH issue, the SEHT is as predicted. In summary, the NGS Demonstration Plan samples indicate that the MCU system, with the Blend Solvent, is operating as expected. The only issue of concern regards the pH of the SEHT, and SRNL is in the process of investigating this. SRNL results support the transition to routine operations.

  16. Method and apparatus for the gas phase decontamination of chemical and biological agents

    DOE Patents [OSTI]

    O'Neill, Hugh J.; Brubaker, Kenneth L.

    2003-10-07T23:59:59.000Z

    An apparatus and method for decontaminating chemical and biological agents using the reactive properties of both the single atomic oxygen and the hydroxyl radical for the decontamination of chemical and biological agents. The apparatus is self contained and portable and allows for the application of gas reactants directly at the required decontamination point. The system provides for the use of ultraviolet light of a specific spectral range to photolytically break down ozone into molecular oxygen and hydroxyl radicals where some of the molecular oxygen is in the first excited state. The excited molecular oxygen will combine with water vapor to produce two hydroxyl radicals.

  17. NAME: Salt Creek Estuary Restoration LOCATION: Salt Creek Watershed, Clallam County, Washington

    E-Print Network [OSTI]

    US Army Corps of Engineers

    NAME: Salt Creek Estuary Restoration LOCATION: Salt Creek Watershed, Clallam County, Washington Federal funds $0 PROJECT DESCRIPTION: The Salt Creek Estuary Reconnection project will significantly enhance tidal and fluvial hydrology to 22.5 acres of salt marsh, which will return the salt marsh to its

  18. Electromagnetic mixed waste processing system for asbestos decontamination

    SciTech Connect (OSTI)

    Kasevich, R.S.; Vaux, W.G.; Nocito, T.

    1995-12-01T23:59:59.000Z

    DOE sites contain a broad spectrum of asbestos materials (cloth, pipe lagging, sprayed insulation and other substances) which are contaminated with a combination of hazardous and radioactive wastes due to its use during the development of the U.S. nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCB`s, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay and fission products of DOE operations. The asbestos must be converted by removing and separating the hazardous and radioactive materials to prevent the formation of mixed wastes and to allow for both sanitary disposal and effective decontamination. Currently, no technology exists that can meet these sanitary and other objectives.

  19. CPP-603 Chloride Removal System Decontamination and Decommissioning. Final report

    SciTech Connect (OSTI)

    Moser, C.L.

    1993-02-01T23:59:59.000Z

    The CPP-603 (annex) Chloride Removal System (CRS) Decontamination and Decommissioning (D&D) Project is described in this report. The CRS was used for removing Chloride ions and other contaminants that were suspended in the waters of the underwater fuel storage basins in the CPP-603 Fuel Receiving and Storage Facility (FRSF) from 1975 to 1981. The Environmental Checklist and related documents, facility characterization, decision analysis`, and D&D plans` were prepared in 1991. Physical D&D activities were begun in mid summer of 1992 and were completed by the end of November 1992. All process equipment and electrical equipment were removed from the annex following accepted asbestos and radiological contamination removal practices. The D&D activities were performed in a manner such that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) occurred.

  20. Accelerated Decontamination and Decommissioning at the Hanford Site

    SciTech Connect (OSTI)

    Hughes, M.C.; Douglas, L.M.; Marske, S.G.

    1994-01-01T23:59:59.000Z

    The Hanford Site has over 100 facilities that have been declared surplus and are scheduled to be decommissioned. In addition to these surplus facilities, there is a significant number of facilities that are currently being shut down, deactivated, and transferred to the Decontamination and Decommissioning (D&D) program. In the last year, Westinghouse Hanford Company and the US Department of Energy, Richland Operations Office, have developed and implemented an initiative to accelerate the D&D work at the Hanford Site. The strategy associated with accelerated D&D is to reduce the number of surplus facilities, eliminate potential safety hazards, demonstrate meaningful cleanup progress, and recycle materials for other uses. This initiative has been extremely successful and has resulted in the safe demolition of 13 facilities in fiscal year (FY) 1993. In addition, four facilities have been completed in FY 1994 and demolition of several other facilities is currently underway.

  1. Laser ablation system, and method of decontaminating surfaces

    DOE Patents [OSTI]

    Ferguson, Russell L. (Idaho Falls, ID); Edelson, Martin C. (Ames, IA); Pang, Ho-ming (Ames, IA)

    1998-07-14T23:59:59.000Z

    A laser ablation system comprising a laser head providing a laser output; a flexible fiber optic cable optically coupled to the laser output and transmitting laser light; an output optics assembly including a nozzle through which laser light passes; an exhaust tube in communication with the nozzle; and a blower generating a vacuum on the exhaust tube. A method of decontaminating a surface comprising the following steps: providing an acousto-optic, Q-switched Nd:YAG laser light ablation system having a fiber optically coupled output optics assembly; and operating the laser light ablation system to produce an irradiance greater than 1.times.10.sup.7 W/cm.sup.2, and a pulse width between 80 and 170 ns.

  2. Concrete decontamination by Electro-Hydraulic Scabbling (EHS). Topical report

    SciTech Connect (OSTI)

    NONE

    1996-03-30T23:59:59.000Z

    Electro-Hydraulic Scabbling (EHS) technology and equipment for decontaminating concrete structures from radionuclides, organic substances, and hazardous metals is being developed by Textron Systems Division (TSD). This wet scabbling technique involves the generation of powerful shock waves and intense cavitation by a strong pulsed electric discharge in a water layer at the concrete surface. The high pressure impulse results in stresses which crack and peel off a concrete layer of a controllable thickness. Scabbling produces contaminated debris of relatively small volume which can be easily removed, leaving clean bulk concrete. This new technology is being developed under Contract No. DE-AC21-93MC30164. The project objective is to develop and demonstrate a cost-efficient, rapid, controllable process to remove the surface layer of contaminated concrete while generating minimal secondary waste. The primary target of this program is uranium-contaminated concrete floors which constitute a substantial part of the contaminated area at DOE weapon facilities.

  3. Plasma Decontamination of Uranium From the Interior of Aluminum Objects

    SciTech Connect (OSTI)

    Veilleux, J.M.; Munson, C.; Fitzpatrick, J.; Chamberlin, E.P.; El-Genk, M.S.

    1997-04-21T23:59:59.000Z

    RF plasma glow discharges are being investigated for removing and recovering radioactive elements from contaminated objects, especially those contaminated with transuranic (TRU) materials. These plasmas, using nitrogen trifluoride as the working gas, have been successful at removing uranium and plutonium contaminants from test coupons of stainless steel and aluminum surfaces, including small cracks and crevices, and the interior surfaces of relatively hard to reach aluminum pipes. Contaminant removal exceeded 99.9% from simple surfaces and contaminant recovery using cryogenic traps has exceeded 50%. Work continues with the objective of demonstrating that transuranic contaminated waste can be transformed to low level waste (LLW) and to better understand the physics of the interaction between plasma and surface contaminants. This work summarizes the preliminary results from plasma decontamination from the interior of aluminum objects--the nooks and crannies experiments.

  4. LIFE Materails: Molten-Salt Fuels Volume 8

    SciTech Connect (OSTI)

    Moir, R; Brown, N; Caro, A; Farmer, J; Halsey, W; Kaufman, L; Kramer, K; Latkowski, J; Powers, J; Shaw, H; Turchi, P

    2008-12-11T23:59:59.000Z

    The goals of the Laser Inertial Fusion Fission Energy (LIFE) is to use fusion neutrons to fission materials with no enrichment and minimum processing and have greatly reduced wastes that are not of interest to making weapons. Fusion yields expected to be achieved in NIF a few times per day are called for with a high reliable shot rate of about 15 per second. We have found that the version of LIFE using TRISO fuel discussed in other volumes of this series can be modified by replacing the molten-flibe-cooled TRISO fuel zone with a molten salt in which the same actinides present in the TRISO particles are dissolved in the molten salt. Molten salts have the advantage that they are not subject to radiation damage, and hence overcome the radiation damage effects that may limit the lifetime of solid fuels such as TRISO-containing pebbles. This molten salt is pumped through the LIFE blanket, out to a heat exchanger and back into the blanket. To mitigate corrosion, steel structures in contact with the molten salt would be plated with tungsten or nickel. The salt will be processed during operation to remove certain fission products (volatile and noble and semi-noble fission products), impurities and corrosion products. In this way neutron absorbers (fission products) are removed and neutronics performance of the molten salt is somewhat better than that of the TRISO fuel case owing to the reduced parasitic absorption. In addition, the production of Pu and rare-earth elements (REE) causes these elements to build up in the salt, and leads to a requirement for a process to remove the REE during operation to insure that the solubility of a mixed (Pu,REE)F3 solid solution is not exceeded anywhere in the molten salt system. Removal of the REE will further enhance the neutronics performance. With molten salt fuels, the plant would need to be safeguarded because materials of interest for weapons are produced and could potentially be removed.

  5. Cite this: DOI: 10.1039/c3lc41271g A Microfluidic Platform for Evaporation-based Salt

    E-Print Network [OSTI]

    Kenis, Paul J. A.

    Cite this: DOI: 10.1039/c3lc41271g A Microfluidic Platform for Evaporation-based Salt Screening,b Yuchuan Gong*b and Paul J. A. Kenis*a We describe a microfluidic platform to screen for salt forms of PC and salt former solutions in a 24-well array (y200 nL/well), which is a drastic reduction

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

    SciTech Connect (OSTI)

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

    1982-01-01T23:59:59.000Z

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

  7. Solvent wash solution

    DOE Patents [OSTI]

    Neace, J.C.

    1984-03-13T23:59:59.000Z

    A process is claimed for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 vol % of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.

  8. Solvent wash solution

    DOE Patents [OSTI]

    Neace, James C. (Blackville, SC)

    1986-01-01T23:59:59.000Z

    Process for removing diluent degradation products from a solvent extraction solution, which has been used to recover uranium and plutonium from spent nuclear fuel. A wash solution and the solvent extraction solution are combined. The wash solution contains (a) water and (b) up to about, and including, 50 volume percent of at least one-polar water-miscible organic solvent based on the total volume of the water and the highly-polar organic solvent. The wash solution also preferably contains at least one inorganic salt. The diluent degradation products dissolve in the highly-polar organic solvent and the organic solvent extraction solvent do not dissolve in the highly-polar organic solvent. The highly-polar organic solvent and the extraction solvent are separated.

  9. Use of flourescent surrogate organisms for enteric pathogens in validation of carcass decontamination treatments

    E-Print Network [OSTI]

    Moseley, Tiffany Marie

    2009-05-15T23:59:59.000Z

    During the harvesting process, meat products can become contaminated with enteric pathogens, such as Escherichia coli O157:H7 and Salmonella Typhimurium. Surrogates for these pathogens would be beneficial for validating carcass decontamination...

  10. EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal for low-level radioactive and mixed wastes generated by decontaminating and decommissioning activities at the U.S. Department of Energy's...

  11. Evaluation of Salmonella disinfection strategies for pre-slaughter broiler crop decontamination

    E-Print Network [OSTI]

    Barnhart, Eric Thomas

    1998-01-01T23:59:59.000Z

    The purpose of the following studies was to evaluate selected potential decontamination methods for ability to reduce the incidence of Salmonella recovery from broiler crops during pre-slaughter feed withdrawal. The efficacy of prolonged lactose...

  12. Purification of alkaline solutions and wastes from actinides and technetium by coprecipitation with some carriers using the method of appearing reagents: Final Report

    SciTech Connect (OSTI)

    Peretrukhin, V.F.; Silin, V.I.; Kareta, A.V.; Gelis, A.V.; Shilov, V.P.; German, K.E.; Firsova, E.V.; Maslennikov, A.G.; Trushina, V.E. [Russian Academy of Sciences, Moscow (Russian Federation). Inst. of Physical Chemistry

    1998-09-01T23:59:59.000Z

    The coprecipitation of transuranium elements (TRU) and technetium from alkaline solutions and from simulants of Hanford Site tank wastes has been studied in reducing and oxidizing conditions on uranium(IV,VI) hydroxocompounds, tetraalkylammonium perrhenate and perchlorate, and on hydroxides of Fe(III), Co(III), Mn(II), and Cr(III) using the method of appearing reagents (MAR). Coprecipitations in alkaline solution have been shown to give high decontamination factors (DF) at low content of carrier and in the presence of high salt concentrations. Uranium(IV) hydroxide in concentrations higher than 3 {times} 10{sup {minus}3} M coprecipitates Pu and Cm in any oxidation state from 0.2 to 4 M NaOH with DFs of 110 to 1000 and Np and Tc with DFs of 51 to 176. Technetium (VII) coprecipitates with (5 to 8) {times} 10{sup {minus}4} M tetrabutylammonium (TBA) perrhenate in 0.01 to 0.02 M TBA hydroxide from 0.5 to 1.5 M NaOH to give DFs of 150 to 200. Coprecipitations of Np and Pu with Co(OH){sub 3}, Fe(OH){sub 3}, Cr(OH){sub 3}, and Mn(OH){sub 2} obtained by the MAR from precursors in the range from pH 10.5 to 0.4 M NaOH give DFs from 80 to 400.

  13. Hot water decontamination of beef carcasses to increase microbiological safety and shelf-life

    E-Print Network [OSTI]

    Barakate, Michelle Lee

    1991-01-01T23:59:59.000Z

    : -:r . ~ &:: ? ri:~ 4 c:r l, &, ?a??. . ' ' !"-' &! ~i i 4?'&. " ~ li r, '?Pil ril i '. ' rl iit'~'. ~a', '. ''+, I";= t I t h( ii il HOT WATER DECONTAMINATION OF BEEF CARCASSES TO INCREASE MICROBIOLOGICAL SAFETY AND SHELF-LIFE A Thesis... by MICHELLE LEE BARKATE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1991 Major Subject: Food Science and Technology HOT WATER DECONTAMINATION...

  14. Comparison of decontamination methods to reduce microbial levels in fresh beef trimmings

    E-Print Network [OSTI]

    Ellebracht, Emily Annette

    1999-01-01T23:59:59.000Z

    COMPARISON OF DECONTAMINATION METHODS TO REDUCE MICROBIAL LEVELS IN FRESH BEEF TRIMMINGS A Thesis EMILY ANNETTE ELLEBRACHT Submitted to the Office of Graduate Studies of Texas ABcM University in partial fulfillment of the requirements... for the degree of MASTER OF SCIENCE May 1999 Major Subject: Food Science and Technology COMPARISON OF DECONTAMINATION METHODS TO REDUCE MICROBIAL LEVELS IN FRESH BEEF TRIMMINGS A Thesis EMILY ANNETTE ELLEBRACHT Submitted to the Office of Graduate Studies...

  15. Spray-chilling and carcass decontamination systems using lactic and acetic acid

    E-Print Network [OSTI]

    Hamby, Patrick Lawrence

    1986-01-01T23:59:59.000Z

    OF SCIENCE December 1986 Najor Subject; Food Science and Technology SPRAY-CHILLING AND CARCASS DECONTAMINATION SYSTEMS USING LACTIC AND ACETIC ACID A Thesis by PATRICK LAWRENCE NAMBY Approved as to style and content by: H. R. Cross (Co...-Chairman of Committee) f W. Sa 11 (Co-Chai n Committee) Fred A. Gardner (Member) C. Vanderz t (Member ary C. Smith (Head of Department) December 1986 ABSTRACT Spray-Chilling and Carcass Decontamination Systems Using Lactic and Acetic Acid (December 1986...

  16. Fracture and Healing of Rock Salt Related to Salt Caverns

    SciTech Connect (OSTI)

    Chan, K.S.; Fossum, A.F.; Munson, D.E.

    1999-03-01T23:59:59.000Z

    In recent years, serious investigations of potential extension of the useful life of older caverns or of the use of abandoned caverns for waste disposal have been of interest to the technical community. All of the potential applications depend upon understanding the reamer in which older caverns and sealing systems can fail. Such an understanding will require a more detailed knowledge of the fracture of salt than has been necessary to date. Fortunately, the knowledge of the fracture and healing of salt has made significant advances in the last decade, and is in a position to yield meaningful insights to older cavern behavior. In particular, micromechanical mechanisms of fracture and the concept of a fracture mechanism map have been essential guides, as has the utilization of continuum damage mechanics. The Multimechanism Deformation Coupled Fracture (MDCF) model, which is summarized extensively in this work was developed specifically to treat both the creep and fracture of salt, and was later extended to incorporate the fracture healing process known to occur in rock salt. Fracture in salt is based on the formation and evolution of microfractures, which may take the form of wing tip cracks, either in the body or the boundary of the grain. This type of crack deforms under shear to produce a strain, and furthermore, the opening of the wing cracks produce volume strain or dilatancy. In the presence of a confining pressure, microcrack formation may be suppressed, as is often the case for triaxial compression tests or natural underground stress situations. However, if the confining pressure is insufficient to suppress fracture, then the fractures will evolve with time to give the characteristic tertiary creep response. Two first order kinetics processes, closure of cracks and healing of cracks, control the healing process. Significantly, volume strain produced by microfractures may lead to changes in the permeability of the salt, which can become a major concern in cavern sealing and operation. The MDCF model is used in three simulations of field experiments in which indirect measures were obtained of the generation of damage. The results of the simulations help to verify the model and suggest that the model captures the correct fracture behavior of rock salt. The model is used in this work to estimate the generation and location of damage around a cylindrical storage cavern. The results are interesting because stress conditions around the cylindrical cavern do not lead to large amounts of damage. Moreover, the damage is such that general failure can not readily occur, nor does the extent of the damage suggest possible increased permeation when the surrounding salt is impermeable.

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

    SciTech Connect (OSTI)

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

    1997-10-01T23:59:59.000Z

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

  18. Conversion of transuranic waste to low level waste by decontamination: a technical and economic evaluation

    SciTech Connect (OSTI)

    Allen, R.P.; Hazelton, R.F.

    1984-12-01T23:59:59.000Z

    A study was conducted to evaluate the technical and economic feasibility of using in-situ decontamination techniques to convert glove boxes and other large TRU-contaminated components directly into LLW. The results of the technical evaluation indicate that in-situ decontamination of these types of components to non-TRU levels is technically feasible. Applicable decontamination techniques include electropolishing, hand scrubbing, chemical washes/sprays, strippable coatings and Freon spray-cleaning. The removal of contamination from crevices and other holdup areas remains a problem, but may be solved through further advances in decontamination technology. Also, the increase in the allowable maximum TRU level from 10 nCi/g to 100 nCi/g as defined in DOE Order 5820.2 reduces the removal requirement and facilitates measurement of the remaining quantities. The major emphasis of the study was on a cost/benefit evaluation that included a review and update of previous analyses and evaluations of TRU-waste volume reduction and conversion options. The results of the economic evaluation show, for the assumptions used, that there is a definite cost incentive to size reduce large components, and that decontamination of sectioned material has become cost competitive with the size reduction options. In-situ decontamination appears to be the lowest cost option when based on routine-type operations conducted by well-trained and properly equipped personnel. 16 references, 1 figure, 7 tables.

  19. Off-site consequences of radiological accidents: methods, costs and schedules for decontamination

    SciTech Connect (OSTI)

    Tawil, J.J.; Bold, F.C.; Harrer, B.J.; Currie, J.W.

    1985-08-01T23:59:59.000Z

    This report documents a data base and a computer program for conducting a decontamination analysis of a large, radiologically contaminated area. The data base, which was compiled largely through interviews with knowledgeable persons both in the public and private sectors, consists of the costs, physical inputs, rates and contaminant removal efficiencies of a large number of decontamination procedures. The computer program utilizes this data base along with information specific to the contaminated site to provide detailed information that includes the least costly method for effectively decontaminating each surface at the site, various types of property losses associated with the contamination, the time at which each subarea within the site should be decontaminated to minimize these property losses, the quantity of various types of labor and equipment necessary to complete the decontamination, dose to radiation workers, the costs for surveying and monitoring activities, and the disposal costs associated with radiological waste generated during cleanup. The program and data base are demonstrated with a decontamination analysis of a hypothetical site. 39 refs., 24 figs., 155 tabs.

  20. Natural gas storage in bedded salt formations

    SciTech Connect (OSTI)

    Macha, G.

    1996-09-01T23:59:59.000Z

    In 1990 Western Resources Inc. (WRI) identified the need for additional natural gas storage capacity for its intrastate natural gas system operated in the state of Kansas. Western Resources primary need was identified as peak day deliverability with annual storage balancing a secondary objective. Consequently, an underground bedded salt storage facility, Yaggy Storage Field, was developed and placed in operation in November 1993. The current working capacity of the new field is 2.1 BCF. Seventy individual caverns are in service on the 300 acre site. The caverns vary in size from 310,000 CF to 2,600,000 CF. Additional capacity can be added on the existing acreage by increasing the size of some of the smaller existing caverns by further solution mining and by development of an additional 30 potential well sites on the property.

