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Note: This page contains sample records for the topic "decontaminated salt solution" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

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

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).

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

2013-04-30T23:59:59.000Z

2

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

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).

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

2012-10-25T23:59:59.000Z

3

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

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.

Peters, T. B.

2014-01-02T23:59:59.000Z

4

Metal Surface Decontamination by the PFC Solution  

SciTech Connect

PFC (per-fluorocarbon) spray decontamination equipment was fabricated and its decontamination behavior was investigated. Europium oxide powder was mixed with the isotope solution which contains Co-60 and Cs-137. The different shape of metal specimens artificially contaminated with europium oxide powder was used as the surrogate contaminants. Before and after the application of the PFC spray decontamination method, the radioactivity of the metal specimens was measured by MCA. The decontamination factors were in the range from 9.6 to 62.4. The spent PFC solution was recycled by distillation. Before and after distillation, the turbidity of PFC solution was also measured. From the test results, it was found that more than 98% of the PFC solution could be recycled by a distillation. (authors)

Hui-Jun Won; Gye-Nam Kim; Wang-Kyu Choi; Chong-Hun Jung; Won-Zin Oh [Korea Atomic Energy Research Institute - KAERI, P.O.Box 105, Yuseong, Daejeon, Korea, 305-353 (Korea, Republic of)

2006-07-01T23:59:59.000Z

5

Electrochromic Salts, Solutions, and Devices  

DOE Patents (OSTI)

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.

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

2008-10-14T23:59:59.000Z

6

Electrochromic Salts, Solutions, and Devices  

DOE Patents (OSTI)

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.

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

2008-11-11T23:59:59.000Z

7

Electrochromic salts, solutions, and devices  

DOE Patents (OSTI)

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.

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

8

Ammonia Solubility in High Concentration Salt Solutions  

SciTech Connect

Solubility data for ammonia in water and various dilute solutions are abundant in the literature. However, there is a noticeable lack of ammonia solubility data for high salt, basic solutions of various mixtures of salts including those found in many of the Hanford Washington underground waste tanks. As a result, models based on solubility data for dilute salt solutions have been used to extrapolate to high salt solutions. These significant extrapolations need to be checked against actual laboratory data. Some indirect vapor measurements have been made. A more direct approach is to determine the ratio of solubility of ammonia in water to its solubility in high salt solutions. In various experiments, pairs of solutions, one of which is water and the other a high salt solution, are allowed to come to equilibrium with a common ammonia vapor pressure. The ratio of concentrations of ammonia in the two solutions is equal to the ratio of the respective ammonia solubilities (Henry's Law constants) at a given temperature. This information can then be used to refine the models that predict vapor space compositions of ammonia. Ammonia at Hanford is of concern because of its toxicity in the environment and its contribution to the flammability of vapor space gas mixtures in waste tanks.

HEDENGREN, D.C.

2000-02-01T23:59:59.000Z

9

ISOPAR L RELEASE RATES FROM SALTSTONE USING SIMULATED SALT SOLUTIONS  

SciTech Connect

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.

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

2008-07-31T23:59:59.000Z

10

Environmental decontamination  

SciTech Connect

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)

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

1981-02-01T23:59:59.000Z

11

Nonmetal-metal transition in metal–molten-salt solutions  

Science Journals Connector (OSTI)

The method of ab initio molecular dynamics, based on finite-temperature density-functional theory, is used to study the nonmetal-metal transition in two different metal–molten-salt solutions, Kx(KCl)1-x and Nax(NaBr)1-x. As the excess metal concentration is increased the electronic density becomes delocalized and percolating conducting paths are formed, making a significant dc electrical conductivity possible. This marks the onset of the metallic regime. By calculating several electronic and structural properties, remarkable differences between the two solutions are observed. The anomalous behavior of Nax(NaBr)1-x, typical of all the Na-NaX solutions, is found to be related to the strong attractive interaction between the sodium ions and the excess electrons. © 1996 The American Physical Society.

Pier Luigi Silvestrelli; Ali Alavi; Michele Parrinello; Daan Frenkel

1996-05-15T23:59:59.000Z

12

Blending of Radioactive Salt Solutions in Million Gallon Tanks - 13002  

SciTech Connect

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)

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

13

Blending Of Radioactive Salt Solutions In Million Gallon Tanks  

SciTech Connect

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.

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

2012-12-10T23:59:59.000Z

14

Electric Polarizability of DNA in Aqueous Salt Solution  

Science Journals Connector (OSTI)

Electric Polarizability of DNA in Aqueous Salt Solution ... At each simulation step, we calculate the contribution to the dipole moment from the first n counterions in the list, constituting the net charge (?x(n), ?y(n), ?z(n)) as follows, where e is the elementary charge and xi, yi, zi are the coordinates of the ith counterion in the list. ... Manning32 has already explained this effect in his two-phase model of polarizability, as reflecting the decreased resistance to distortion of the condensation layer. ...

Hitoshi Washizu; Kazuo Kikuchi

2006-01-26T23:59:59.000Z

15

Viscosity and Diffusion: Crowding and Salt Effects in Protein Solutions  

E-Print Network (OSTI)

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.

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

16

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

SciTech Connect

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).

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

2013-03-01T23:59:59.000Z

17

ISOPAR L Release Rates from Saltstone Using Simulated Salt Solutions  

SciTech Connect

The Modular Caustic-Side Solvent Extraction (CSSX) Unit (MCU) and the Salt Waste Processing Facility (SWPF) will produce a Deactivated 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 allowable concentration of Isopar{reg_sign} L in the DSS sent to SPF has been calculated at approximately 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 mg/L 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 Isopar{reg_sign} L release data can be treated as a percentage of initial concentration in the concentration range studied. 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 is larger than at lower temperatures. In one test at 95 C essentially all of the Isopar{reg_sign} L was released in three months. Initial curing temperature was found to be very important as slight variations during the first few days affected the final Isopar{reg_sign} L amount released. Short scoping tests at 95 C with solvent containing all components (Isopar{reg_sign} L, extractant, suppressor, and modifier) released less Isopar{reg_sign} L than the tests run with Isopar{reg_sign} L. Based on the 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 yield distributions were produced. From an SPF pouring perspective where saltstone will be poured in a shorter time period of one to two weeks, prior to being capped, the release of Isopar{reg_sign} L occurring in two weeks is more important. The average percentages of Isopar{reg_sign} L released after 13 days from saltstone are, to one sigma standard deviation: 60% {+-} 17% at 95 C, 13% {+-} 4.3% at 75 C, and 4.6% {+-} 1.2% at ambient temperature.

Bronikowski, M

2006-02-06T23:59:59.000Z

18

Concentration and precipitation of NaCl and KCl from salt cake leach solutions by electrodialysis  

SciTech Connect

Electrodialysis was investigated for cost-effective recovery of salt from salt cake leach solutions. (Salt cake is a waste stream generated by the aluminum industry during treatment of aluminum drosses and scrap.) We used a pilot-scale electrodialysis stack of 5 membrane pairs, each with an effective area of 0.02 m{sup 2}. The diluate stream contained synthetic NaCl, KCl,mixtures of NaCl and KCl, and actual salt cake leach solutions (mainly NaCl and KCl, with small amounts of MgCl{sub 2}). We concentrated and precipitated NaCl and KCl salts from the concentrate steam when the initial diluate stream concentration was 21.5 to 28.8 wt% NaCl and KCl. We found that water transferring through the membranes was a significant factor in overall efficiency of salt recovery by electrodialysis.

Sreenivasarao, K; Patsiogiannis, F.; Hryn, J.N.

1997-02-09T23:59:59.000Z

19

Ultralow Protein Adsorbing Coatings from Clickable PEG Nanogel Solutions: Bene ts of Attachment under Salt-Induced Phase  

E-Print Network (OSTI)

Ultralow Protein Adsorbing Coatings from Clickable PEG Nanogel Solutions: Bene ts of Attachment nanogel solutions attached with salt adsorbed signi cantly less brinogen than other 100% PEG coatings

Mitra, Rob

20

Salt  

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

Salt Salt Nature Bulletin No. 340-A April 12, 1969 Forest Preserve District of Cook County George W. Dunne, President Roland F. Eisenbeis, Supt. of Conservation SALT It is fortunate that Salt -- common salt, known to chemists as sodium chloride and to mineralogists as Halite -- is one of the most abundant substances on earth, because most of us crave it and must have it. Eskimos get along without salt because they live mostly on the uncooked flesh of fish and mammals. A few nomad tribes never eat it and do not need it because their diet contains so much milk cheese, and meat eaten raw or roasted. We people who eat boiled meat and many vegetables must have salt. Of the millions of tons produced commercially each year, only about three percent is used as table salt. Large quantities are required for refrigeration meat packing, curing and preserving fish, pickles, sauerkraut, and for other foods prepared in brine. A lot of it is needed for livestock. Salt is spread on sidewalks, streets and highways to melt ice in winter. It is used to glaze pottery, sewer pipe and other ceramics. It is required in many metallurgical processes, chemical industries, and the manufacture of such products as leather, glass, soap, bleaching powder and photographic supplies. It has about 14,000 uses.

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


21

Electrodialysis of vanadium(III) and iron(II) ions from a simulated decontamination solution  

SciTech Connect

The transport of vanadium(III) and iron(II) ions through the Nafion 117 cation-exchange membrane in the presence of picolinic acid was investigated by simulating the equilibrium distribution of ionic species as a function of pH, and by electrodialyzing the simulated waste solution. From distribution calculations of the model reaction systems it could be predicted that at pH 1.6 most vanadium ions exist predominantly in the form of the V{sup III}(Pic{sup {minus}}){sub 2}{sup +} complex, and this form of complex permeates across the cation-exchange membrane during electrodialysis. The experimental results, including variations in the color and cation concentrations of the catholyte, confirm the existence of the vanadium(III) picolinate complex. Iron ions permeated into the catholyte were converted to their hydroxide precipitates, which could be formed at the high pH condition resulting from the reduction of hydrogen ions and the production of OH{sup {minus}} ions by water electrolysis at the cathode. It was also found that the in-situ precipitation of iron in the electrodialyzer could be self-modulated by shifting the catholyte pH from the acidic state to the alkaline state during electrodialysis operation.

Shim, J.B.; Oh, W.Z.; Lee, B.J.; Park, H.S. [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)] [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of); Kim, J.D. [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Chemical Engineering] [Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Chemical Engineering

1999-07-01T23:59:59.000Z

22

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

SciTech Connect

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.

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

2010-09-30T23:59:59.000Z

23

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

E-Print Network (OSTI)

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

Fayer, Michael D.

24

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

SciTech Connect

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.

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

2004-03-29T23:59:59.000Z

25

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

E-Print Network (OSTI)

; Khan et al. , 1981). The Kinetics of Water Uptake by Seeds Many seeds placed in distilled water in petri dishes under optimum conditions for germination show a triphasic pattern of water uptake (Hadas, 1982). The first stage of water uptake... OF PANSY SEED AT HIGH TEMPERATURES BY PRIMING WITH SALT SOLUTIONS Introduction Seed germination can be divided into three separate but overlapping phases: imbibition, transition or lag, and radicle emergence (Hadas, 1982). An osmotically adjusted...

Yoon, Beyoung-Han

1995-01-01T23:59:59.000Z

26

Decontaminating lead bricks and shielding  

SciTech Connect

Lead used for shielding is often surface contaminated with radioisotopes and is therefore a RCRA D008 mixed waste. The technology-based standard for treatment is macroencapsulation. However, decontaminating and recycling the clean lead is a more attractive solution. Los Alamos National Laboratory decontaminates material and equipment contaminated with radioisotopes. Decontaminating lead poses special problems because of the RCRA hazard classification and the size of the inventory, now about 50 tons and likely to grow substantially because of planned decommissioning operations. This lead, in the form of bricks and other shield shapes, is surface contaminated with fission products. One of the best methods for decontaminating lead is removing the thin superficial layer of contamination with an abrasive medium trader pressure. For lead, a mixture of alumina with water and air at about 40 psig rapidly and effectively decontaminates the lead. The abrasive medium is sprayed onto the lead in a sealed-off area. The slurry of abrasive and particles of lead falls through a floor grating and is collected in a sump. A pump sends the slurry mixture back to the spray gun, creating a continuous process. The process generates small volumes of contaminated lead slurry that can be solidified and, because it passes the TCLP, is not a mixed waste. The decontaminated lead can be released for recycling.

Lussiez, G.W.

1993-05-01T23:59:59.000Z

27

Decontaminating lead bricks and shielding  

SciTech Connect

Lead used for shielding is often surface contaminated with radioisotopes and is therefore a RCRA D008 mixed waste. The technology-based standard for treatment is macroencapsulation. However, decontaminating and recycling the clean lead is a more attractive solution. Los Alamos National Laboratory decontaminates material and equipment contaminated with radioisotopes. Decontaminating lead poses special problems because of the RCRA hazard classification and the size of the inventory, now about 50 tons and likely to grow substantially because of planned decommissioning operations. This lead, in the form of bricks and other shield shapes, is surface contaminated with fission products. One of the best methods for decontaminating lead is removing the thin superficial layer of contamination with an abrasive medium trader pressure. For lead, a mixture of alumina with water and air at about 40 psig rapidly and effectively decontaminates the lead. The abrasive medium is sprayed onto the lead in a sealed-off area. The slurry of abrasive and particles of lead falls through a floor grating and is collected in a sump. A pump sends the slurry mixture back to the spray gun, creating a continuous process. The process generates small volumes of contaminated lead slurry that can be solidified and, because it passes the TCLP, is not a mixed waste. The decontaminated lead can be released for recycling.

Lussiez, G.W.

1993-01-01T23:59:59.000Z

28

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

E-Print Network (OSTI)

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.

Benjamin Monreal

2014-09-30T23:59:59.000Z

29

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

E-Print Network (OSTI)

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.

Monreal, Benjamin

2014-01-01T23:59:59.000Z

30

Nuclear reactor cooling system decontamination reagent regeneration  

DOE Patents (OSTI)

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.

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

31

Decontaminating lead bricks and shielding  

SciTech Connect

Lead used for shielding is often surface contaminated with radioisotopes and is therefore a RCRA D008 mixed waste. The technology-based standard for treatment is macroencapsulation. However, decontaminating and recycling the clean lead is a more attractive solution. Los Alamos National Laboratory decontaminates material and equipment contaminated with radioisotopes. Decontaminating lead poses special problems because of the RCRA hazard classification and the size of the inventory, now about 50 tons and likely to grow substantially of planned decommissioning operations. Thus lead, in the form of bricks and other shield shapes, is surface contaminated with fission products. One of the best methods for contaminated lead is removing the superficial layer of contamination with an abrasive medium under pressure. For lead, a mixture of alumina with water and air at about 40 psig rapidly and effectively decontaminates the lead. The abrasive medium is sprayed onto the lead in a scaled-off area. The slurry of abrasive and particles of lead falls through a floor and is collected in a sump. A pump sends the slurry mixture back to the spray gun, creating a continuous process. The process generates small volumes of lead slurry that can be solidified and, because it passes the TCLP, is not a mixed waste. The decontaminated lead can be released for recycling.

Lussiez, G.

1994-02-01T23:59:59.000Z

32

Acemetacin cocrystals and salts: structure solution from powder X-ray data and form selection of the piperazine salt  

Science Journals Connector (OSTI)

Multi-component crystals of the anti-inflammatory drug acemetacin were prepared by melt crystallization and their X-ray crystal structures solved using single-crystal and high-resolution powder X-ray diffraction (PXRD) data. The acemetacin-para-aminobenzoic acid adduct and the acemetacin piperazine salt are stable to hydration in the aqueous medium (up to 24 h).

Sanphui, P.

2014-02-28T23:59:59.000Z

33

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

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

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

34

Reactive decontamination formulation  

DOE Patents (OSTI)

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.

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

35

Decontamination & decommissioning focus area  

SciTech Connect

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.

NONE

1996-08-01T23:59:59.000Z

36

Experimental monitoring of a solution-mining Cavern in Salt: Identifying and Analyzing Early-Warning Signals Prior to Collapse  

E-Print Network (OSTI)

Experimental monitoring of a solution-mining Cavern in Salt: Identifying and Analyzing Early. This was the context when the opportunity was taken to instrument a large size in use saline cavern, so as to test that initiate and govern the evolution of the cavern up to its collapse. After a stationary period combined

Paris-Sud XI, Université de

37

Electroosmotic decontamination of concrete  

SciTech Connect

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}).

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

38

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

SciTech Connect

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.

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

2011-01-12T23:59:59.000Z

39

Gross decontamination experiment report  

SciTech Connect

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.

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

1983-07-01T23:59:59.000Z

40

Decontamination of metals using chemical etching  

DOE Patents (OSTI)

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.

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

1980-01-01T23:59:59.000Z

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


41

Decontaminating Flooded Wells  

E-Print Network (OSTI)

This publication explains how to decontaminate and disinfect a well, test the well water and check for well damage after a flood....

Boellstorff, Diana; Dozier, Monty; Provin, Tony; Dictson, Nikkoal; McFarland, Mark L.

2005-09-30T23:59:59.000Z

42

Chemical decontamination specification preparation  

SciTech Connect

Since the first low-concentration chemical decontamination in the United States at Vermont Yankee in 1979, > 75 decontamination applications have been made at > 20 nuclear electrical generating stations. Chemical decontamination has become a common technique for reducing person-rem exposures. Two vendors are currently offering low-concentration chemical decontamination reagents for application in boiling water reactor and pressurized water reactor systems. All technical aspects associated with the chemical decontamination technology have been commercially tested and are well advanced beyond the research and development stage. Extensive corrosion and material compatibility testing has been performed on the major solvent systems with satisfactory results. The material compatibility testing for the three main solvent systems, CANDECON, CITROX, and LOMI, has been documented in numerous Electric Power Research Institute reports.

Miller, M.A.; Remark, J.F.; Vandergriff, D.M.

1988-01-01T23:59:59.000Z

43

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

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.

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

44

Electrodialysis-ion exchange for the separation of dissolved salts  

SciTech Connect

The Department of Energy generates and stores a significant quantity of low level, high level, and mixed wastes. As some of the DOE facilities are decontaminated and decommissioned, additional and possibly different forms of wastes will be generated. A significant portion of these wastes are aqueous streams containing acids, bases, and salts, or are wet solids containing inorganic salts. Some of these wastes are quite dilute solutions, whereas others contain large quantities of nitrates either in the form of dissolved salts or acids. Many of the wastes are also contaminated with heavy metals, radioactive products, or organics. Some of these wastes are in storage because a satisfactory treatment and disposal processes have not been developed. This report describes the process of electrodialysis-ion exchange (EDIX) for treating aqueous wastes streams consisting of nitrates, sodium, organics, heavy metals, and radioactive species.

Baroch, C.J.; Grant, P.J.

1995-12-31T23:59:59.000Z

45

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

DOE Patents (OSTI)

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.

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

1980-06-06T23:59:59.000Z

46

THE PHYSICAL PROPERTIES OF AQUEOUS SALT SOLUTIONS IN RELATION TO THE IONIC THEORY  

Science Journals Connector (OSTI)

...two salts, and y and y2 their degrees of ionization in the pres-ence of each other: C1Y (Cyl1+ C2Y2) =Kl (C1'Yl + C2u'2)n-I c1(1O y,) or of sodium chloride and potassium sul-phate. Up to at least 0.2 normal concen-tration, the...

ARTHUR A. NOYES

1904-11-04T23:59:59.000Z

47

Decontamination and decommissioning  

SciTech Connect

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. These four phases of work were conducted in accordance with applicable regulations for D and D of research facilities and applicable regulations for packaging, transportation, and burial and storage of radioactive materials. The final result is that the Advanced Fuel Laboratories now meet requirements of ANSI 13.12 and can be released for unrestricted use. The four principal documents utilized in the D and D of the Cheswick Site were: (1) Plan for Fully Decontaminating and Decommissioning, Revision 3; (2) Environmental Assessment for Decontaminating and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pa.; (3) WARD-386, Quality Assurance Program Description for Decontaminating and Decommissioning Activities; and (4) Health Physics, Fire Control, and Site Emergency Manual. These documents are provided as Attachments 1, 2, 3 and 4.

Adams, G.A.; Bowen, W.C.; Cromer, P.M.; Cwynar, J.C.; Jacoby, W.R.; Woodsum, H.G.

1982-02-01T23:59:59.000Z

48

Small-angle neutron scattering study of structure and interaction during salt-induced liquid-liquid phase transition in protein solutions  

Science Journals Connector (OSTI)

The liquid-liquid phase transition (LLPT) in aqueous salt solutions of lysozyme protein has been studied by small-angle neutron scattering. Measurements have been carried out on fixed protein concentration with varying salt concentration approaching LLPT. The data are fitted considering protein interaction by the two Yukawa (2Y) potential which combines short-range attraction and long-range repulsion. We show that LLPT arises because of enhancement of non-DLVO (Derjaguin-Landau-Verwey-Overbeek) short-range attraction without any conformational structural change of the protein. The salt concentration required for LLPT as well as corresponding short-range attraction decreases significantly with increase in protein concentration.

A. J. Chinchalikar; V. K. Aswal; J. Kohlbrecher; A. G. Wagh

2013-06-18T23:59:59.000Z

49

Decontaminating metal surfaces  

DOE Patents (OSTI)

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.

Childs, E.L.

1984-01-23T23:59:59.000Z

50

Decontaminating metal surfaces  

DOE Patents (OSTI)

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/l of NaNO.sub.3, or by using nitrate-containing electrolytes which are acidic, e.g., of a pH<6.