  1. Salt Stress in Desulfovibrio vulgaris Hildenborough: An integrated genomics approach

    E-Print Network [OSTI]

    Mukhopadhyay, Aindrila

    2010-01-01T23:59:59.000Z

    machinery against salt-induced damage in Synechococcus.Lactobacillus plantarum to salt and nonelectrolyte stress. Jregulation of acid, heat, and salt tolerance in Escherichia

  2. Salt Dynamics in Non-Riparian Freshwater Wetlands

    E-Print Network [OSTI]

    Stacey, Mark T

    2007-01-01T23:59:59.000Z

    Resources Center Project “Salt Dynamics in Non-RiparianTechnical Completion Report “Salt Dynamics in Non-Riparianindicate that the flux of salt between the soil and water

  3. Production of chlorine from chloride salts

    DOE Patents [OSTI]

    Rohrmann, Charles A. (Kennewick, WA)

    1981-01-01T23:59:59.000Z

    A process for converting chloride salts and sulfuric acid to sulfate salts and elemental chlorine is disclosed. A chloride salt and sulfuric acid are combined in a furnace where they react to produce a sulfate salt and hydrogen chloride. Hydrogen chloride from the furnace contacts a molten salt mixture containing an oxygen compound of vanadium, an alkali metal sulfate and an alkali metal pyrosulfate to recover elemental chlorine. In the absence of an oxygen-bearing gas during the contacting, the vanadium is reduced, but is regenerated to its active higher valence state by separately contacting the molten salt mixture with an oxygen-bearing gas.

  4. Transient nature of salt movement with wetting front in an unsaturated soil

    E-Print Network [OSTI]

    Soman, Vishwas Vinayak

    1992-01-01T23:59:59.000Z

    from unit area of soil (me/sq. m), () is moisture content of the soil layer at time of extraction for salt (cc/cc), Co is initial average salt concentration in the soil solution at moisture content 8 (me/liter) and C1 is average concentration...TRANSIENT NATURE OF SALT MOVEMENT WITH WETTING FRONT IN AN UNSATURATED SOIL A Thesis bY VISHWAS VINAYAK SOMAN Submitted to the Office of Graduate Studies of Texas A&M UniversitY in partial fulfillment of the requirements for the degree...

  5. Large-Scale Urban Decontamination; Developments, Historical Examples and Lessons Learned

    SciTech Connect (OSTI)

    Rick Demmer

    2007-02-01T23:59:59.000Z

    Recent terrorist threats and actual events have lead to a renewed interest in the technical field of large scale, urban environment decontamination. One of the driving forces for this interest is the real potential for the cleanup and removal of radioactive dispersal device (RDD or “dirty bomb”) residues. In response the U. S. Government has spent many millions of dollars investigating RDD contamination and novel decontamination methodologies. Interest in chemical and biological (CB) cleanup has also peaked with the threat of terrorist action like the anthrax attack at the Hart Senate Office Building and with catastrophic natural events such as Hurricane Katrina. The efficiency of cleanup response will be improved with these new developments and a better understanding of the “old reliable” methodologies. Perhaps the most interesting area of investigation for large area decontamination is that of the RDD. While primarily an economic and psychological weapon, the need to cleanup and return valuable or culturally significant resources to the public is nonetheless valid. Several private companies, universities and National Laboratories are currently developing novel RDD cleanup technologies. Because of its longstanding association with radioactive facilities, the U. S. Department of Energy National Laboratories are at the forefront in developing and testing new RDD decontamination methods. However, such cleanup technologies are likely to be fairly task specific; while many different contamination mechanisms, substrate and environmental conditions will make actual application more complicated. Some major efforts have also been made to model potential contamination, to evaluate both old and new decontamination techniques and to assess their readiness for use. Non-radioactive, CB threats each have unique decontamination challenges and recent events have provided some examples. The U. S. Environmental Protection Agency (EPA), as lead agency for these emergency cleanup responses, has a sound approach for decontamination decision-making that has been applied several times. The anthrax contamination at the U. S. Hart Senate Office Building and numerous U. S. Post Office facilities are examples of employing novel technical responses. Decontamination of the Hart Office building required development of a new approach for high level decontamination of biological contamination as well as techniques for evaluating the technology effectiveness. The World Trade Center destruction also demonstrated the need for, and successful implementation of, appropriate cleanup methodologies. There are a number of significant lessons that can be gained from a look at previous large scale cleanup projects. Too often we are quick to apply a costly “package and dispose” method when sound technological cleaning approaches are available. Understanding historical perspectives, advanced planning and constant technology improvement are essential to successful decontamination.

  6. Reduced weight decontamination formulation utilizing a solid peracid compound for neutralization of chemical and biological warfare agents

    DOE Patents [OSTI]

    Tucker, Mark D. (Albuquerque, NM)

    2011-09-20T23:59:59.000Z

    A reduced weight decontamination formulation that utilizes a solid peracid compound (sodium borate peracetate) and a cationic surfactant (dodecyltrimethylammonium chloride) that can be packaged with all water removed. This reduces the packaged weight of the decontamination formulation by .about.80% (as compared to the "all-liquid" DF-200 formulation) and significantly lowers the logistics burden on the warfighter. Water (freshwater or saltwater) is added to the new decontamination formulation at the time of use from a local source.

  7. Concrete decontamination by electro-hydraulic scabbling (EHS). Final report

    SciTech Connect (OSTI)

    NONE

    1997-10-01T23:59:59.000Z

    Contamination of concrete structures by radionuclides, hazardous metals and organic substances (including PCB`s) occurs at many DOE sites. The contamination of concrete structures (walls, floors, ceilings, etc.) varies in type, concentration, and especially depth of penetration into the concrete. In many instances, only the surface layer of concrete is contaminated, up to a depth of one inch, according to estimates provided in the R and D ID document. Then, removal of the concrete surface layer (scabbling) is considered to be the most effective decontamination method. Textron Systems Corp. (TSC) has developed a scabbling concept based on electro-mechanical phenomena accompanying strong electric pulses generated by applying high voltage at the concrete/water interface. Depending on the conditions, the electric discharge may occur either through a waste layer or through the concrete body itself. This report describes the development, testing, and results of this electro-mechanical process. Phase 1 demonstrated the feasibility of the process for the controlled removal of a thin layer of contaminated concrete. Phase 2 designed, fabricated, and tested an integrated subscale unit. This was tested at Fernald. In Phase 3, the scabbling unit was reconfigured to increase its power and processing rate. Technology transfer to an engineering contracting company is continuing.

  8. DECONTAMINATING AND PROCESSING DREDGED MATERIAL FOR BENEFICIAL USE

    SciTech Connect (OSTI)

    CLESCERI,N.L.; STERN,E.A.; FENG,H.; JONES,K.W.

    2000-07-01T23:59:59.000Z

    Management of contaminated dredged material is a major problem in the Port of New York and New Jersey. One component of an overall management plan can be the application of a decontamination technology followed by creation of a product suitable for beneficial use. This concept is the focus of a project now being carried out by the US Environmental Protection Agency-Region 2, the US Army Corps of Engineers-New York District, the US Department of Energy-Brookhaven National Laboratory, and regional university groups that have included Rensselaer Polytechnic Institute, Rutgers University, New Jersey Institute of Technology, and Stevens Institute of Technology. The project has gone through phased testing of commercial technologies at the bench scale (15 liters) and pilot scale (1.5--500 m{sup 3}) levels. Several technologies are now going forward to large-scale demonstrations that are intended to treat from 23,000 to 60,000 m{sup 3}. Selections of the technologies were made based on the effectiveness of the treatment process, evaluation of the possible beneficial use of the treated materials, and other factors. Major elements of the project are summarized here.

  9. Salt dome discoveries mounting in Mississippi

    SciTech Connect (OSTI)

    Ericksen, R.L. [Mississippi Office of Geology, Jackson, MS (United States)

    1996-06-17T23:59:59.000Z

    Exploratory drilling around piercement salt domes in Mississippi has met with a string of successes in recent months. Exploration of these salt features is reported to have been initiated through the review of non-proprietary, 2D seismic data and subsurface control. This preliminary data and work were then selectively upgraded by the acquisition of additional, generally higher quality, conventional 2D seismic lines. This current flurry of successful exploration and ensuing development drilling by Amerada Hess Corp. on the flanks of salt domes in Mississippi has resulted in a number of significant Hosston discoveries/producers at: Carson salt dome in Jefferson Davis County; Dry Creek salt dome in Covington County, Midway salt dome in lamar County, Monticello salt dome in Lawrence County, and Prentiss salt dome in Jefferson Davis County. The resulting production from these fields is gas and condensate, with wells being completed on 640 acre production units.

  10. Chloride Depletion in Aged Sea Salt Particles

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

    Chloride Depletion in Aged Sea Salt Particles Chloride Depletion in Aged Sea Salt Particles Print Wednesday, 06 February 2013 00:00 Particles or aerosols can be directly released...

  11. Salt index of potassium phosphate fertilizers and its relation to germination and early plant growth of field crops

    E-Print Network [OSTI]

    Freeouf, Jerry Allen

    1975-01-01T23:59:59.000Z

    determined by the displacement of soil solutions that are in equilibrium with applied fertilizer salts. This procedure is time consuming and requires extraction of large quantities of soil in leaching columns to obtain the soil solution. Although... SALT INDEX OF POTASSIUM PHOSPHATE FERTILIZERS AND ITS RELATION TO GERMINATION AND EARLY PLANT GROWTH OF FIELD CROPS A Thesis by JERRY ALLEN FREEOUF Submitted to the Graduate College of Texas A&M University in partial fulfillment...

  12. EA-1266: Proposed Decontamination and Disassembly of the Argonne Thermal Source Reactor (ATSR) At Argonne National Laboratory, Argonne, Illinois

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts for the proposal for the decontamination and disassembly of the U.S. Department of Energy's Argonne Thermal Source Reactor.

  13. Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312

    SciTech Connect (OSTI)

    Fournel, B.; Barre, Y.; Lepeytre, C.; Peycelon, H. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Grandjean, A. [Institut de Chimie Separative de Marcoule, UMR5257 CEA-CNRS-UM2-ENSCM, BP17171, 30207 Bagnols sur Ceze (France); Prevost, T.; Valery, J.F. [AREVA NC, Paris La Defense (France); Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191 Gif sur Yvette (France)

    2012-07-01T23:59:59.000Z

    Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

  14. First Robert Stobie SALT Workshop Science with SALT Workshop Proceedings, Vol. 2, 2004

    E-Print Network [OSTI]

    Bershady, Matthew A.

    First Robert Stobie SALT Workshop Science with SALT Workshop Proceedings, Vol. 2, 2004 D.A.H. Buckley Galaxy Kinematics with SALT M. A. Bershady1, M. A. W. Verheijen2, D. R. Andersen3, R. A. Swaters4-gathering power of SALT coupled with the high-throughput performance of the Prime Focus Imaging Spec- trograph

  15. Disparities in Salt Lake County and Salt Lake City Mortgage Outcomes and

    E-Print Network [OSTI]

    Feschotte, Cedric

    Disparities in Salt Lake County and Salt Lake City Mortgage Outcomes and Lending Practices Darius of lending practices. This article is an adapted excerpt from the Salt Lake County Regional Analysis impediments in the home mortgage application process. The HMDA data from 2006 to 2011 were compiled for Salt

  16. Salt marsh geomorphology: Physical and ecological effects on landform Keywords: salt marsh geomorphology; AGU Chapman Conference

    E-Print Network [OSTI]

    Fagherazzi, Sergio

    Editorial Salt marsh geomorphology: Physical and ecological effects on landform Keywords: salt marsh geomorphology; AGU Chapman Conference Evidence that the three-dimensional structure of salt marsh, and the ratio of marsh edge:marsh interior have all been shown to affect the distribution and density of salt

  17. 8, 7194, 2008 Sea salt aerosol

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ACPD 8, 71­94, 2008 Sea salt aerosol refractive indices R. Irshad et al. Title Page Abstract Discussions Laboratory measurements of the optical properties of sea salt aerosol R. Irshad 1 , R. G. Grainger salt aerosol refractive indices R. Irshad et al. Title Page Abstract Introduction Conclusions

  18. Chemical System Decontamination at PWR Power Stations Biblis A and B by Advanced System Decontamination by Oxidizing Chemistry (ASDOC-D) Process Technology - 13081

    SciTech Connect (OSTI)

    Loeb, Andreas; Runge, Hartmut; Stanke, Dieter [NIS Ingenieurgesellschaft mbH, Industriestrasse 13, 63755 Alzenau (Germany)] [NIS Ingenieurgesellschaft mbH, Industriestrasse 13, 63755 Alzenau (Germany); Bertholdt, Horst-Otto [NCT Consulting, Leonhardstrasse 16-18, 90443 Nuernberg (Germany)] [NCT Consulting, Leonhardstrasse 16-18, 90443 Nuernberg (Germany); Adams, Andreas; Impertro, Michael; Roesch, Josef [RWE Power, 68643 Biblis (Germany)] [RWE Power, 68643 Biblis (Germany)

    2013-07-01T23:59:59.000Z

    For chemical decontamination of PWR primary systems the so called ASDOC-D process has been developed and qualified at the German PWR power station Biblis. In comparison to other chemical decontamination processes ASDOC-D offers a number of advantages: - ASDOC-D does not require separate process equipment but is completely operated and controlled by the nuclear site installations. Feeding of chemical concentrates into the primary system is done by means of the site's dosing systems. Process control is performed by standard site instrumentation and analytics. - ASDOC-D safely prevents any formation and precipitation of insoluble constituents - Since ASDOC-D is operated without external equipment there is no need for installation of such equipment in high radioactive radiation surrounding. The radioactive exposure rate during process implementation and process performance may therefore be neglected in comparison to other chemical decontamination processes. - ASDOC-D does not require auxiliary hose connections which usually bear high leakage risk. The above mentioned technical advantages of ASDOC-D together with its cost-effectiveness gave rise to Biblis Power station to agree on testing ASDOC-D at the volume control system of PWR Biblis unit A. By involving the licensing authorities as well as expert examiners into this test ASDOC-D received the official qualification for primary system decontamination in German PWR. As a main outcome of the achieved results NIS received contracts for full primary system decontamination of both units Biblis A and B (each 1.200 MW) by end of 2012. (authors)

  19. Petroleum storage potential of the Chacahoula salt dome, Louisiana

    SciTech Connect (OSTI)

    Magorian, T.R. (Magorian (Thomas R.), Amherst, NY (USA)); Neal, J.T. (Sandia National Labs., Albuquerque, NM (USA))

    1990-01-01T23:59:59.000Z

    Chacahoula salt dome, eight miles southwest of Thibodaux, LA, could be solution mined to create caverns for storing as much as 500 million barrels (MMB) of crude oil, should the Strategic Petroleum Reserve (SPR) require additional storage volume. The salt mass geometry is confirmed by more than 50 oil wells, and also from previous exploratory drilling for sulphur. Top of salt occurs at {minus}1100 ft, and some 1300 acres exist within the {minus}2000 ft salt contour. Frasch mining of 1.35 million long tons of sulphur caused the surface to subside about one foot on the northeastern part of the dome. Creep-induced subsidence averaging {approximately}2.7 ft over 30 yrs is estimated for a 200 MMB cavern array, which would require perimeter diking to control localized perennial flooding. Earthquakes approaching intensity MM 6 have occurred nearby and are expected to recur on the order of {approximately}100 yrs but would not affect cavern stability. Additional study of brine disposal methods and hurricane surge probabilities are needed to establish design parameters and cost estimates for storage. 11 refs., 8 figs., 2 tabs.

  20. Solution Package Scope Definition, Report 72, Salt Waste (SP #72) |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transfer toSensorSoftware Helps KentuckyRenewableDepartment of

  1. Dry Creek salt dome, Mississippi Interior Salt basin

    SciTech Connect (OSTI)

    Montgomery, S.L.; Ericksen, R.L.

    1997-03-01T23:59:59.000Z

    Recent drilling of salt dome flanks in the Mississippi Salt basin has resulted in important new discoveries and the opening of a frontier play. This play is focused on gas/condensate reserves in several Cretaceous formations, most notably the Upper Cretaceous Eutaw and lower Tuscaloosa intervals and Lower Cretaceous Paluxy and Hosston formations. As many as eight domes have been drilled thus far; sandstones in the upper Hosston Formation comprise the primary target. Production has been as high as 3-5 Mcf and 500-1200 bbl of condensate per day, with estimated ultimate reserves in the range of 0.2 to 1.5 MBOE (million barrels oil equivalent) per well. As typified by discovery at Dry Creek salt dome, traps are related to faulting, unconformities, and updip loss of permeability. Previous drilling at Dry Creek, and in the basin generally, avoided the flank areas of most domes, due to geologic models that predicted latestage (Tertiary) piercement and breached accumulations. Recent data from Dry Creek and other productive domes suggest that growth was episodic and that piercement of Tertiary strata did not affect deeper reservoirs charged with hydrocarbons in the Late Cretaceous.

  2. Analysis of the application of decontamination technologies to radioactive metal waste minimization using expert systems

    SciTech Connect (OSTI)

    Bayrakal, S.

    1993-09-30T23:59:59.000Z

    Radioactive metal waste makes up a significant portion of the waste currently being sent for disposal. Recovery of this metal as a valuable resource is possible through the use of decontamination technologies. Through the development and use of expert systems a comparison can be made of laser decontamination, a technology currently under development at Ames Laboratory, with currently available decontamination technologies for applicability to the types of metal waste being generated and the effectiveness of these versus simply disposing of the waste. These technologies can be technically and economically evaluated by the use of expert systems techniques to provide a waste management decision making tool that generates, given an identified metal waste, waste management recommendations. The user enters waste characteristic information as input and the system then recommends decontamination technologies, determines residual contamination levels and possible waste management strategies, carries out a cost analysis and then ranks, according to cost, the possibilities for management of the waste. The expert system was developed using information from literature and personnel experienced in the use of decontamination technologies and requires validation by human experts and assignment of confidence factors to the knowledge represented within.

  3. All-Weather Hydrogen Peroxide-Based Decontamination of CBRN Contaminants

    SciTech Connect (OSTI)

    Wagner, George W.; Procell, Lawrence R.; Sorrick, David C.; Lawson, Glenn E.; Wells, Claire M.; Reynolds, Charles M.; Ringelberg, D. B.; Foley, Karen L.; Lumetta, Gregg J.; Blanchard, David L.

    2010-04-07T23:59:59.000Z

    A hydrogen peroxide-based decontaminant, Decon Green, is efficacious for the decontamination of chemical agents VX (S-2-(diisopropylamino)ethyl O-ethyl methylphosphonothioate), GD (Soman, pinacolyl methylphosphonofluoridate), and HD (mustard, bis(2-chloroethyl) sulfide); the biological agent anthrax (Bacillus anthracis); and radiological isotopes Cs-137 and Co-60; thus demonstrating the ability of this decontamination approach to ameliorate the aftermath of all three types of weapons of mass destruction (WMD). Reaction mechanisms afforded for the chemical agents are discussed as are rationales for the enhanced removal efficacy of recalcitrant 60Co on certain surfaces. Decontaminants of this nature can be deployed, and are effective, at very low temperatures (-32 ?C), as shown for studies done with VX and HD simulants, without the need for external heat sources. Finally, the efficacy of a lower-logistics, dry decontaminant powder concentrate (utilizing the solid active-oxygen compounds peracetyl borate and Peroxydone) which can be reconstituted with water in the field prior to use, is presented.

  4. Radar investigation of the Hockley salt dome

    E-Print Network [OSTI]

    Hluchanek, James Andrew

    1973-01-01T23:59:59.000Z

    : Geophysics RADAR INVESTIGATION OF THE HOCKLEY SALT DOME A Thesis by UAMES ANDREW HLUCHANEK A'pproved as to style and content by: (Head of Departme t ? Member) May 1. 973 ABSTRACT Radar investigation of the Hockley Salt Dome. . (Nay, 1973) James... Andrew Hluchanek, B. S. , Texas A&M University Directed by: Dr. Robert R. Unterberger Radar probing through salt was accomplished at 17 radar stations established in the United Salt Company mine at Hockley, Texas. The top of the salt dom is mapped...

  5. Mobile worksystems for decontamination and decommissioning operations. Final report

    SciTech Connect (OSTI)

    NONE

    1997-02-01T23:59:59.000Z

    This project is an interdisciplinary effort to develop effective mobile worksystems for decontamination and decommissioning (D&D) of facilities within the DOE Nuclear Weapons Complex. These mobile worksystems will be configured to operate within the environmental and logistical constraints of such facilities and to perform a number of work tasks. Our program is designed to produce a mobile worksystem with capabilities and features that are matched to the particular needs of D&D work by evolving the design through a series of technological developments, performance tests and evaluations. The Phase I effort was based on a robot called the Remote Work Vehicle (RWV) that was previously developed by CMU for use in D&D operations at the Three Mile Island Unit 2 Reactor Building basement. During Phase I of this program, the RWV was rehabilitated and upgraded with contemporary control and user interface technologies and used as a testbed for remote D&D operations. We established a close working relationship with the DOE Robotics Technology Development Program (RTDP). In the second phase, we designed and developed a next generation mobile worksystem, called Rosie, and a semi-automatic task space scene analysis system, called Artisan, using guidance from RTDP. Both systems are designed to work with and complement other RTDP D&D technologies to execute selective equipment removal scenarios in which some part of an apparatus is extricated while minimally disturbing the surrounding objects. RTDP has identified selective equipment removal as a timely D&D mission, one that is particularly relevant during the de-activation and de-inventory stages of facility transitioning as a means to reduce the costs and risks associated with subsequent surveillance and monitoring. In the third phase, we tested and demonstrated core capabilities of Rosie and Artisan; we also implemented modifications and enhancements that improve their relevance to DOE`s facility transitioning mission.

  6. Citric Acid-Modified Fenton's Reaction for the Oxidation of Chlorinated Ethylenes in Soil Solution Systems

    E-Print Network [OSTI]

    Seol, Yongkoo

    2008-01-01T23:59:59.000Z

    essential for effective decontamination. Batch tests withoptimum and safe decontamination when Fenton’s reaction isoperational conditions for decontamination activity. Further

  7. Thermophysical properties of reconsolidating crushed salt.

    SciTech Connect (OSTI)

    Bauer, Stephen J.; Urquhart, Alexander

    2014-03-01T23:59:59.000Z

    Reconsolidated crushed salt is being considered as a backfilling material placed upon nuclear waste within a salt repository environment. In-depth knowledge of thermal and mechanical properties of the crushed salt as it reconsolidates is critical to thermal/mechanical modeling of the reconsolidation process. An experimental study was completed to quantitatively evaluate the thermal conductivity of reconsolidated crushed salt as a function of porosity and temperature. The crushed salt for this study came from the Waste Isolation Pilot Plant (WIPP). In this work the thermal conductivity of crushed salt with porosity ranging from 1% to 40% was determined from room temperature up to 300oC, using two different experimental methods. Thermal properties (including thermal conductivity, thermal diffusivity and specific heat) of single-crystal salt were determined for the same temperature range. The salt was observed to dewater during heating; weight loss from the dewatering was quantified. The thermal conductivity of reconsolidated crushed salt decreases with increasing porosity; conversely, thermal conductivity increases as the salt consolidates. The thermal conductivity of reconsolidated crushed salt for a given porosity decreases with increasing temperature. A simple mixture theory model is presented to predict and compare to the data developed in this study.

  8. 2010 New Mexico Water Research Symposium August 3, 2010 E-1 Photocatalytic Decontamination of Wastewater with Porous Material HNb3O8

    E-Print Network [OSTI]

    Johnson, Eric E.

    2010 New Mexico Water Research Symposium ­ August 3, 2010 E-1 Photocatalytic Decontamination decontamination. They exhibited excellent catalytic activity, but with a strong pH dependence on the photo

  9. Plutonium Decontamination Using CBI Decon Gel 1101 in Highly Contaminated and Unique Areas at LLNL

    SciTech Connect (OSTI)

    Sutton, M; Fischer, R P; Thoet, M M; O'Neill, M; Edgington, G

    2008-06-09T23:59:59.000Z

    A highly contaminated glove-box at LLNL containing plutonium was decontaminated using a strippable decontamination gel. 6 x 12 inch quadrants were mapped out on each of the surfaces. The gel was applied to various surfaces inside the glove-box and was allowed to cure. The radioactivity in each quadrant was measured using a LLNL Blue Alpha meter with a 1.5 inch standoff distance. The results showed decontamination factors of 130 and 210 on cast steel and Lexan{reg_sign} surfaces respectively after several applications. The gel also absorbed more than 91% of the radiation emitted from the surfaces during gel curing. The removed strippable film was analyzed by neutron multiplicity counting and gamma spectroscopy, yielding relative mass information and radioisotopic composition respectively.

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

    SciTech Connect (OSTI)

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

    1996-06-01T23:59:59.000Z

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

  11. Biohazard Decontamination Form. Fax completed form to 352-392-3647 or scan and email to BSO@ehs.ufl.edu Biological Safety Office

    E-Print Network [OSTI]

    Jawitz, James W.

    Ver. 2014 Biohazard Decontamination Form. Fax completed form to 352-392-3647 or scan and email, contaminated with a biohazardous material must be decontaminated before it is: Repaired by Physical Plant to find out company policies for decontamination) Instructions: 1. Complete the information on the next

  12. Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    SciTech Connect (OSTI)

    M.E. Lumia; C.A. Gentile

    2002-01-18T23:59:59.000Z

    A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.

  13. Proceedings of the 2007 ANS Topical Meeting on Decommissioning, Decontamination, and Reutilization - DD and R 2007

    SciTech Connect (OSTI)

    NONE

    2008-01-15T23:59:59.000Z

    The American Nuclear Society (ANS) Topical Meeting on Decommissioning, Decontamination, and Reutilization (DD and R 2007), 'Capturing Decommissioning Lessons Learned', is sponsored by the ANS Decommissioning, Decontamination and Reutilization; Environmental Sciences; and Fuel Cycle and Waste Management Divisions. This meeting provides a forum for an international exchange of technical knowledge and project management experience gained from the ongoing process of decommissioning nuclear facilities. Of particular note is the number of projects that are approaching completion. This document gathers 113 presentations given at this meeting.

  14. Transportation cask decontamination and maintenance at the potential Yucca Mountain repository; Yucca Mountain Site characterization project

    SciTech Connect (OSTI)

    Hartman, D.J.; Miller, D.D. [Bechtel National, Inc., San Francisco, CA (United States); Hill, R.R. [Sandia National Labs., Albuquerque, NM (United States)

    1992-04-01T23:59:59.000Z

    This study investigates spent fuel cask handling experience at existing nuclear facilities to determine appropriate cask decontamination and maintenance operations at the potential Yucca Mountain repository. These operations are categorized as either routine or nonroutine. Routine cask decontamination and maintenance tasks are performed in the cask preparation area at the repository. Casks are taken offline to a separate cask maintenance area for major nonroutine tasks. The study develops conceptual designs of the cask preparation area and cask maintenance area. The functions, layouts, and major features of these areas are also described.

  15. Investigation of the possibility of decontamination of bitumen concrete pavement contaminated with radionuclides

    SciTech Connect (OSTI)

    Karlina, O.K.; Ovchinnikov, A.V.; Ozhovan, M.I. [and others

    1995-10-01T23:59:59.000Z

    Radioactive contamination of the environment is possible during operation of nuclear power plants and the utilization of radionuclide sources in the economy. The problem of decontaminating the surfaces of industrial objects and environmental objects which are contaminated by radionuclides can be solved by different methods of depending on the character of the object: chemical treatment of metallic surfaces of equipment parts by application of different washing fluids, mechanical removal of contaminants or washing contaminants off with a jet of liquid, as well as adding different abrasive additives, the use of film-forming substances for sorption and removal of the decontaminating layer from the surface being cleaned, and other methods.

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

    SciTech Connect (OSTI)

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

    1995-01-01T23:59:59.000Z

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

  17. Industrial Hygiene Concerns during the Decontamination and Decommissioning of the Tokamak Fusion Test Reactor

    E-Print Network [OSTI]

    Lumia, M E

    2002-01-01T23:59:59.000Z

    A significant industrial hygiene concern during the Decontamination and Decommissioning (D and D) of the Tokamak Fusion Test Reactor (TFTR) was the oxidation of the lead bricks' surface, which were utilized for radiation shielding. This presented both airborne exposure and surface contamination issues for the workers in the field removing this material. This paper will detail the various protection and control methods tested and implemented to protect the workers, including those technologies deployed to decontaminate the work surfaces. In addition, those techniques employed to recycle the lead for additional use at the site will be discussed.

  18. Fiscal years 1993 and 1994 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Decontamination and Decommissioning Projects Department

    SciTech Connect (OSTI)

    NONE

    1995-12-31T23:59:59.000Z

    This photobriefing book describes the ongoing decontamination and decommissioning projects at the Argonne National Laboratory (ANL)-East Site near Lemont, Illinois. The book is broken down into three sections: introduction, project descriptions, and summary. The introduction elates the history and mission of the Decontamination and Decommissioning (D and D) Projects Department at ANL-East. The second section describes the active ANL-East D and D projects, giving a project history and detailing fiscal year (FY) 1993 and FY 1994 accomplishments and FY 1995 goals. The final section summarizes the goals of the D and D Projects Department and the current program status. The D/D projects include the Experimental Boiling Water Reactor, Chicago Pile-5 Reactor, that cells, and plutonium gloveboxes. 73 figs.

  19. Interior cavern conditions and salt fall potential

    SciTech Connect (OSTI)

    Munson, D.E.; Molecke, M.A. [Sandia National Labs., Albuquerque, NM (United States); Myers, R.E. [Strategic Petroleum Reserve, New Orleans, LA (United States)

    1998-03-01T23:59:59.000Z

    A relatively large number of salt caverns are used for fluid hydrocarbon storage, including an extensive set of facilities in the Gulf Coast salt domes for the Strategic Petroleum Reserve (SPR) Program. Attention is focused on the SPR caverns because of available histories that detail events involving loss and damage of the hanging string casing. The total number of events is limited, making the database statistically sparse. The occurrence of the events is not evenly distributed, with some facilities, and some caverns, more susceptible than others. While not all of these events could be attributed to impacts from salt falls, many did show the evidence of such impacts. As a result, a study has been completed to analyze the potential for salt falls in the SPR storage caverns. In this process, it was also possible to deduce some of the cavern interior conditions. Storage caverns are very large systems in which many factors could possibly play a part in casing damage. In this study, all of the potentially important factors such as salt dome geology, operational details, and material characteristics were considered, with all being logically evaluated and most being determined as secondary in nature. As a result of the study, it appears that a principal factor in determining a propensity for casing damage from salt falls is the creep and fracture characteristics of salt in individual caverns. In addition the fracture depends strongly upon the concentration of impurity particles in the salt. Although direct observation of cavern conditions is not possible, the average impurity concentration and the accumulation of salt fall material can be determined. When this is done, there is a reasonable correlation between the propensity for a cavern to show casing damage events and accumulation of salt fall material. The accumulation volumes of salt fall material can be extremely large, indicating that only a few of the salt falls are large enough to cause impact damage.

  20. Molten fluoride fuel salt chemistry

    SciTech Connect (OSTI)

    Toth, L.M.; Del Cul, G.D.; Dai, S.; Metcalf, D.H. [Oak Ridge National Lab., TN (United States). Chemical Technology Div.

    1994-09-01T23:59:59.000Z

    The chemistry of molten fluorides is traced from their development as fuels in the Molten Salt Reactor Experiment with important factors in their selection being discussed. Key chemical characteristics such as solubility, redox behavior, and chemical activity are explained as they relate to the behavior of molten fluoride fuel systems. Fission product behavior is described along with processing experience. Development requirements for fitting the current state of the chemistry to modern nuclear fuel system are described. It is concluded that while much is known about molten fluoride behavior, processing and recycle of the fuel components is a necessary factor if future systems are to be established.

  1. Factors influencing algal biomass in hydrologically dynamic salt ponds in a subtropical salt marsh

    E-Print Network [OSTI]

    Miller, Carrie J.

    2009-05-15T23:59:59.000Z

    by channels and shallow ponds that are subject to flooding by winds, tides, and storm surges. Coastal salt marshes are widely regarded as zones of high macrophyte productivity. However, microalgae may contribute more to salt marsh productivity than previously...

  2. Noncentrosymmetric salt inclusion oxides: Role of salt lattices and counter ions in bulk polarity

    SciTech Connect (OSTI)

    West, J. Palmer [Department of Chemistry, Clemson University, Clemson, SC 29634-0973 (United States)] [Department of Chemistry, Clemson University, Clemson, SC 29634-0973 (United States); Hwu, Shiou-Jyh, E-mail: shwu@clemson.edu [Department of Chemistry, Clemson University, Clemson, SC 29634-0973 (United States)] [Department of Chemistry, Clemson University, Clemson, SC 29634-0973 (United States)

    2012-11-15T23:59:59.000Z

    The synthesis and structural features of a newly emerged class of salt-inclusion solids (SISs) are reviewed. The descriptive chemistry with respect to the role of ionic salt and its correlation with bulk noncentrosymmetricity and polarity of the covalent oxide lattice in question is discussed by means of structure analysis. These unprecedented discoveries have opened doors to novel materials synthesis via the utilities of salt-inclusion chemistry (SIC) that are otherwise known as the molten-salt approach. The result of these investigations prove that the bulk acentricity, or cancellation of which, can be accounted for from the perspective of ionic and/or salt lattices. Highlights: Black-Right-Pointing-Pointer Synthesis and structure of newly emerged salt-inclusion solids are reviewed. Black-Right-Pointing-Pointer Salt lattice and its symmetry correlation with polar framework are discussed. Black-Right-Pointing-Pointer Preservation of acentricity is accounted for from the perspective of ionic and salt lattices.

  3. Solubility of hydrocarbons in salt water

    SciTech Connect (OSTI)

    Yaws, C.L.; Lin, X. (Lamar Univ., Beaumont, TX (United States). Dept. of Chemical Engineering)

    1994-01-01T23:59:59.000Z

    In the design and operation of industrial processes, physical and thermodynamic property data are required. Increasingly stringent regulations are making water solubility of substances even more critical. Water solubility data of naphthenes, or cycloalkanes, is applicable for the complete range of salt concentrations, including water without salt to water saturated with salt. The results are intended for use in initial engineering and environmental applications. Solubility values from the correlation are useful in determining the distribution of a hydrocarbon spill on its contact with sea water. Solubility values at other salt concentrations also may be computed. Results are presented for water solubility of hydrocarbons (naphthenes) as a function of salt concentration (log(S) = A + BX + CX[sup 2]). The correlation constants, A, B and C, are displayed in an easy-to-use tabular format that is applicable for rapid engineering use with the personal computer or hand-held calculator. The results for solubility in salt water are applicable for the complete range of salt concentrations. This range covers water without salt, X = 0, to water saturated with salt, X = 358,700 ppM(wt). Correlation and experimental results are in favorable agreement.

  4. Electrolytic orthoborate salts for lithium batteries

    DOE Patents [OSTI]

    Angell, Charles Austen [Mesa, AZ; Xu, Wu [Tempe, AZ

    2009-05-05T23:59:59.000Z

    Orthoborate salts suitable for use as electrolytes in lithium batteries and methods for making the electrolyte salts are provided. The electrolytic salts have one of the formulae (I). In this formula anionic orthoborate groups are capped with two bidentate chelating groups, Y1 and Y2. Certain preferred chelating groups are dibasic acid residues, most preferably oxalyl, malonyl and succinyl, disulfonic acid residues, sulfoacetic acid residues and halo-substituted alkylenes. The salts are soluble in non-aqueous solvents and polymeric gels and are useful components of lithium batteries in electrochemical devices.

  5. Electrolytic orthoborate salts for lithium batteries

    DOE Patents [OSTI]

    Angell, Charles Austen (Mesa, AZ); Xu, Wu (Tempe, AZ)

    2008-01-01T23:59:59.000Z

    Orthoborate salts suitable for use as electrolytes in lithium batteries and methods for making the electrolyte salts are provided. The electrolytic salts have one of the formulae (I). In this formula anionic orthoborate groups are capped with two bidentate chelating groups, Y1 and Y2. Certain preferred chelating groups are dibasic acid residues, most preferably oxalyl, malonyl and succinyl, disulfonic acid residues, sulfoacetic acid residues and halo-substituted alkylenes. The salts are soluble in non-aqueous solvents and polymeric gels and are useful components of lithium batteries in electrochemical devices.

  6. Granular Salt Summary: Reconsolidation Principles and Applications

    SciTech Connect (OSTI)

    Hansen, Frank; Popp, Till; Wieczorek, Klaus; Stührenberg, Dieter

    2014-07-01T23:59:59.000Z

    The purposes of this paper are to review the vast amount of knowledge concerning crushed salt reconsolidation and its attendant hydraulic properties (i.e., its capability for fluid or gas transport) and to provide a sufficient basis to understand reconsolidation and healing rates under repository conditions. Topics covered include: deformation mechanisms and hydro-mechanical interactions during reconsolidation; the experimental data base pertaining to crushed salt reconsolidation; transport properties of consolidating granulated salt and provides quantitative substantiation of its evolution to characteristics emulating undisturbed rock salt; and extension of microscopic and laboratory observations and data to the applicable field scale.

  7. Multiphase Flow and Cavern Abandonment in Salt

    SciTech Connect (OSTI)

    Ehgartner, Brian; Tidwell, Vince

    2001-02-13T23:59:59.000Z

    This report will explore the hypothesis that an underground cavity in gassy salt will eventually be gas filled as is observed on a small scale in some naturally occurring salt inclusions. First, a summary is presented on what is known about gas occurrences, flow mechanisms, and cavern behavior after abandonment. Then, background information is synthesized into theory on how gas can fill a cavern and simultaneously displace cavern fluids into the surrounding salt. Lastly, two-phase (gas and brine) flow visualization experiments are presented that demonstrate some of the associated flow mechanisms and support the theory and hypothesis that a cavity in salt can become gas filled after plugging and abandonment

  8. Orientationally ordered aggregates of stiff polyelectrolytes in the presence of multivalent salt

    E-Print Network [OSTI]

    Sarah Mohammadinejad; Hossein Fazli; Ramin Golestanian

    2009-03-25T23:59:59.000Z

    Aggregation of stiff polyelectrolytes in solution and angle- and distance-dependent potential of mean force between two like-charged rods are studied in the presence of 3-valent salt using molecular dynamics simulations. In the bulk solution, formation of long-lived metastable structures with similarities to the raft-like structures of actin filaments is observed within a range of salt concentration. The system finally goes to a state with lower free energy in which finite-sized bundles of parallel polyelectrolytes form. Preferred angle and interaction type between two like-charged rods at different separations and salt concentrations are also studied, which shed some light on the formation of orientationally ordered structures.

  9. DECONTAMINATION AND BENEFICIAL REUSE OF DREDGED ESTUARINE SEDIMENT: THE WESTINGHOUSE PLASMA VITRIFICATION PROCESS

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    DECONTAMINATION AND BENEFICIAL REUSE OF DREDGED ESTUARINE SEDIMENT: THE WESTINGHOUSE PLASMA of the New York/New Jersey Harbor requires regular dredging. The offshore dumping facility has been closed, dredged material disposal, demonstration testing, process design. 1 McLaughlin, D. F., Fellow Engineer

  10. Maintaining Access to America's Intermodal Ports/Technologies for Decontamination of Dredged

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    Maintaining Access to America's Intermodal Ports/Technologies for Decontamination of Dredged will be the control and treatment of contaminated sediments dredged from our nation's waterways. More than 306 million cubic meters (m 3 ) (400 million cubic yards [cy]) of sediments are dredged annually from U.S. waterways

  11. DECONTAMINATION AND BENEFICIAL REUSE OF DREDGED MATERIAL USING EXISTING INFRASTRUCTURE FOR THE MANUFACTURE OF LIGHTWEIGHT

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    1 DECONTAMINATION AND BENEFICIAL REUSE OF DREDGED MATERIAL USING EXISTING INFRASTRUCTURE an environmentally acceptable and economically beneficial reuse option for the management of dredged material is self/UPCYCLE Associates' technological and commercial approach focuses on the utilization of dredged material

  12. RIS-M-2473 WEATHERING AND DECONTAMINATION OF RADIOACTIVITY DEPOSITED ON

    E-Print Network [OSTI]

    the decontamination of Rubidiunt86 (representing Cesium134 and Cesium137) deposited on concrete surfaces. Measurements; GAMMA RADIATION; REACTOR ACCIDENTS; ROADS; RUBIDIUM 86; SURFACE CLEANING; SURFACE CONTAMINATION; URBAN the reduction in dose rate from a contaminated outdoor surface caused by the influence of the outdoor conditions

  13. RIS-M-2273 WEATHERING AND DECONTAMINATION OF RADIOACTIVITY DEPOSITED ON

    E-Print Network [OSTI]

    the decontamination of Rubidium86 (representing Cesium134 and 137) Barium-Lanthanum 140 and Ruthenium103 deposited for calculating doses to the population in the land contamination project (Risø-R-462). INIS descriptors: REACTOR ACCIDENTS; EXTERNAL IRRADIATION; GAMMA RADIATION; FISSION PRODUCTS; ROADS; ASPHALTS; SURFACE CONTAMINATION

  14. Advanced Sediment Washing for Decontamination of New York/New Jersey Harbor Dredged Materials

    E-Print Network [OSTI]

    Brookhaven National Laboratory

    .S. Army Corps of Engineers (USACE) ­ New York District, with the U.S. Department of Energy (DOE1 Advanced Sediment Washing for Decontamination of New York/New Jersey Harbor Dredged Materials Focus: New York / New Jersey Harbor Region In the New York / New Jersey Harbor Region, the effect

  15. EIS-0133: Decontamination and Waste Treatment Facility for the Lawrence Livermore National Laboratory Livermore, California

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy’s San Francisco Operations Office developed this statement to analyze the potential environmental and socioeconomic impacts of alternatives for constructing and operating a Decontamination and Waste Treatment Facility for nonradioactive (hazardous and nonhazardous) mixed and radioactive wastes at Lawrence Livermore National Laboratory.