Childs, Everett L. (Boulder, CO)

1984-11-06T23:59:59.000Z

51

Application of Ultrasonic for Decontamination of Contaminated Soil - 13142  

SciTech Connect

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)

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

52

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents (OSTI)

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.

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

1984-01-01T23:59:59.000Z

53

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents (OSTI)

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.

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

1982-05-19T23:59:59.000Z

54

The Effects of High Dose Rates of Ionizing Radiations on Solutions of Iron and Cerium Salts  

Science Journals Connector (OSTI)

...research-article The Effects of High Dose Rates of Ionizing Radiations on Solutions of Iron and Cerium...of 1.3 duration and over a range of dose rates from 0.5 to 20 000 rads/pulse. Radiation yields at constant dose rate...

1960-01-01T23:59:59.000Z

55

Decontamination impacts on solidification  

SciTech Connect

The increased occupational exposure resulting from the accumulation of activated corrosion products in the primary system of LWRs has led to the development of chemical methods to remove the contamination. In the past, the problem of enhanced migration of radionuclides away from trenches used to dispose of low-level radioactive waste, has been linked to the presence, at the disposal unit, of chelating or complexing agents such as those used in decontamination processes. These agents have further been found to reduce the normal sorptive capacity of soils for radionuclides. The degree to which these agents inhibit the normal sorptive processes is dependent on the type of complexing agent, the radionuclide of concern, the soil properties and whether the nuclide is present as a complex or is already sorbed to the soil. Since the quantity of reagent employed in a full system decontamination is large (200 to 25,000 kg), the potential for enhanced migration of radionuclides from a site used to dispose of the decontamination wastes should be addressed and guidelines established for the safe disposal of these wastes.

Piciulo, P.L.; Davis, M.S.

1985-01-01T23:59:59.000Z

56

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

E-Print Network (OSTI)

, and that reaction is difficult to reverse (Streitwieser and Heathcock, 1976; King and Poole, 1994). Tertiary amines (R, N) do not form amides but generally give lower K, values than secondary amines. For the extraction of undissociated carboxylic acids, aliphatic... by acidifying with carbon dioxide under pressure in the presence of a suitable solvent (Busche, 1988). Gregor has used electrodialysis to recover acetic acid from dilute (1-5 wt%) acetate solutions. With newer membranes, acid concentrations up to 30% were...

Gaskin, David J

1997-01-01T23:59:59.000Z

57

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

DOE Patents (OSTI)

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.

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

58

Decontamination of process equipment using recyclable chelating solvent  

SciTech Connect

The Department of Energy (DOE) is now faced with the task of meeting decontamination and decommissioning obligations at numerous facilities by the year 2019. Due to the tremendous volume of material involved, innovative decontamination technologies are being sought that can reduce the volumes of contaminated waste materials and secondary wastes requiring disposal. With sufficient decontamination, some of the material from DOE facilities could be released as scrap into the commercial sector for recycle, thereby reducing the volume of radioactive waste requiring disposal. Although recycling may initially prove to be more costly than current disposal practices, rapidly increasing disposal costs are expected to make recycling more and more cost effective. Additionally, recycling is now perceived as the ethical choice in a world where the consequences of replacing resources and throwing away reusable materials are impacting the well-being of the environment. Current approaches to the decontamination of metals most often involve one of four basic process types: (1) chemical, (2) manual and mechanical, (3) electrochemical, and (4) ultrasonic. {open_quotes}Hard{close_quotes} chemical decontamination solutions, capable of achieving decontamination factors (Df`s) of 50 to 100, generally involve reagent concentrations in excess of 5%, tend to physically degrade the surface treated, and generate relatively large volumes of secondary waste. {open_quotes}Soft{close_quotes} chemical decontamination solutions, capable of achieving Df`s of 5 to 10, normally consist of reagents at concentrations of 0.1 to 1%, generally leave treated surfaces in a usable condition, and generate relatively low secondary waste volumes. Under contract to the Department of Energy, the Babcock & Wilcox Company is developing a chemical decontamination process using chelating agents to remove uranium compounds and other actinide species from process equipment.

Jevec, J.; Lenore, C.; Ulbricht, S.

1995-12-01T23:59:59.000Z

59

Integrated decontamination process for metals  

DOE Patents (OSTI)

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.

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

1991-01-01T23:59:59.000Z

60

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

E-Print Network (OSTI)

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.

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

2015-01-06T23:59:59.000Z

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


61

Oxidative Tritium Decontamination System  

SciTech Connect

The Princeton Plasma Physics Laboratory, Tritium Systems Group has developed and fabricated an Oxidative Tritium Decontamination System (OTDS), which is designed to reduce tritium surface contamination on various components and items. The system is configured to introduce gaseous ozone into a reaction chamber containing tritiated items that require a reduction in tritium surface contamination. Tritium surface contamination (on components and items in the reaction chamber) is removed by chemically reacting elemental tritium to tritium oxide via oxidation, while purging the reaction chamber effluent to a gas holding tank or negative pressure HVAC system. Implementing specific concentrations of ozone along with catalytic parameters, the system is able to significantly reduce surface tritium contamination on an assortment of expendable and non-expendable items. This paper will present the results of various experimentation involving employment of this system.

Charles A. Gentile; John J. Parker; Gregory L. Guttadora; Lloyd P. Ciebiera

2002-02-11T23:59:59.000Z

62

Glovebox decontamination technology comparison  

SciTech Connect

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.

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

1999-09-26T23:59:59.000Z

63

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)

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.

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

2011-04-06T23:59:59.000Z

64

DECONTAMINATION TECHNOLOGIES FOR FACILITY REUSE  

SciTech Connect

As nuclear research and production facilities across the U.S. Department of Energy (DOE) nuclear weapons complex are slated for deactivation and decommissioning (D&D), there is a need to decontaminate some facilities for reuse for another mission or continued use for the same mission. Improved technologies available in the commercial sector and tested by the DOE can help solve the DOE's decontamination problems. Decontamination technologies include mechanical methods, such as shaving, scabbling, and blasting; application of chemicals; biological methods; and electrochemical techniques. Materials to be decontaminated are primarily concrete or metal. Concrete materials include walls, floors, ceilings, bio-shields, and fuel pools. Metallic materials include structural steel, valves, pipes, gloveboxes, reactors, and other equipment. Porous materials such as concrete can be contaminated throughout their structure, although contamination in concrete normally resides in the top quarter-inch below the surface. Metals are normally only contaminated on the surface. Contamination includes a variety of alpha, beta, and gamma-emitting radionuclides and can sometimes include heavy metals and organic contamination regulated by the Resource Conservation and Recovery Act (RCRA). This paper describes several advanced mechanical, chemical, and other methods to decontaminate structures, equipment, and materials.

Bossart, Steven J.; Blair, Danielle M.

2003-02-27T23:59:59.000Z

65

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

SciTech Connect

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.

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

1982-06-01T23:59:59.000Z

66

Pressure-tuning spectroscopy of charge-transfer salts. X-ray crystallography and comparative studies in solution and in the solid state  

SciTech Connect

The highly colored pyridinium (P{sup +}) and cobaltocenium (C{sup +}) iodides are charge-transfer salts by virtue of the new electronic absorption bands that follow Mulliken theory. X-ray crystallography establishes the relevant interionic separation and steric orientation of the cation/anion pairs P{sup +}I{sup {minus}} and C{sup +}I{sup {minus}} constrained for optimum charge-transfer interaction in the crystal lattice. Spectral comparisons of the charge-transfer (CT) transitions by absorption (solution) and by diffuse reflectance (solid-state) measurements reveals the commonality of contact ion pairs (CIP) in aprotic nonpolar solvents (dichloromethane) with those extant in crystalline charge-transfer salts. As such, the compression of the charge-transfer salts P{sup +}I{sup {minus}} in the solid state by the application of pressures up to 140 kbar leads to unusual red shifts of the CT bands indicative of the dominance of destabilizing charge-transfer interactions.

Bockman, T.M.; Kochi, J.K. (Univ. of Houston, TX (USA)); Chang, H.R.; Drickamer, H.G. (Univ. of Illinois, Urbana (USA))

1990-11-01T23:59:59.000Z

67

Decontamination Options for Drinking Water Contaminated with Bacillus anthracis Spores  

SciTech Connect

Five parameters were evaluated with surrogates of Bacillus anthracis spores to determine effective decontamination options for use in a contaminated drinking water supply. The parameters were: (1) type of Bacillus spore surrogate (B. thuringiensis or B. atrophaeus); (2) spore concentration in suspension (10{sup 2} to 10{sup 6} spores/ml); (3) chemical characteristics of decontaminant [sodium dicholor-s-triazinetrione dihydrate (Dichlor), hydrogen peroxide, potassium peroxymonosulfate (Oxone), sodium hypochlorite, and VirkonS{reg_sign}]; (4) decontaminant concentration (0.01% to 5%); and (5) decontaminant exposure time (10 min to 24 hr). Results from 162 suspension tests with appropriate controls are reported. Hydrogen peroxide at a concentration of 5%, and Dichlor and sodium hypochlorite at a concentration of 2%, were effective at spore inactivation regardless of spore type tested, spore exposure time, or spore concentration evaluated. This is the first reported study of Dichlor as an effective decontaminant for B. anthracis spore surrogates. Dichlor's desirable characteristics of high oxidation potential, high level of free chlorine, and more neutral pH than that of other oxidizers evaluated appear to make it an excellent alternative. All three oxidizers were effective against B. atrophaeus spores in meeting EPA's biocide standard of greater than a 6 log kill after a 10-minute exposure time and at lower concentrations than typically reported for biocide use. Solutions of 5% VirkonS{reg_sign} and Oxone were less effective decontaminants than other options evaluated in this study and did not meet the EPA's efficacy standard for biocides. Differences in methods and procedures reported by other investigators make quantitative comparisons among studies difficult.

Raber, E; Burklund, A

2010-02-16T23:59:59.000Z

68

Surface Decontamination of System Components in Uranium Conversion Plant at KAERI  

SciTech Connect

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.

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

2003-02-25T23:59:59.000Z

69

Determination of Single-Ion Activities of H+ and Cl– in Aqueous Hydrochloric Acid Solutions by Use of an Ionic Liquid Salt Bridge  

Science Journals Connector (OSTI)

Many of the problems inherent to KCl-type salt bridges can be circumvented by use of a salt bridge made of a moderately hydrophobic ionic liquid, that is, an ionic liquid salt bridge (ILSB). ... A newly emerged salt bridge based on moderately hydrophobic ionic liqs. is promising to solve many of the problems that KCl-type salt bridges are unable to, possibly making the future of electroanal. ... The new salt bridge is free from most of the problems inherent to KCl-based salt bridges. ...

Hideaki Sakaida; Takashi Kakiuchi

2011-09-20T23:59:59.000Z

70

Decontamination Systems Information and Research Program  

SciTech Connect

The Decontamination Systems Information and Research Program at West Virginia University consists of research and development associated with hazardous waste remediation problems at the Department of Energy complex and elsewhere. This program seeks to facilitate expedited development and implementation of solutions to the nation`s hazardous waste clean-up efforts. By a unique combination of university research and private technology development efforts, new paths toward implementing technology and speeding clean-ups are achievable. Mechanisms include aggressive industrial tie-ins to academic development programs, expedited support of small business technology development efforts, enhanced linkages to existing DOE programs, and facilitated access to hazardous waste sites. The program topically falls into an information component, which includes knowledge acquisition, technology evaluation and outreach activities and an R and D component, which develops and implements new and improved technologies. Projects began in February 1993 due to initiation of a Cooperative Agreement between West Virginia University and the Department of Energy.

Berg, M.; Sack, W.A.; Gabr, M. [and others

1994-12-31T23:59:59.000Z

71

SciTech Connect: Waste Isolation Pilot Plant Salt Decontamination...  

Office of Scientific and Technical Information (OSTI)

tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high,...

72

The Influence of Adrenalin, Modified By Salt Solutions, On Blood-Pressure of the Frog and Cat  

E-Print Network (OSTI)

of Bingerts solution: NaCl, 0.7#; CaCl 2, 0.026^; KCl, 0.03#. - 6 - an M/S solution (which is of nearly physiological osmotic pressure) caused no change either in blood-pressure or heart action? and an M/ 2 solution produced only a slight rise in bloodr... inthis way only in the cat); Uric acid; and Na^PCXj., M/16. Those depressing the pressure: KCl, M/l6 and M/32 (not in the frog); CaCl2, M/l6; MgS04, M/8. Those which showed no definite action are: Ringer's solution; NaCl, M/8; CaClg, M / 3 2 ; Na 2HP0...

Burket, Ivan R.

1911-01-01T23:59:59.000Z

73

Laser Decontamination of Metals | The Ames Laboratory  

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

Laser Decontamination of Metals Zapping contamination with lasers may be just the answer for safely and efficiently treating some of the waste awaiting disposal across the country....

74

Radioactive Material or Multiple Hazardous Materials Decontamination  

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

The purpose of this procedure is to provide guidance for performing decontamination of individuals who have entered a “hot zone” during transportation incidents involving  radioactive.

75

DECONTAMINATION OF ZIRCALOY SPENT FUEL CLADDING HULLS  

SciTech Connect

The reprocessing of commercial spent nuclear fuel (SNF) generates a Zircaloy cladding hull waste which requires disposal as a high level waste in the geologic repository. The hulls are primarily contaminated with fission products and actinides from the fuel. During fuel irradiation, these contaminants are deposited in a thin layer of zirconium oxide (ZrO{sub 2}) which forms on the cladding surface at the elevated temperatures present in a nuclear reactor. Therefore, if the hulls are treated to remove the ZrO{sub 2} layer, a majority of the contamination will be removed and the hulls could potentially meet acceptance criteria for disposal as a low level waste (LLW). Discard of the hulls as a LLW would result in significant savings due to the high costs associated with geologic disposal. To assess the feasibility of decontaminating spent fuel cladding hulls, two treatment processes developed for dissolving fuels containing zirconium (Zr) metal or alloys were evaluated. Small-scale dissolution experiments were performed using the ZIRFLEX process which employs a boiling ammonium fluoride (NH{sub 4}F)/ammonium nitrate (NH{sub 4}NO{sub 3}) solution to dissolve Zr or Zircaloy cladding and a hydrofluoric acid (HF) process developed for complete dissolution of Zr-containing fuels. The feasibility experiments were performed using Zircaloy-4 metal coupons which were electrochemically oxidized to produce a thin ZrO{sub 2} layer on the surface. Once the oxide layer was in place, the ease of removing the layer using methods based on the two processes was evaluated. The ZIRFLEX and HF dissolution processes were both successful in removing a 0.2 mm (thick) oxide layer from Zircaloy-4 coupons. Although the ZIRFLEX process was effective in removing the oxide layer, two potential shortcomings were identified. The formation of ammonium hexafluorozirconate ((NH{sub 4}){sub 2}ZrF{sub 6}) on the metal surface prior to dissolution in the bulk solution could hinder the decontamination process by obstructing the removal of contamination. The thermal decomposition of this material is also undesirable if the cladding hulls are melted for volume reduction or to produce waste forms. Handling and disposal of the corrosive off-gas stream and ZrO{sub 2}-containing dross must be addressed. The stability of Zr{sup 4+} in the NHF{sub 4}/NH{sub 4}NO{sub 3} solution is also a concern. Precipitation of ammonium zirconium fluorides upon cooling of the dissolving solution was observed in the feasibility experiments. Precipitation of the solids was attributed to the high fluoride to Zr ratios used in the experiments. The solubility of Zr{sup 4+} in NH{sub 4}F solutions decreases as the free fluoride concentration increases. The removal of the ZrO{sub 2} layer from Zircaloy-4 coupons with HF showed a strong dependence on both the concentration and temperature. Very rapid dissolution of the oxide layer and significant amounts of metal was observed in experiments using HF concentrations {ge} 2.5 M. Treatment of the coupons using HF concentrations {le} 1.0 M was very effective in removing the oxide layer. The most effective conditions resulted in dissolution rates which were less than approximately 2 mg/cm{sup 2}-min. With dissolution rates in this range, uniform removal of the oxide layer was obtained and a minimal amount of Zircaloy metal was dissolved. Future HF dissolution studies should focus on the decontamination of actual spent fuel cladding hulls to determine if the treated hulls meet criteria for disposal as a LLW.

Rudisill, T; John Mickalonis, J

2006-09-27T23:59:59.000Z

76

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

SciTech Connect

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.

EWALT, J.R.

2005-06-06T23:59:59.000Z

77

INTEGRATED VERTICAL AND OVERHEAD DECONTAMINATION SYSTEM  

SciTech Connect

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).

M.A. Ebadian, Ph.D.

1999-01-01T23:59:59.000Z

78

Decontamination Dressdown at a Transportation Accident Involving  

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

Decontamination Dressdown at a Transportation Accident Involving Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on how the decontamination dressdown process is implemented. During this discussion, the instructor can present various scenarios, each of which would discuss decontamination at the accident scene. The purpose of this discussion would be to cover how responders

79

Surface Decontamination [Laser Applications Laboratory] - Nuclear  

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

Surface Decontamination Surface Decontamination Capabilities Engineering Experimentation Reactor Safety Experimentation Aerosol Experiments System Components Laser Applications Overview Laser Oil & Gas Well Drilling Laser Heat Treatment Laser Welding of Metals On-line Monitoring Laser Beam Delivery Laser Glazing of Railroad Rails High Power Laser Beam Delivery Decontamination and Decommissioning Refractory Alloy Welding Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Laser Applications Laboratory Surface Decontamination Project description: Laser processing technology for decontamination of surfaces. Category: internal R&D project Bookmark and Share Fiber-optic beam-delivery systems for multi-kilowatt Nd:YAG laser beams are

80

Summary of decontamination cover manufacturing experience  

SciTech Connect

Decontamination cover forming cracks and vent cup assembly leaks through the decontamination covers were early manufacturing problems. The decontamination cover total manufacturing process yield was as low as 55%. Applicable tooling and procedures were examined. All manufacturing steps from foil fabrication to final assembly leak testing were considered as possible causes or contributing factors to these problems. The following principal changes were made to correct these problems: (1) the foil annealing temperature was reduced from 1375{degrees} to 1250{degrees}C, (2) the decontamination cover fabrication procedure (including visual inspection for surface imperfections and elimination of superfluous operations) was improved, (3) the postforming dye penetrant inspection procedure was revised for increased sensitivity, (4) a postforming (prewelding) 1250{degrees}C/1 h vacuum stress-relief operation was added, (5) a poststress relief (prewelding) decontamination cover piece-part leak test was implemented, (6) the hold-down fixture used during the decontamination cover-to-cup weld was modified, and concomitantly, and (7) the foil fabrication process was changed from the extruding and rolling of 63-mm-diam vacuum arc-remelted ingots (extrusion process) to the rolling of 19-mm-square arc-melted drop castings (drop cast process). Since these changes were incorporated, the decontamination cover total manufacturing process yield has been 91 %. Most importantly, more than 99% of the decontamination covers welded onto vent cup assemblies were acceptable. The drastic yield improvement is attributed primarily to the change in the foil annealing temperature from 1375{degrees} to 1250{degrees}C and secondarily to the improvements in the decontamination cover fabrication procedure.

Ulrich, G.B.; Berry, H.W.

1995-02-01T23:59:59.000Z

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


81

Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) |  

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

Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) Decontamination & Decommissioning/ Facilities Engineering (D&D/FE) As the DOE complex sites prepare for closure, a large number of buildings and facilities must be deactivated and decommissioned. These facilities contain many complex systems (e.g. ventilation), miles of contaminated pipelines, glove boxes, and unique processing equipment that require labor intensive deactivation and decommissioning methods. Although

82

Decontamination formulation with additive for enhanced mold remediation  

DOE Patents (OSTI)

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.

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

2010-02-16T23:59:59.000Z

83

Urban Decontamination Experience at Pripyat Ukraine - 13526  

SciTech Connect

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)

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

84

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

SciTech Connect

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.

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

2014-09-29T23:59:59.000Z

85

Drilling Waste Management Fact Sheet: Disposal in Salt Caverns  

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

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

86

Fundamental Properties of Salts  

SciTech Connect

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.

Toni Y Gutknecht; Guy L Fredrickson

2012-11-01T23:59:59.000Z

87

DECONTAMINATION OF ZIRCALOY CLADDING HULLS FROM SPENT NUCLEAR FUEL  

SciTech Connect

The feasibility of decontaminating spent fuel cladding hulls using hydrofluoric acid (HF) was investigated as part of the Global Energy Nuclear Partnership (GNEP) Separations Campaign. The concentrations of the fission product and transuranic (TRU) isotopes in the decontaminated hulls were compared to the limits for determining the low level waste (LLW) classification in the United States (US). The {sup 90}Sr and {sup 137}Cs concentrations met the disposal criteria for a Class C LLW; although, in a number of experiments the criteria for disposal as a Class B LLW were met. The TRU concentration in the hulls generally exceeded the Class C LLW limit by at least an order of magnitude. The concentration decreased sharply as the initial 30-40 {micro}m of the cladding hull surface were removed. At depths beyond this point, the TRU activity remained relatively constant, well above the Class C limit. Reprocessing of spent nuclear fuel generates a cladding waste which would likely require disposal as a Greater than Class C LLW in the US. If the cladding hulls could be treated to remove a majority of the actinide and fission product contamination, the hulls could potentially meet acceptance criteria for disposal as a LLW or allow recycle of the Zr metal. Discard of the hulls as a LLW would result in significant cost savings compared to disposal as a Greater than Class C waste which currently has no disposition path. During fuel irradiation and reprocessing, radioactive materials are produced and deposited in the Zircaloy cladding. Due to short depths of penetration, the majority of the fission products and actinide elements are located in the ZrO{sub 2} layer which forms on the surface of the cladding during fuel irradiation. Therefore, if the oxide layer is removed, the majority of the contamination should also be removed. It is very difficult, if not impossible to remove all of the activity from spent fuel cladding since traces of U and Th in the unirradiated Zircaloy adsorb neutrons generating higher actinides in the bulk material. During fuel irradiation, {sup 92}Zr is also converted to radioactive {sup 93}Zr by neutron adsorption. Methods for decontaminating and conditioning irradiated Zircaloy cladding hulls have been investigated in Europe, Japan, and the US during the last 35 years; however, a method to decontaminate the hulls to an activity level which meets US acceptance criteria for disposal as a LLW was not deployed on a commercial scale. The feasibility of decontaminating spent fuel cladding hulls was investigated as part of the GNEP Separations Campaign. Small-scale experiments were used to demonstrate the removal of the ZrO{sub 2} layer from Zircaloy coupons using dilute solutions ({le}1.0 M) of HF. The most effective conditions resulted in dissolution rates which were less than approximately 2 mg/cm{sup 2}-min. With dissolution rates in this range, uniform removal of the oxide layer was obtained and a minimal amount of Zircaloy metal was dissolved. To test the HF decontamination process, experiments were subsequently performed using actual spent fuel cladding hulls. Decontamination experiments were performed to measure the fission product and actinide concentrations as a function of the depth of the surface removed from the cladding hull. The experimental methods used to perform these experiments and a discussion of the results and observations are presented in the following sections.

Rudisill, T.

2010-09-29T23:59:59.000Z

88

Iodized Salt  

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

Iodized Salt Iodized Salt Name: Theresa Location: N/A Country: N/A Date: N/A Question: Why do they put iodine in salt? Replies: Iodine was introduced into salt at earlier this century when it was discovered that certain areas of the US had a mark deficiency in iodine in the diet of people, and people developed a neck swelling (goiter). The Great Lakes region is one of these areas where the soil is lacking iodine. Goiter can be caused when the thyroid gland swells because of a lack of iodine in the diet. Most medical advise now states that iodine in salt is no longer necessary due to our food sources arising from all over the world. Steve Sample Hi Theresa...see, there are a variety of elements and compounds that are necessary for the proper maintenance of our life. One of these is iodine, since a small quantity of iodine is needed for the adequate functioning of the thyroid gland. A deficiency of iodine produces dire effects, as goiter, where the thyroid gland swollens due to the lack of iodine traces in the diet. The iodine affects directly the tyrhoid gland secretions, which themselves, to a great extent, control heart action, nerve response to stimuli, rate of body growth and metabolism.

89

Mechanical decontamination techniques for floor drain systems  

SciTech Connect

The unprecedented nature of cleanup activities at Three Mile Island Unit 2 (TMI-2) following the 1979 accident has necessitated the development of new techniques to deal with radiation and contamination in the plant. One of these problems was decontamination of floor drain systems, which had become highly contaminated with various forms of dirt and sludge containing high levels of fission products and fuel from the damaged reactor core. The bulk of this contamination is loosely adherent to the drain pipe walls; however, significant amounts of contamination have become incorporated into pipe wall oxide and corrosion layers and embedded in microscopic pits and fissures in the pipe wall material. The need to remove this contamination was recognized early in the TMI-2 cleanup effort. A program consisting of development and laboratory testing of floor drain decontamination techniques was undertaken early in the cleanup with support from the Electric Power Research Institute (EPRI). Based on this initial research, two techniques were judged to show promise for use at TMI-2: a rotating brush hone system and a high-pressure water mole nozzle system. Actual use of these devices to clean floor drains at TMI-2 has yielded mixed decontamination results. The decontamination effectiveness that has been obtained is highly dependent on the nature of the contamination in the drain pipe and the combination of decontamination techniques used.

Palau, G.L.; Saigusa, Moriyuki

1987-01-01T23:59:59.000Z

90

DECONTAMINATION AND BENEFICIAL USE OF DREDGED MATERIALS.  

SciTech Connect

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.

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

2000-12-03T23:59:59.000Z

91

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

SciTech Connect

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.

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

2012-01-03T23:59:59.000Z

92

Decontamination, decommissioning, and vendor advertorial issue, 2007  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major articles/reports in this issue include: An interesting year ahead of us, by Tom Christopher, AREVA NP Inc.; U.S.-India Civil Nuclear Cooperation; Decontamination and recycling of retired components, by Sean P. Brushart, Electric Power Research Institute; and, ANO is 33 and going strong, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The industry innovation article is: Continuous improvement process, by ReNae Kowalewski, Arkansas Nuclear One.

Agnihotri, Newal (ed.)

2007-07-15T23:59:59.000Z

93

E-Print Network 3.0 - aqueous homogeneous solution Sample Search...  

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

of Liquids 6. Invited Contributions (a)Gordon Research... Salts Molten Salts Solid State :Ceramics Molten Salts Phys.Chem. Glasses Water & Aqueous Solutions... Liquids Solids...

94

Structural Evaluation and Solution Integrity of Alkali Metal Salt Complexes of the Manganese 12-Metallacrown-4 (12-MC-4) Structural Type  

E-Print Network (OSTI)

of crystalline salts (LiCl2)[12-MCMn(III)N(shi)-4]- ([(LiCl2),1]-), (Li(trifluoro- acetate))[12-MCMn(III)N(shi)-4:1 metal:metallacrown adducts with lithium and 2:1 metal:metallacrown complexes with sodium and potassium

Gibney, Brian R.

95

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

SciTech Connect

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)

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

96

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

E-Print Network (OSTI)

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...

Carlsson, Charlotta Elisabeth

2012-06-07T23:59:59.000Z

97

INTEGRATED VERTICAL AND OVERHEAD DECONTAMINATION (IVOD) SYSTEM  

SciTech Connect

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.

M.A. Ebadian, Ph.D.

2001-01-01T23:59:59.000Z

98

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

SciTech Connect

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.

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

2013-08-08T23:59:59.000Z

99

SAFETY STUDIES TO MEASURE EXOTHERMIC REACTIONS OF SPENT PLUTONIUM CONTAMINATION CHEMICALS USING WET AND DRY DECONTAMINATION METHODS  

SciTech Connect

The Plutonium Finishing Plant (PFP) at the Hanford site in Eastern Washington is currently being decommissioned by Fluor Hanford. 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 and sequestering agents. Aggressive chemicals are commonly used to remove transuranic contaminants from process equipment to allow disposal of the equipment as low level waste. Fluor's decontamination procedure involves application of chemical solutions as a spray on the contaminated surfaces, followed by a wipe-down with rags. Alternatively, a process of applying oxidizing Ce IV ions contained in a gel matrix and vacuuming a dry gel material is being evaluated. These processes effectively transfer the transuranic materials to rags or a gel matrix which is then packaged as TRU waste and disposed. Fluor is investigating plutonium decontamination chemicals as a result of concerns regarding the safety of chemical procedures following a fire at Rocky Flats in 2003. The fire at Rocky Flats 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. Although the investigation of the fire was not conclusive as to cause, the reviewers noted that rags were found in the glovebox, suggesting that the combination of rags and chemicals may have contributed to the fire. Because of this underlying uncertainty, Fluor began an investigation into the potential for fire when using the chemicals and materials using wet disposition and dry disposition of the waste generated in the decontamination process and the storage conditions to which the waste drum would be exposed. 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. Hanford waste storage conditions are such that there is added heat to the containers from ambient conditions during storage especially during the summer months. Treatability tests under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) were used to assess the use of certain chemicals and wipes (wet method) and chemical-gel matrices (dry method) 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 decontamination agents such as RadPro? , Glygel? and ASPIGEL 100?. 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. From these wet and dry method treatability studies, certain limiting conditions have been defined that will aid in assuring safe operations and waste packaging during the decommissioning and waste disposition process.

Hopkins, Andrea M.; Jackson, George W.; Minette, Michael J.; Ewalt, John R.; Cooper, Thurman D.; Scott, Paul A.; Jones, Susan A.; Scheele, Randall D.; Charboneau, Stacy L.

2005-10-12T23:59:59.000Z

100

Salt-assistant combustion synthesis of nanocrystalline Nd{sub 2}(Zr{sub 1-x}Sn{sub x}){sub 2}O{sub 7} (0 {<=} x {<=} 1) solid solutions  

SciTech Connect

Nanocrystalline Nd{sub 2}(Zr{sub 1-x}Sn{sub x}){sub 2}O{sub 7} series solid solutions were prepared by a convenient salt-assisted combustion process using glycine as fuel. The samples were characterized by X-ray diffraction, Fourier transform infrared spectroscopy, Raman spectroscopy, transmission electron microscopy and high-resolution transmission electron microscopy. The results showed the Zr ion can be partially replaced by Sn ion. The partial substituted products were still single-phase solid solutions and the crystal form remained unchanged. TEM images reveal that the products are composed of well-dispersed square-shaped nanocrystals. The method provides a convenient and low-cost route for the synthesis of nanostructures of oxide materials.

Tong Yuping, E-mail: huabeitong@yahoo.cn [School of Civil Engineering and Communication, North China Institute of Water Conservancy and Hydroelectric Power, Zhengzhou 450011 (China); Wang Yanping [College of Mechanical Engineering and Automation, Zhejiang Sci-Tech University, Hangzhou 310018 (China)

2009-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "decontaminated salt solution" from the National Library of EnergyBeta (NLEBeta).
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to obtain the most current and comprehensive results.


101

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

SciTech Connect

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.

Kyser, E.

2012-07-25T23:59:59.000Z

102

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

SciTech Connect

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.

HOPKINS, A.M.

2005-02-23T23:59:59.000Z

103

Chapter 20 - Uranium Enrichment Decontamination & Decommissioning Fund  

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

0. Uranium Enrichment Decontamination and Decommissioning Fund 20-1 0. Uranium Enrichment Decontamination and Decommissioning Fund 20-1 CHAPTER 20 URANIUM ENRICHMENT DECONTAMINATION AND DECOMMISSIONING FUND 1. INTRODUCTION. a. Purpose. To establish policies and procedures for the financial management, accounting, budget preparation, cash management of the Uranium Enrichment Decontamination and Decommissioning Fund, referred to hereafter as the Fund. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are directly or indirectly involved with the Fund. c. Requirements and Sources of the Fund. (1) The Energy Policy Act of 1992 (EPACT) requires DOE to establish and administer the Fund. EPACT authorizes that the

104

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

SciTech Connect

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.

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

2011-11-10T23:59:59.000Z

105

Decontamination and reuse of ORGDP aluminum scrap  

SciTech Connect

The Gaseous Diffusion Plants, or GDPs, have significant amounts of a number of metals, including nickel, aluminum, copper, and steel. Aluminum was used extensively throughout the GDPs because of its excellent strength to weight ratios and good resistance to corrosion by UF{sub 6}. This report is concerned with the recycle of aluminum stator and rotor blades from axial compressors. Most of the stator and rotor blades were made from 214-X aluminum casting alloy. Used compressor blades were contaminated with uranium both as a result of surface contamination and as an accumulation held in surface-connected voids inside of the blades. A variety of GDP studies were performed to evaluate the amounts of uranium retained in the blades; the volume, area, and location of voids in the blades; and connections between surface defects and voids. Based on experimental data on deposition, uranium content of the blades is 0.3%, or roughly 200 times the value expected from blade surface area. However, this value does correlate with estimated internal surface area and with lengthy deposition times. Based on a literature search, it appears that gaseous decontamination or melt refining using fluxes specific for uranium removal have the potential for removing internal contamination from aluminum blades. A melt refining process was used to recycle blades during the 1950s and 1960s. The process removed roughly one-third of the uranium from the blades. Blade cast from recycled aluminum appeared to perform as well as blades from virgin material. New melt refining and gaseous decontamination processes have been shown to provide substantially better decontamination of pure aluminum. If these techniques can be successfully adapted to treat aluminum 214-X alloy, internal and, possibly, external reuse of aluminum alloys may be possible.

Compere, A.L.; Griffith, W.L.; Hayden, H.W.; Wilson, D.F.

1996-12-01T23:59:59.000Z

106

Microwave concrete decontamination - Phase II results  

SciTech Connect

This report documents the results of the second phase of a four-phase development program to develop a system to decontaminate concrete using microwave energy. In the first phase of the program the feasibility of using microwaves to remove concrete surfaces was demonstrated. In the first phase experiments, concrete slabs were placed on a translator and moved beneath a stationery microwave system. The second phase demonstrated the ability to mobilize the technology to remove the surfaces from concrete floors. Phases III and IV will further develop the technology to be remotely operated and capable of removing concrete from floors as well as from vertical surfaces.

White, T.L.; Foster, D. Jr.

1994-06-01T23:59:59.000Z

107

Decontamination, decommissioning, and vendor advertorial issue, 2005  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Major interviews, articles and reports in this issue include: Increasing momentum, by Gary Taylor, Entergy Nuclear, Inc.; An acceptable investment, by Tom Chrisopher, Areva, Inc.; Fuel recycling for the U.S. and abroad, by Philippe Knoche, Areva, France; We're bullish on nuclear power, by Dan R. Keuter, Entergy Nuclear, Inc.; Ten key actions for decommissioning, by Lawrence E. Boing, Argonne National Laboratory; Safe, efficient and cost-effective decommissioning, by Dr. Claudio Pescatore and Torsten Eng, OECD Nuclear Energy Agency (NEA), France; and, Plant profile: SONGS decommissioning.

Agnihotri, Newal (ed.)

2005-07-15T23:59:59.000Z

108

SEDIMENT DECONTAMINATION TREATMENT TRAIN: COMMERCIAL-SCALE DEMONSTRATION  

E-Print Network (OSTI)

1 SEDIMENT DECONTAMINATION TREATMENT TRAIN: COMMERCIAL-SCALE DEMONSTRATION FOR THE PORT OF NEW YORK York and New Jersey. We describe here a regional contaminated sediment decontamination program) public outreach. Several types of treatment technologies suitable for use with varying levels of sediment

Brookhaven National Laboratory

109

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

DOE Patents (OSTI)

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.

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

110

EA-1266: Proposed Decontamination and Disassembly of the Argonne Thermal  

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

266: Proposed Decontamination and Disassembly of the Argonne 266: Proposed Decontamination and Disassembly of the Argonne Thermal Source Reactor (ATSR) At Argonne National Laboratory, Argonne, Illinois EA-1266: Proposed Decontamination and Disassembly of the Argonne Thermal Source Reactor (ATSR) At Argonne National Laboratory, Argonne, Illinois SUMMARY 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. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 15, 1998 EA-1266: Finding of No Significant Impact Proposed Decontamination and Disassembly of the Argonne Thermal Source Reactor (ATSR) At Argonne National Laboratory July 15, 1998 EA-1266: Final Environmental Assessment

111

High solute rejecting membranes for reverse osmosis: Polyetheramide hydrazide  

SciTech Connect

Synthesis of benzhydrazide polymers and determination of reverse osmosis properties of their membranes were reported earlier. Their performance was not adequate for seawater desalination or for high radioactive decontamination factors (DF). The same hydrazide polymers modified by incorporation of additional monomers with ether linkages were synthesized by low temperature polycondensation of freshly prepared m-amino benzhydrazide, p-amino benzhydrazide, and 4,4{prime}-diamino diphenyl ether, with isophthaloyl chloride and terephthaloyl chloride in dimethyl acetamide solvent. A series of film-forming polymers prepared by altering the molar ratios of the reacting monomers were characterized in terms of percent moisture regain, inherent viscosity, solubility parameters, and interfacial sorption characteristics. Asymmetric membranes prepared from these polymer samples were characterized in terms of the pure water permeability constant and the solute transport parameter, and were tested for their reverse osmosis performance. An optimum mole ratio of reaching monomers has been identified for the synthesis of polymer and the resulting membrane offered the best performance for reverse osmosis (salt rejection as high as 99.4% for 3.5% sodium chloride solution). The incorporation of aromatic ether linkages in the polyamide benzhydrazide polymeric chains appears to alter the polar and nonpolar character of the bulk polymer, and also the membrane solution interface characteristics, resulting in enhanced solute separation. These membranes appear to be potential candidates for single-stage seawater desalination and also for a variety of industrial effluent treatment applications for significantly high DF radioactive effluent treatment.

Bindal, R.C.; Ramachandhran, V.; Misra, B.M.; Ramani, M.P.S. (Bhabha Atomic Research Centre, Bombay (India))

1991-01-01T23:59:59.000Z

112

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

SciTech Connect

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

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

2014-01-21T23:59:59.000Z

113

Long-term decontamination engineering study. Volume 1  

SciTech Connect

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.

Geuther, W.J.

1995-04-03T23:59:59.000Z

114

Decontamination, decommissioning, and vendor advertorial issue, 2008  

SciTech Connect

The focus of the July-August issue is on Decontamination, decommissioning, and vendor advertorials. Articles and reports in this issue include: D and D technical paper summaries; The role of nuclear power in turbulent times, by Tom Chrisopher, AREVA, NP, Inc.; Enthusiastic about new technologies, by Jack Fuller, GE Hitachi Nuclear Energy; It's important to be good citizens, by Steve Rus, Black and Veatch Corporation; Creating Jobs in the U.S., by Guy E. Chardon, ALSTOM Power; and, and, An enviroment and a community champion, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovations article is titled Best of the best TIP achievement 2008, by Edward Conaway, STP Nuclear Operating Company.

Agnihotri, Newal (ed.)

2008-07-15T23:59:59.000Z

115

Decontamination Technologies, Task 3, Urban Remediation and Response Project  

SciTech Connect

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).

Heiser,J.; Sullivan, T.

2009-06-30T23:59:59.000Z

116

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

SciTech Connect

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

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

2011-05-26T23:59:59.000Z

117

Surface Decontamination Using Laser Ablation Process - 12032  

SciTech Connect

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)

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

2012-07-01T23:59:59.000Z

118

Phase 2 microwave concrete decontamination results  

SciTech Connect

The authors report on the results of the second phase of a four-phase program at Oak Ridge National Laboratory to develop a system to decontaminate concrete using microwave energy. The microwave energy is directed at the concrete surface through the use of an optimized wave guide antenna, or applicator, and this energy rapidly heats the free water present in the interstitial spaces of the concrete matrix. The resulting steam pressure causes the surface to burst in much the same way popcorn pops in a home microwave oven. Each steam explosion removes several square centimeters of concrete surface that are collected by a highly integrated wave guide and vacuum system. The authors call this process the microwave concrete decontamination, or MCD, process. In the first phase of the program the principle of microwaves concrete removal concrete surfaces was demonstrated. In these experiments, concrete slabs were placed on a translator and moved beneath a stationary microwave system. The second phase demonstrated the ability to mobilize the technology to remove the surfaces from concrete floors. Area and volume concrete removal rates of 10.4 cm{sup 2}/s and 4.9 cm{sup 3}/S, respectively, at 18 GHz were demonstrated. These rates are more than double those obtained in Phase 1 of the program. Deeper contamination can be removed by using a longer residence time under the applicator to create multiple explosions in the same area or by taking multiple passes over previously removed areas. Both techniques have been successfully demonstrated. Small test sections of painted and oil-soaked concrete have also been removed in a single pass. Concrete with embedded metal anchors on the surface has also been removed, although with some increased variability of removal depth. Microwave leakage should not pose any operational hazard to personnel, since the observed leakage was much less than the regulatory standard.

White, T.L.; Foster, D. Jr.; Wilson, C.T.; Schaich, C.R.

1995-04-01T23:59:59.000Z

119

Retrospective salt tectonics  

SciTech Connect

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.