  16. Decontamination and inspection plan for Phase 3 closure of the 300 area waste acid treatment system

    SciTech Connect (OSTI)

    LUKE, S.N.

    1999-02-01T23:59:59.000Z

    This decontamination and inspection plan (DIP) describes decontamination and verification activities in support of Phase 3 closure of the 300 Area Waste Acid Treatment System (WATS). Phase 3 is the third phase of three WATS closure phases. Phase 3 attains clean closure conditions for WATS portions of the 334 and 311 Tank Farms (TF) and the 333 and 303-F Buildings. This DIP also describes designation and management of waste and debris generated during Phase 3 closure activities. Information regarding Phase 1 and Phase 2 for decontamination and verification activities closure can be found in WHC-SD-ENV-AP-001 and HNF-1784, respectively. This DIP is provided as a supplement to the closure plan (DOE/RL-90-11). This DIP provides the documentation for Ecology concurrence with Phase 3 closure methods and activities. This DIP is intended to provide greater detail than is contained in the closure plan to satisfy Ecology Dangerous Waste Regulations, Washington Administrative Code (WAC) 173-303-610 requirement that closure documents describe the methods for removing, transporting, storing, and disposing of all dangerous waste at the unit. The decontamination and verification activities described in this DIP are based on the closure plan and on agreements reached between Ecology and the U.S. Department of Energy, Richland Operations Office (DOE-RL) during Phase 3 closure activity workshops and/or project manager meetings (PMMs).

  17. Reduced weight decontamination formulation for neutralization of chemical and biological warfare agents

    SciTech Connect (OSTI)

    Tucker, Mark D.

    2014-06-03T23:59:59.000Z

    A reduced weight DF-200 decontamination formulation that is stable under high temperature storage conditions. The formulation can be pre-packed as an all-dry (i.e., no water) or nearly-dry (i.e., minimal water) three-part kit, with make-up water (the fourth part) being added later in the field at the point of use.

  18. Mesoporous titanium-manganese dioxide for sulphur mustard and soman decontamination

    SciTech Connect (OSTI)

    Stengl, Vaclav, E-mail: stengl@iic.cas.cz [Department of Solid State Chemistry, Institute of Inorganic Chemistry AS CR v.v.i., 250 68 Rez (Czech Republic)] [Department of Solid State Chemistry, Institute of Inorganic Chemistry AS CR v.v.i., 250 68 Rez (Czech Republic); Bludska, Jana [Department of Solid State Chemistry, Institute of Inorganic Chemistry AS CR v.v.i., 250 68 Rez (Czech Republic)] [Department of Solid State Chemistry, Institute of Inorganic Chemistry AS CR v.v.i., 250 68 Rez (Czech Republic); Oplustil, Frantisek; Nemec, Tomas [Military Technical Institute of Protection Brno, Veslarska 230, 628 00 Brno (Czech Republic)] [Military Technical Institute of Protection Brno, Veslarska 230, 628 00 Brno (Czech Republic)

    2011-11-15T23:59:59.000Z

    Highlights: {yields} New nano-dispersive materials for warfare agents decontamination. {yields} 95% decontamination activities for sulphur mustard. {yields} New materials base on titanium and manganese oxides. -- Abstract: Titanium(IV)-manganese(IV) nano-dispersed oxides were prepared by a homogeneous hydrolysis of potassium permanganate and titanium(IV) oxo-sulphate with 2-chloroacetamide. Synthesised samples were characterised using Brunauer-Emmett-Teller (BET) surface area and Barrett-Joiner-Halenda porosity (BJH), X-ray diffraction (XRD), infrared spectroscopy (IR), and scanning electron microscopy (SEM). These oxides were taken for an experimental evaluation of their reactivity with sulphur mustard (HD or bis(2-chloroethyl)sulphide) and soman (GD or (3,3'-dimethylbutan-2-yl)-methylphosphonofluoridate). Mn{sup 4+} content affects the decontamination activity; with increasing Mn{sup 4+} content the activity increases for sulphur mustard and decreases for soman. The best decontamination activities for sulphur mustard and soman were observed for samples TiMn{sub 3}7 with 18.6 wt.% Mn and TiMn{sub 5} with 2.1 wt.% Mn, respectively.

  19. Environmental assessment for decontaminating and decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA

    SciTech Connect (OSTI)

    Not Available

    1980-12-01T23:59:59.000Z

    The Department of Energy has prepared an environmental assessment on the proposed decontamination and decommissioning of the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pennsylvania. Based on the environmental assessment, which is available to the public on request, the Department has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969, 42 USC 4321 et seq. Therefore, no environmental impact statement is required. The proposed action is to decontaminate and decommission the Westinghouse Advanced Reactors Division fuel fabrication facilities (the Plutonium Laboratory - Building 7, and the Advanced Fuels Laboratory - Building 8). Decontamination and decommissioning of the facilities would require removal of all process equipment, the associated service lines, and decontamination of the interior surfaces of the buildings so that the empty buildings could be released for unrestricted use. Radioactive waste generated during these activities would be transported in licensed containers by truck for disposal at the Department's facility at Hanford, Washington. Useable non-radioactive materials would be sold as excess material, and non-radioactive waste would be disposed of by burial as sanitary landfill at an approved site.

  20. Ketone Production from the Thermal Decomposition of Carboxylate Salts 

    E-Print Network [OSTI]

    Landoll, Michael 1984-

    2012-08-15T23:59:59.000Z

    . Mixtures of calcium carboxylate salts were thermally decomposed at 450 degrees C. Low lime-to-salt ratios (g Ca(OH)2/g salt) of 0.00134 and less had a negligible effect on ketone yield. In contrast, salts with higher lime-to-salt ratios of 0.00461, 0.0190...

  1. Refrigerated Equipment Decontamination Checklist If this is not possible, or if the equipment is beyond its useful life, then it must be disposed via the University appointed supplier for the disposal of WEEE

    E-Print Network [OSTI]

    Guo, Zaoyang

    Refrigerated Equipment Decontamination Checklist If this is not possible, or if the equipment & decontaminated prior to transfer or disposal Upon decomissioning & decontamination a 'Safe for disposal' notice. Equipment has been completely decontaminated and presents no chemical/biological/radiological or other

  2. Investigation of gas-phase decontamination of internally radioactively contaminated gaseous diffusion process equipment and piping

    SciTech Connect (OSTI)

    Bundy, R.D.; Munday, E.B.

    1991-01-01T23:59:59.000Z

    Construction of the gaseous diffusion plants (GDPs) was begun during World War 2 to produce enriched uranium for defense purposes. These plants, which utilized UF{sub 6} gas, were used primarily for this purpose through 1964. From 1959 through 1968, production shifted primarily to uranium enrichment to supply the nuclear power industry. Additional UF{sub 6}-handling facilities were built in feed and fuel-processing plants associated with the uranium enrichment process. Two of the five process buildings at Oak ridge were shut down in 1964. Uranium enrichment activities at Oak Ridge were discontinued altogether in 1985. In 1987, the Department of Energy (DOE) decided to proceed with a permanent shutdown of the Oak Ridge Gaseous Diffusion Plant (ORGDP). DOE intends to begin decommissioning and decontamination (D D) of ORGDP early in the next century. The remaining two GDPs are expected to be shut down during the next 10 to 40 years and will also require D D, as will the other UF{sub 6}-handling facilities. This paper presents an investigation of gas- phase decontamination of internally radioactively contaminated gaseous diffusion process equipment and piping using powerful fluorinating reagents that convert nonvolatile uranium compounds to volatile UF{sub 6}. These reagents include ClF{sub 3}, F{sub 2}, and other compounds. The scope of D D at the GDPs, previous work of gas-phase decontamination, four concepts for using gas-phase decontamination, plans for further study of gas-phase decontamination, and the current status of this work are discussed. 13 refs., 15 figs.

  3. Decision Analysis Science Modeling for Application and Fielding Selection Applied to Concrete Decontamination Technologies

    SciTech Connect (OSTI)

    Ebadian, M.A. Ross, T.L.

    1998-01-01T23:59:59.000Z

    Concrete surfaces contaminated with radionuclides present a significant challenge during the decontamination and decommissioning (D and D) process. As structures undergo D and D, coating layers and/or surface layers of the concrete containing the contaminants must be removed for disposal in such a way as to present little to no risk to human health or the environment. The selection of a concrete decontamination technology that is safe, efficient, and cost-effective is critical to the successful D and D of contaminated sites. To support U.S. Department of Energy (DOE) Environmental Management objectives and to assist DOE site managers in the selection of the best-suited concrete floor decontamination technology(s) for a given site, two innovative and three baseline technologies have been assessed under standard, non-nuclear conditions at the Hemispheric Center for Environmental Technology (HCET) at Florida International University (FIU). The innovative technologies assessed include the Pegasus Coating Removal System and Textron's Electro-Hydraulic Scabbling System. The three baseline technologies assessed include: the Wheelabrator Blastrac model 1-15D, the NELCO Porta Shot Blast{trademark} model GPx-1O-18 HO Rider, and the NELCO Porta Shot Blast{trademark} model EC-7-2. These decontamination technology assessments provide directly comparable performance data that have previously been available for only a limited number of technologies under restrictive site-specific constraints. Some of the performance data collected during these technology assessments include: removal capability, production rate, removal gap, primary and secondary waste volumes, and operation and maintenance requirements. The performance data generated by this project is intended to assist DOE site managers in the selection of the safest, most efficient, and cost-effective decontamination technologies to accomplish their remediation objectives.

  4. Mining Induced Seismicity -Monitoring of a Large Scale Salt Cavern Collapse

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Mining Induced Seismicity - Monitoring of a Large Scale Salt Cavern Collapse E. Klein* (Ineris), I ground failure phenomenon induced by old underground mining works, a field experiment was undertaken in collaboration with the SOLVAY mining company: a solution mine was instrumented in 2004 previously to its

  5. Metal salt catalysts for enhancing hydrogen spillover

    DOE Patents [OSTI]

    Yang, Ralph T; Wang, Yuhe

    2013-04-23T23:59:59.000Z

    A composition for hydrogen storage includes a receptor, a hydrogen dissociating metal doped on the receptor, and a metal salt doped on the receptor. The hydrogen dissociating metal is configured to spill over hydrogen to the receptor, and the metal salt is configured to increase a rate of the spill over of the hydrogen to the receptor.

  6. Modeling of Porous Electrodes in Molten-Salt Systems

    E-Print Network [OSTI]

    Newman, John

    1986-01-01T23:59:59.000Z

    of Porous Electrodes in Molten-Salt Systems^ John Newmanon High-Temperature Molten Salt B a t - teries, Argonneby the modeling of molten-salt cells, including some

  7. THE MECHANISM OF INTRAGRANULAR MIGRATION OF BRINE INCLUSIONS IN SALT

    E-Print Network [OSTI]

    Machiels, A.J.

    2010-01-01T23:59:59.000Z

    of Brine Inclusions in a Salt Repository", ORM. -5526 (JulyOF BRINE INCLUSIONS IN SALT A.J. Machiels, S. Yagnik, D.R.OF BRINE INCLUSIONS IN SALT by A.J. Machiels S. Yagnik D.R.

  8. Neutrinoless Double Beta Decay in Light of SNO Salt Data

    E-Print Network [OSTI]

    Murayama, Hitoshi

    2009-01-01T23:59:59.000Z

    Beta Decay in Light of SNO Salt Data Hitoshi Murayama andBeta Decay in Light of SNO Salt Data Hitoshi Murayama ? andIn the SNO data from its salt run, probably the most signi?

  9. THERMAL GRADIENT MIGRATION OF BRINE INCLUSIONS IN SALT

    E-Print Network [OSTI]

    Yagnik, S.K.

    2010-01-01T23:59:59.000Z

    OF BRINE INCLUSIONS IN SALT Suresh K. Yagnik February 1982 TOF BRINE INCLUSIONS IN SALT by Suresh K. Yagnik Materialsb u i l t in future. The salt deposits, however, are known

  10. Advances in alleviating growth limitations of maize under salt stress

    E-Print Network [OSTI]

    Schubert, Sven

    2009-01-01T23:59:59.000Z

    during the first phase of salt stress. J. Appl. Bot. 2004;during the first phase of salt stress. J. Plant Nutr. SoilC, Hartung W, Schubert S. Salt resistance is determined by

  11. Salt glacier and composite sediment-salt glacier models for the emplacement and early burial of allochthonous salt sheets

    SciTech Connect (OSTI)

    Fletcher, R.C.; Hudec, M.R.; Watson, I.A. [Exxon Production Research Company, Houston, TX (United States)

    1996-12-31T23:59:59.000Z

    Allochthonous salt sheets in the northern Gulf of Mexico were emplaced as extrusive {open_quotes}salt glaciers{close_quotes} at the sediment-water interface. Massive dissolution was suppressed by a thin carapace of pelagic sediments. During emplacement, several hundred meters of bathymetric relief restricted rapid sedimentation to outside the glacial margins. The glaciers acted as sediment dams, influencing the transport and deposition of sediment from an upslope source. Because of contemporaneous sedimentation, the base of the glaciers climbed upward in all directions away from their feeder stocks, and successive sedimentary horizons were truncated against it. The local slope at the base of the sheets is equal to the local rate of sedimentation divided by the local rate of salt advance. Alternating episodes of slow and rapid sedimentation gave rise to a basal salt surface of alternating flats and ramps, which are preserved. Many salt sheets have nearly circular map patterns but are strongly asymmetric. Feeder stocks occur near upslope edges, and base-of-salt slopes are greater updip of the feeder. The asymmetry is due to more rapid sedimentation at the upslope edge and to slower advance induced by the smaller hydraulic head between the salt fountain and the upslope edge compared to the downslope edge. Rapid emplacement of the Mickey salt sheet (Mitchell dome) from a preexisting salt stock took {approximately}4 m.y, as {approximately}1 km of sediment was deposited. A three-dimensional geomechanical model for the rapid salt emplacement yields the following relationship for the diapir`s downdip radius versus time: R(t) {approx} Mt{sup q} {approx} B[({rho} - {rho}{sub w})gK{sup 3} / {eta}]{sup 1/8}t{sup q}, where M, q, b, and K are constants related to salt supply into the sheet, {rho} and {rho}{sub w} are the densities of salt water, g is the acceleration of gravity, {eta} is salt viscosity, and t is a model time extrapolated back to zero sheet volume at t = 0.

  12. Black liquor viscosity reduction through salt additives: A novel environmentally benign processing alternative

    SciTech Connect (OSTI)

    Roberts, J.E.; Khan, S.A.; Spontak, R.J. [North Carolina State Univ., Raleigh, NC (United States)

    1996-10-01T23:59:59.000Z

    Processing black liquor at high solids would reduce SO{sub x} emissions, facilitate the use of non-chlorine bleaching techniques and enhance the energy efficiency of the pulping process. However, black liquor exhibits and exponential increase in viscosity as its solids content rises, thus hindering its processability in the composition range of interest (>70% solids). In this study, we present a new approach for controlling viscosity at high solids content by {open_quotes}salting in{close_quotes} black liquor through addition of thiocyanate salts. These salts increases the solubility of the polymer constituents in black liquor leading to a decrease in its viscosity. Several salts capable of viscosity reduction by as much as two orders of magnitude have been identified. The effects of cation size, solution pH and temperature on viscosity reduction is presented and interpreted in terms of the underlying principles of {open_quotes}salting in{close_quotes} and how it affects aqueous solution structure.

  13. Pore-scale dynamics of salt transport and distribution in drying porous media

    SciTech Connect (OSTI)

    Shokri, Nima, E-mail: nima.shokri@manchester.ac.uk [School of Chemical Engineering and Analytical Science, University of Manchester, Manchester M13 9PL (United Kingdom)] [School of Chemical Engineering and Analytical Science, University of Manchester, Manchester M13 9PL (United Kingdom)

    2014-01-15T23:59:59.000Z

    Understanding the physics of water evaporation from saline porous media is important in many natural and engineering applications such as durability of building materials and preservation of monuments, water quality, and mineral-fluid interactions. We applied synchrotron x-ray micro-tomography to investigate the pore-scale dynamics of dissolved salt distribution in a three dimensional drying saline porous media using a cylindrical plastic column (15 mm in height and 8 mm in diameter) packed with sand particles saturated with CaI{sub 2} solution (5% concentration by mass) with a spatial and temporal resolution of 12 ?m and 30 min, respectively. Every time the drying sand column was set to be imaged, two different images were recorded using distinct synchrotron x-rays energies immediately above and below the K-edge value of Iodine. Taking the difference between pixel gray values enabled us to delineate the spatial and temporal distribution of CaI{sub 2} concentration at pore scale. Results indicate that during early stages of evaporation, air preferentially invades large pores at the surface while finer pores remain saturated and connected to the wet zone at bottom via capillary-induced liquid flow acting as evaporating spots. Consequently, the salt concentration increases preferentially in finer pores where evaporation occurs. Higher salt concentration was observed close to the evaporating surface indicating a convection-driven process. The obtained salt profiles were used to evaluate the numerical solution of the convection-diffusion equation (CDE). Results show that the macro-scale CDE could capture the overall trend of the measured salt profiles but fail to produce the exact slope of the profiles. Our results shed new insight on the physics of salt transport and its complex dynamics in drying porous media and establish synchrotron x-ray tomography as an effective tool to investigate the dynamics of salt transport in porous media at high spatial and temporal resolution.

  14. Solar Policy Environment: Salt Lake

    Broader source: Energy.gov [DOE]

    The overall objective of the “Solar Salt Lake” (SSL) team is to develop a fully-scoped city and county-level implementation plan that will facilitate at least an additional ten megawatts of solar photovoltaic (PV) installations in the government, commercial, industrial, and residential sectors by 2015. To achieve this aggressive goal, the program strategy includes a combination of barrier identification, research, and policy analysis that utilizes the input of various stakeholders. Coupled with these activities will be the development and implementation of pilot installations in the government and residential sectors, and broad outreach to builders and potential practitioners of solar energy products in the process. In this way, while creating mechanisms to enable a demand for solar, SSL will also facilitate capacity building for suppliers, thereby helping to ensure long-term sustainability for the regional market.

  15. EIA - Natural Gas Pipeline Network - Salt Cavern Storage Reservoir...

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

    Salt Cavern Underground Natural Gas Storage Reservoir Configuration Salt Cavern Underground Natural Gas Storage Reservoir Configuration Source: PB Energy Storage Services Inc....

  16. Sandia National Laboratories: molten salt energy storage demonstration

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

    molten salt energy storage demonstration Sandia-AREVA Commission Solar ThermalMolten Salt Energy-Storage Demonstration On May 21, 2014, in Capabilities, Concentrating Solar Power,...

  17. Enterprise Assessments Review of the Savannah River Site Salt...

    Energy Savers [EERE]

    the Savannah River Site Salt Waste Processing Facility Construction Quality and Startup Test Plans - June 2015 Enterprise Assessments Review of the Savannah River Site Salt Waste...