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

1996-12-31T23:59:59.000Z

120

EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell  

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

3: Decontaminating and Decommissioning the General Atomics 3: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California EA-1053: Decontaminating and Decommissioning the General Atomics Hot Cell Facility, San Diego, California SUMMARY 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 General Atomics' Hot Cell Facility would be transported to either a DOE owned facility, such as the Hanford site in Washington, or to a commercial facility, such as Envirocare in Utah, for treatment and/or storage and disposal. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD August 14, 1995 EA-1053: Finding of No Significant Impact

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121

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

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

NONE

1994-09-01T23:59:59.000Z

122

LITERATURE REVIEWS TO SUPPORT ION EXCHANGE TECHNOLOGY SELECTION FOR MODULAR SALT PROCESSING  

SciTech Connect

This report summarizes the results of literature reviews conducted to support the selection of a cesium removal technology for application in a small column ion exchange (SCIX) unit supported within a high level waste tank. SCIX is being considered as a technology for the treatment of radioactive salt solutions in order to accelerate closure of waste tanks at the Savannah River Site (SRS) as part of the Modular Salt Processing (MSP) technology development program. Two ion exchange materials, spherical Resorcinol-Formaldehyde (RF) and engineered Crystalline Silicotitanate (CST), are being considered for use within the SCIX unit. Both ion exchange materials have been studied extensively and are known to have high affinities for cesium ions in caustic tank waste supernates. RF is an elutable organic resin and CST is a non-elutable inorganic material. Waste treatment processes developed for the two technologies will differ with regard to solutions processed, secondary waste streams generated, optimum column size, and waste throughput. Pertinent references, anticipated processing sequences for utilization in waste treatment, gaps in the available data, and technical comparisons will be provided for the two ion exchange materials to assist in technology selection for SCIX. The engineered, granular form of CST (UOP IE-911) was the baseline ion exchange material used for the initial development and design of the SRS SCIX process (McCabe, 2005). To date, in-tank SCIX has not been implemented for treatment of radioactive waste solutions at SRS. Since initial development and consideration of SCIX for SRS waste treatment an alternative technology has been developed as part of the River Protection Project Waste Treatment Plant (RPP-WTP) Research and Technology program (Thorson, 2006). Spherical RF resin is the baseline media for cesium removal in the RPP-WTP, which was designed for the treatment of radioactive waste supernates and is currently under construction in Hanford, WA. Application of RF for cesium removal in the Hanford WTP does not involve in-riser columns but does utilize the resin in large scale column configurations in a waste treatment facility. The basic conceptual design for SCIX involves the dissolution of saltcake in SRS Tanks 1-3 to give approximately 6 M sodium solutions and the treatment of these solutions for cesium removal using one or two columns supported within a high level waste tank. Prior to ion exchange treatment, the solutions will be filtered for removal of entrained solids. In addition to Tanks 1-3, solutions in two other tanks (37 and 41) will require treatment for cesium removal in the SCIX unit. The previous SCIX design (McCabe, 2005) utilized CST for cesium removal with downflow supernate processing and included a CST grinder following cesium loading. Grinding of CST was necessary to make the cesium-loaded material suitable for vitrification in the SRS Defense Waste Processing Facility (DWPF). Because RF resin is elutable (and reusable) and processing requires conversion between sodium and hydrogen forms using caustic and acidic solutions more liquid processing steps are involved. The WTP baseline process involves a series of caustic and acidic solutions (downflow processing) with water washes between pH transitions across neutral. In addition, due to resin swelling during conversion from hydrogen to sodium form an upflow caustic regeneration step is required. Presumably, one of these basic processes (or some variation) will be utilized for MSP for the appropriate ion exchange technology selected. CST processing involves two primary waste products: loaded CST and decontaminated salt solution (DSS). RF processing involves three primary waste products: spent RF resin, DSS, and acidic cesium eluate, although the resin is reusable and typically does not require replacement until completion of multiple treatment cycles. CST processing requires grinding of the ion exchange media, handling of solids with high cesium loading, and handling of liquid wash and conditioning solutions. RF processing requires h

King, W

2007-11-30T23:59:59.000Z

123

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular  

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

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics The report addresses granular salt reconsolidation from three vantage points: laboratory testing, modeling, and petrofabrics. The experimental data 1) provide greater insight and understanding into the role of elevated temperature and pressure regimes on physical properties of reconsolidated crushed salt, 2) can supplement an existing database used to develop a reconsolidation constitutive model and 3) provide data for model evaluation. The constitutive model accounts for the effects of moisture through pressure solution and dislocation creep, with both terms dependent

124

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular  

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

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics The report addresses granular salt reconsolidation from three vantage points: laboratory testing, modeling, and petrofabrics. The experimental data 1) provide greater insight and understanding into the role of elevated temperature and pressure regimes on physical properties of reconsolidated crushed salt, 2) can supplement an existing database used to develop a reconsolidation constitutive model and 3) provide data for model evaluation. The constitutive model accounts for the effects of moisture through pressure solution and dislocation creep, with both terms dependent

125

Salt Tolerance of Desorption Electrospray Ionization (DESI)  

SciTech Connect

Suppression of ion intensity in the presence of high salt matrices is common in most mass spectrometry ionization techniques. Desorption electrospray ionization (DESI) is an ionization method that exhibits salt tolerance, and this is investigated. DESI analysis was performed on three different drug mixtures in the presence of 0, 0.2, 2, 5, 10, and 20% NaCl:KCl weight by volume from seven different surfaces. At physiological concentrations individual drugs in each mixture were observed with each surface. Collision-induced dissociation (CID) was used to provide additional confirmation for select compounds. Multiple stage experiments, to MS5, were performed for select compounds. Even in the absence of added salt, the benzodiazepine containing mixture yielded sodium and potassium adducts of carbamazepine which masked the ions of interest. These adducts were eliminated by adding 0.1% 7M ammonium acetate to the standard methanol:water (1:1) spray solvent. Comparison of the salt tolerance of DESI with that of electrospray ionization (ESI) demonstrated much better signal/noise characteristics for DESI in this study. The salt tolerance of DESI was also studied by performing limit of detection and dynamic range experiments. Even at a salt concentration significantly above physiological concentrations, select surfaces were effective in providing spectra that allowed the ready identification of the compounds of interest. The already high salt tolerance of DESI can be optimized further by appropriate choices of surface and spray solution.

Jackson, Ayanna U. [Purdue University; Talaty, Nari [Purdue University; Cooks, R G [Purdue University; Van Berkel, Gary J [ORNL

2007-01-01T23:59:59.000Z

126

Salt Wells Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Salt Wells Geothermal Area Salt Wells Geothermal Area (Redirected from Salt Wells Area) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Salt Wells Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Future Plans 5 Exploration History 6 Well Field Description 7 Research and Development Activities 8 Technical Problems and Solutions 9 Geology of the Area 9.1 Regional Setting 9.2 Stratigraphy 9.3 Structure 10 Hydrothermal System 11 Heat Source 12 Geofluid Geochemistry 13 NEPA-Related Analyses (9) 14 Exploration Activities (28) 15 References Area Overview Geothermal Area Profile Location: Nevada Exploration Region: Northwest Basin and Range Geothermal Region GEA Development Phase: Operational"Operational" is not in the list of possible values (Phase I - Resource Procurement and Identification, Phase II - Resource Exploration and Confirmation, Phase III - Permitting and Initial Development, Phase IV - Resource Production and Power Plant Construction) for this property.

127

Mobile workstation for decontamination and decommissioning operations  

SciTech Connect

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.

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

1993-10-01T23:59:59.000Z

128

Kit systems for granulated decontamination formulations  

DOE Patents (OSTI)

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.

Tucker, Mark D. (Albuquerque, NM)

2010-07-06T23:59:59.000Z

129

A simplified model of decontamination by BWR steam suppression pools  

SciTech Connect

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.

Powers, D.A.

1997-05-01T23:59:59.000Z

130

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

SciTech Connect

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.

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

131

Ancient Salt Beds  

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

North Carolina School of Medicine. In examining fluid inclusions in the salt and solid halite crystals, scientists found abundant cellulose microfibers, estimated to be 250 million...

132

Inside Sea Salt | EMSL  

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

Sea salt particles are emitted into the atmosphere by the action of ocean waves and bubble bursting at the ocean surface. They are ubiquitous in the atmospheric environment....

133

Electrochemical Decontamination of Painted and Heavily Corroded Metals  

SciTech Connect

The radioactive metal wastes that are generated from nuclear fuel plants and radiochemical laboratories are mainly contaminated by the surface deposition of radioactive isotopes. There are presently several techniques used in removing surface contamination involving physical and chemical processes. However, there has been very little research done in the area of soiled, heavily oxidized, and painted metals. Researchers at Los Alamos National Laboratory have been developing electrochemical procedures for the decontamination of bare and painted metal objects. These methods have been found to be effective on highly corroded as well as relatively new metals. This study has been successful in decontaminating projectiles and shrapnel excavated during environmental restoration projects after 40+ years of exposure to the elements. Heavily corroded augers used in sampling activities throughout the area were also successfully decontaminated. This process has demonstrated its effectiveness and offers several advantages over the present metal decontamination practices of media blasting and chemical solvents. These advantages include the addition of no toxic or hazardous chemicals, low operating temperature and pressure, and easily scaleable equipment. It is in their future plans to use this process in the decontamination of gloveboxes destined for disposal as TRU waste.

Marczak, S.; Anderson, J.; Dziewinski, J.

1998-09-08T23:59:59.000Z

134

Technology needs for decommissioning and decontamination  

SciTech Connect

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.

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

1993-12-01T23:59:59.000Z

135

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

SciTech Connect

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

Not Available

1993-09-01T23:59:59.000Z

136

Mineral Salt: A Source of Costly Energy?  

Science Journals Connector (OSTI)

...required to pump salt water into a solution cavity...the flow of cooling water of a conventional or...con-siderable preliminary treatment. Os-motic flow through...process of in-verse electrodialysis, only the ions pass...nor extensive pre-treatment of the fluids (1...

W. GARY WILLIAMS

1979-01-26T23:59:59.000Z

137

Idaho Site Closes Out Decontamination and Decommissioning Project about  

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

Site Closes Out Decontamination and Decommissioning Project Site Closes Out Decontamination and Decommissioning Project about $440 Million under Cost Idaho Site Closes Out Decontamination and Decommissioning Project about $440 Million under Cost November 8, 2012 - 12:00pm Addthis Workers demolish the Test Area North Hot Shop Complex, shown here. Workers demolish the Test Area North Hot Shop Complex, shown here. Crews demolish CPP-601, a building used during used nuclear fuel reprocessing at the Idaho Nuclear Technology and Engineering Center. Crews demolish CPP-601, a building used during used nuclear fuel reprocessing at the Idaho Nuclear Technology and Engineering Center. The Engineering Test Reactor vessel is shown here removed, loaded and ready for transport to the on-site landfill. The Engineering Test Reactor vessel is shown here removed, loaded and ready

138

DOE Awards Contract for Decontamination & Decommissioning Project for the  

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

DOE Awards Contract for Decontamination & Decommissioning Project DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park April 29, 2011 - 12:00pm Addthis Media Contact Mike Koentop (865) 576-0885 www.oakridge.doe.gov Oak Ridge, Tenn. - As part of its ongoing commitment to cleaning up the legacy of the Cold War at sites across the weapons complex, the U.S. Department of Energy has awarded a contract for the remaining environmental cleanup at the East Tennessee Technology Park (ETTP) to URS | CH2M Oak Ridge, LLC. The $2.2 billion contract will complete cleanup and provide support functions at ETTP, while supporting local jobs and area small businesses. "Today's contract announcement means that we can continue to meet our

139

DOE Awards Contract for Decontamination & Decommissioning Project for the  

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

Decontamination & Decommissioning Project Decontamination & Decommissioning Project for the East Tennessee Technology Park DOE Awards Contract for Decontamination & Decommissioning Project for the East Tennessee Technology Park April 29, 2011 - 12:00pm Addthis Media Contact Mike Koentop (865) 576-0885 www.oakridge.doe.gov Oak Ridge, Tenn. - As part of its ongoing commitment to cleaning up the legacy of the Cold War at sites across the weapons complex, the U.S. Department of Energy has awarded a contract for the remaining environmental cleanup at the East Tennessee Technology Park (ETTP) to URS | CH2M Oak Ridge, LLC. The $2.2 billion contract will complete cleanup and provide support functions at ETTP, while supporting local jobs and area small businesses. "Today's contract announcement means that we can continue to meet our

140

SUBJECT: Statement of Clearance - Decontamination Op'erations;  

Office of Legacy Management (LM)

Statement of Clearance - Decontamination Op'erations; Statement of Clearance - Decontamination Op'erations; Raritan Arsenal TO: Comtnanding General U. S. Army Supply and Maintenance Command ,kTTN: iii-LSSM.-S" * 9T ;/ i-~'-~-.-y/"+,,y-- Washingto,n, D. C. 20315 ;l. Reference: ~Paragraph 5b, AR 405-90. : : 2. Forwarded for approval are a.Stateinent of Clearance afld supporting 'documents covering the decontamination of the Ammuhition Arca at Raritan Arsellal, Mctuchen, New Jersey. I I 3. Transl%ittal of the Statement of Clearance was deferred pend- iny, the removal of the scrap material from the Arsenal, referred to in pa'ragraph 6 of CMT 1 of the supporting documents. This action was completed 5 December 1963. i 4. The Statement-of Clearance and supporting documents 'Bre to be forwaided to District Engineer, New York District, 80 Lafayette Street,

Note: This page contains sample records for the topic "decontaminated salt solution" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Development of Molten-Salt Heat Trasfer Fluid Technology for...  

Office of Environmental Management (EM)

- ranged from 450C to 585C M easurement frequency: salt chemistry - 200 hours off-gas composition - 12 hours Innovat ive Technology Solut ions f or Sustainability ABENGOA...

142

Concrete decontamination by Electro-Hydraulic Scabbling (EHS)  

SciTech Connect

EHS is being developed for decontaminating concrete structures from radionuclides, organic substances, and hazardous metals. EHS involves the generation of powerful shock waves and intense cavitation by a strong pulsed electric discharge in a water layer at the concrete surface; high impulse pressure results in stresses which crack and peel off a concrete layer of controllable thickness. Scabbling produces contaminated debris of relatively small volume which can be easily removed, leaving clean bulk concrete. Objective of Phase I was to prove the technical feasibility of EH for controlled scabbling and decontamination of concrete. Phase I is complete.

NONE

1994-11-01T23:59:59.000Z

143

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

DOE Patents (OSTI)

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.

Silver, G.L.

1980-09-24T23:59:59.000Z

144

The results of HLW processing using zirconium salt of dibutyl phosphoric acid  

SciTech Connect

Available in abstract form only. Full text of publication follows: Zirconium salt of dibutyl-phosphoric acid (ZS HDBP) dissolved in a diluent, is a promising solvent for liquid HLW processing. The investigations carried out earlier showed that ZS HDBP can recover a series of radionuclides (TPE, RE, U, Pu, Np, Sr) and some other elements (Mo, Ca, Fe) from aqueous solutions. The possibility of TPE and RE effective recovery and separation into appropriate fractions with high purification from each other was demonstrated as well. The results of extraction tests in the mixer-settlers in the course of liquid HLW treatment in hot cells, using ZS HDBP (0.4 M HDBP and 0.044 M Zr) dissolved in 30% TBP are presented. 30 liters of the feed solution containing TPE, RE, Sr and Cs with the total specific activity of 520 MBq/L and acidity of 2 M HNO{sub 3} were processed using the two-cycle flowsheet. TPE and RE recovery with subsequent stripping was realized in the first cycle, while Sr was recovered and concentrated in the second cycle. Raffinate of the latter contained almost all Cs. The degree of TPE and RE recovery was 104, and that of Sr was {approx}10. Decontamination factor of TPE and RE from Cs and Sr was 104, and that of Sr from TPE and Cs was 103. So, ZS HDBP can be used for separation of long-lived radionuclides from HLW with respect to radio-toxic category of the process products. (authors)

Fedorov, Yury; Zilberman, Boris; Shmidt, Olga; Saprikin, Vladimir; Ryasantsev, Valery [V. G. Khlopin Radium Institute, 194021, 28, 2nd Murinsky pr., Saint-Petersburg (Russian Federation)

2007-07-01T23:59:59.000Z

145

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

SciTech Connect

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.

Elder, H.H.

2001-07-11T23:59:59.000Z

146

Technical Report: Contaminant Organic Complexes: Their structure and energetics in surface decontamination  

SciTech Connect

The Department of Energy has a goal of decontaminating an estimated 180,000 metric tons of metal wastes in various surplus facilities. Uranium (U) and other radioactive actinides and lanthanides are embedded within the mixed oxide structures of the passivity layers of corroded iron and steel. These toxic metals can be dissolved out of the surface layers by a naturally occurring bacterial siderophore called Desferrioxamine B (DFB). DFB is a trihydroxamate ligand with one amine (pK1 =10.89) and three hydroxamate groups (pK2 =9.70, pK3 =9.03, and pK4 =8.30), which chelates with metals through hydroxamate coordination. Complexation of DFB with U can be utilized in decontamination strategy of the passivity layers. Therefore, we have been studying reactions of uranyl U(VI) with zerovalent iron (Fe0) followed by dissolution by DFB. The objectives were to determine the structure and speciation of solution and solid phases of U and to assess the effectiveness of DFB in U dissolution.

Samuel J. Traina; Shankar Sharma

2007-04-22T23:59:59.000Z

147

EnergySolutions Inc | Open Energy Information  

Open Energy Info (EERE)

Salt Lake City, Utah Zip: 84101 Sector: Services Product: Utah-based international nuclear services company that provides services and solutions to the nuclear industry....

148

Laboratory simulation of salt dissolution during waste removal  

SciTech Connect

Laboratory experiments were performed to support the field demonstration of improved techniques for salt dissolution in waste tanks at the Savannah River Site. The tests were designed to investigate three density driven techniques for salt dissolution: (1) Drain-Add-Sit-Remove, (2) Modified Density Gradient, and (3) Continuous Salt Mining. Salt dissolution was observed to be a very rapid process as salt solutions with densities between 1.38-1.4 were frequently removed. Slower addition and removal rates and locating the outlet line at deeper levels below the top of the saltcake provided the best contact between the dissolution water and the saltcake. It was observed that dissolution with 1 M sodium hydroxide solution resulted in salt solutions that were within the current inhibitor requirements for the prevention of stress corrosion cracking. This result was independent of the density driven technique. However, if inhibited water (0.01 M sodium hydroxide and 0.011 M sodium nitrite) was utilized, the salt solutions were frequently outside the inhibitor requirements. Corrosion testing at conditions similar to the environments expected during waste removal was recommended.

Wiersma, B.J.; Parish, W.R.

1997-01-01T23:59:59.000Z

149

Thermal Stability of LiPF6 Salt and Li-ion Battery Electrolytes Containing LiPF6  

E-Print Network (OSTI)

Thermal Stability of LiPF 6 Salt and Li-ion Batterythermal stability of the neat LiPF 6 salt and of 1 molal solutions of LiPF 6 in prototypical Li-ion battery

Yang, Hui; Zhuang, Guorong V.; Ross Jr., Philip N.

2006-01-01T23:59:59.000Z

150

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

151

Advanced technologies for decontamination and conversion of scrap metal  

SciTech Connect

In October 1993, Manufacturing Sciences Corporation was awarded DOE contract DE-AC21-93MC30170 to develop and test recycling of radioactive scrap metal (RSM) to high value and intermediate and final product forms. This work was conducted to help solve the problems associated with decontamination and reuse of the diffusion plant barrier nickel and other radioactively contaminated scrap metals present in the diffusion plants. Options available for disposition of the nickel include decontamination and subsequent release or recycled product manufacture for restricted end use. Both of these options are evaluated during the course of this research effort. work during phase I of this project successfully demonstrated the ability to make stainless steel from barrier nickel feed. This paved the way for restricted end use products made from stainless steel. Also, after repeated trials and studies, the inducto-slag nickel decontamination process was eliminated as a suitable alternative. Electro-refining appeared to be a promising technology for decontamination of the diffusion plant barrier material. Goals for phase II included conducting experiments to facilitate the development of an electro-refining process to separate technetium from nickel. In parallel with those activities, phase II efforts were to include the development of the necessary processes to make useful products from radioactive scrap metal. Nickel from the diffusion plants as well as stainless steel and carbon steel could be used as feed material for these products.

MacNair, V.; Muth, T.; Shasteen, K.; Liby, A.; Hradil, G.; Mishra, B.

1996-12-31T23:59:59.000Z

152

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

153

Amine salts of nitroazoles  

DOE Patents (OSTI)

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.

Kienyin Lee; Stinecipher, M.M.

1993-10-26T23:59:59.000Z

154

Salt Selected (FINAL)  

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

WHY SALT WAS SELECTED AS A DISPOSAL MEDIUM WHY SALT WAS SELECTED AS A DISPOSAL MEDIUM Waste Isolation Pilot Plant U.S. Department Of Energy Government officials and scientists chose the Waste Isolation Pilot Plant (WIPP) site through a selection process that started in the 1950s. At that time, the National Academy of Sciences conducted a nationwide search for geological formations stable enough to contain radioactive wastes for thousands of years. In 1955, after extensive

155

A Dash of Salt  

E-Print Network (OSTI)

tx H2O | pg. 18 A Texas A&M researcher is assessing the impact of using moderately saline water for irrigating urban landscapes in West Texas and southern New Mexico. A DASH OF SALT Researcher assesses salinity impacts on grasses, trees... and shrubs A Dash of Salt Story by Danielle Supercinski { } tx H2O | pg. 19 ?The primary purpose of using moderately saline water for irrigation, including reclaimed water, is to conserve potable [drinkable] water,? said Dr. Seiichi Miyamoto, a...

Supercinski, Danielle

2006-01-01T23:59:59.000Z

156

Salt Wells Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Salt Wells Geothermal Area Salt Wells Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Salt Wells Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Future Plans 5 Exploration History 6 Well Field Description 7 Research and Development Activities 8 Technical Problems and Solutions 9 Geology of the Area 9.1 Regional Setting 9.2 Stratigraphy 9.3 Structure 10 Hydrothermal System 11 Heat Source 12 Geofluid Geochemistry 13 NEPA-Related Analyses (9) 14 Exploration Activities (28) 15 References Area Overview Geothermal Area Profile Location: Nevada Exploration Region: Northwest Basin and Range Geothermal Region GEA Development Phase: Operational"Operational" is not in the list of possible values (Phase I - Resource Procurement and Identification, Phase II - Resource Exploration and Confirmation, Phase III - Permitting and Initial Development, Phase IV - Resource Production and Power Plant Construction) for this property.

157

Brine flow in heated geologic salt.  

SciTech Connect

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.

Kuhlman, Kristopher L.; Malama, Bwalya

2013-03-01T23:59:59.000Z

158

Process for cesium decontamination and immobilization  

DOE Patents (OSTI)

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.

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

1989-01-01T23:59:59.000Z

159

Salt caverns for oil field waste disposal.  