  18. Development of Molten-Salt Heat Trasfer Fluid Technology for...

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

    of Molten-Salt Heat Transfer Fluid Technology for Parabolic Trough Solar Power Plants, seeks to determine whether the inorganic fluids (molten salts) offer a sufficient...

  19. Development Wells At Salt Wells Area (Nevada Bureau of Mines...

    Open Energy Info (EERE)

    Salt Wells Area (Nevada Bureau of Mines and Geology, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Development Wells At Salt Wells Area...

  20. Inexpensive, Nonfluorinated Anions for Lithium Salts and Ionic...

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

    Anions for Lithium Salts and Ionic Liquids for Lithium Battery Electrolytes Inexpensive, Nonfluorinated Anions for Lithium Salts and Ionic Liquids for Lithium Battery Electrolytes...

  1. New lithium-based ionic liquid electrolytes that resist salt...

    Energy Savers [EERE]

    lithium-based ionic liquid electrolytes that resist salt concentration polarization New lithium-based ionic liquid electrolytes that resist salt concentration polarization...

  2. Effects of Carbonate Solvents and Lithium Salts on Morphology...

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

    Carbonate Solvents and Lithium Salts on Morphology and Coulombic Efficiency of Lithium Electrode. Effects of Carbonate Solvents and Lithium Salts on Morphology and Coulombic...

  3. Compound and Elemental Analysis At Salt Wells Area (Shevenell...

    Open Energy Info (EERE)

    ENERGYGeothermal Home Exploration Activity: Compound and Elemental Analysis At Salt Wells Area (Shevenell & Garside, 2003) Exploration Activity Details Location Salt Wells...

  4. Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance...

    Open Energy Info (EERE)

    Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance To The Hydrocarbon Exploration In The Tuz Golu (Salt Lake) Basin, Central Anatolia, Turkey Jump to: navigation,...

  5. DOE - Office of Legacy Management -- Penn Salt Manufacturing...

    Office of Legacy Management (LM)

    Salt Manufacturing Co Whitemarsh Research Laboratories - PA 20 FUSRAP Considered Sites Site: PENN SALT MANUFACTURING CO., WHITEMARSH RESEARCH LABORATORIES (PA.20) Eliminated from...

  6. Characterization of Organic Coatings on Hygroscopic Salt Particles...

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

    Organic Coatings on Hygroscopic Salt Particles and their Atmospheric Impacts. Characterization of Organic Coatings on Hygroscopic Salt Particles and their Atmospheric Impacts....

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

    Office of Environmental Management (EM)

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

  8. asse ii salt: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  9. arutlus salt lake: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  10. avery island salt: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  11. awra salt lake: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  12. alkyl ammonium salts: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  13. alkali salt deposition: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  14. aluminium salt cakes: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  15. aminodifluorosulfinium tetrafluoroborate salts: Topics by E-print...

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  16. aqueous salt systems: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  17. aromatic diazonium salts: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  18. alkyl ester salts: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  19. allylic silanolate salts: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  20. alternative salt processing: Topics by E-print Network

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

    of nutrients and heavy metals in experimental salt marsh ecosystems. Environmental Pollution,effects of nutrients and heavy metals in experimental salt marsh ecosystems....

  1. Energy Department Completes Salt Coolant Material Transfer to...

    Office of Environmental Management (EM)

    Completes Salt Coolant Material Transfer to Czech Republic for Advanced Reactor Research Energy Department Completes Salt Coolant Material Transfer to Czech Republic for Advanced...

  2. Voluntary Protection Program Onsite Review, Salt Waste Processing...

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

    Salt Waste Processing Facility Construction Project - February 2013 Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project - February 2013...

  3. Voluntary Protection Program Onsite Review, Parsons Corp., Salt...

    Office of Environmental Management (EM)

    Parsons Corp., Salt Waste Processing Facility Construction Project - May 2014 Voluntary Protection Program Onsite Review, Parsons Corp., Salt Waste Processing Facility Construction...

  4. Correlation of Creep Behavior of Domal Salts

    SciTech Connect (OSTI)

    Munson, D.E.

    1999-02-16T23:59:59.000Z

    The experimentally determined creep responses of a number of domal salts have been reported in, the literature. Some of these creep results were obtained using standard (conventional) creep tests. However, more typically, the creep data have come from multistage creep tests, where the number of specimens available for testing was small. An incremental test uses abrupt changes in stress and temperature to produce several time increments (stages) of different creep conditions. Clearly, the ability to analyze these limited data and to correlate them with each other could be of considerable potential value in establishing the mechanical characteristics of salt domes, both generally and specifically. In any analysis, it is necessary to have a framework of rules to provide consistency. The basis for the framework is the Multimechanism-Deformation (M-D) constitutive model. This model utilizes considerable general knowledge of material creep deformation to supplement specific knowledge of the material response of salt. Because the creep of salt is controlled by just a few micromechanical mechanisms, regardless of the origin of the salt, certain of the material parameters are values that can be considered universal to salt. Actual data analysis utilizes the methodology developed for the Waste Isolation Pilot Plant (WIPP) program, and the response of a bedded pure WIPP salt as the baseline for comparison of the domal salts. Creep data from Weeks Island, Bryan Mound, West Hackberry, Bayou Choctaw, and Big Hill salt domes, which are all sites of Strategic Petroleum Reserve (SPR) storage caverns, were analyzed, as were data from the Avery Island, Moss Bluff, and Jennings salt domes. The analysis permits the parameter value sets for the domal salts to be determined in terms of the M-D model with various degrees of completeness. In turn this permits detailed numerical calculations simulating cavern response. Where the set is incomplete because of the sparse database, reasonable assumptions permit the set to be completed. From the analysis, two distinct response groups were evident, with the salts of one group measurably more creep resistant than the other group. Interestingly, these groups correspond well with the indirectly determined creep closure of the SPR storage caverns, a correlation that probably should be expected. Certainly, the results suggest a simple laboratory determination of the creep characteristics of a salt material from a dome site can indicate the relative behavior of any potential cavern placed within that dome.

  5. Ecological superiority and inhibition of growth of pathogens in ground beef chubs produced from decontaminated beef carcasses

    E-Print Network [OSTI]

    Shellenberger, Amy King

    2000-01-01T23:59:59.000Z

    growth. In order to detect potential differences in spoilage patterns due to carcass decontamination treatments, bacteria were isolated and identified from packages of ground beef that were obtained from the treated carcasses. Additional studies were...

  6. Closure Report for Corrective Action Unit 254: Area 25, R-MAD Decontamination Facility, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    G. N. Doyle

    2002-02-01T23:59:59.000Z

    Corrective Action Unit (CAU) 254 is located in Area 25 of the Nevada Test Site (NTS), approximately 100 kilometers (km) (62 miles) northwest of Las Vegas, Nevada. The site is located within the Reactor Maintenance, Assembly and Disassembly (R-MAD) compound and consists of Building 3126, two outdoor decontamination pads, and surrounding areas within an existing fenced area measuring approximately 50 x 37 meters (160 x 120 feet). The site was used from the early 1960s to the early 1970s as part of the Nuclear Rocket Development Station program to decontaminate test-car hardware and tooling. The site was reactivated in the early 1980s to decontaminate a radiologically contaminated military tank. This Closure Report (CR) describes the closure activities performed to allow un-restricted release of the R-MAD Decontamination Facility.

  7. Corrective Action Plan for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    C. M. Obi

    2000-12-01T23:59:59.000Z

    The Area 25 Reactor Maintenance, Assembly, and Disassembly Decontamination Facility is identified in the Federal Facility Agreement and Consent Order (FFACO) as Corrective Action Unit (CAU) 254. CAU 254 is located in Area 25 of the Nevada Test Site and consists of a single Corrective Action Site CAS 25-23-06. CAU 254 will be closed, in accordance with the FFACO of 1996. CAU 254 was used primarily to perform radiological decontamination and consists of Building 3126, two outdoor decontamination pads, and surrounding soil within an existing perimeter fence. The site was used to decontaminate nuclear rocket test-car hardware and tooling from the early 1960s through the early 1970s, and to decontaminate a military tank in the early 1980s. The site characterization results indicate that, in places, the surficial soil and building materials exceed clean-up criteria for organic compounds, metals, and radionuclides. Closure activities are expected to generate waste streams consisting of nonhazardous construction waste. petroleum hydrocarbon waste, hazardous waste, low-level radioactive waste, and mixed waste. Some of the wastes exceed land disposal restriction limits and will require off-site treatment before disposal. The recommended corrective action was revised to Alternative 3- ''Unrestricted Release Decontamination, Verification Survey, and Dismantle Building 3126,'' in an addendum to the Correction Action Decision Document.

  8. Examination of Liquid Fluoride Salt Heat Transfer

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L [ORNL] [ORNL

    2014-01-01T23:59:59.000Z

    The need for high efficiency power conversion and energy transport systems is increasing as world energy use continues to increase, petroleum supplies decrease, and global warming concerns become more prevalent. There are few heat transport fluids capable of operating above about 600oC that do not require operation at extremely high pressures. Liquid fluoride salts are an exception to that limitation. Fluoride salts have very high boiling points, can operate at high temperatures and low pressures and have very good heat transfer properties. They have been proposed as coolants for next generation fission reactor systems, as coolants for fusion reactor blankets, and as thermal storage media for solar power systems. In each case, these salts are used to either extract or deliver heat through heat exchange equipment, and in order to design this equipment, liquid salt heat transfer must be predicted. This paper discusses the heat transfer characteristics of liquid fluoride salts. Historically, heat transfer in fluoride salts has been assumed to be consistent with that of conventional fluids (air, water, etc.), and correlations used for predicting heat transfer performance of all fluoride salts have been the same or similar to those used for water conventional fluids an, water, etc). A review of existing liquid salt heat transfer data is presented, summarized, and evaluated on a consistent basis. Less than 10 experimental data sets have been found in the literature, with varying degrees of experimental detail and measured parameters provided. The data has been digitized and a limited database has been assembled and compared to existing heat transfer correlations. Results vary as well, with some data sets following traditional correlations; in others the comparisons are less conclusive. This is especially the case for less common salt/materials combinations, and suggests that additional heat transfer data may be needed when using specific salt eutectics in heat transfer equipment designs. All of the data discussed above were taken under forced convective conditions (both laminar and turbulent). Some recent data taken at ORNL under free convection conditions are also presented and results discussed. This data was taken using a simple crucible experiment with an instrumented nickel heater inserted in the salt to induce natural circulation within the crucible. The data was taken over a temperature range of 550oC to 650oC in FLiNaK salt. This data covers both laminar and turbulent natural convection conditions, and is compared to existing forms of natural circulation correlations.

  9. Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project

    SciTech Connect (OSTI)

    A. M Smith; G. E. Matthern; R. H. Meservey

    1998-11-01T23:59:59.000Z

    The Idaho National Engineering and Environmental Laboratory (INEEL), Fernald Environmental Management Project (FEMP), and Argonne National Laboratory - East (ANL-E) teamed to establish the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project to increase the use of improved technologies in D&D operations. The project is making the technologies more readily available, providing training, putting the technologies to use, and spreading information about improved performance. The improved technologies are expected to reduce cost, schedule, radiation exposure, or waste volume over currently used baseline methods. They include some of the most successful technologies proven in the large-scale demonstrations and in private industry. The selected technologies are the Pipe Explorer, the GammaCam, the Decontamination Decommissioning and Remediation Optimal Planning System (DDROPS), the BROKK Demolition Robot, the Personal Ice Cooling System (PICS), the Oxy-Gasoline Torch, the Track-Mounted Shear, and the Hand-Held Shear.

  10. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect (OSTI)

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19T23:59:59.000Z

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D D. Additional details on specific technologies and applications to D D will be made available on request.

  11. Available decontamination and decommissioning capabilities at the Savannah River Technology Center

    SciTech Connect (OSTI)

    Polizzi, L.M.; Norkus, J.K.; Paik, I.K.; Wooten, L.A.

    1992-08-19T23:59:59.000Z

    The Safety Analysis and Engineering Services Group has performed a survey of the Savannah River Technology Center (SRTC) technical capabilities, skills, and experience in Decontamination and Decommissioning (D&D) activities. The goal of this survey is to enhance the integration of the SRTC capabilities with the technical needs of the Environmental Restoration Department D&D program and the DOE Office of Technology Development through the Integrated Demonstration Program. This survey has identified technical capabilities, skills, and experience in the following D&D areas: Characterization, Decontamination, Dismantlement, Material Disposal, Remote Systems, and support on Safety Technology for D&D. This review demonstrates the depth and wealth of technical capability resident in the SRTC in relation to these activities, and the unique qualifications of the SRTC to supply technical support in the area of DOE facility D&D. Additional details on specific technologies and applications to D&D will be made available on request.

  12. An overview of plutonium-238 decontamination and decommissioning (D and D) projects at Mound

    SciTech Connect (OSTI)

    Bond, W.H.; Davis, W.P.; Draper, D.G.; Geichman, J.R.; Harris, J.C.; Jaeger, R.R.; Sohn, R.L.

    1987-01-01T23:59:59.000Z

    Mound is currently decontaminating for restricted reuse and/or decommissioning for conditional release four major plutonium-238 contaminated facilities that contained 1700 linear feet of gloveboxes and associated equipment and services. Several thousand linear feet of external underground piping, associated tanks, and contaminated soil are being removed. Two of the facilities contain ongoing operations and will be reused for both radioactive and nonradioactive programs. Two others will be completely demolished and the land area will become available for future DOE building sites. An overview of the successful techniques and equipment used in the decontamination and decommissioning of individual pieces of equipment, gloveboxes, services, laboratories, sections of buildings, entire buildings, and external underground piping, tanks, and soil in a highly populated residential area is described and pictorially presented.

  13. DECISION ANALYSIS AND TECHNOLOGY ASSESSMENTS FOR METAL AND MASONRY DECONTAMINATION TECHNOLOGIES

    SciTech Connect (OSTI)

    M.A. Ebadian, Ph.D.

    1999-01-01T23:59:59.000Z

    The purpose of this investigation was to conduct a comparative analysis of innovative technologies for the non-aggressive removal of coatings from metal and masonry surfaces and the aggressive removal of one-quarter to one-inch thickness of surface from structural masonry. The technologies tested should be capable of being used in nuclear facilities. Innovative decontamination technologies are being evaluated under standard, non-nuclear conditions at the FIU-HCET technology assessment site in Miami, Florida. This study is being performed to support the OST, the Deactivation and Decommissioning (D&D) Focus Area, and the environmental restoration of DOE facilities throughout the DOE complex by providing objective evaluations of currently available decontamination technologies.

  14. Decontamination systems information and research program. Quarterly report, January 1996--March 1996

    SciTech Connect (OSTI)

    NONE

    1996-04-01T23:59:59.000Z

    West Virginia University (WVU) and the US Department of Energy, Morgantown Energy Technology Center (DOE/METC) entered into a Cooperative Agreement in August 1992 titled {open_quotes}Decontamination Systems Information and Research Programs{close_quotes} (DOE Instrument No.: DE-FC21-92MC29467). Requirements stipulated by the Agreement require WVU to submit quarterly Technical Progress reports. This report contains the efforts of the research projects comprising the Agreement for the 1st calendar quarter of 1996. For the period January 1 through December 31, 1996 twelve projects have been selected for funding, and the Kanawha Valley will continue under a no-cost extension. Three new projects have also been added to the program. This document describes these projects involving decontamination, decommissioning and remedial action issues and technologies.

  15. Nevada Test Site Decontamination and Decommissioning Program History, Regulatory Framework, and Lessons Learned

    SciTech Connect (OSTI)

    Michael R. Kruzic, Bechtel Nevada; Patrick S. Morris, Bechtel Nevada; Jerel G. Nelson, Polestar Applied Technology, Inc.

    2005-08-07T23:59:59.000Z

    Decontamination and Decommissioning (D&D) of radiologically and/or chemically contaminated facilities at the Nevada Test Site (NTS) are the responsibility of the Environmental Restoration (ER) Project. Facilities identified for D&D are listed in the Federal Facilities Agreement and Consent Order (FFACO) and closed under the Resource Conservation and Recovery Act process. This paper discusses the NTS D&D program, including facilities history, D&D regulatory framework, and valuable lessons learned.

  16. A Planning Tool for Estimating Waste Generated by a Radiological Incident and Subsequent Decontamination Efforts - 13569

    SciTech Connect (OSTI)

    Boe, Timothy [Oak Ridge Institute for Science and Education, Research Triangle Park, NC 27711 (United States)] [Oak Ridge Institute for Science and Education, Research Triangle Park, NC 27711 (United States); Lemieux, Paul [U.S. Environmental Protection Agency, Research Triangle Park, NC 27711 (United States)] [U.S. Environmental Protection Agency, Research Triangle Park, NC 27711 (United States); Schultheisz, Daniel; Peake, Tom [U.S. Environmental Protection Agency, Washington, DC 20460 (United States)] [U.S. Environmental Protection Agency, Washington, DC 20460 (United States); Hayes, Colin [Eastern Research Group, Inc, Morrisville, NC 26560 (United States)] [Eastern Research Group, Inc, Morrisville, NC 26560 (United States)

    2013-07-01T23:59:59.000Z

    Management of debris and waste from a wide-area radiological incident would probably constitute a significant percentage of the total remediation cost and effort. The U.S. Environmental Protection Agency's (EPA's) Waste Estimation Support Tool (WEST) is a unique planning tool for estimating the potential volume and radioactivity levels of waste generated by a radiological incident and subsequent decontamination efforts. The WEST was developed to support planners and decision makers by generating a first-order estimate of the quantity and characteristics of waste resulting from a radiological incident. The tool then allows the user to evaluate the impact of various decontamination/demolition strategies on the waste types and volumes generated. WEST consists of a suite of standalone applications and Esri{sup R} ArcGIS{sup R} scripts for rapidly estimating waste inventories and levels of radioactivity generated from a radiological contamination incident as a function of user-defined decontamination and demolition approaches. WEST accepts Geographic Information System (GIS) shape-files defining contaminated areas and extent of contamination. Building stock information, including square footage, building counts, and building composition estimates are then generated using the Federal Emergency Management Agency's (FEMA's) Hazus{sup R}-MH software. WEST then identifies outdoor surfaces based on the application of pattern recognition to overhead aerial imagery. The results from the GIS calculations are then fed into a Microsoft Excel{sup R} 2007 spreadsheet with a custom graphical user interface where the user can examine the impact of various decontamination/demolition scenarios on the quantity, characteristics, and residual radioactivity of the resulting waste streams. (authors)

  17. Conversion of transuranic waste to low level waste by decontamination: a site specific update

    SciTech Connect (OSTI)

    Allen, R.P.; Hazelton, R.F.

    1985-09-01T23:59:59.000Z

    As a followup to an FY-1984 cost/benefit study, a program was conducted in FY-1985 to transfer to the relevant DOE sites the information and technology for the direct conversion of transuranic (TRU) waste to low-level waste (LLW) by decontamination. As part of this work, the economic evaluation of the various TRUW volume reduction and conversion options was updated and expanded to include site-specific factors. The results show, for the assumptions used, that size reduction, size reduction followed by decontamination, or in situ decontamination are cost effective compared with the no-processing option. The technology transfer activities included site presentations and discussions with operations and waste management personnel to identify application opportunities and site-specific considerations and constraints that could affect the implementation of TRU waste conversion principles. These discussions disclosed definite potential for the beneficial application of these principles at most of the sites, but also confirmed the existence of site-specific factors ranging from space limitations to LLW disposal restrictions that could preclude particular applications or diminish expected benefits. 8 refs., 2 figs., 4 tabs.

  18. Decontamination and decarburization of stainless and carbon steel by melt refining

    SciTech Connect (OSTI)

    Mizia, R.E.; Worcester, S.A.; Twidwell, L.G.; Webber, D.; Paolini, D.J.; Weldon, T.A.

    1996-09-05T23:59:59.000Z

    With many nuclear reactors and facilities being decommissioned in the next ten to twenty years the concern for handling and storing Radioactive Scrap Metal (RSM) is growing. Upon direction of the DOE Office of Environmental Restoration and Waste Management, Lockheed Idaho Technology Company (LITCO) is developing technologies for the conditioning of spent fuels and high-level wastes for interim storage and repository acceptance, including the recycling of Radioactive Scrap Metals (RSM) for beneficial reuse with the DOE complex. In February 1993, Montana Tech of the University of Montana was contracted to develop and demonstrate technologies for the decontamination of stainless steel RSM. The general objectives of the Montana Tech research program included conducting a literature survey, performing laboratory scale melt refining experiments to optimize decontaminating slag compositions, performing an analysis of preferred melting techniques, coordinating pilot scale and commercial scale demonstrations, and producing sufficient quantities of surrogate-containing material for all of the laboratory, pilot and commercial scale test programs. Later on, the program was expanded to include decontamination of carbon steel RSM. Each research program has been completed, and results are presented in this report.