SciTech Connect

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

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

2000-07-01T23:59:59.000Z

160

Water Research 38 (2004) 33313339 Testing a surface tension-based model to predict the salting  

E-Print Network (OSTI)

Water Research 38 (2004) 3331­3339 Testing a surface tension-based model to predict the salting out associated with transferring solutes from water to a salt solution to the difference in surface tensions likely reflects the inability of the simple surface tension model to account for all interactions among

Herbert, Bruce

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


161

Salt Creek Student Homepage  

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

Salt Creek Investigation Salt Creek Investigation</2> "Whales Dying in the Pacific Ocean" "Fish Dying in Lake Michigan" Recent headlines remind us of environmental problems near and far away. Scientists have been wondering if these problems could be due to the warmer temperatures this past spring and summer or could there be other reasons? Lack of rain and near drought conditions have forced many areas to restrict water use. We know from past history that pollution affects our drinking water and marine life. Remember what we read about Lake Erie and from reading A River Ran Wild by Lynne Cherry. There are many factors affecting the environment around us . . . even in Salt Creek which runs through our area. We may not be able to investigate the Pacific Ocean and Lake Michigan

162

Decontamination of the Plum Brook Reactor Facility Hot Cells  

SciTech Connect

The NASA Plum Brook Reactor Facility decommissioning project recently completed a major milestone with the successful decontamination of seven hot cells. The cells included thick concrete walls and leaded glass windows, manipulator arms, inter cell dividing walls, and roof slabs. There was also a significant amount of embedded conduit and piping that had to be cleaned and surveyed. Prior to work starting evaluation studies were performed to determine whether it was more cost effective to do this work using a full up removal approach (rip and ship) or to decontaminate the cells to below required clean up levels, leaving the bulk of the material in place. This paper looks at that decision process, how it was implemented, and the results of that effort including the huge volume of material that can now be used as fill during site restoration rather than being disposed of as LLRW. (authors)

Peecook, K.M. [NASA Glenn Research Center, Plum Brook Station, Sandusky, OH (United States)

2008-07-01T23:59:59.000Z

163

Environmental Assessment for decontamination and dismantlement, Pinellas Plant  

SciTech Connect

The US Department of Energy (DOE) has prepared an Environmental Assessment (EA) (DOE/EA-1092) of the proposed decontamination and dismantlement of the Pinellas Plant in Largo, Florida. Under the Decontamination and Dismantlement EA, the DOE proposes to clean up facilities, structures, and utilities; dismantle specific structures; and mitigate or eliminate any environmental impacts associated with the cleanup, dismantlement, and related activities. Related activities include utilization of specific areas by new tenants prior to full-scale cleanup. Based on the analyses in the EA, the DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act of 1969. Therefore, the preparation of an environmental impact statement is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

NONE

1995-06-01T23:59:59.000Z

164

Decontamination of an Analytical Laboratory Hot Cell Facility  

SciTech Connect

An Analytical Laboratory Hot Cell Facility at Argonne National Laboratory-West (ANL-W) had been in service for nearly thirty years. In order to comply with current DOE regulations governing such facilities and meet programmatic requirements, a major refurbishment effort was mandated. Due to the high levels of radiation and contamination within the cells, a decontamination effort was necessary to provide an environment that permitted workers to enter the cells to perform refurbishment activities without receiving high doses of radiation and to minimize the potential for the spread of contamination. State-of-the-art decontamination methods, as well as time-proven methods were utilized to minimize personnel exposure as well as maximize results.

Michelbacher, J.A.; Henslee, S.P.; Rosenberg, K.E.; Coleman, R.M.

1995-11-01T23:59:59.000Z

165

Laser-based characterization and decontamination of contaminated facilities  

SciTech Connect

This study examines the application of laser ablation to the characterization and decontamination of painted and unpainted concrete and metal surfaces that are typical of many facilities within the US Department of Energy complex. The utility of this promising technology is reviewed and the essential requirements for efficient ablation extracted. Recent data obtained on the ablation of painted steel surfaces and concrete are presented. The affects of beam irradiance, ablation speed and efficiency, and characteristics of the aerosol effluent are discussed. Characterization of the ablated components of the surface offers the ability of concurrent determination of the level of contamination. This concept can be applied online where the ablation endpoint can be determined. A conceptual system for the characterization and decontamination of surfaces is proposed.

Leong, K.H.; Hunter, B.V.; Grace, J.E.; Pellin, M.J. [Argonne National Lab., IL (United States); Leidich, H.F.; Kugler, T.R. [Lumonics Corp., Livonia, MI (United States)

1996-12-31T23:59:59.000Z

166

Decontamination and Decommissioning activities photobriefing book FY 1997  

SciTech Connect

The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

NONE

1998-04-01T23:59:59.000Z

167

Assessment of strippable coatings for decontamination and decommissioning  

SciTech Connect

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.

Ebadian, M.A.

1998-01-01T23:59:59.000Z

168

Decontamination of Battelle-Columbus' Plutonium Facility. Final report  

SciTech Connect

The Plutonium Laboratory, owned and operated by Battelle Memorial Institute's Columbus Division, was located in Battelle's Nuclear Sciences area near West Jefferson, Ohio, approximately 17 miles west of Columbus, Ohio. Originally built in 1960 for plutonium research and processing, the Plutonium Laboratory was enlarged in 1964 and again in 1967. With the termination of the Advanced Fuel Program in March, 1977, the decision was made to decommission the Plutonium Laboratory and to decontaminate the building for unrestricted use. Decontamination procedures began in January, 1978. All items which had come into contact with radioactivity from the plutonium operations were cleaned or disposed of through prescribed channels, maintaining procedures to ensure that D and D operations would pose no risk to the public, the environment, or the workers. The entire program was conducted under the cognizance of DOE's Chicago Operations Office. The building which housed the Plutonium Laboratory has now been decontaminated to levels allowing it to house ordinary laboratory and office operations. A ''Finding of No Significant Impact'' (FNSI) was issued in May, 1980.

Rudolph, A.; Kirsch, G.; Toy, H.L. (comps.)

1984-11-12T23:59:59.000Z

169

Ammoniated salt heat pump  

SciTech Connect

A thermochemical heat pump/energy storage system using liquid ammoniate salts is described. The system, which can be used for space heating or cooling, provides energy storage for both functions. The bulk of the energy is stored as chemical energy and thus can be stored indefinitely. The system is well suited to use with a solar energy source or industrial waste heat.

Haas, W.R.; Jaeger, F.J.; Giordano, T.J.

1981-01-01T23:59:59.000Z

170

Ventilation System to Improve Savannah River Site's Liquid Waste...  

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

A process vessel ventilation system is being installed in a facility that houses two tanks that will process decontaminated salt solution at the Saltstone Production Facility. A...

171

Corrosion evaluation of the PNS CITROX process for chemical decontamination of BWR structural materials  

SciTech Connect

The effects of PNS Citrox decontamination on the corrosion and intergranular stress corrosion cracking (IGSCC) of sensitized Type 304 stainless steel and Alloy 600 were assessed. Evaluations involved decontaminated surface morphology examination, as well as constant extension rate tensile (CERT) testing in BWR water. Quenched and tempered low alloy steel was also included for evaluation of general corrosion. The Pacific Nuclear Services (PNS) Citrox decontamination included laboratory one- and three-step processes as well as an in-plant three- step Citrox process applied at the Vermont Yankee Power Plant. For the laboratory Citrox decontamination, intergranular attack (IGA) up to 3.2 mils in depth was observed in the sensitized Type 304 stainless steel. No IGA occurred in the laboratory decontaminated Alloy 600. On the other hand, no IGA was found in sensitized Type 304 stainless steel for the in-plant Citrox decontamination, but shallow and extremely narrow IGA was observed in the Alloy 600. Results of CERT stress corrosion cracking tests indicated that sensitized Type 304 stainless steel exposed to the three-step laboratory Citrox decontamination suffered degradation of IGSCC resistance. However, no degradation of IGSCC resistance was observed for the steel exposed to the one-step laboratory process or to PNS Citrox decontamination at the Vermont Yankee Plant. Moderate general corrosion in the range of one to three mils per decontamination cycle was observed in quenched and tempered low alloy steel. However, very low general corrosion was found in sensitized Type 304 stainless steel and Alloy 600.

Wang, M.T.

1986-08-01T23:59:59.000Z

172

Exposure to Tritiated Moisture and Decontamination of Components for ITER Remote Maintenance Equipment  

Science Journals Connector (OSTI)

Decontamination and Waste / Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001

Takeshi Higashijima; Kenjiro Obara; Kiyoshi Shibanuma; Koichi Koizumi; Kazuhiro Kobayashi; Yasuhisa Oya; Wataru Shu; Takumi Hayashi; Masataka Nishi

173

Simulation of Atmospheric Pressure Non-Thermal Plasma Discharges for Surface Decontamination Applications  

Science Journals Connector (OSTI)

Numerical simulations are conducted to characterize atmospheric pressure plasma discharges for surface decontamination applications. A self ... dimensional hybrid model is developed to simulate the atmospheric pr...

T. Farouk; B. Farouk; A. Gutsol; A. Fridman

2008-01-01T23:59:59.000Z

174

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

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

175

DEGRADED TBP SOLVENT REGENERATION TECHNOLOGY USING BUTYLAMINE AS A SOLVENT WASHING TO REDUCE SOLID SALT WASTE  

SciTech Connect

Normal butylamine compounds are studied as salt-free wash reagents for degraded solvent used in PUREX process in spent fuel reprocessing. The solvent wash tests were carried out with two types of butylamine compounds, n-butylamine oxalate and n-butylamine bicarbonate, by counter-current mode using a small size mixer-settler composed of two 4-stage wash steps. Di-n-butyl phosphoric acid (HDBP), the main degradation product from TBP, was removed from real degraded solvent with decontamination factor of 2.5 {approx} 7.9. The study on electrolytic decomposition of butylamine compounds was also conducted for waste treatment.

Asakura, T.; Itoh, Y.; Hotoku, S.; Morita, Y.; Uchiyama, G.

2003-02-27T23:59:59.000Z

176

Decontamination Process of Internal Part Pipes - 13442  

SciTech Connect

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)

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

177

Salt Creek Scenario  

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

Scenario Scenario HELP Index Summary Scenario References Student Pages Two branches of Salt Creek run through the city of Rolling Meadows, Illinois, not far from our school. Five members of our team of eighth grade teachers from different subject areas (science, language arts, bilingual education and special education), decided to develop an interdisciplinary study of Salt Creek as a way of giving our students authentic experiences in environmental studies. The unit begins when students enter school in August, running through the third week of September, and resuming for three weeks in October. Extension activities based on using the data gathered at the creek continue throughout the school year, culminating in a presentation at a city council meeting in the spring.

178

ACTION DESCRIPTION MEMORANDUM PROPOSED DECONTAMINATION OF THREE BUILDINGS AT THE  

Office of Legacy Management (LM)

ACTION DESCRIPTION MEMORANDUM ACTION DESCRIPTION MEMORANDUM PROPOSED DECONTAMINATION OF THREE BUILDINGS AT THE UNIVERSITY OF CHICAGO CONTAMINATED AS A RESULT OF PREVIOUS MED/AEC ACTIVITIES Prepared by Environmental Research Division Argonne National Laboratory Argonne, Illinois December 1983 Prepared for U.S. Department of Energy Oak Ridge Operations Technical Services Division Oak Ridge, Tennessee II-39 CONTENTS Page Summary of Proposed Action ....................... 1 Setting . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. 1 Background and Need for Action ..................... 2 Proposed Remedial Action ........................ 3 Potential Issues ................... ......... 4 Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. 6 Tables. ............ .................. 7 References ................... ............ 8

179

Cost Savings through Innovation in Decontamination, Decommissioning, and Dismantlement  

SciTech Connect

The United States Department of Energy (DOE) continually seeks safer and more cost effective technologies for the decontamination and decommissioning (D&D) of nuclear facilities. The Deactivation and Decommissioning Focus Area (DDFA) of the DOE's Office of Science and Technology (OST) sponsored large-scale demonstration and deployment projects (LSDDPs) to help bring new technologies into the D&D programs. The Idaho National Engineering and Environmental Laboratory (INEEL) LSDDP generated a list of needs defining specific problems where improved technologies could be incorporated into ongoing D&D tasks. The needs fell into 5 major categories--characterization, dismantlement, safety, material dispositioning, and decontamination. Technologies were carefully selected that provide a large benefit for a small investment. The technologies must provide significant improvements in cost, safety, radiation exposure, waste volume reduction, or schedule savings and widely applicable throughout the DOE complex. The LSDDP project provided training for the new technologies and worked with technology suppliers to resolve any questions that arose. Since 1998, 26 technologies have been demonstrated or deployed through the LSDDP for the D&D program at the INEEL. Of the 26 demonstrated and deployed technologies, 14 were in characterization, 3 were in decontamination, 4 were in dismantlement, 3 were in safety, and 2 were in material dispositioning. To promote the use of these technologies at other sites within the DOE complex, the LSDDP team published fact sheets, videos, technology summary reports, articles in INEEL star newspaper, posters, and maintained an internet home page on the project. As a result, additional deployments have taken place at the Hanford, Mound, Fernald, Oak Ridge, Ashtabula, and West Valley. Eight of the 26 technologies evaluated were developed in foreign countries. The technologies demonstrated have been shown to be faster, less expensive, and/or safer. The technologies evaluated through the LSDDP have provided improvements in the following D&D areas: robotic underwater characterization of fuel storage pools, characterization of scrap metal for recycle, PCB and RCRA metals analysis in soil, water, paint, or sludge, subsurface characterization, personnel safety, waste disposal, scaffolding use, and remote radiation characterization of buildings and soil. It is estimated that the technologies demonstrated and deployed through this program will save more than $50 million dollars over the next 10 years at the INEEL alone. Of the $50 million estimated dollars saved, about 75% of the savings will come from characterization technologies, 11% from technologies associated with material dispositioning, 10% are associated with dismantlement technologies and the balance split between safety and decontamination.

Neal A. Yancey

2003-02-27T23:59:59.000Z

180

Decontamination of the populated areas contaminated as a result of nuclear accident  

SciTech Connect

Decontamination tests on urban surfaces contaminated by the Chernobyl accident have shown that Chernobyl fallout behaves differently from fallout from nuclear weapons tests and contamination on surfaces in nuclear power plant. The effectiveness of various decontamination compositions for removing Chernobyl fallout from urban surfaces and machinery was determined in a series of laboratory experiments and field trials.

Voronik, N.I.; Shatilo, N.N.; Davydov, Y.P. [Institute of Radioecological Problems, Minsk-Sosny (Belarus)

1996-12-31T23:59:59.000Z

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


181

An extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear  

E-Print Network (OSTI)

An extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear Blignyabcd Nuclear activities generate radioactive elements which require processes for their decontamination of an extremophile autotrophic eukaryote, Coccomyxa actinabiotis nov. sp., that we isolated from a nuclear facility

Boyer, Edmond

182

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

E-Print Network (OSTI)

of the United States and thereby reducing overall energy consumption. The purpose of this paper is to describeDecontamination 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

Brookhaven National Laboratory

183

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

SciTech Connect

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.

NONE

1996-09-01T23:59:59.000Z

184

Testing, expanding and implementing pollution prevention tools for environmental restoration and decontamination and decommissioning  

SciTech Connect

Pollution Prevention (P2) programs and projects within the DOE Environmental Restoration (ER) and Decontamination and Decommissioning (D and D) Programs have been independently developed and implemented at various sites. As a result, unique, innovative solutions used at one site may not be known to other sites, and other sites may continue to duplicate efforts to develop and implement similar solutions. Several DOE Program offices have funded the development of tools to assist ER/D and D P2 projects. To realize the full value of these tools, they need to be evaluated and publicized to field sites. To address these needs and concerns, Sandia National Laboratory (SNL/NM), Los Alamos National Laboratory (LANL), and the Oak Ridge Field Office (DOE-OR) have teamed to pilot test DOE training and tracking tools; transfer common P2 analyses between sites, and evaluate and expand P2 tools and methodologies. The project is supported by FY 98 DOE Pollution Prevention Complex-Wide Project Funds. This paper presents the preliminary results for each of the following project modules: Training, Waste Tracking Pilot, Information Exchange, Evaluate P2 Tools for ER/D and D, Field Test of P2 Tools; and DOE Information Exchange.

Roybal, J.A. [Sandia National Lab., Albuquerque, NM (United States); McInroy, D. [Los Alamos National Lab., NM (United States); Watson, J. [GTS Duratek, Albuquerque, NM (United States); Mizner, J. [ICF Kaiser, Albuquerque, NM (United States)

1998-06-01T23:59:59.000Z

185

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

SciTech Connect

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.

NONE

1997-12-31T23:59:59.000Z

186

Decontamination and decommissioning surveillance and maintenance report for FY 1991  

SciTech Connect

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.

Not Available

1991-12-01T23:59:59.000Z

187

Advanced technologies for decontamination and conversion of scrap metals  

SciTech Connect

Recycle of radioactive scrap metals (RSM) from decommissioning of DOE uranium enrichment and nuclear weapons manufacturing facilities is mandatory to recapture the value of these metals and avoid the high cost of disposal by burial. The scrap metals conversion project detailed below focuses on the contaminated nickel associated with the gaseous diffusion plants. Stainless steel can be produced in MSC`s vacuum induction melting process (VIM) to the S30400 specification using nickel as an alloy constituent. Further the case alloy can be rolled in MSC`s rolling mill to the mechanical property specification for S30400 demonstrating the capability to manufacture the contaminated nickel into valuable end products at a facility licensed to handle radioactive materials. Bulk removal of Technetium from scrap nickel is theoretically possible in a reasonable length of time with the high calcium fluoride flux, however the need for the high temperature creates a practical problem due to flux volatility. Bulk decontamination is possible and perhaps more desirable if nickel is alloyed with copper to lower the melting point of the alloy allowing the use of the high calcium fluoride flux. Slag decontamination processes have been suggested which have been proven technically viable at the Colorado School of Mines.

Muth, T.R. [Manufacturing Sciences Corp., Oak Ridge, TN (United States); Moore, J.; Olson, D.; Mishra, B. [Colorado School of Mines, Golden, CO (United States)

1994-12-31T23:59:59.000Z

188

salt lake city.cdr  

Office of Legacy Management (LM)

Locations of the Salt Lake City Processing and Disposal Sites Locations of the Salt Lake City Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site at Salt Lake City, Utah. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Salt Lake City, Utah, Processing and Disposal Sites Site Descriptions and History Regulatory Setting The former Salt Lake City processing site is located about 4 miles south-southwest of the center of Salt Lake City, Utah, at 3300 South and Interstate 15. The Vitro Chemical Company processed uranium and vanadium ore at the site from 1951 until 1968. Milling operations conducted at the processing site created radioactive tailings, a predominantly sandy material.

189

Molten salt lithium cells  

DOE Patents (OSTI)

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.

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

1980-07-18T23:59:59.000Z

190

Molten salt lithium cells  

DOE Patents (OSTI)

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).

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

1982-02-09T23:59:59.000Z

191

Batteries using molten salt electrolyte  

DOE Patents (OSTI)

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.

Guidotti, Ronald A. (Albuquerque, NM)

2003-04-08T23:59:59.000Z

192

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

E-Print Network (OSTI)

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

Fayer, Michael D.

193

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

SciTech Connect

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.

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

1996-11-15T23:59:59.000Z

194

Plant salt-tolerance mechanisms  

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.

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

2014-06-01T23:59:59.000Z

195

RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE  

Office of Legacy Management (LM)

h h ' . * ' 1. MI). q-8 RADIOLOGICAL EVALUATION OF DECONTAMINATION DEBRIS LOCATED AT THE FUTURA CHEMICAL COMPANY FACILITY 9200 LATTY AVENUE HAZELWOOD, MISSOURI L.W. Cole J.D. Berger W.O. Helton B.M. Putnam T.J. Sowell C.F. Weaver R.D. Condra September 9, 1981 Work performed by Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37830 Under Interagency Agreement DOE No. 40-770-80 NRC Fin. No. A-9093-0 Between the U.S. Nuclear Regulatory Commission and the Department of Energy I_--___- ". TABLE OF CONTENTS Page List of Figures. . . . . . . . . . . . . . . . . . . . . . ii List of Tables . . . . . . . . . . . . . . . . . . . . . . iii Introduction . . . . . . . . . . . . . . . . . . . . . . . 1.

196

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

SciTech Connect

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.

NONE

1996-03-30T23:59:59.000Z

197

REVIEW SHEET 3 (1) A tank contains 100 gallon of salt water which ...  

E-Print Network (OSTI)

solution of 2lbs of salt per gallon enters the tank at a rate of 3 gallons per minute while a flow of fresh water runs into the tank at a rate of 5 gallons per minute.

2014-04-30T23:59:59.000Z

198

Independent Oversight Assessment, Salt Waste Processing Facility...  

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

199

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

SciTech Connect

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.