  19. SEDIMENT DECONTAMINATION WITH BENEFICIAL USE FOR THE PORT OF NEW YORK AND NEW JERSEY.

    SciTech Connect (OSTI)

    STERN,E.A.; JONES,K.W.; DOUGLAS,W.S.; FENG,H.; CLESCERI,N.L.; LODGE,J.L.

    2002-05-01T23:59:59.000Z

    Effective operation of the multi-state Port ofNew York/New Jersey (Port), which contributes $20 billion to the regional economy and generates nearly 250,000 jobs, is dependent on yearly navigational dredging of several million m{sup 3} of sediment for channel maintenance and deepening. Further dredging is required for remediation of environmentally sensitive areas. However, more stringent ocean placement testing regulations in the Port region have necessitated a search for other means of handling the most contaminated dredged materials. Here, we describe a dredged material decontamination program for the Port aimed at the creation of sediment decontamination facilities that produce a beneficial use product to obviate the need for ocean placement. These facilities, to be a viable component of an overall dredged material management plan, must be environmentally balanced and economically feasible with the predictable ability to process large volumes of dredged materials with rapid turn-around. Our program recognizes that the responsible management of contaminated dredged materials is a complex problem that requires the effective application and coordination of a variety of cross-cutting skills to make decontamination facilities a reality. Participants do not come from a single agency, but are ad hoc teams of scientists, engineers, regulators, port authorities and operators, technology development firms, federal/state/local governments, business interests and community groups, among others, who are brought together by the need to solve the complex problem of managing dredged material in the Port region.

  20. Integrated sediment decontamination for the New York/New Jersey Harbor

    SciTech Connect (OSTI)

    Stern, W.A. [Environmental Protection Agency, New York, NY (United States); Donato, K.R. [Army Corps of Engineers, New York, NY (United States); Clesceri, N.L. [Rensselaer Polytechnic Inst., Troy, NY (United States); Jones, K.W. [Brookhaven National Lab., Upton, NY (United States)

    1998-02-01T23:59:59.000Z

    Disposal of dredged material taken from the New York/New Jersey (NY/NJ) Harbor is problematic because of the presence of inorganic and organic contaminants that under revised testing criteria render it unsuitable for return to the ocean or for beneficial reuse. Decontamination of the dredged material followed by beneficial reuse is one attractive component of the overall comprehensive dredged material management plan being developed by the US Army Corps of Engineers New York District. A demonstration program to validate decontamination processes and to bring them into full-scale use in the NY/NJ Harbor is now in progress. Tests of selected technologies have been completed at the bench scale and pilot-scale (2--15 m{sup 3}) levels. Procedures for demonstration testing on scales from 750 m{sup 3} to 75,000 m{sup 3} are being developed with the goal of producing a useable decontamination system by the end of 1999. The overall project goals and present status of the project are reviewed here.

  1. Decontamination of metals by melt refinings/slagging: An annotated bibliography

    SciTech Connect (OSTI)

    Mizia, R.E. [ed.; Worcester, S.A.; Twidwell, L.G.; Paolini, D.J.; Weldon, T.A.

    1993-07-01T23:59:59.000Z

    As the number of nuclear installations undergoing decontamination and decommissioning (D&D) increases, current radioactive waste storage space is consumed and establishment of new waste storage areas becomes increasingly difficult, the problem of handling and storing radioactive scrap metal (RSM) gains increasing importance in the DOE Environmental Restoration and Waste Management Program. To alleviate present and future waste storage problems, Westinghouse Idaho Nuclear Company (WINCO) is managing a program for the recycling of RSM for beneficial use within the DOE complex. As part of that effort, Montana Tech has been awarded a contract to help optimize melting and refining technology for the recycling of stainless steel RSM. The scope of the Montana Tech program includes a literature survey, a decontaminating slag design study, small scale melting studies to determine optimum slag compositions for removal of radioactive contaminant surrogates, analysis of preferred melting techniques, and coordination of large scale melting demonstrations (100--500 lbs) to be conducted at selected facilities. The program will support recycling and decontaminating stainless steel RSM for use in waste canisters for Idaho Waste Immobilization Facility densified high level waste. This report is the result of the literature search conducted to establish a basis for experimental melt/slag program development.

  2. Decision Analysis Science Modeling for Application and Fielding Selection Applied to Metal Decontamination Technologies

    SciTech Connect (OSTI)

    Lagos, L.E.; Ebadian, M.A.

    1998-01-01T23:59:59.000Z

    During the decontamination and decommissioning (D and D) activities being conducted by the U.S. Department of Energy (DOE), approximately 550,000 metric tons of contaminated metal will be generated by the disposition of contaminated buildings. The majority of the structural steel is considered to be radiologically contaminated. The D and D activities require the treatment of the structural steel to reduce occupational and environmental radiological exposures during dismantlement. Treatment technologies may also be required for possible recycling. Many proven commercial treatment technologies are available. These treatment processes vary in aggressiveness, safety requirements, secondary waste generation, necessary capital, and operation and maintenance costs. Choosing the appropriate technology to meet the decontamination objectives for structural steel is a difficult process. A single information source comparing innovative and nuclear and non-nuclear technologies in the areas of safety, cost and effectiveness is not currently commercially available to perform a detailed analysis. This study presents comparable data related to operation and maintenance, cost, and health and safely aspects of three readily available technologies and one innovative technology for nuclear decontamination. The technologies include Advance Recyclable Media System (ARMS{trademark}), NELCO Porta Shot Blast{trademark} (JHJ-2000), Pegasus Coating Removal System 7 (PCRS-7) and the innovative laser ablation technology called the Yag Eraser{trademark}.

  3. Industrial Technology of Decontamination of Liquid Radioactive Waste in SUE MosSIA 'Radon' - 12371

    SciTech Connect (OSTI)

    Adamovich, Dmitry V.; Neveykin, Petr P.; Karlin, Yuri V.; Savkin, Alexander E. [SUE MosSIA 'Radon', 7th Rostovsky lane 2/14, Moscow 119121 (Russian Federation)

    2012-07-01T23:59:59.000Z

    SUE MosSIA 'RADON' - this enterprise was created more than 50 years ago, which deals with the recycling of radioactive waste and conditioning of spent sources of radiation in stationary and mobile systems in the own factory and operating organizations. Here is represented the experience SUE MosSIA 'Radon' in the field of the management with liquid radioactive waste. It's shown, that the activity of SUE MosSIA 'RADON' is developing in three directions - improvement of technical facilities for treatment of radioactive waters into SUE MosSIA 'RADON' development of mobile equipment for the decontamination of radioactive waters in other organizations, development of new technologies for decontamination of liquid radioactive wastes as part of various domestic Russian and international projects including those related to the operation of nuclear power and nuclear submarines. SUE MosSIA 'RADON' has processed more than 270 thousand m{sup 3} of radioactive water, at that more than 7000 m{sup 3} in other organizations for more than 50 years. It is shown that a number of directions, particularly, the development of mobile modular units for decontamination of liquid radioactive waste, SUE MosSIA 'RADON' is a leader in the world. (authors)

  4. Advanced heat exchanger development for molten salts

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Sabharwall, Piyush; Clark, Denis; Glazoff, Michael; Zheng, Guiqiu; Sridharan, Kumar; Anderson, Mark

    2014-12-01T23:59:59.000Z

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet materialmore »in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically « less

  5. Salt Lake City- High Performance Buildings Requirement

    Broader source: Energy.gov [DOE]

    Salt Lake City's mayor issued an executive order in July 2005 requiring that all public buildings owned and controlled by the city be built or renovated to meet the requirements of LEED "silver"...

  6. Novel coordination geometries in fluoroaluminate salts

    SciTech Connect (OSTI)

    Herron, N.; Harlow, R.L.; Thorn, D.L. (E.I. du Pont de Nemours and Comp., Wilmington, DE (United States))

    1993-07-07T23:59:59.000Z

    Two tetramethylammonium salts of new fluoroaluminate species have been crystallographically characterized and reveal structural motifs previously unknown for such species. The elusive tetrahedral [AlF[sub 4][sup [minus

  7. Molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, William A. (Livermore, CA); Upadhye, Ravindra S. (Pleasanton, CA); Pruneda, Cesar O. (Livermore, CA)

    1995-01-01T23:59:59.000Z

    A molten salt destruction process is used to treat and destroy energetic waste materials such as high explosives, propellants, and rocket fuels. The energetic material is pre-blended with a solid or fluid diluent in safe proportions to form a fluid fuel mixture. The fuel mixture is rapidly introduced into a high temperature molten salt bath. A stream of molten salt is removed from the vessel and may be recycled as diluent. Additionally, the molten salt stream may be pumped from the reactor, circulated outside the reactor for further processing, and delivered back into the reactor or cooled and circulated to the feed delivery system to further dilute the fuel mixture entering the reactor.

  8. Molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, W.A.; Upadhye, R.S.; Pruneda, C.O.

    1995-07-18T23:59:59.000Z

    A molten salt destruction process is used to treat and destroy energetic waste materials such as high explosives, propellants, and rocket fuels. The energetic material is pre-blended with a solid or fluid diluent in safe proportions to form a fluid fuel mixture. The fuel mixture is rapidly introduced into a high temperature molten salt bath. A stream of molten salt is removed from the vessel and may be recycled as diluent. Additionally, the molten salt stream may be pumped from the reactor, circulated outside the reactor for further processing, and delivered back into the reactor or cooled and circulated to the feed delivery system to further dilute the fuel mixture entering the reactor. 4 figs.

  9. Reversible electro-optic device employing aprotic molten salts and method

    DOE Patents [OSTI]

    Warner, Benjamin P. (Los Alamos, NM); McCleskey, T. Mark (Los Alamos, NM); Burrell, Anthony K. (Los Alamos, NM); Hall, Simon B. (Palmerston North, NZ)

    2008-01-08T23:59:59.000Z

    A single-compartment reversible mirror device having a solution of aprotic molten salt, at least one soluble metal-containing species comprising metal capable of being electrodeposited, and at least one anodic compound capable of being oxidized was prepared. The aprotic molten salt is liquid at room temperature and includes lithium and/or quaternary ammonium cations, and anions selected from trifluoromethylsulfonate (CF.sub.3SO.sub.3.sup.-), bis(trifluoromethylsulfonyl)imide ((CF.sub.3SO.sub.2).sub.2N.sup.-), bis(perfluoroethylsulfonyl)imide ((CF.sub.3CF.sub.2SO.sub.2).sub.2N.sup.-) and tris(trifluoromethylsulfonyl)methide ((CF.sub.3SO.sub.2).sub.3C.sup.-). A method for preparing substantially pure molten salts is also described.

  10. Reversible Electro-Optic Device Employing Aprotic Molten Salts And Method

    DOE Patents [OSTI]

    Warner, Benjamin P. (Los Alamos, NM); McCleskey, T. Mark (Los Alamos, NM); Burrell, Anthony K. (Los Alamos, NM); Hall, Simon B. (Palmerston North, NZ)

    2005-03-01T23:59:59.000Z

    A single-compartment reversible mirror device having a solution of aprotic molten salt, at least one soluble metal-containing species comprising metal capable of being electrodeposited, and at least one anodic compound capable of being oxidized was prepared. The aprotic molten salt is liquid at room temperature and includes lithium and/or quaternary ammonium cations, and anions selected from trifluoromethylsulfonate (CF.sub.3 SO.sub.3.sup.-), bis(trifluoromethylsulfonyl)imide ((CF.sub.3 SO.sub.2).sub.2 N.sup.-), bis(perfluoroethylsulfonyl)imide ((CF.sub.3 CF.sub.2 SO.sub.2).sub.2 N.sup.-) and tris(trifluoromethylsulfonyl)methide ((CF.sub.3 SO.sub.2).sub.3 C.sup.-). A method for preparing substantially pure molten salts is also described.

  11. Impact of the organic halide salt on final perovskite composition for photovoltaic applications

    SciTech Connect (OSTI)

    Moore, David T.; Sai, Hiroaki; Wee Tan, Kwan; Estroff, Lara A.; Wiesner, Ulrich, E-mail: ubw1@cornell.edu [Department of Materials Science and Engineering, Cornell University, Ithaca, New York 14853 (United States)

    2014-08-01T23:59:59.000Z

    The methylammonium lead halide perovskites have shown significant promise as a low-cost, second generation, photovoltaic material. Despite recent advances, however, there are still a number of fundamental aspects of their formation as well as their physical and electronic behavior that are not well understood. In this letter we explore the mechanism by which these materials crystallize by testing the outcome of each of the reagent halide salts. We find that components of both salts, lead halide and methylammonium halide, are relatively mobile and can be readily exchanged during the crystallization process when the reaction is carried out in solution or in the solid state. We exploit this fact by showing that the perovskite structure is formed even when the lead salt's anion is a non-halide, leading to lower annealing temperature and time requirements for film formation. Studies into these behaviors may ultimately lead to improved processing conditions for photovoltaic films.

  12. SALT---Structured Assertion Language for Temporal Logic

    E-Print Network [OSTI]

    Leucker, Martin

    SALT---Structured Assertion Language for Temporal Logic Andreas Bauer, Martin Leucker,leucker,streit}@informatik.tu­muenchen.de Abstract. This paper presents Salt. Salt is a general purpose speci­ fication and assertion language other formalisms used for temporal specification of properties, Salt does not target a specific domain

  13. SALT--Structured Assertion Language for Temporal Logic

    E-Print Network [OSTI]

    SALT--Structured Assertion Language for Temporal Logic Andreas Bauer, Martin Leucker , and Jonathan,leucker,streit}@informatik.tu-muenchen.de Abstract. This paper presents Salt. Salt is a general purpose speci- fication and assertion language other formalisms used for temporal specification of properties, Salt does not target a specific domain

  14. SALT CREEK ROADWI-80North STADIUMDRIVE

    E-Print Network [OSTI]

    Powers, Robert

    thSt. 0thSt. 1thSt. 2thSt. 3thSt. 4thSt. . t. 10 SALT CREEK ROADWI-80North 10THSTREET 14THSTREET W STADIUM DRIVE PARKING GARAGE 9thSt. 10thSt. 11thSt. 12thSt. 13thSt. 14thSt. 16thSt. 10thSt. SALT CREEK

  15. Salt tolerance of grasses for range seeding

    E-Print Network [OSTI]

    Hartmann, Francis Stephen

    1973-01-01T23:59:59.000Z

    . 0 bars with polyethylene glycol. Emergence and rate of growth were measured for caryopses planted in an artificially salinized soil where the osmotic tensions of the saturated extract were the same as those of the salt solu- tions during..., chloride, and sulfate i n the saturated extract were measured by ti tration (Richards et al. , 1954). The mechanical analyses were taken from unpublished data of the Fanning et al. , 1965. Movement of salts was studied in Catarina, Montell...

  16. Salt Tolerance of Guayule (Parthenium argentatum).

    E-Print Network [OSTI]

    Miyamoto, S.; Davis, J.; Madrid, L.

    1990-01-01T23:59:59.000Z

    TDOC Z TA245 .7 8873 NO.1651 ---- Salt Tolerance of yUayu{e ~" y r , B -1651 The Texas Agricultural Experiment Station? Charles J. Arntzen, Director? The Texas A&M University System? College Station, Texas (Blank Pille In Origblll...BUUetlal? . "! . . . " k ? ..... . . - ... Salt Tolerance of Guayule (Parthenium argentatum) by s. Miyamoto J. Davis L. Madrid 1 1 Professor, former research technician, and graduate assistant, respectively, Texas A&M University Agricultural Research Center at EI...

  17. The Effect of Salt Water on Rice.

    E-Print Network [OSTI]

    Fraps, G. S. (George Stronach)

    1909-01-01T23:59:59.000Z

    ERIME .-- - --- - -- BULLETIN NO. izz. June, 1909. THE EFFECT OF SALT WATE ON RICE, LAPS, Che Postoffice College Station, 1 --- Texas. TEXAS AGRICULTURAL EXPERIMENT S I'ATIONS. OFFICERS. GOVERNING BOARD. (Board of Directors A. and M... is Col- lege Station, Texas. Reports and bulletins are sent upon application to the Director. The Effect of Salt Water on Rice. . ...... By G. S. FRAPS. At some of the rice farms located near the coast, the amount of water lxml~etl is sometimes...

  18. Manning free counterions fraction for a rod-like polyion - short DNA fragments in very low salt

    E-Print Network [OSTI]

    Tomislav Vuletic; Sanja Dolanski Babic; Danijel Grgicin; Damir Aumiler; Joachim Raedler; Francoise Livolant; Silvia Tomic

    2011-01-05T23:59:59.000Z

    We quantified the Manning free (uncondensed) counterions fraction $\\theta$ for dilute solutions of rod-like polyions - 150bp DNA fragments, in very low salt $salt environment, with the decrease in DNA concentration itself. The extremes of the experimental $\\theta(c)$ range occur towards the highest, above 1 mM and the lowest, below 0.05 mM, DNA concentrations, and correspond to the theoretical $\\theta$ values for dsDNA and ssDNA, respectively. Therefore, we confirmed Manning condensation and conductivity models to be valuable in description of dilute solutions of rod-like polyions.

  19. Thermal Characterization of Molten Salt Systems

    SciTech Connect (OSTI)

    Toni Y. Gutknecht; Guy L. Fredrickson

    2011-09-01T23:59:59.000Z

    The phase stability of molten salts in an electrorefiner (ER) may be adversely affected by the buildup of sodium, fission products, and transuranics in the electrolyte. Potential situations that need to be avoided are the following: (1) salt freezing due to an unexpected change in the liquidus temperature, (2) phase separation or non-homogeneity of the molten salt due to the precipitation of solids or formation of immiscible liquids, and (3) any mechanism that can result in the separation and concentration of fissile elements from the molten salt. Any of these situations would result in an off-normal condition outside the established safety basis for electrorefiner (ER) operations. The stability (and homogeneity) of the phases can potentially be monitored through the thermal characterization of the salts, which can be a function of impurity concentration. This report describes the experimental results of typical salts compositions, which consist of chlorides of potassium, lithium, strontium, samarium, praseodymium, lanthanum, barium, cerium, cesium, neodymium, sodium and gadolinium chlorides as a surrogate for both uranium and plutonium, used for the processing of used nuclear fuels.

  20. Thermal Analysis of Surrogate Simulated Molten Salts with Metal Chloride Impurities for Electrorefining Used Nuclear Fuel

    SciTech Connect (OSTI)

    Toni Y. Gutknecht; Guy L. Fredrickson; Vivek Utgikar

    2012-04-01T23:59:59.000Z

    This project is a fundamental study to measure thermal properties (liquidus, solidus, phase transformation, and enthalpy) of molten salt systems of interest to electrorefining operations, which are used in both the fuel cycle research & development mission and the spent fuel treatment mission of the Department of Energy. During electrorefining operations the electrolyte accumulates elements more active than uranium (transuranics, fission products and bond sodium). The accumulation needs to be closely monitored because the thermal properties of the electrolyte will change as the concentration of the impurities increases. During electrorefining (processing techniques used at the Idaho National Laboratory to separate uranium from spent nuclear fuel) it is important for the electrolyte to remain in a homogeneous liquid phase for operational safeguard and criticality reasons. The phase stability of molten salts in an electrorefiner may be adversely affected by the buildup of fission products in the electrolyte. Potential situations that need to be avoided are: (i) build up of fissile elements in the salt approaching the criticality limits specified for the vessel (ii) freezing of the salts due to change in the liquidus temperature and (iii) phase separation (non-homogenous solution) of elements. The stability (and homogeneity) of the phases can potentially be monitored through the thermal characterization of the salts, which can be a function of impurity concentration. This work describes the experimental results of typical salts compositions, consisting of chlorides of strontium, samarium, praseodymium, lanthanum, barium, cerium, cesium, neodymium, sodium and gadolinium (as a surrogate for both uranium and plutonium), used in the processing of used nuclear fuels. Differential scanning calorimetry was used to analyze numerous salt samples providing results on the thermal properties. The property of most interest to pyroprocessing is the liquidus temperature. It was previously known the liquidus temperature of the molten salt would change as spent fuel is processed through the Mk-IV electrorefiner. However, the extent of the increase in liquidus temperature was not known. This work is first of its kind in determining thermodynamic properties of a molten salt electrolyte containing transuranics, fission products and bond sodium. Experimental data concluded that the melting temperature of the electrolyte will become greater than the operating temperature of the Mk-IV ER during current fuel processing campaigns. Collected data also helps predict when the molten salt electrolyte will no longer be able to support electrorefining operations.