Hovorka, Susan D.; Nava, Robin

2000-06-13T23:59:59.000Z

200

EIS-0082-S2: Savannah River Site Salt Processing, Savannah River Site,  

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

082-S2: Savannah River Site Salt Processing, Savannah River 082-S2: Savannah River Site Salt Processing, Savannah River Site, Aiken, South Carolina EIS-0082-S2: Savannah River Site Salt Processing, Savannah River Site, Aiken, South Carolina SUMMARY 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 now stored in underground tanks at the Savannah River Site (SRS) near Aiken, South Carolina. The high-activity fraction of the high-level waste (HLW) salt solution would then be vitrified in the Defense Waste Processing Facility (DWPF) and stored until it could be disposed of as HLW in a geologic repository. The low activity fraction would be disposed of as low-level waste (saltstone)

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


201

Math 315 Exam #3 Solutions in Brief 1. (20 points) Two tanks contain 10 liters of water each. Initially tank  

E-Print Network (OSTI)

Math 315 Exam #3 Solutions in Brief 1. (20 points) Two tanks contain 10 liters of water each. Initially tank 1 contains no salt and tank 2 contains 246 grams of salt. Water con- taining 50 grams of salt per liter is added to tank 1 at the rate 2 liters/minute. Water containing no salt is added to tank 2

202

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

E-Print Network (OSTI)

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...

Barnhart, Eric Thomas

2012-06-07T23:59:59.000Z

203

Decontamination of VX Surrogate Malathion by Atmospheric Pressure Radio-frequency Plasma Jet  

Science Journals Connector (OSTI)

Decontamination of the VX surrogate (malathion) by the atmospheric pressure radio-frequency plasma jet (APPJ) was investigated. Optical emission ... the neutral gas temperature. The effects of RF input power and ...

Wen-Chao Zhu; Bai-Rong Wang; Hai-Ling Xi…

2010-06-01T23:59:59.000Z

204

Lasers and high-energy light as a decontamination tool for nuclear applications  

SciTech Connect

Light-aided decontamination (LAD) removal of paint and concrete layers is competitive with sand blasting rates. Remote operations, up to 137 m (450 ft), and lower waste volumes can provide cost, safety, and environmental advantages for nuclear facilities.

Flesher, D.J.

1993-12-01T23:59:59.000Z

205

NE-24 R&D Decontamination Projects Under the Formerly Utilized...  

Office of Legacy Management (LM)

for each project should be to decontaminate the vicinity properties and store the waste on the site pending long-term disposal. Control measures should be taken on the site...

206

Effect of acid decontamination on the microbiological and sensory characteristics of beef strip loin steaks  

E-Print Network (OSTI)

EFFECT OF ACID DECONTAMINATION ON THE MICROBIOLOGICAL AND SENSORY CHARACTERISTICS OF BEEF STRIP LOIN STEAKS A Thesis by Z IS CA DIXON Submitted to the Graduate College of Texas A & M University in partial fullfillment of the requirement... for the degree of MASTER OF SCIENCE August 19B7 Major Subject: Food Scienc and Technology / / / EFFECT OF ACID DECONTAMINATION ON THE MICROBIOLOGICAL AND SENSORY CHARACTERISTICS OF BEEF STRIP LOIN STEAKS A Thesis by ZISCA DIXON Approved as to style...

Dixon, Zisca

2012-06-07T23:59:59.000Z

207

1-Dodecane-sulfonic-acid-sodium-salt(LAS) assisted hydrothermal synthesis of Cd{sub x}Zn{sub 1-x}S solid solution as efficient photocatalysts under visible light irradiation  

SciTech Connect

With anionic surfactant LAS assisted, series of zinc cadmium sulfide semiconductor photocatalysts were synthesized by hydrothermal method. These products were characterized by X-ray diffraction (XRD), UV-Vis absorption spectra (UV-Vis) and scanning electron microscopy (FESEM). The photocatalytic activities of as-prepared samples were evaluated by photocatalytic hydrogen production from water under visible-light irradiation. The best synthesis parameters are: Composition 0.9:0.1 (Cd:Zn molar ratio), Temperature 160 deg. C, Hydrothermal Time 48 Hour, LAS Concentration 1.7 mmol/L, the maximum visible-light-catalytic hydrogen production rate is 161.25 {mu}mol/h (lambda>430 nm) which is higher than those of by coprecipitation method. The experiment results indicate that surfactant assisted hydrothermal method is an effective way to get highly active CdZnS solid solution photocatalyst.

Jia, B.; Guo, L. J. [State Key Laboratory of Multiphase Flow in power Engineering, Xi'an Jiaotong University (China)

2010-03-01T23:59:59.000Z

208

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

SciTech Connect

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.

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

1985-08-01T23:59:59.000Z

209

Results From The Salt Disposition Project Next Generation Solvent Demonstration Plan  

SciTech Connect

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.

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

2014-04-02T23:59:59.000Z

210

Solvent wash solution  

DOE Patents (OSTI)

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.

Neace, J.C.

1984-03-13T23:59:59.000Z

211

LIFE Materails: Molten-Salt Fuels Volume 8  

SciTech Connect

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.

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

212

Electromagnetic mixed waste processing system for asbestos decontamination  

SciTech Connect

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 US nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCBs, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay, and fission products of DOE operations. To allow disposal, the asbestos must be converted chemically, followed 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. An attempt was made to apply techniques that have already proved successful in the mining, oil, and metals processing industries to the development of a multi-stage process to remove and separate hazardous chemical radioactive materials from asbestos. This process uses three methods: ABCOV chemicals which converts the asbestos to a sanitary waste; dielectric heating to volatilize the organic materials; and electrochemical processing for the removal of heavy metals, RCRA wastes and radionuclides. This process will result in the destruction of over 99% of the asbestos; limit radioactive metal contamination to 0.2 Bq alpha per gram and 1 Bq beta and gamma per gram; reduce hazardous organics to levels compatible with current EPA policy for RCRA delisting; and achieve TCLP limits for all solidified waste.

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

1994-12-31T23:59:59.000Z

213

Disposal of soluble salt waste from coal gasification  

SciTech Connect

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

McKnight, C.E.

1980-06-01T23:59:59.000Z

214

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

SciTech Connect

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)

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

215

Freshwater fish in salt water  

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

Freshwater fish in salt water Freshwater fish in salt water Name: Shannon Location: N/A Country: N/A Date: N/A Question: What would actually happen if a fresh water fish had to live in salt water? Replies: For most fish, they would die. But some, like eels and salmon, can move freely between the two at certain stages of their lives. To do this they have special mechanisms of excretion and absorption of salt and water. --ProfBill If you put a freshwater fish into saltwater, most fish would lose weight (from losing water from its body) and eventually die. Approximately 2% of all 21000 species of fish actually move from freshwater to saltwater or from salt to fresh at some point in their lives, the move would kill any other fish. But even with these special varieties of fish, the move must be gradual so their bodies can adjust, or they too, will die from the change. If you want to learn more about why the freshwater fish will lose water, (or why a saltwater fish in freshwater would gain water), look up the words "diffusion" and "osmosis"

216

Fracture and Healing of Rock Salt Related to Salt Caverns  

SciTech Connect

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.

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

1999-03-01T23:59:59.000Z

217

MODELING OF A NOVEL SOLUTION POTASH MINING PROCESS Sergio Almada, Harvey Haugen  

E-Print Network (OSTI)

by drilling followed by a number of steps to develop a solution mining cavern. Water is injected to dissolve a sump area within the salt at the base of the solution mining cavern. The sump allows insoluble materials settle within the cavern to avoid affecting the solution mining process and the dissolved salt can

218

Preliminary standard review guide for Environmental Restoration/Decontamination and Decommissioning safety analyses  

SciTech Connect

The review guide is based on the shared experiences, approaches, and philosophies of the Environmental Restoration/Decontamination and Decommissioning (ER/D&D) subgroup members. It is presented in the form of a review guide to maximize the benefit to both the safety analyses practitioner and reviewer. The guide focuses on those challenges that tend to be unique to ER/D&D cleanup activities. Some of these experiences, approaches, and philosophies may find application or be beneficial to a broader spectrum of activities such as terminal cleanout or even new operations. Challenges unique to ER/D&D activities include (1) consent agreements requiring activity startup on designated dates; (2) the increased uncertainty of specific hazards; and (3) the highly variable activities covered under the broad category of ER/D&D. These unique challenges are in addition to the challenges encountered in all activities; e.g., new and changing requirements and multiple interpretations. The experiences in approaches, methods, and solutions to the challenges are documented from the practitioner and reviewer`s perspective, thereby providing the viewpoints on why a direction was taken and the concerns expressed. Site cleanup consent agreements with predetermined dates for restoration activity startup add the dimension of imposed punitive actions for failure to meet the date. Approval of the safety analysis is a prerequisite to startup. Actions that increase expediency are (1) assuring activity safety; (2) documenting that assurance; and (3) acquiring the necessary approvals. These actions increase the timeliness of startup and decrease the potential for punitive action. Improvement in expediency has been achieved by using safety analysis techniques to provide input to the line management decision process rather than as a review of line management decisions. Expediency is also improved by sharing the safety input and resultant decisions with reviewers and regulators.

Ellingson, D.R.

1993-06-01T23:59:59.000Z

219

Next Generation Non-particulate Dry Nonwoven Pad for Chemical Warfare Agent Decontamination  

SciTech Connect

New, non-particulate decontamination materials promise to reduce both military and civilian casualties by enabling individuals to decontaminate themselves and their equipment within minutes of exposure to chemical warfare agents or other toxic materials. One of the most promising new materials has been developed using a needlepunching nonwoven process to construct a novel and non-particulate composite fabric of multiple layers, including an inner layer of activated carbon fabric, which is well-suited for the decontamination of both personnel and equipment. This paper describes the development of a composite nonwoven pad and compares efficacy test results for this pad with results from testing other decontamination systems. The efficacy of the dry nonwoven fabric pad was demonstrated specifically for decontamination of the chemical warfare blister agent bis(2-chloroethyl)sulfide (H or sulfur mustard). GC/MS results indicate that the composite fabric was capable of significantly reducing the vapor hazard from mustard liquid absorbed into the nonwoven dry fabric pad. The mustard adsorption efficiency of the nonwoven pad was significantly higher than particulate activated carbon (p=0.041) and was similar to the currently fielded US military M291 kit (p=0.952). The nonwoven pad has several advantages over other materials, especially its non-particulate, yet flexible, construction. This composite fabric was also shown to be chemically compatible with potential toxic and hazardous liquids, which span a range of hydrophilic and hydrophobic chemicals, including a concentrated acid, an organic solvent and a mild oxidant, bleach.

Ramkumar, S S; Love, A; Sata, U R; Koester, C J; Smith, W J; Keating, G A; Hobbs, L; Cox, S B; Lagna, W M; Kendall, R J

2008-05-01T23:59:59.000Z

220

Why Sequence Great Salt Lake?  

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

Great Salt Lake? Great Salt Lake? On average, the Great Salt Lake is four times saltier than the ocean and also has heavy metals, high concentrations of sulfur and petroleum seeps. In spite of all this, the lake is the saltiest body of water to support life. The lake hosts brine shrimp, algae and a diverse array of microbes, not to mention the roughly 5 million birds that migrate there annually. The secret to these microbes' ability to survive under such harsh conditions might be revealed in their genes. Researchers expect the genetic data will provide insight into how the microorganisms tolerate pollutants such as sulfur and detoxify pollutants such as sulfur and heavy metals like mercury. The information could then be used to develop bioremediation techniques. Researchers also expect that sequencing microorganisms sampled

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


221

EM Gains Insight from Germany on Salt-Based Repositories | Department of  

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

Gains Insight from Germany on Salt-Based Repositories Gains Insight from Germany on Salt-Based Repositories EM Gains Insight from Germany on Salt-Based Repositories December 14, 2011 - 12:00pm Addthis Participants in the workshops in Germany toured Asse II, one of Germany’s two salt-based repositories, to gain insights into that facility’s technical challenges and proposed solutions. Pictured, left to right, are an Asse II employee, Bernhard Kienzler of the Karlsruhe Institute of Technology, CBFO Chief Scientist Roger Nelson, CBFO International Programs Manager Dr. Abraham Van Luik, and Andrew Wolfsberg, Acting Deputy Division Leader for Earth and Environmental Sciences at Los Alamos National Laboratory. Participants in the workshops in Germany toured Asse II, one of Germany's two salt-based repositories, to gain insights into that facility's

222

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

SciTech Connect

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

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

1997-10-01T23:59:59.000Z

223

Mobile worksystems for decontamination and decommissioning operations. Final report  

SciTech Connect

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.

NONE

1997-02-01T23:59:59.000Z

224

E-Print Network 3.0 - aqueous nitrate solutions Sample Search...  

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

Biology and Medicine 23 Evaluation for Biological Reduction of Nitrate and Perchlorate in Brine Water Using Summary: in high salt solution. One culture was capable of reducing up...

225

Salt Lake Community College | .EDUconnections  

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

SLCC Partners with DOE's Rocky Mountain Solar Training Program This program is a joint partnership between DOE's Solar Energy Technogies Program, Salt Lake Community College, Solar Energy International, and the Utah Solar Energy Association that works to accelerate use of solar electric technologies, training and facilities at community and technical college solar training programs within a 15 western United States region. DOE Solar Instructor Training Network Salt Lake City, Utah DOE Applauds SLCC's Science and Technical Programs Architectural Technology Biology Biotechnology Biomanufacturing Chemistry Computer Science Electric Sector Training Energy Management Engineering Geographic Information Sciences Geosciences InnovaBio Manufacturing & Mechanical Engineering Technology

226

NE-24 R&D Decontamination Projects Under the Formerly Utilized Sites Remedial  

Office of Legacy Management (LM)

" _ ,' ,:.' : " _ ,' ,:.' : NE-24 R&D Decontamination Projects Under the Formerly Utilized Sites Remedial Action Program (FUSRAP) '. * * ,~~'.'J.' L.aGrone, Manager Oak Ridge Operations O fffce As a result of the House-Senate Conference Report and the Energy and W a ter Appropriations Act for FY 1984, and based on the data in the attached reports indicating radioactive contamination In excess of acceptable guidelines, the sites listed In the attachment and their respectfve vicinity properties (contaminated with radioactive materials from these sites) are being designated as decontamination research and development projects under the FUSRAP. Each site and the associated vicinity properties should be treated as a separate project. . . -_ The objectjve of each project is to decontaminate the vicinity properties

227

Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996  

SciTech Connect

OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D&D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D&D activities beginning in 1997.

None

1997-05-06T23:59:59.000Z

228

Thermal Stability Studies of Candidate Decontamination Agents for Hanford’s Plutonium Finishing Plant Plutonium-Contaminated Gloveboxes  

SciTech Connect

This report provides the results of PNNL's and Fluor's studies of the thermal stabilities of potential wastes arising from decontamination of Hanford's Plutonium Finishing Plant's plutonium contaminated gloveboxes. The candidate wastes arising from the decontamination technologies ceric nitrate/nitric acid, RadPro, Glygel, and Aspigel.

Scheele, Randall D.; Cooper, Thurman D.; Jones, Susan A.; Ewalt, John R.; Compton, James A.; Trent, Donald S.; Edwards, Matthew K.; Kozelisky, Anne E.; Scott, Paul A.; Minette, Michael J.

2005-09-29T23:59:59.000Z

229

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

E-Print Network (OSTI)

Sediment Decontamination For Navigational And Environmental Restoration In NY/NJ Harbor ­ Case, Arlington, VA 22230 Sediments in the NY/NJ Harbor are widely contaminated with toxic organic and inorganic compounds. Decontamination of these sediments is one tool that can be used to cope with the problems posed

Brookhaven National Laboratory

230

Preliminary design and estimate of capital and operating costs for a production scale application of laser decontamination technology  

SciTech Connect

The application of laser ablation technology to the decontamination of radioactive metals, particularly the surfaces of equipment, is discussed. Included is information related to the design, capital and operating costs, and effectiveness of laser ablation technology, based on commercial excimer and Nd:YAG lasers, for the decontamination of production scale equipment.

Pang, Ho-ming; Edelson, M.C.

1994-08-06T23:59:59.000Z

231

ENVIRONMENTAL MANAGEMENT SCIENCE PROGRAM RESEARCH PROJECTS TO IMPROVE DECONTAMINATION AND DECOMMISIONING OF U.S. DEPARTMENT OF ENERGY FACILITIES  

SciTech Connect

This paper describes fourteen basic science projects aimed at solving decontamination and decommissioning (D&D) problems within the U.S. Department of Energy (DOE). Funded by the Environmental Science Management Program (EMSP), these research projects address D&D problems where basic science is needed to expand knowledge and develop solutions to help DOE meet its cleanup milestones. EMSP uses directed solicitations targeted at identified Environmental Management (EM) needs to ensure that research results are directly applicable to DOE's EM problems. The program then helps transition the projects from basic to applied research by identifying end-users and coordinating proof-of-principle field tests. EMSP recently funded fourteen D&D research projects through the directed solicitation process. These research projects will be discussed, including description, current status, and potential impact. Through targeted research and proof-of-principle tests, it is hoped that EMSP's fourteen D&D basic research projects will directly impact and provide solutions to DOE's D&D problems.

Phillips, Ann Marie

2003-02-27T23:59:59.000Z

232

Salt dome discoveries mounting in Mississippi  

SciTech Connect

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.

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

1996-06-17T23:59:59.000Z

233

Evaporation-driven growth of large crystallized salt structures in a porous medium  

Science Journals Connector (OSTI)

Subflorescence refers to crystallized salt structures that form inside a porous medium. We report a drying experiment revealing major development of subflorescence in the dry region of the porous medium away from the liquid zone. Using a combination of image analyses and numerical computations, we show that the growth is directly correlated to the evaporation flux distribution along the boundary of the growing salt structure. This indicates that the salt is transported into the domain occupied by the salt structure in the porous medium up to the structure periphery, where salt deposition takes place. This is confirmed when a growing salt structure encounters dry subflorescence formed earlier during the drying process. The dry subflorescence is reimbibed and resumes its growth. The analysis also suggests that the solution within the growing subflorescence is in equilibrium with the crystallized salt wall. These results shed light on the growth mechanisms of subflorescence, a phenomenon that can play a fundamental role in several important issues such as carbon dioxide sequestration or salt weathering.

N. Sghaier; S. Geoffroy; M. Prat; H. Eloukabi; S. Ben Nasrallah

2014-10-14T23:59:59.000Z

234

Decontamination and decommissioning of building 889 at Rocky Flats Environmental Technology Site  

SciTech Connect

At the Rocky Flats site, the building 889 decommissioning project was the first large-scale decommissioning project of a radiologically contaminated facility at Rocky Flats. The scope consisted of removal of all equipment and utility systems from the interior of the building, decontamination of interior building surfaces, and the demolition of the facility to ground level. Details of the project management plan, including schedule, engineering, cost, characterization methodologies, decontamination techniques, radiological control requirements, and demolition methods, are provided in this article. 1 fig., 3 tabs.

Dorr, K.A. [Kaiser-Hill Co., Golden, CO (United States); Hickman, M.E.; Henderson, B.J. [Rocky Mountain Remediation Services, Golden, CO (United States); Sexton, R.J. [Scientific Ecology Group, Golden, CO (United States)

1997-09-01T23:59:59.000Z

235

Criticality safety aspects of decontamination and decommissioning at defense nuclear facilities  

SciTech Connect

Defense nuclear facilities have operated for forty years with a well-defined mission to produce weapons components for the nation. With the end of the cold war, the facilities` missions have changed to one of decontamination and decommissioning. Off-normal operations and use of new procedures, such as will exist during these activities, have often been among the causal factors in previous criticality accidents at process facilities. This paper explores the similarities in causal factors in previous criticality accidents to the conditions existing in current defense nuclear facilities undergoing the transition to decontamination and decommissioning. Practices to reduce the risk to workers, the public, and the environment are recommended.

Croucher, D.W.

1994-02-01T23:59:59.000Z

236

Charge Density Effects in Salt-Free Polyelectrolyte Solution Rheology  

E-Print Network (OSTI)

of 2-vinyl pyridine and N-methyl-2-vinyl pyridinium chloride random copolymers in ethylene glycol of 2-vinyl pyridine and N- methyl-2-vinyl pyridinium chloride (PMVP-Cl) of any charge density was studied over wide ranges of con- centration and effective charge. The fraction of quaternized monomers

Colby, Ralph H.

237

Location of microseismic swarms induced by salt solution mining  

Science Journals Connector (OSTI)

......understanding of the mechanisms governing such a geohazard and to test the potential of geophysical methods to prevent them, the development...source seismology|Earthquake dynamics|Seismic monitoring and test-ban treaty verification|Earthquake interaction, forecasting......

J. Kinscher; P. Bernard; I. Contrucci; A. Mangeney; J.P. Piguet; P. Bigarre

2015-01-01T23:59:59.000Z

238

Use of Authorized Limits During Decontamination and Demolition Phase  

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

USE OF AUTHORIZED LIMITS DURING DECONTAMINATION AND DEMOLITION PHASE Protecting the public and the environment against undue risk from radiation associated with radiological activities conducted under the control of the Department of Energy (DOE) is the purpose of DOE environmental radiation protection programs. To meet this objective, DOE Order (O) 458.1, Radiation Protection of the Public and the Environment contains radiation protection requirements including a 100 mrem/yr public dose limit and two property clearance dose constraints, 1 mrem/yr and 25 mrem/yr. During D&D activities of facilities, some waste and materials generated results in the clearance of property that does not meet the requirements for unrestricted release of surface contaminated objects as set forth in DOE O 458.1. Radioactive material on or within material, equipment, and real property which is approved for release when the radiological conditions of the material, equipment, and real property that have been documented to comply with the criteria for release set forth in a DOE Authorized Limits are exempt from 10 CFR Part 835. The development of Authorized Limits involves an evaluation process whereby land and structures, discrete items, or personal property may be cleared even though they contain minute, residual amounts of radioactivity from DOE activities. DOE O 458.1 outlines the requirements for the development and approval of Authorized Limits. By developing and applying Authorized Limits, some of the waste generated during the D&D may be sent to a public or DOE landfill for disposal instead of a Low Level Waste disposal facility without compromise in health and safety. Authorized Limits have been developed, approved, and are being applied in D&D activities at the Portsmouth and Paducah Gaseous Diffusion Plants. The development of more Authorized Limits is planned for upcoming D&D activities. The waste streams to which Authorized Limits are applied include liquid waste (oil) and solid waste. Authorized Limits have also been developed for buffer land surrounding the Paducah Gaseous Diffusion Plant as part of the long-term property management plan for the area. Currently, Authorized Limits for DOE buffer land at Portsmouth is being developed.

239

Arylsulfatase Activity in Salt Marsh Soils  

Science Journals Connector (OSTI)

...Arylsulfatase Activity in Salt Marsh Soils R. L. Oshrain W. J. Wiebe...Arylsulfatase Activity in Salt Marsh Soilst R. L. OSHRAIN: AND W...Gallagher, J. L., R. J. Reimold, and D...Remote sensing and salt marsh productivity, p. 338-348...

R. L. Oshrain; W. J. Wiebe

1979-08-01T23:59:59.000Z

240

The economics of salt cake recycling  

SciTech Connect

The Process Evaluation Section at Argonne National Laboratory (ANL) has a major program aimed at developing cost-effective technologies for salt cake recycling. This paper addresses the economic feasibility of technologies for the recovery of aluminum, salt, and residue-oxide fractions from salt cake. Four processes were assessed for salt recovery from salt cake: (1) base case: leaching in water at 25{degree}C, with evaporation to crystallize salts; (2) high-temperature case: leaching in water at 250{degree}C, with flash crystallization to precipitate salts; (3) solventlantisolvent case: leaching in water at 25{degree}C, concentrating by evaporation, and reacting with acetone to precipitate salts; and (4) electrodialysis: leaching in water at 25{degree}C, with concentration and recovery of salts by electrodialysis. All test cases for salt recovery had a negative present value, given current pricing structure and 20% return on investment. Although manufacturing costs (variable plus fixed) could reasonably be recovered in the sales price of the salt product, capital costs cannot. The economics for the recycling processes are improved, however, if the residueoxide can be sold instead of landfilled. For example, the base case process would be profitable at a wet oxide value of $220/metric ton. The economics of alternative scenarios were also considered, including aluminum recovery with landfilling of salts and oxides.

Graziano, D.; Hryn, J.N.; Daniels, E.J.

1996-03-01T23:59:59.000Z

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


241

Simple Method for Killing Halophilic Bacteria in Contaminated Solar Salt  

Science Journals Connector (OSTI)

...growth and also to sterilize solar salt. Two samples of solar salt, contaminated with red...it had a much lower buffering capacity than the used salt, presumably...economical method of freeing solar salt from halophilic bacteria...

D. J. Kushner; G. Masson; N. E. Gibbons

1965-03-01T23:59:59.000Z

242

Radar investigation of the Hockley salt dome  

E-Print Network (OSTI)

: 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...

Hluchanek, James Andrew

2012-06-07T23:59:59.000Z

243

Environmental Assessment Proposed Decontamination and Demolition of Building 301 at Argonne National Laboratory  

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

85 85 ENVIRONMENTAL ASSESSMENT PROPOSED DECONTAMINATION AND DEMOLITION OF BUILDING 301 AT ARGONNE NATIONAL LABORATORY U. S. Department of Energy Argonne Site Office Argonne, Illinois Final March 26, 2007 ii TABLE OF CONTENTS 1.0 BACKGROUND ................................................................................................................ 1 1.1 Facility Description and History ............................................................................................ 1 1.2 Current Status......................................................................................................................... 7 1.3 Public Involvement ................................................................................................................

244

Decontamination of Hot Cells and Hot Pipe Tunnel at NASA's Plum Brook Reactor Facility  

SciTech Connect

The large scale decontamination of the concrete Hot Cells and Hot Pipe Tunnel at NASA's Plum Brook Reactor Facility demonstrates that novel management and innovative methods are crucial to ensuring that the successful remediation of the most contaminated facilities can be achieved with minimal risk to the project stakeholders. (authors)

Anderson, M.G.; Halishak, W.F. [MOTA Corporation, West Columbia, SC (United States)

2008-07-01T23:59:59.000Z

245

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

SciTech Connect

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.

Tucker, Mark D.

2014-06-03T23:59:59.000Z

246

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

SciTech Connect

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).

LUKE, S.N.

1999-02-01T23:59:59.000Z

247

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

E-Print Network (OSTI)

1 Advanced Sediment Washing for Decontamination of New York/New Jersey Harbor Dredged Materials Sediment Issue One of the greatest drivers for maintaining access to America's intermodal ports and related of contaminated sediments dredged from our nations waterways. More than 400 million cubic yards (CY) of sediments

Brookhaven National Laboratory

248

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

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

249

Radionuclide-Chelating Agent Complexes in Low-Level Radioactive Decontamination Waste; Stability, Adsorption and Transport Potential  

SciTech Connect

Speciation calculations were done to determine whether organic complexants facilitate transport of radionuclides leached from waste buried in soils. EDTA readily mobilizes divalent transition metals and moderately impacts trivalent actinides. Picolinate readily mobilizes only Ni2+ and Co2+. These speciation predictions ignore the influence of soil adsorption and biodegradation that break apart the complexes. In adsorption studies, picolinate concentrations have to be >10-4 M to lower the adsorption of Ni and Co. For Sm(III), Th(IV), Np(V), U(VI), and Pu, the picolinate concentration must be >10-3 M before adsorption decreases. EDTA forms strong complexes with divalent transition metals and can stop adsorption of Ni and Co when EDTA solution concentrations are 10-5 M. EDTA complexes with Np(V), U(VI), and Pu are much weaker; EDTA concentrations would have to be >10-3 M to adversely effects non-transition metal/radionuclide adsorption. Most picolinate and ETDA-metal complexes appear to readily dissociate during interactions with soils. The enhanced migration of radionuclide-organic complexes may be limited to a few unique conditions. We recommend that mixtures of metal/radionuclides and EDTA should not be solidified or co-disposed with high pH materials such as cement. For weaker binding organic complexants, such as picolinate, citrate and oxalate, co-disposal of decontamination wastes and concrete should be acceptable.

Serne, R. Jeffrey; Cantrell, Cantrell J.; Lindenmeier, Clark W.; Owen, Antionette T.; Kutnyakov, Igor V.; Orr, Robert D.; Felmy, Andrew R.

2002-02-01T23:59:59.000Z

250

The Salt Defense Disposal Investigations (SDDI)  

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

Salt Defense Disposal Investigations (SDDI) Salt Defense Disposal Investigations (SDDI) will utilize a newly mined Underground Research Lab (URL) in WIPP to perform a cost effective, proof-of-principle field test of the emplacement of heat-generating radioactive waste and validate modeling efforts. The goals of the SDDI Thermal Test are to: * Demonstrate a proof-of-principle concept for in-drift disposal in salt. * Investigate, in a specific emplacement concept, the response of the salt to heat. * Develop a full-scale response for run-of- mine (ROM) salt. * Develop a validated coupled process model for disposal of heat-generating wastes in salt. * Evaluate the environmental conditions of the

251

The use of laser therapy for dental implant surface decontamination: a narrative review of in vitro studies  

Science Journals Connector (OSTI)

The aim of this narrative review was to critically evaluate in vitro studies assessing the efficacy of lasers in the bacterial decontamination of titanium implant surfaces. The MEDLINE, Web of Knowledge and Em...

Marina Salah Kamel; Amardeep Khosa; Andrew Tawse-Smith…

2014-11-01T23:59:59.000Z

252

Multiphase Flow and Cavern Abandonment in Salt  

SciTech Connect

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

Ehgartner, Brian; Tidwell, Vince

2001-02-13T23:59:59.000Z

253

Workplace Charging Challenge Partner: Salt River Project  

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

The mission of Salt River Project's (SRP) Electric Vehicle Initiative is to encourage greater use of clean energy transportation. Under this program, SRP's headquarters received two Level 2...

254

Sandia National Laboratories: molten salt test loop  

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

Partnership, Renewable Energy, Research & Capabilities, Solar, Solar Newsletter, SunShot, Systems Engineering AREVA and Sandia began operations of their molten salt...

255

Granular Salt Summary: Reconsolidation Principles and Applications  

SciTech Connect

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.

Frank Hansen; Till Popp; Klaus Wieczorek; Dieter Stührenberg

2014-07-01T23:59:59.000Z

256

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

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

DOE/EA-1483 DOE/EA-1483 Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois March 2004 U.S. Department of Energy Chicago Operations Office Argonne Area Office Argonne, Illinois Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois Table of Contents Acronyms....................................................................................................................................... iii 1.0 Background ..........................................................................................................................1 1.1 Facility History ........................................................................................................1

257

ANALYSIS OF THE REACTIVITY OF RADPRO SOLUTION WITH COTTON RAGS  

SciTech Connect

Rags containing RadPro{reg_sign} solution will be generated during the decontamination of the Plutonium Finishing Plant (PFP). Under normal conditions, the rags will be neutralized with sodium carbonate prior to placing in the drums. The concern with RadPro solutions and cotton rags is that some of the RadPro solutions contain nitric acid. Under the right conditions, nitric acid and cotton rags exothermically react. The concern is, will RadPro solutions react with cotton rags exothermically? The potential for a runaway reaction for any of the RadPro solutions used was studied in Section 5.2 of PNNL-15410, Thermal Stability Studies of Candidate Decontamination Agents for Hanford's Plutonium Finishing Plant Plutonium-Contaminated Gloveboxes. This report shows the thermal behavior of cotton rags having been saturated in one of the various neutralized and non-neutralized RadPro solutions. The thermal analysis was performed using thermogravimetric Analysis (TGA), Differential Thermal Analysis (DTA) and Accelerating Rate Calorimetry (ARC).

MARUSICH RM

2009-08-11T23:59:59.000Z

258

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

E-Print Network (OSTI)

who applied for Salt Lake County properties selected West Valley. · As the overall application volume). · Over 54 percent of all Salt Lake County mortgage applications from 2006 to 2011 were for homes in West Valley, unincorporated areas, West Jordan, and Salt Lake City. For Hispanic/Latino applicants

Feschotte, Cedric

259

Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit  

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

Uranium Uranium Enrichment Decontamination and Decommissioning Fund's Fiscal Year 2011 Financial Statement Audit OAS-FS-13-02 October 2012 September 7, 2012 Mr. Gregory Friedman Inspector General U.S. Department of Energy 1000 Independence Avenue, S.W. Room 5D-039 Washington, DC 20585 Dear Mr. Friedman: We have audited the financial statements of the Department of Energy's (the Department) Uranium Enrichment Decontamination and Decommissioning Fund (D&D Fund) as of and for the year ended September 30, 2011, and have issued our report thereon dated September 7, 2012. In planning and performing our audit of the consolidated financial statements, in accordance with auditing standards generally accepted in the United States of America, we considered the Department's internal control

260

DECISION ANALYSIS AND TECHNOLOGY ASSESSMENTS FOR METAL AND MASONRY DECONTAMINATION TECHNOLOGIES  

SciTech Connect

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.

M.A. Ebadian, Ph.D.

1999-01-01T23:59:59.000Z

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


261

Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project  

SciTech Connect

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.

A. M Smith; G. E. Matthern; R. H. Meservey

1998-11-01T23:59:59.000Z

262

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

E-Print Network (OSTI)

SPRAY-CHILLING AND CARCASS DECONTANINATION SYSTEMS USING LAC1'IC AND ACETIC ACID A Thesis by PATRICK LAWRENCE HAMBY Submitted to the Graduate College of TEXAS A&M UNIVERSITY in partial fulfillment of the requirements for the degree NASTER... 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...

Hamby, Patrick Lawrence

2012-06-07T23:59:59.000Z

263

Criticality prevention during postaccident decontamination of TMI-2 (Three Mile Island Unit 2) plant systems  

SciTech Connect

Following the accident at Three Mile Island Unit 2 (TMI-2), the likelihood of a criticality outside of the reactor coolant system (RCS) during the plant cleanup was very small. Given the consequence of any possible critical event in the TMI-2 systems, However, it was always necessary to ensure that all steps were taken to prevent criticality. Therefore, engineered controls were developed to ensure that decontamination of plant systems containing fuel material could be conducted in a manner that precluded criticality.

Palau, G. L.

1988-01-01T23:59:59.000Z

264

Transpiring wall supercritical water oxidation reactor salt deposition studies  

SciTech Connect

Sandia National Laboratories has teamed with Foster Wheeler Development Corp. and GenCorp, Aerojet to develop and evaluate a new supercritical water oxidation reactor design using a transpiring wall liner. In the design, pure water is injected through small pores in the liner wall to form a protective boundary layer that inhibits salt deposition and corrosion, effects that interfere with system performance. The concept was tested at Sandia on a laboratory-scale transpiring wall reactor that is a 1/4 scale model of a prototype plant being designed for the Army to destroy colored smoke and dye at Pine Bluff Arsenal in Arkansas. During the tests, a single-phase pressurized solution of sodium sulfate (Na{sub 2}SO{sub 4}) was heated to supercritical conditions, causing the salt to precipitate out as a fine solid. On-line diagnostics and post-test observation allowed us to characterize reactor performance at different flow and temperature conditions. Tests with and without the protective boundary layer demonstrated that wall transpiration provides significant protection against salt deposition. Confirmation tests were run with one of the dyes that will be processed in the Pine Bluff facility. The experimental techniques, results, and conclusions are discussed.

Haroldsen, B.L.; Mills, B.E.; Ariizumi, D.Y.; Brown, B.G. [and others

1996-09-01T23:59:59.000Z

265

Conceptual Decontamination and Decommissioning Plan for the Waste Isolation Pilot Plant  

SciTech Connect

The Conceptual Decontamination and Decommissioning Plan (D&D) was developed as a concept for progressing from the final actions of the Disposal Phase, through the Decontamination and Decommissioning Phase, and into the initiation of the Long-Term Monitoring Phase. This plan was written in a manner that coincides with many of the requirements specified in DOE Order 5820.2A. Radioactive Waste Management; ASTM El 167 87, Standard Guide for Radiation Protection Program for Decommissioning Operations; and other documents listed in Attachment 3 of the D&D Plan. However, this conceptual plan does not meet all of the requirements necessary for a Decontamination and Decommissioning plan necessary for submission to the U.S. Congress in accordance with the Land Withdrawal Act (P.L. 102-579). A complete D&D plan that will meet the requirements of all of these documents and of the Land Withdrawal Act will be prepared and submitted to Congress by October 1997.

Westinghouse Electric Corporation Waste Isolation Division, now Washington TRU Solutions LLC

1995-01-30T23:59:59.000Z

266

Decontamination and decarburization of stainless and carbon steel by melt refining  

SciTech Connect

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.

Mizia, R.E.; Worcester, S.A.; Twidwell, L.G.; Webber, D.; Paolini, D.J.; Weldon, T.A.

1996-09-05T23:59:59.000Z

267

Efficient and Regioselective Halogenations of 2-Amino-1,3-thiazoles with Copper Salts  

E-Print Network (OSTI)

Efficient and Regioselective Halogenations of 2-Amino-1,3-thiazoles with Copper Salts Fabrice G. Halogenations proceed easily in the presence of copper(I) or copper(II) chlorides, bromides, or iodides directly in solution or with supported copper halides. 1,3-Thiazole rings appear in many compounds that exhibit

Shen, Jun

268

Molten Salt Oxidation of mixed wastes  

SciTech Connect

Molten Salt Oxidation (MSO) can be characterized as a simple noncombustion process; the basic concept is to introduce air and wastes into a bed of molten salt, oxidize the organic wastes in the molten salt, use the heat of oxidation to keep the salt molten and remove the salt for disposal or processing and recycling. The process has been developed through bench-scale and pilot-scale testing, with successful destruction demonstration of a wide variety of hazardous and mixed (radioactive and hazardous) wastes including chemical warfare agents, combustible solids, halogenated solvents, polychlorinated biphenyls, plutonium-contaminated solids, uranium-contaminated solvents and fission product-contaminated oil. The MSO destruction efficiency of the hazardous organic constituents in the wastes exceeds 99.9999%. Radioactive species, such as actinides and rare earth fission products, are retained in the salt bath. These elements can be recovered from the spent salt using conventional chemical processes, such as ion exchange, to render the salt as nonradioactive and nonhazardous. This paper reviews the principles and capabilities of MSO, previous mixed waste studies, and a new US Department of Energy program to demonstrate the process for the treatment of mixed wastes.

Gay, R.L.; Navratil, J.D.; Newman, C. [Rockwell International Corp., Canoga Park, CA (United States). Rocketdyne Div.

1993-12-31T23:59:59.000Z

269

Metal salt catalysts for enhancing hydrogen spillover  

SciTech Connect

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.

Yang, Ralph T; Wang, Yuhe

2013-04-23T23:59:59.000Z

270

Salt Wells Geothermal Exploratory Drilling Program EA  

Open Energy Info (EERE)

Salt Wells Geothermal Exploratory Drilling Program EA Salt Wells Geothermal Exploratory Drilling Program EA (DOI-BLM-NV-C010-2009-0006-EA) Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Salt Wells Geothermal Exploratory Drilling Program EA (DOI-BLM-NV-C010-2009-0006-EA) Abstract No abstract available. Author Bureau of Land Management Published U.S. Department of the Interior- Bureau of Land Management, Carson City Field Office, Nevada, 09/14/2009 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Salt Wells Geothermal Exploratory Drilling Program EA (DOI-BLM-NV-C010-2009-0006-EA) Citation Bureau of Land Management. Salt Wells Geothermal Exploratory Drilling Program EA (DOI-BLM-NV-C010-2009-0006-EA) [Internet]. 09/14/2009. Carson City, NV. U.S. Department of the Interior- Bureau of Land Management,

271

Solar Policy Environment: Salt Lake  

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

272

Underground Salt Haul Truck Fire at the Waste Isolation Pilot...  

Office of Environmental Management (EM)

Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant February 5, 2014 March 2014 Salt Haul Truck Fire at the Waste Isolation Pilot Plant Salt Haul Truck Fire at the...

273

Sandia National Laboratories: Molten Nitrate Salt Initial Flow...  

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

David Gill, ddgill@sandia.gov, (505)-844-1524. Tagged with: Concentrating Solar Power * CSP * Molten Salt * molten salt test loop * National Solar Thermal Test Facility * NSTTF *...

274

Sandia National Laboratories: molten salt energy storage demonstration  

NLE Websites -- All DOE Office Websites (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,...

275

New lithium-based ionic liquid electrolytes that resist salt...  

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

New lithium-based ionic liquid electrolytes that resist salt concentration polarization New lithium-based ionic liquid electrolytes that resist salt concentration polarization...

276

Development of Molten-Salt Heat Trasfer Fluid Technology for...  

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

Development of Molten-Salt Heat Trasfer Fluid Technology for Parabolic Trough Solar Power Plants Development of Molten-Salt Heat Trasfer Fluid Technology for Parabolic Trough Solar...

277

DOE - Office of Legacy Management -- Tatum Salt Dome Test Site...  

Office of Legacy Management (LM)

Tatum Salt Dome Test Site - MS 01 FUSRAP Considered Sites Site: Tatum Salt Dome Test Site (MS.01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site...

278

Project Profile: Modular and Scalable Baseload Molten Salt Plant...  

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

salt receiver A distributed molten salt transport system Hybridization with natural gas or biofuels. Publications, Patents, and Awards J. E. Pacheco, C. Moursund, D. Rogers;...

279

Project Profile: Novel Molten Salts Thermal Energy Storage for...  

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

Novel Molten Salts Thermal Energy Storage for Concentrating Solar Power Generation Project Profile: Novel Molten Salts Thermal Energy Storage for Concentrating Solar Power...

280

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot...  

Office of Environmental Management (EM)

Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics Coupled Thermal-Hydrological-Mechanical Processes...

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


281

Tropospheric Chemistry of Internally Mixed Sea Salt and Organic...  

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

Tropospheric Chemistry of Internally Mixed Sea Salt and Organic Particles: Surprising Reactivity of NaCl with Weak Organic Acids Tropospheric Chemistry of Internally Mixed Sea Salt...

282

Project Profile: Deep Eutectic Salt Formulations Suitable as...  

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

Deep Eutectic Salt Formulations Suitable as Advanced Heat Transfer Fluids Project Profile: Deep Eutectic Salt Formulations Suitable as Advanced Heat Transfer Fluids Halotechnics...

283

Electromagnetic mixed-waste processing system for asbestos decontamination  

SciTech Connect

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.

NONE

1995-04-01T23:59:59.000Z

284

Chemical decontamination of process equipment using recyclable chelating agents  

SciTech Connect

The Babcock and Wilcox Company is performing research and development in the application of chelating chemicals to dissolve uranium compounds and other actinide species from the surfaces of DOE process equipment. A chelating system specific for the removal of uranium and other actinides will be applied to the component selected for full-scale demonstration of the process. After application of the chelating solvent for an appropriate time period, the spent solvent will be removed to a waste processing facility, and the dissolved radioactive contaminants will be precipitated out of the solution. The regenerated chelating solvent will then be available for reuse in the cleaning system, thereby minimizing the amount of secondary waste generated by the process. Phase 1 activity has begun with bench-scale tests in the laboratory, to screen and optimize candidate solvent systems, and will proceed to development of a chemical cleaning process that will be tested in a pilot facility on an actual piece of contaminated equipment. The potential for application of the chelating agent as a foam rather than a liquid will also be investigated. The advantage of foaming application is a reduction of solvent volume requiring eventual treatment. The second phase of this program will be a full-scale demonstration of the developed technology on contaminated process equipment at a DOE site.