  1. Area 6 Decontamination Pond Corrective Action Unit 92 Post-Closure Inspection Annual Report for the Period January 2000-December 2000

    SciTech Connect (OSTI)

    J. L. Traynor

    2001-03-01T23:59:59.000Z

    The Area 6 Decontamination Pond, Corrective Action Unit 92, was closed in accordance with the Resource Conservation and Recovery Act (RCRA) Part B Operational Permit (Nevada Division of Environmental Protection [NDEP, 1995]) and the Federal Facility Agreement and Consent Order (NDEP, 1996) on May 11, 1999. Historically the Decontamination Pond was used for the disposal of partially treated liquid effluent discharged from the Decontamination Facility (Building 6-05) and the Industrial Laundry (Building 6-07) (U.S. Department of Energy, Nevada Operations Office [DOE/NV], 1996). The Decontamination Pond was constructed and became operational in 1979. Releases of RCRA-regulated hazardous waste or hazardous waste constituents have not been discharged to the Decontamination Pond since 1988 (DOE/NV, 1996). The pipe connecting the Decontamination Pond and Decontamination Facility and Industrial Laundry were cut and sealed at the Decontamination Pad Oil/Water Separator in 1992. The Decontamination Pond was closed in place by installing a RCRA cover. Fencing was installed around the periphery to prevent accidental damage to the cover. Post-closure monitoring at the site consists of quarterly inspections of the RCRA cover and fencing, and a subsidence survey. Additional inspections are conducted if: Precipitation occurs in excess of 1.28 centimeters (cm) (0.50 inches [in]) in a 24-hour period, or An earthquake occurs with a magnitude exceeding 4.5 on the Richter scale within 100 kilometers (km) (62 miles [mi]) of the closure.

  2. Salt as non-food 1 Salt as a `non-food': to what extent do gustatory perceptions

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Salt as non-food 1 Salt as a `non-food': to what extent do gustatory perceptions determine non chloride. In the same vein, the present utilisation of salt in cooked foods throughout the world led several scientists to consider that salt is a basic and compulsory part of the human diet and that our

  3. Low temperature oxidation using support molten salt catalysts

    DOE Patents [OSTI]

    Weimer, Alan W.; Czerpak, Peter J.; Hilbert, Patrick M.

    2003-05-20T23:59:59.000Z

    Molten salt reactions are performed by supporting the molten salt on a particulate support and forming a fluidized bed of the supported salt particles. The method is particularly suitable for combusting hydrocarbon fuels at reduced temperatures, so that the formation NO.sub.x species is reduced. When certain preferred salts are used, such as alkali metal carbonates, sulfur and halide species can be captured by the molten salt, thereby reducing SO.sub.x and HCl emissions.

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

    SciTech Connect (OSTI)

    Veil, J. A.

    1999-01-27T23:59:59.000Z

    Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of nonhazardous oil field wastes (NOW) and naturally occurring radioactive materials (NORM), the risk to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne's research indicates that disposal of NOW into salt caverns is feasible and, in most cases, would not be prohibited by state agencies (although those agencies may need to revise their wastes management regulations). A risk analysis of several cavern leakage scenarios suggests that the risk from cavern disposal of NOW and NORM wastes is below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

  5. Electromagnetic mixed-waste processing system for asbestos decontamination

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    The first phase of a program to develop and demonstrate a cost-effective, integrated process for remediation of asbestos-containing material that is contaminated with organics, heavy metals, and radioactive compounds was successfully completed. Laboratory scale tests were performed to demonstrate initial process viability for asbestos conversion, organics removal, and radionuclide and heavy metal removal. All success criteria for the laboratory tests were met. (1) Ohio DSI demonstrated greater than 99% asbestos conversion to amorphous solids using their commercial process. (2) KAI demonstrated 90% removal of organics from the asbestos suspension. (3) Westinghouse STC achieved the required metals removal criteria on a laboratory scale (e.g., 92% removal of uranium from solution, resin loadings of 0.6 equivalents per liter, and greater than 50% regeneration of resin in a batch test.) Using the information gained in the laboratory tests, the process was reconfigured to provide the basis for the mixed waste remediation system. An integrated process is conceptually developed, and a Phase 2 program plan is proposed to provide the bench-scale development needed in order to refine the design basis for a pilot processing system.

  6. Electromagnetic mixed waste processing system for asbestos decontamination

    SciTech Connect (OSTI)

    Kasevich, R.S.; Vaux, W. [KAI Technologies, Inc., Portsmouth, NH (United States); Ulerich, N. [Westinghouse Electric Corp., Pittsburgh, PA (United States). Science and Technology Center; Nocito, T. [Ohio DSI Corporation, New York (New York)

    1996-12-31T23:59:59.000Z

    The overall objective of this three-phase program is to develop an integrated process for treating asbestos-containing material that is contaminated with radioactive and hazardous constituents. The integrated process will attempt to minimize processing and disposal costs. The objectives of Phase 1 were to establish the technical feasibility of asbestos decomposition, inorganic radionuclide nd heavy metal removal, and organic volatilization. Phase 1 resulted in the successful bench-scale demonstration of the elements required to develop a mixed waste treatment process for asbestos-containing material (ACM) contaminated with radioactive metals, heavy metals, and organics. Using the Phase 1 data, a conceptual process was developed. The Phase 2 program, currently in progress, is developing an integrated system design for ACM waste processing. The Phase 3 program will target demonstration of the mixed waste processing system at a DOE facility. The electromagnetic mixed waste processing system employs patented technologies to convert DOE asbestos to a non-hazardous, radionuclide-free, stable waste. The dry, contaminated asbestos is initially heated with radiofrequency energy to remove organic volatiles. Second,the radionuclides are removed by solvent extraction coupled with ion exchange solution treatment. Third, the ABCOV method converts the asbestos to an amorphous silica suspension at low temperature (100{degrees}C). Finally the amorphous silica is solidified for disposal.

  7. THE IMPACT OF DISSOLVED SALTS ON PASTES CONTAINING FLY ASH, CEMENT AND SLAG

    SciTech Connect (OSTI)

    Harbour, J.; Edwards, T.; Williams, V.

    2009-09-21T23:59:59.000Z

    The degree of hydration of a mixture of cementitious materials (Class F fly ash, blast furnace slag and portland cement) in highly concentrated alkaline salt solutions is enhanced by the addition of aluminate to the salt solution. This increase in the degree of hydration, as monitored with isothermal calorimetry, leads to higher values of dynamic Young's modulus and compressive strength and lower values of total porosity. This enhancement in performance properties of these cementitious waste forms by increased hydration is beneficial to the retention of the radionuclides that are also present in the salt solution. The aluminate ions in the solution act first to retard the set time of the mix but then enhance the hydration reactions following the induction period. In fact, the aluminate ions increase the degree of hydration by {approx}35% over the degree of hydration for the same mix with a lower aluminate concentration. An increase in the blast furnace slag concentration and a decrease in the water to cementitious materials ratio produced mixes with higher values of Young's modulus and lower values of total porosity. Therefore, these operational factors can be fine tuned to enhance performance properties of cementitious waste form. Empirical models for Young modulus, heat of hydration and total porosity were developed to predict the values of these properties. These linear models used only statistically significant compositional and operational factors and provided insight into those factors that control these properties.

  8. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    SciTech Connect (OSTI)

    Washington, A. L. II; Peters, T. B.; Fink, S. D.

    2013-02-25T23:59:59.000Z

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

  9. Chemistry control and corrosion mitigation of heat transfer salts for the fluoride salt reactor (FHR)

    SciTech Connect (OSTI)

    Kelleher, B. C.; Sellers, S. R.; Anderson, M. H.; Sridharan, K.; Scheele, R. D. [Dept. of Engineering Physics, Univ.of Wisconsin - Madison, 1500 Engineering Drive, Madison, WI 53706 (United States)

    2012-07-01T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) was a prototype nuclear reactor which operated from 1965 to 1969 at Oak Ridge National Laboratory. The MSRE used liquid fluoride salts as a heat transfer fluid and solvent for fluoride based {sup 235}U and {sup 233}U fuel. Extensive research was performed in order to optimize the removal of oxide and metal impurities from the reactor's heat transfer salt, 2LiF-BeF{sub 2} (FLiBe). This was done by sparging a mixture of anhydrous hydrofluoric acid and hydrogen gas through the FLiBe at elevated temperatures. The hydrofluoric acid reacted with oxides and hydroxides, fluorinating them while simultaneously releasing water vapor. Metal impurities such as iron and chromium were reduced by hydrogen gas and filtered out of the salt. By removing these impurities, the corrosion of reactor components was minimized. The Univ. of Wisconsin - Madison is currently researching a new chemical purification process for fluoride salts that make use of a less dangerous cleaning gas, nitrogen trifluoride. Nitrogen trifluoride has been predicted as a superior fluorinating agent for fluoride salts. These purified salts will subsequently be used for static and loop corrosion tests on a variety of reactor materials to ensure materials compatibility for the new FHR designs. Demonstration of chemistry control methodologies along with potential reduction in corrosion is essential for the use of a fluoride salts in a next generator nuclear reactor system. (authors)

  10. Anomalous zones in Gulf Coast Salt domes with special reference to Big Hill, TX, and Weeks Island, LA

    SciTech Connect (OSTI)

    Neal, J.T. [Sandia National Labs., Albuquerque, NM (United States); Magorian, T.R. [Magorian (Thomas R.), Amherst, NY (United States); Thoms, R.L. [AGM, Inc., College Station, TX (United States); Autin, W.J.; McCulloh, R.P. [Louisiana Geological Survey, Baton Rouge, LA (United States); Denzler, S.; Byrne, K.O. [Acres International Corp., Amherst, NY (United States)

    1993-07-01T23:59:59.000Z

    Anomalous features in Gulf Coast Salt domes exhibit deviations from normally pure salt and vary widely in form from one dome to the next, ranging considerably in length and width. They have affected both conventional and solution mining in several ways. Gas outbursts, insolubles, and potash (especially carnallite) have led to the breakage of tubing in a number of caverns, and caused irregular shapes of many caverns through preferential leaching. Such anomalous features essentially have limited the lateral extent of conventional mining at several salt mines, and led to accidents and even the closing of several other mines. Such anomalous features, are often aligned in anomalous zones, and appear to be related to diapiric processes of salt dome development. Evidence indicates that anomalous zones are found between salt spines, where the differential salt intrusion accumulates other materials: Anhydrite bands which are relatively strong, and other, weaker impurities. Shear zones and fault displacement detected at Big Hill and Weeks Island domes have not yet had any known adverse impacts on SPR oil storage, but new caverns at these sites conceivably may encounter some potentially adverse conditions. Seismic reflection profiles at Big Hill dome have shown numerous fractures and faults in the caprock, and verified the earlier recognition of a major shear zone transecting the entire salt stock and forming a graben in the overlying caprock. Casing that is placed in such zones can be at risk. Knowledge of these zones should create awareness of possible effects rather than preclude the future emplacement of caverns. To the extent possible, major anomalous zones and salt stock boundaries should be avoided. Shear zones along overhangs may be particularly hazardous, and otherwise unknown valleys in the top of salt may occur along shear zones. These zones often can be mapped geophysically, especially with high-resolution seismic techniques.

  11. The solubilities of significant organic compounds in HLW tank supernate solutions -- FY 1995 progress report

    SciTech Connect (OSTI)

    Barney, G.S.

    1996-04-26T23:59:59.000Z

    At the Hanford Site organic compounds were measured in tank supernate simulant solutions during FY 1995. This solubility information will be used to determine if these organic salts could exist in solid phases (saltcake or sludges) in the waste where they might react violently with the nitrate or nitrite salts present in the tanks. Solubilities of sodium glycolate, succinate, and caproate salts; iron and aluminum and butylphosphate salts; and aluminum oxalate were measured in simulated waste supernate solutions at 25 {degree}C, 30 {degree}C, 40 {degree}C, and 50 {degree}C. The organic compounds were selected because they are expected to exist in relatively high concentrations in the tanks. The solubilities of sodium glycolate, succinate, caproate, and butylphosphate in HLW tank supernate solutions were high over the temperature and sodium hydroxide concentration ranges expected in the tanks. High solubilities will prevent solid sodium salts of these organic acids from precipitating from tank supernate solutions. The total organic carbon concentrations (YOC) of actual tank supernates are generally much lower than the TOC ranges for simulated supernate solutions saturated (at the solubility limit) with the organic salts. This is so even if all the dissolved carbon in a given tank and supernate is due to only one of these eight soluble compounds (an unlikely situation). Metal ion complexes of and butylphosphate and oxalate in supernate solutions were not stable in the presence of the hydroxide concentrations expected in most tanks. Iron and aluminum dibutylphosphate compounds reacted with hydroxide to form soluble sodium dibutylphosphate and precipitated iron and aluminum hydroxides. Aluminum oxalate complexes were also not stable in the basic simulated supernate solutions. Solubilities of all the organic salts decrease with increasing sodium hydroxide concentration because of the common ion effect of Na+. Increasing temperatures raised the solubilities of the organic salts, especially the succinate and caproate salts.

  12. Borehole locations on seven interior salt domes

    SciTech Connect (OSTI)

    Simcox, A.C.; Wampler, S.L.

    1982-08-01T23:59:59.000Z

    This report is designed as an inventory of all wells known to have been drilled within a five-mile radius of each of seven salt domes within the Interior Salt Basin in east Texas, northern Louisiana and Mississippi. There are 72 boreholes that entered salt above an elevation of -3000 feet mean sea level. For these, details of location, drilling dates, depth of casing and cement, elevation of top of caprock and salt, etc., are given on tables in the appendix. Of the seven domes, Oakwood has the largest number of boreholes, thirty-eight (including two sidetracked wells) that enter the salt stock above -3000 feet mean sea level; another dome in northeast Texas, Keechi, has eight; in northern Louisiana, Rayburn's has four and Vacherie has five; in southern Mississippi, Cypress Creek has seven, Lampton has one, and Richton has nine. In addition, all wells known outside the supra-domal area, but within a five-mile radius of the center of the 7 domes are separately catalogued.

  13. Disposition of the fluoride fuel and flush salts from the Molten Salt Reactor experiment at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Peretz, F.J.

    1996-03-01T23:59:59.000Z

    The Molten Salt Reactor Experiment (MSRE) is an 8 MW reactor that was operated at Oak Ridge National Laboratory (ORNL) from 1965 through 1969. The reactor used a unique liquid salt fuel, composed of a mixture of LIF, BeF{sub 2}, ZrF{sub 4}, and UF{sub 4}, and operated at temperatures above 600{degrees}C. The primary fuel salt circulation system consisted of the reactor vessel, a single fuel salt pump, and a single primary heat exchanger. Heat was transferred from the fuel salt to a coolant salt circuit in the primary heat exchanger. The coolant salt was similar to the fuel salt, except that it contains only LiF (66%) and BeF, (34%). The coolant salt passed from the primary heat exchanger to an air-cooled radiator and a coolant salt pump, and then returned to the primary heat exchanger. Each of the salt loops was provided with drain tanks, located such that the salt could be drained out of either circuit by gravity. A single drain tank was provided for the non-radioactive coolant salt. Two drain tanks were provided for the fuel salt. Since the fuel salt contained radioactive fuel, fission products, and activation products, and since the reactor was designed such that the fuel salt could be drained immediately into the drain tanks in the event of a problem in the fuel salt loop, the fuel salt drain tanks were provided with a system to remove the heat generated by radioactive decay. A third drain tank connected to the fuel salt loop was provided for a batch of flush salt. This batch of salt, similar in composition to the coolant salt, was used to condition the fuel salt loop after it had been exposed to air and to flush the fuel salt loop of residual fuel salt prior to accessing the reactor circuit for maintenance or experimental activities. This report discusses the disposition of the fluoride fuel and flush salt.

  14. Agricultural pathogen decontamination technology-reducing the threat of infectious agent spread.

    SciTech Connect (OSTI)

    Betty, Rita G.; Bieker, Jill Marie; Tucker, Mark David

    2005-10-01T23:59:59.000Z

    Outbreaks of infectious agricultural diseases, whether natural occurring or introduced intentionally, could have catastrophic impacts on the U.S. economy. Examples of such agricultural pathogens include foot and mouth disease (FMD), avian influenza (AI), citrus canker, wheat and soy rust, etc. Current approaches to mitigate the spread of agricultural pathogens include quarantine, development of vaccines for animal diseases, and development of pathogen resistant crop strains in the case of plant diseases. None of these approaches is rapid, and none address the potential persistence of the pathogen in the environment, which could lead to further spread of the agent and damage after quarantine is lifted. Pathogen spread in agricultural environments commonly occurs via transfer on agricultural equipment (transportation trailers, tractors, trucks, combines, etc.), having components made from a broad range of materials (galvanized and painted steel, rubber tires, glass and Plexiglas shields, etc), and under conditions of heavy organic load (mud, soil, feces, litter, etc). A key element of stemming the spread of an outbreak is to ensure complete inactivation of the pathogens in the agricultural environment and on the equipment used in those environments. Through the combination of enhanced agricultural pathogen decontamination chemistry and a validated inactivation verification methodology, important technologies for incorporation as components of a robust response capability will be enabled. Because of the potentially devastating economic impact that could result from the spread of infectious agricultural diseases, the proposed capability components will promote critical infrastructure protection and greater border and food supply security. We investigated and developed agricultural pathogen decontamination technologies to reduce the threat of infectious-agent spread, and thus enhance agricultural biosecurity. Specifically, enhanced detergency versions of the patented Sandia decontamination chemistry were developed and tested against a few surrogate pathogens under conditions of relatively heavy organic load. Tests were conducted on surfaces commonly found in agricultural environments. Wide spectrum decontamination efficacy, low corrosivity, and biodegradability issues were addressed in developing an enhanced detergency formulation. A method for rapid assessment of loss of pathogenic activity (inactivation) was also assessed. This enhanced technology will enable rapid assessment of contamination following an intentional event, and will also be extremely useful in routine assessment of agricultural environments. The primary effort during the second year was progress towards a demonstration of both decontamination and viral inactivation technologies of Foot and Mouth virus (FMDv) using the modified SNL chemistry developed through this project. Lab studies using a surrogate virus (bovine enterovirus) were conducted using DF200, modified DF200 chemistry, and decontaminants currently recommended for use in heavily loaded organic, agricultural environments (VirkonS, 10% bleach, sodium hydroxide and citric acid). Tests using actual FMD virus will be performed at the Department of Homeland Security's Plum Island facilities in the fall of 2005. Success and the insight gained from this project will lead to enhanced response capability, which will benefit agencies such as USDA, DHS, DOD, and the agricultural industry.

  15. Application of Robotics in Decommissioning and Decontamination - 12536

    SciTech Connect (OSTI)

    Banford, Anthony; Kuo, Jeffrey A. [National Nuclear Laboratory, Risley, Warrington (United Kingdom); Bowen, R.A. [National Nuclear Laboratory, Sellafield, Cumbria (United Kingdom); Szilagyi, Andrew; Kirk, Paula [U.S. Department of Energy, Washington, D.C. (United States)

    2012-07-01T23:59:59.000Z

    Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better environmental information identifies hazards, which can be assessed, managed and mitigated. - Tele-autonomous control in a congested unstructured environment is more reliable compared to a human operator. Advances in Human Machine Interfaces contribute to reliability and task optimization. Use of standardized dexterous manipulators and COTS, including standardized communication protocols reduces project time scales. - The technologies identified, if developed to a sufficient TRL would all contribute to cost reductions. Additionally, optimizing a project's position on a Remote Intervention Scale, a Bespoke Equipment Scale and a Tele-autonomy Scale would provide cost reductions from the start of a project. Of the technologies identified, tele-autonomy is arguably the most significant, because this would provide a fundamental positive change for robotic control in the nuclear industry. The challenge for technology developers is to develop versatile robotic technology that can be economically deployed to a wide range of future D and D projects and industrial sectors. The challenge for facility owners and project managers is to partner with the developers to provide accurate systems requirements and an open and receptive environment for testing and deployment. To facilitate this development and deployment effort, the NNL and DOE have initiated discussions to explore a collaborative R and D program that would accelerate development and support the optimum utilization of resources. (authors)

  16. Osmotic Pressure of Aqueous Chondroitin Sulfate Solution: A Molecular Modeling Investigation

    E-Print Network [OSTI]

    Bathe, Mark

    The osmotic pressure of chondroitin sulfate (CS) solution in contact with an aqueous 1:1 salt reservoir of fixed ionic strength is studied using a recently developed coarse-grained molecular model. The effects of sulfation ...

  17. Transient Analysis for the Multimechanism-Deformation Parameters of Several Domal Salts

    SciTech Connect (OSTI)

    Munson, Darrell E.

    1999-08-16T23:59:59.000Z

    Use of Gulf Coast salt domes for construction of very large storage caverns by solution mining has grown significantly in the last several decades. In fact, a nationally important Strategic Petroleum Reserve (SPR) storage occurs in large cavern arrays in some of these domes. Although caverns have been operated economically for these many years, these caverns have a range of relatively poorly understood behaviors, involving creep closure fluid loss and damage from salt falls. It is certainly possible to postulate that many of these behaviors stem from geomechanical or deformational aspects of the salt response. As a result, a method of correlating the cavern response to mechanical creep behavior as determined in the laboratory could be of considerable importance. Recently, detailed study of the creep response of domal salts has cast some insight into the influence of different salt origins on cavern behavior. The study used a simple graphical analysis of the limited non-steady state data to give a bound, or an approach to steady state, as an estimate of the steady state behavior of a given domal salt. This permitted the analysis of sparse creep databases for domal salts. It appears that a shortcoming of the steady state analysis was in masking some of the salt material differences. In an attempt to overcome the steady state analysis shortcomings, a method was developed based on the integration of the Multimechanism-Deformation (M-D) creep constitutive model to fit the transient response. This integration process essentially permits definition of the material sensitive parameters of the model, while those parameters that are either constants or material insensitive parameters are fixed independently. The transient analysis method has proven more sensitive to differences in the creep characteristics and has provided a way of defining different behaviors within a given dome. Creep characteristics, as defined by the transient analysis of the creep rate, are related quantitatively to the volume loss creep rate of the caverns. This type of understanding of the domal material creep response already has pointed to the possibility of establishing various distinct material spines within a given dome. Furthermore, if the creep databases for domal salts can be expanded, one could expect additional definition of domal geology and structure.

  18. Multimechanism-Deformation Parameters of Domal Salts Using Transient Creep Analysis

    SciTech Connect (OSTI)

    MUNSON, DARRELL E

    1999-09-01T23:59:59.000Z

    Use of Gulf Coast salt domes for construction of very large storage caverns by solution mining has grown significantly in the last several decades. In fact, among the largest developers of storage caverns along the Gulf Coast is the Strategic Petroleum Reserve (SPR) which has purchased or constructed 62 crude oil storage caverns in four storage sites (domes). Although SPR and commercial caverns have been operated economically for many years, the caverns still exhibit some relatively poorly understood behaviors, especially involving creep closure volume loss and hanging string damage from salt falls. Since it is possible to postulate that some of these behaviors stem from geomechanical or reformational aspects of the salt, a method of correlating the cavern response to mechanical creep behavior as determined in the laboratory could be of considerable value. Recently, detailed study of the creep response of domal salts has cast some insight into the influence of different salt origins on cavern behavior. The study used a simple graphical analysis of limited non-steady state data to establish an approach or bound to steady state, as an estimate of the steady state behavior of a given salt. This permitted analysis of sparse creep databases for domal salts. It appears that a shortcoming of this steady state analysis method is that it obscures some critical differences of the salt material behavior. In an attempt to overcome the steady state analysis shortcomings, a method was developed based on integration of the Multimechanism-Deformation (M-D) creep constitutive model to obtain fits to the transient response. This integration process permits definition of all the material sensitive parameters of the model, while those parameters that are constants or material insensitive parameters are fixed independently. The transient analysis method has proven more sensitive to differences in the creep characteristics and has provided a way of defining different behaviors within a given dome. Characteristics defined by the transient analysis are related quantitatively to the volume loss creep rate of the SPR caverns. This increase in understanding of the domal material creep response already has pointed to the possibility y of delineating the existence of material spines within a specific dome. Further definition of the domal geology and structure seems possible only through expansion of the creep databases for domal salts.

  19. Method for cleaning solution used in nuclear fuel reprocessing

    DOE Patents [OSTI]

    Tallent, O.K.; Crouse, D.J.; Mailen, J.C.

    1980-12-17T23:59:59.000Z

    Nuclear fuel processing solution consisting of tri-n-butyl phosphate and dodecane, with a complex of uranium, plutonium, or zirconium and with a solvent degradation product such as di-n-butyl phosphate therein, is contacted with an aqueous solution of a salt formed from hydrazine and either a dicarboxylic acid or a hydroxycarboxylic acid, thereby removing the aforesaid complex from the processing solution.

  20. Molecular-Based Mechanisms of Mendelian Forms of Salt-Dependent Hypertension: Questioning the Prevailing Theory.

    E-Print Network [OSTI]

    Kurtz, TW; Dominiczak, AF; DiCarlo, SE; Pravenec, M; Morris, RC

    2015-01-01T23:59:59.000Z

    Inherited disorders of renal salt homeostasis: Insights fromof Mendelian Forms of Salt-Dependent Hypertension:AC. Hypertension caused by salt loading in the dog. 3. Onset

  1. Effect of Salt Stress on Purslane and Potential Health Benefits: Oxalic Acid and Fatty Acids Profile

    E-Print Network [OSTI]

    Carvalho, Isabel S.; Teixeira, Mónica; Brodelius, Maria

    2009-01-01T23:59:59.000Z

    IS. 2009. Effects of salt stress on purslane (Portulacaacid concentration occurs when the salt stress concentrationfor higher concentration of salt in both purslanes. In GL

  2. Control of Soluble Salts in Farming and Gardening.

    E-Print Network [OSTI]

    Longenecker, D. E.; Lyerly, P. J.

    1974-01-01T23:59:59.000Z

    waters pass through beds of salt, dissolving appreciable quantities before they emerge and enter the rivers. Ocean waters, much too salty for irrigation, contain about 3 percent salt, or about 40 tons of salt per acre-foot of water... ater are applied each year are shown in Table 2. Salts I (.in ilrcnmulate very rapidly. The water containing 1 ton of jdt per acre-foot is generally considered to be good ,I~,~lit\\* water, yet in 2 years enough salt could accumu- I,ltr to harm salt...

  3. Exploratory Use of Microaerosol Decontamination Technology (PAEROSOL) in Enclosed, Unoccupied Hospital Setting

    SciTech Connect (OSTI)

    Rainina, Evguenia I.; McCune, D. E.; Luna, Maria L.; Cook, J. E.; Soltis, Michele A.; Demons, Samandra T.; Godoy-Kain, Patricia; Weston, J. H.

    2012-05-31T23:59:59.000Z

    The goal of this study was to validate the previously observed high biological kill performance of PAEROSOL, a semi-dry, micro-aerosol decontamination technology, against common HAI in a non-human subject trial within a hospital setting of Madigan Army Medical Center (MAMC) on Joint Base Lewis-McChord in Tacoma, Washington. In addition to validating the disinfecting efficacy of PAEROSOL, the objectives of the trial included a demonstration of PAEROSOL environmental safety, (i.e., impact to hospital interior materials and electronic equipment exposed during testing) and PAEROSOL parameters optimization for future deployment.

  4. Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities

    SciTech Connect (OSTI)

    Erickson, T.A.

    1998-11-01T23:59:59.000Z

    The objectives of this task are to: Develop a model (paper) to estimate the cost and waste generation of cleanup within the Environmental Management (EM) complex; Identify technologies applicable to decontamination and decommissioning (D and D) operations within the EM complex; Develop a database of facility information as linked to project baseline summaries (PBSs). The above objectives are carried out through the following four subtasks: Subtask 1--D and D Model Development, Subtask 2--Technology List; Subtask 3--Facility Database, and Subtask 4--Incorporation into a User Model.

  5. Mechanisms of Radionuclide-Hyroxycarboxylic Acid Interactions for Decontamination of Metallic Surfaces

    SciTech Connect (OSTI)

    A.J. Francis; C.J. Dodge; J.B. Gillow; G.P. Halada; C.R. Clayton

    2002-04-24T23:59:59.000Z

    Is this EMSP program we investigated the key fundamental issues involved in the use of simple and safe methods for the removal of radioactive contamination from equipment and facilities using hydroxycarboxylic acids. Specifically, we investigate (i) the association of uranium with various iron oxides commonly formed on corroding plain carbon steel surfaces, (ii) the association of uranium with corroding metal coupons under a variety of conditions, and (iii) the decontamination of the uranium contaminated metal coupons by citric acid or citric acid formulations containing oxalic acid and hydrogen peroxide.

  6. Surveillance and Maintenance Plan for the ORNL Decontamination and Decommissioning Program FY 1993--2002

    SciTech Connect (OSTI)

    Ford, M.K.; Holder, L. Jr.

    1992-07-01T23:59:59.000Z

    The Decontamination and Decommissioning (D D) Program at the Oak Ridge National Laboratory (ORNL) is part of the Department of Energy (DOE) Environmental Restoration D D program. The purpose and objectivesof this program include: (1) surveillance and maintenance (S M) of facilities awaiting decommissioning; (2) planning for the orderly decommissioning of these facilities; and (3) implementation of a program to accomplish facility disposition in a safe, cost-effective, and timely manner. Participating D D contractors are required to prepare formal plans that document the S M programs established for each site. This report has been prepared to provide this documentation for those facilities included in the ORNL D D Program.

  7. Decontamination systems information and research program. Quarterly report, April--June 1995

    SciTech Connect (OSTI)

    NONE

    1995-07-01T23:59:59.000Z

    West Virginia University (WVU) and the US Department of Energy Morgantown Energy Technology Center (DOE/METC) entered into a Cooperative Agreement on August 29, 1992 titled `Decontamination Systems Information and Research Programs`. Requirements stipulated by the Agreement require WVU to submit Technical Progress reports on a quarterly basis. This report contains the efforts of the fourteen research projects comprising the Agreement for the period April 1 to June 30, 1995. During this period three new projects have been funded by the Agreement. These projects are: (1) WERC National Design Contest, (2) Graduate Interns to the Interagency Environmental Technology Office under the National Science and Technology Council, and (3) WV High Tech Consortium.

  8. Office of Environmental Management Uranium Enrichment Decontamination and Decommissioning Fund financial statements, September 30, 1995 and 1994

    SciTech Connect (OSTI)

    NONE

    1996-02-21T23:59:59.000Z

    The Energy Policy Act of 1992 (Act) requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located at the K-25 site in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. The Act transferred the uranium enrichment enterprise to the United States Enrichment Corporation (USEC) as of July 1, 1993, and established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

  9. Office of Environmental Management uranium enrichment decontamination and decommissioning fund financial statements. September 30, 1994 and 1993

    SciTech Connect (OSTI)

    Marwick, P.

    1994-12-15T23:59:59.000Z

    The Energy Policy Act of 1992 (Act) transferred the uranium enrichment enterprise to the United States Enrichment Corporation as of July 1, 1993. However, the Act requires the Department of Energy to retain ownership and responsibility for the costs of environmental cleanup resulting from the Government`s operation of the three gaseous diffusion facilities located in Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio (diffusion facilities). The Act established the Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) to: Pay for the costs of decontamination and decommissioning at the diffusion facilities; Pay the annual costs for remedial action at the diffusion facilities to the extent that the amount in the Fund is sufficient; and Reimburse uranium/thorium licensees for the costs of decontamination, decommissioning, reclamation, and other remedial actions which are incident to sales to the Government.

  10. Method for using salt deposits for storage

    SciTech Connect (OSTI)

    Hooper, M. W.; Voorhees, E. J.

    1984-12-18T23:59:59.000Z

    A method for developing, evacuating, using, sealing, and re-entering multiple stacked cavities which are created from a single well in salt deposits. The cavities are created in a salt deposit by circulating raw water through concentric casing strings in the well. Each of the cavities is evacuated of liquids prior to use. After storage material is injected into a cavity, the cavity is sealed by setting a plug in the well bore above the top of the cavity. The cavities may be re-entered by drilling out the plug or by drilling a directional well directly into the cavity.

  11. The Effect of Salt Water on Rice.

    E-Print Network [OSTI]

    Fraps, G. S. (George Stronach)

    1927-01-01T23:59:59.000Z

    mq A QTF *'. ' . - - . 1 bC1 r*. .. r * - .=.-ksl-, G v $. THE EFFECT OF SALT WATER ON RICE AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS T. 0. WALTON, President \\ STATION ,,,bfINISTRATION: *B. YOUNGBLOOD, M. S., Ph. D.,, Director A B CONNER... of Agriculture. ****In cooperation with the School of Agriculture. SYNOPSIS Rice farmers sometimes have trouble with salt in the water used for irrigation. Varying conditions, such as character of soil, amount of water already on the land, stage of growth...

  12. Order of wetting transitions in electrolyte solutions

    SciTech Connect (OSTI)

    Ibagon, Ingrid, E-mail: ingrid@is.mpg.de; Bier, Markus, E-mail: bier@is.mpg.de; Dietrich, S. [Max-Planck-Institut für Intelligente Systeme, Heisenbergstr. 3, 70569 Stuttgart, Germany and IV. Institut für Theoretische Physik, Universität Stuttgart, Pfaffenwaldring 57, 70569 Stuttgart (Germany)] [Max-Planck-Institut für Intelligente Systeme, Heisenbergstr. 3, 70569 Stuttgart, Germany and IV. Institut für Theoretische Physik, Universität Stuttgart, Pfaffenwaldring 57, 70569 Stuttgart (Germany)

    2014-05-07T23:59:59.000Z

    For wetting films in dilute electrolyte solutions close to charged walls we present analytic expressions for their effective interface potentials. The analysis of these expressions renders the conditions under which corresponding wetting transitions can be first- or second-order. Within mean field theory we consider two models, one with short- and one with long-ranged solvent-solvent and solvent-wall interactions. The analytic results reveal in a transparent way that wetting transitions in electrolyte solutions, which occur far away from their critical point (i.e., the bulk correlation length is less than half of the Debye length) are always first-order if the solvent-solvent and solvent-wall interactions are short-ranged. In contrast, wetting transitions close to the bulk critical point of the solvent (i.e., the bulk correlation length is larger than the Debye length) exhibit the same wetting behavior as the pure, i.e., salt-free, solvent. If the salt-free solvent is governed by long-ranged solvent-solvent as well as long-ranged solvent-wall interactions and exhibits critical wetting, adding salt can cause the occurrence of an ion-induced first-order thin-thick transition which precedes the subsequent continuous wetting as for the salt-free solvent.

  13. THE DEACTIVATION DECONTAMINATION & DECOMMISSIONING OF THE PLUTONIUM FINISHING PLANT (PFP) A FORMER PLUTONIUM PROCESSING FACILITY AT DOE HANFORD SITE

    SciTech Connect (OSTI)

    CHARBONEAU, S.L.

    2006-02-01T23:59:59.000Z

    The Plutonium Finishing Plant (PFP) was constructed as part of the Manhattan Project during World War II. The Manhattan Project was developed to usher in the use of nuclear weapons to end the war. The primary mission of the PFP was to provide plutonium used as special nuclear material (SNM) for fabrication of nuclear devices for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race and later the processing of fuel grade mixed plutonium-uranium oxide to support DOE's breeder reactor program. In October 1990, at the close of the production mission for PFP, a shutdown order was prepared by the Department of Energy (DOE) in Washington, DC and issued to the Richland DOE field office. Subsequent to the shutdown order, a team from the Defense Nuclear Facilities Safety Board (DNFSB) analyzed the hazards at PFP associated with the continued storage of certain forms of plutonium solutions and solids. The assessment identified many discrete actions that were required to stabilize the different plutonium forms into stable form and repackage the material in high integrity containers. These actions were technically complicated and completed as part of the PFP nuclear material stabilization project between 1995 and early 2005. The completion of the stabilization project was a necessary first step in deactivating PFP. During stabilization, DOE entered into negotiations with the U.S. Environmental Protection Agency (EPA) and the State of Washington and established milestones for the Deactivation and Decommissioning (D&D) of the PFP. The DOE and its contractor, Fluor Hanford (Fluor), have made great progress in deactivating, decontaminating and decommissioning the PFP at the Hanford Site as detailed in this paper. Background information covering the PFP D&D effort includes descriptions of negotiations with the State of Washington concerning consent-order milestones, milestones completed to date, and the vision of bringing PFP to slab-on-grade. Innovative approaches in planning and regulatory strategies, as well new technologies from within the United States and from other countries and field decontamination techniques developed by workforce personnel, such as the ''turkey roaster'' and the ''lazy Susan'' are covered in detail in the paper. Critical information on issues and opportunities during the performance of the work such as concerns regarding the handling and storage of special nuclear material, concerns regarding criticality safety and the impact of SNM de-inventory at PFP are also provided. The continued success of the PFP D&D effort is due to the detailed, yet flexible, approach to planning that applied innovative techniques and tools, involved a team of experienced independent reviewers, and incorporated previous lessons learned at the Hanford site, Rocky Flats, and commercial nuclear D&D projects. Multi-disciplined worker involvement in the planning and the execution of the work has produced a committed workforce that has developed innovative techniques, resulting in safer and more efficient work evolutions.

  14. Reducing the Risks. In the aftermath of a terrorist attack, wastewater utilities may have to contend with decontamination water containing chemical, biological, or radiological substances

    SciTech Connect (OSTI)

    Warren, Linda P.; Hornback, Chris; Strom, Daniel J.

    2006-08-01T23:59:59.000Z

    In the aftermath of a chemical, biological, or radiological (CBR) attack, decontamination of people and infrastructure will be needed. Decontamination inevitably produces wastewater, and wastewater treatment plants (WTPs) need to know how to handle decontamination wastewater. This article describes CBR substances; planning, coordinating, and communicating responses across agencies; planning within a utility; coordination with local emergency managers and first responders; mitigating effects of decontamination wastewater; and mitigating effects on utility personnel. Planning for Decontamination Wastewater: A Guide for Utilities, the document on which this article is based, was developed under a cooperative agreement from the U.S. Environmental Protection Agency by the National Association of Clean Water Agencies (NACWA) and its contractor, CH2MHILL, Inc.

  15. MATH 302 Differential Equations (Bueler) 28 February 2009 Solutions to Midterm Exam #1

    E-Print Network [OSTI]

    Bueler, Ed

    .1 + 0.1(0.1 + 1.1) = 1.1 + 0.12 = 1.22 y(0.2). 3. A brine solution of salt flows at a constant rate of 8 L/min into a large tank that initially held 100 L of brine solution in which was dissolved 0.5 kg. If the concentration of salt in the brine entering the tank is 0.05 kg/L, determine the mass of salt in the tank after

  16. Tank 41-H salt level fill history 1985 to 1987

    SciTech Connect (OSTI)

    Ross, R.H.

    1996-05-16T23:59:59.000Z

    The fill rate of the evaporator drop waste tank (i.e., salt tank) at Savannah River Site contained in the Waste Management Technology (WMT) monthly data record is based upon a simple formula that apportioned 10 percent of the evaporator output concentrate to the salt fill volume. Periodically, the liquid level of the salt tank would be decanted below the salt level surface and a visual inspection of the salt profile would be accomplished. The salt volume of the drop tank would then be corrected, if necessary, based upon the visual elevation of the salt formation. This correction can erroneously indicate an excess amount of salt fill occurred in a short time period. This report established the correct fill history for Tank 41H.

  17. Thorium Molten Salt Reactor : from high breeding to simplified reprocessing

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Thorium Molten Salt Reactor : from high breeding to simplified reprocessing L. Mathieu, D. Heuer, A- ceptable. The Thorium Molten Salt Reactor (TMSR) may contribute to solve these problems. The thorium cycle

  18. Spatial and Temporal Dynamics of Salt Marsh Vegetation across Scales

    E-Print Network [OSTI]

    Kim, Daehyun

    2010-10-12T23:59:59.000Z

    Biogeographic patterns across a landscape are developed by the interplay of environmental processes operating at different spatial and temporal scales. This research investigated dynamics of salt marsh vegetation on the Skallingen salt marsh...

  19. Corrosion Studies in High-Temperature Molten Salt Systems for...

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

    Corrosion Studies in High-Temperature Molten Salt Systems for CSP Applications - FY13 Q1 Corrosion Studies in High-Temperature Molten Salt Systems for CSP Applications - FY13 Q1...

  20. Fundamental Corrosion Studies in High-Temperature Molten Salt...

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

    Fundamental Corrosion Studies in High-Temperature Molten Salt Systems for Next-Generation CSP Systems - FY13 Q2 Fundamental Corrosion Studies in High-Temperature Molten Salt...