Palmer, P.A.

1994-10-01T23:59:59.000Z

285

Category:Salt Lake City, UT | Open Energy Information  

Open Energy Info (EERE)

UT UT Jump to: navigation, search Go Back to PV Economics By Location Media in category "Salt Lake City, UT" The following 16 files are in this category, out of 16 total. SVFullServiceRestaurant Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png SVFullServiceRestauran... 57 KB SVHospital Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png SVHospital Salt Lake C... 57 KB SVLargeHotel Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png SVLargeHotel Salt Lake... 55 KB SVLargeOffice Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png SVLargeOffice Salt Lak... 57 KB SVMediumOffice Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png SVMediumOffice Salt La... 62 KB SVMidriseApartment Salt Lake City UT Moon Lake Electric Assn Inc (Utah).png

286

Examination of Liquid Fluoride Salt Heat Transfer  

SciTech Connect

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.

Yoder Jr, Graydon L [ORNL] [ORNL

2014-01-01T23:59:59.000Z

287

Acoustic probing of salt using sonar  

E-Print Network (OSTI)

ACOUSTIC PROBING OF SALT USING SONAR A Thesis by KENNETH BRYAN BUTLER Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree of MASTER OF SCIENCE Oecember 1977 Major Subject...: Geophysics ACOUSTIC PROBING OF SALT USING SONAR A Thesis by KENNETH BRYAN BUTLER Approved as to style and content by: C airman of Com ttee ea of e r nt em er ember December 1977 ABSTRACT Acoustic Probing of Salt Using Sonar. (December 1977...

Butler, Kenneth Bryan

2012-06-07T23:59:59.000Z

288

Plan for fully decontaminating and decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick, Revision 3  

SciTech Connect

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This volume contains the following 3 attachments: (1) Plan for Fully Decontamination and Decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick; (2) Environmental Assessment for Decontamination and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA; and (3) WARD-386, Quality Assurance Program Description for Decontamination and Decommissioning Activities.

Not Available

1982-01-01T23:59:59.000Z

289

Decontamination and decommissioning of the Chemical Process Cell (CPC): Topical report for the period January 1985-March 1987  

SciTech Connect

To support interim storage of vitrified High-Level Waste (HLW) at the West Valley Demonstration Project, the shielded, remotely operated Chemical Process Cell (CPC) was decommissioned and decontaminated. All equipment was removed, packaged and stored for future size reduction and decontamination. Floor debris was sampled, characterized, and vacuumed into remotely handled containers. The cell walls, ceiling, and floor were decontaminated. Three 20 Mg (22.5 ton) concrete neutron absorber cores were cut with a high-pressure water/abrasive jet cutting system and packaged for disposal. All operations were performed remotely using two overhead bridge cranes which included two 1.8 Mg (2 ton) hoists, one 14.5 Mg (16 ton) hoist, and an electromechanical manipulator or an industrial robot mounted on a mobile platform. Initial general area dose rates in the cell ranged from 1 to 50 R/h. Target levels of less than 10 mR/h general area readings were established before decontamination and decommissioning was initiated; general area dose rates between 200 mR/h and 1200 mR/h were obtained at the completion of the decontamination work. 4 refs., 11 figs., 8 tabs.

Meigs, R. A.

1987-07-01T23:59:59.000Z

290

Application of inorganic aluminum salts to intensification of the clarification of cinder and oil-containing waste water  

SciTech Connect

The effects of inorganic coagulants together with polyacrylamide (PAA) were tested in waste water containing oil and finely dispersed cinder. It has been established that concentrated solutions of aluminum salts have the maximal clarification efficiency (82%). It has been shown that the residual alkali content of water is higher when concentrated (20%) solutions of aluminum salts are used than in the case of the use of dilute (1%) solutions. The expediency of the use of aluminum salts for the treatment of waste water with a low initial alkalinity (below 1.0 meq/liter) has been established. It has been established that aluminum sulfate is maximally effective when the alkali content of the water being purified is less than 1.8 or greater than 4.5 meq/liter.

Shub, V.B.; Khukhryanskaya, I.A.

1987-10-10T23:59:59.000Z

291

Studies on the reverse osmosis treatment of uranyl nitrate solution  

SciTech Connect

The aqueous effluent generated in uranium processing, particularly in the nuclear fuel fabrication step, contains mainly uranium nitrate. This requires treatment before discharge into the environment to meet stringent standards. This paper presents the performance of cellulose acetate membranes with regard to rejection of uranium under reverse osmotic conditions for feed concentrations up to 200 mg/l of uranium, which corresponds to the levels normally prevalent in the effluents. The use of additives like the disodium salt of ethylenediaminetetraacetic acid and sodium sulfate for the improvement of reverse osmosis performance of the above membranes was also investigated. In the light of the experimental results, the suitability of reverse osmosis for the decontamination of uranium effluents is discussed.

Prabhakar, S.; Panicker, S.T.; Misra, B.M.; Ramani, P.S. (Bhabha Atomic Research Centre, Bombay (India))

1992-03-01T23:59:59.000Z

292

Molten Salt Batteries and Fuel Cells  

Science Journals Connector (OSTI)

This chapter describes recent work on batteries and fuel cells using molten salt electrolytes. This entails a comparison with other batteries and fuel cells utilizing aqueous and organic electrolytes; for...(1,2)

D. A. J. Swinkels

1971-01-01T23:59:59.000Z

293

Determining Salt Tolerance Among Sunflower Genotypes  

E-Print Network (OSTI)

Crop lands around the world are becoming more salt-affected due to natural processes and agricultural practices. Due to this increase of salinization, acquisition of saline tolerant germplasm for breeding purposes is becoming a priority. Although...

Masor, Laura Lee

2012-02-14T23:59:59.000Z

294

BNL Building 650 lead decontamination and treatment feasibility study. Final report  

SciTech Connect

Lead has been used extensively at Brookhaven National Laboratory (BNL) for radiation shielding in numerous reactor, accelerator and other research programs. A large inventory of excess lead (estimated at 410,000 kg) in many shapes and sizes is currently being stored. Due to it`s toxicity, lead and soluble lead compounds are considered hazardous waste by the Environmental Protection Agency. Through use at BNL, some of the lead has become radioactive, either by contamination of the surface or through activation by neutrons or deuterons. This study was conducted at BNL`s Environmental and Waste Technology Center for the BNL Safety and Environmental Protection Division to evaluate feasibility of various treatment options for excess lead currently being stored. The objectives of this effort included investigating potential treatment methods by conducting a review of the literature, developing a means of screening lead waste to determine the radioactive characteristics, examining the feasibility of chemical and physical decontamination technologies, and demonstrating BNL polyethylene macro-encapsulation as a means of treating hazardous or mixed waste lead for disposal. A review and evaluation of the literature indicated that a number of physical and chemical methods are available for decontamination of lead. Many of these techniques have been applied for this purpose with varying degrees of success. Methods that apply mechanical techniques are more appropriate for lead bricks and sheet which contain large smooth surfaces amenable to physical abrasion. Lead wool, turnings, and small irregularly shaped pieces would be treated more effectively by chemical decontamination techniques. Either dry abrasion or wet chemical methods result in production of a secondary mixed waste stream that requires treatment prior to disposal.

Kalb, P.D.; Cowgill, M.G.; Milian, L.W. [and others

1995-10-01T23:59:59.000Z

295

The Effect of Salt Water on Rice.  

E-Print Network (OSTI)

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...

Fraps, G. S. (George Stronach)

1909-01-01T23:59:59.000Z

296

Decontamination and dismantlement of the old hot laundry, CFA-669. Final report  

SciTech Connect

This final report describes the decontamination and dismantlement (D&D) of the old hot laundry, located at the Idaho National Engineering Laboratory (INEL) Central Facilities Area (CFA). The report describes the site before and after D&D, processes used, cost and duration, and waste volume generated. In addition, lessons learned are presented. Pre-D&D characterization indicated gross alpha concentrations in the building ranged from 6 to 310 pCi/g and gross beta measurements from 6 to 15,000 pCi/g. Gamma spectrum analysis identified cobalt-60, cesium-137, antimony-125, europium-152, europium-154, and niobium-94.

Smith, D.L.; Perry, E.F.

1995-01-01T23:59:59.000Z

297

Task 21 - Development of Systems Engineering Applications for Decontamination and Decommissioning Activities  

SciTech Connect

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.

Erickson, T.A.

1998-11-01T23:59:59.000Z

298

Exploratory Use of Microaerosol Decontamination Technology (PAEROSOL) in Enclosed, Unoccupied Hospital Setting  

SciTech Connect

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.

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

299

Office of Environmental Management Uranium Enrichment Decontamination and Decommissioning Fund financial statements, September 30, 1995 and 1994  

SciTech Connect

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.

NONE

1996-02-21T23:59:59.000Z

300

Chemical decontamination of process equipment using recyclable chelating solvent Phase I. Final report, September 1993--June 1995  

SciTech Connect

The Department of Energy (DOE) is now faced with the task of meeting decontamination and decommissioning obligations at numerous facilities by the year 2019. Due to the tremendous volume of material involved, innovative decontamination technologies are being sought that can reduce the volumes of contaminated waste materials and secondary wastes requiring disposal. With sufficient decontamination, some of the material from DOE facilities could be released as scrap into the commercial sector for recycle, thereby reducing the volume of radioactive waste requiring disposal. Although recycling may initially prove to be more costly than current disposal practices, rapidly increasing disposal costs are expected to make recycling more and more cost effective. Additionally, recycling is now perceived as the ethical choice in a world where the consequences of replacing resources and throwing away reusable materials are impacting the well-being of the environment.

NONE

1995-10-01T23:59:59.000Z

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


301

Environmental Assessment for Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory Â… East Argonne, Illinois  

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

Finding of No Significant Impact Finding of No Significant Impact Proposed Decontamination and Decommissioning of the Juggernaut Reactor at Argonne National Laboratory - East Argonne, Illinois AGENCY: U. S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has prepared an Environmental Assessment (EA), DOE/EA-1483, evaluating the decontamination and decommissioning of the Juggernaut Reactor at Argonne National Laboratory-East (ANL-E), in Argonne, Illinois. The decontamination and decommissioning of the reactor is needed to ensure the protection of the health and safety of the public, DOE and contractor employees, and the environment, consistent with DOE Order 5400.5, Radiation Protection of the Public and the Environment. Based on the analysis in the EA, DOE has determined that the proposed action does not

302

Ethylenediamine salt of 5-nitrotetrazole and preparation  

DOE Patents (OSTI)

Ethylenediamine salt of 5-nitrotetrazole and preparation. This salt has been found to be useful as an explosive alone and in eutectic mixtures with ammonium nitrate and/or other explosive compounds. Its eutectic with ammonium nitrate has been demonstrated to behave in a similar manner to a monomolecular explosive such as TNT, and is less sensitive than the pure salt. Moreover, this eutectic mixture, which contains 87.8 mol % of ammonium nitrate, is close to the CO.sub.2 -balanced composition of 90 mol %, and has a relatively low melting point of 110.5 C. making it readily castable. The ternary eutectic system containing the ethylenediamine salt of 5-nitrotetrazole, ammonium nitrate and ethylenediamine dinitrate has a eutectic temperature of 89.5 C. and gives a measured detonation pressure of 24.8 GPa, which is 97.6% of the calculated value. Both the pure ethylenediamine salt and its known eutectic compounds behave in substantially ideal manner. Methods for the preparation of the salt are described.

Lee, Kien-yin (Los Alamos, NM); Coburn, Michael D. (Los Alamos, NM)

1985-01-01T23:59:59.000Z

303

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

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

Blending in Nuclear Waste Tanks Blending in Nuclear Waste Tanks Bob Leishear Savannah River Remediation Salt Disposition Engineering November 17, 2010 Print Close 2 Blending in Nuclear Waste Tanks Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Salt Supernate 12 MCi (3%) Saltcake 15.8 Mgal (43%) Print Close 3 Blending in Nuclear Waste Tanks Sample of Vitrified Radioactive Glass Print Close 4 Blending in Nuclear Waste Tanks SDU 3 SDU 3 SDU 2 SDU 2 SDU (Vault) 4 SDU (Vault) 4 SDU (Vault) 1 SDU (Vault) 1 Cell A Cell B Saltstone Production Facility Saltstone Production Facility Print Close 5 Blending in Nuclear Waste Tanks Print Close 6 Blending in Nuclear Waste Tanks Sludge Salt Feed Solutions Print Close 7 Experimental Strategy Scale-

304

Test plan for immobilization of salt-containing surrogate mixed wastes using polyester resins  

SciTech Connect

Past operations at many Department of Energy (DOE) sites have resulted in the generation of several waste streams with high salt content. These wastes contain listed and characteristic hazardous constituents and are radioactive. The salts contained in the wastes are primarily chloride, sulfate, nitrate, metal oxides, and hydroxides. DOE has placed these types of wastes under the purview of the Mixed Waste Focus Area (MWFA). The MWFA has been tasked with developing and facilitating the implementation of technologies to treat these wastes in support of customer needs and requirements. The MWFA has developed a Technology Development Requirements Document (TDRD), which specifies performance requirements for technology owners and developers to use as a framework in developing effective waste treatment solutions. This project will demonstrate the use of polyester resins in encapsulating and solidifying DOE`s mixed wastes containing salts, as an alternative to conventional and other emerging immobilization technologies.

Biyani, R.K.; Douglas, J.C.; Hendrickson, D.W.

1997-07-07T23:59:59.000Z

305

Oxidation and stabilization of hydrocarbon fuels in contact with rock salt  

SciTech Connect

Underground storage is the most ecologically clean and economical method for extended storage of natural gas, crude oil, and petroleum products. Such storage reservoirs are created in stable rock (granites, gneisses, limestone, etc.), rock salt deposits, clays, abandoned mines, and permafrost formations. In this investigation of the influence of rock salt deposits on the oxidation of hydrocarbons (summer-grade straight-run diesel fuel L and automotive gasoline A-76 [unleaded, low-octane]), the authors carried out a kinetic study of hydroperoxide accumulation during the oxidation of these fuels after contact with a saturated solution of rock salt (brine). The experiments were performed in a bubbler-type unit with various ratios of brine to fuel.

Klinaeva, E.V.; Golubeva, I.A.; Tolstykh, L.I. [and others

1995-11-01T23:59:59.000Z

306

DOE/EA-1670: Environmental Assessment for the Proposed Decontamination and Demolition of Building 310 at Argonne National Laboratory (April 2010)  

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

0 0 ENVIRONMENTAL ASSESSMENT for the PROPOSED DECONTAMINATION AND DEMOLITION OF BUILDING 310 AT ARGONNE NATIONAL LABORATORY U.S. Department of Energy Argonne Site Office Argonne, Illinois April 2010 Page intentionally left blank. Environmental Assessment for the Proposed Decontamination and Demolition of Building 310 at Argonne National Laboratory i TABLE OF CONTENTS LIST OF ACRONYMS AND ABBREVIATIONS ...................................................................... iii

307

Waste Isolation Pilot Plant's Excavated Salt Agreement Supports  

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

Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Conservation Education, Other Public Initiatives Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Conservation Education, Other Public Initiatives November 14, 2013 - 12:00pm Addthis Approximately 1.8 million tons of salt have been mined out of the underground at WIPP. Approximately 1.8 million tons of salt have been mined out of the underground at WIPP. Proceeds from the WIPP salt allowed hundreds of southeast New Mexico students to learn about resource conservation. Proceeds from the WIPP salt allowed hundreds of southeast New Mexico students to learn about resource conservation. The crushed salt is used as a supplement in cattle feed. Since the salt from WIPP has been mined from the middle of a large salt formation, its quality is high, according to Magnum Minerals.

308

Waste Isolation Pilot Plant's Excavated Salt Agreement Supports  

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

Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Conservation Education, Other Public Initiatives Waste Isolation Pilot Plant's Excavated Salt Agreement Supports Conservation Education, Other Public Initiatives November 14, 2013 - 12:00pm Addthis Approximately 1.8 million tons of salt have been mined out of the underground at WIPP. Approximately 1.8 million tons of salt have been mined out of the underground at WIPP. Proceeds from the WIPP salt allowed hundreds of southeast New Mexico students to learn about resource conservation. Proceeds from the WIPP salt allowed hundreds of southeast New Mexico students to learn about resource conservation. The crushed salt is used as a supplement in cattle feed. Since the salt from WIPP has been mined from the middle of a large salt formation, its quality is high, according to Magnum Minerals.

309

Thermal Analysis of Surrogate Simulated Molten Salts with Metal Chloride Impurities for Electrorefining Used Nuclear Fuel  

SciTech Connect

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.

Toni Y. Gutknecht; Guy L. Fredrickson; Vivek Utgikar

2012-04-01T23:59:59.000Z

310

Decontamination and Volume Reduction System for Transuranic Waste at Los Alamos National Laboratory, Los Alamos, New Mexico Environmental Assessment  

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

69 69 Decontamination and Volume Reduction System for Transuranic Waste at Los Alamos National Laboratory, Los Alamos, New Mexico Environmental Assessment Final Document Date Prepared: June 23, 1999 Prepared by: U.S. Department of Energy, Los Alamos Area Office Final document Decontamination and Volume Reduction System EA June 23, 1999 DOE/LAAO iii TABLE OF CONTENTS ACRONYMS AND TERMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v EXECUTIVE SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii 1.0 PURPOSE AND NEED FOR AGENCY ACTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

311

Environmental Assessment for the Decontamination, Demolition, and Removal of Certain Facilities at the West Valley Demonstration Project  

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

52 52 Environmental Assessment for the Decontamination, Demolition, and Removal of Certain Facilities at the West Valley Demonstration Project Final U.S. Department of Energy West Valley Demonstration Project West Valley, New York September 14, 2006 Final EA - Decontamination, Demolition, and Removal of Certain Facilities at WVDP i Table of Contents CHAPTER 1 INTRODUCTION AND PURPOSE AND NEED FOR AGENCY ACTION................ 1 1.1 Overview....................................................................................................................... 1 1.2 West Valley Demonstration Project.............................................................................. 2 1.3 Purpose and Need for Agency Action ..........................................................................

312

Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests  

SciTech Connect

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.

Washington, A. L. II; Peters, T. B.; Fink, S. D.

2013-02-25T23:59:59.000Z

313

Phase equilibria in the system H{sub 2}O-NaCl-KCl-MgCl{sub 2} relevant to salt cake processing  

SciTech Connect

One waste product in recycling of Al is salt cake, a mixture of Al, salts, and residue oxides. Several methods have been proposed to recycle salt cake, one involving high-temperature leaching of salts from the salt cake. The salt composition can be approximated as a mixture predominantly of NaCl and KCl salts, with lesser amounts of Mg chloride. In order to better assess the feasibility of recycling salt cake, an experimental study was conducted of phase equilibria in the system H{sub 2}O-NaCl-KCl-MgCl{sub 2} at pressure (P), temperature (T), and composition conditions appropriate for high- temperature salt cake recycling. These experiments were designed to evaluate the effect of small amounts (2-10 wt%) of MgCl{sub 2} on solubilities of halite (NaCl) and sylvite (KCl) in saturated solutions (30-50 wt% NaCl+KCl; NaCl:KCl = 1:1 and 3:1) at elevated P and T.

Bodnar, R.J.; Vityk, M.O. [Virginia Polytechnic Inst., Blacksburg, VA (United States)] [Virginia Polytechnic Inst., Blacksburg, VA (United States); Hryn, J.N. [Argonne National Lab., IL (United States)] [Argonne National Lab., IL (United States); Mavrogenes, J. [Australian National Univ., Canberra, ACT (Australia)] [Australian National Univ., Canberra, ACT (Australia)

1997-02-01T23:59:59.000Z

314

Independent verification of plutonium decontamination on Johnston Atoll (1992--1996)  

SciTech Connect

The Field Command, Defense Special Weapons Agency (FCDSWA) (formerly FCDNA) contracted Oak Ridge National Laboratory (ORNL) Environmental Technology Section (ETS) to conduct an independent verification (IV) of the Johnston Atoll (JA) Plutonium Decontamination Project by an interagency agreement with the US Department of Energy in 1992. The main island is contaminated with the transuranic elements plutonium and americium, and soil decontamination activities have been ongoing since 1984. FCDSWA has selected a remedy that employs a system of sorting contaminated particles from the coral/soil matrix, allowing uncontaminated soil to be reused. The objective of IV is to evaluate the effectiveness of remedial action. The IV contractor`s task is to determine whether the remedial action contractor has effectively reduced contamination to levels within established criteria and whether the supporting documentation describing the remedial action is adequate. ORNL conducted four interrelated tasks from 1992 through 1996 to accomplish the IV mission. This document is a compilation and summary of those activities, in addition to a comprehensive review of the history of the project.

Wilson-Nichols, M.J.; Wilson, J.E.; McDowell-Boyer, L.M.; Davidson, J.R.; Egidi, P.V.; Coleman, R.L.

1998-05-01T23:59:59.000Z

315

Evaluation of the Three Mile Island Unit 2 reactor building decontamination process  

SciTech Connect

Decontamination activities from the cleanup of the Three Mile Island Unit 2 Reactor Building are generating a variety of waste streams. Solid wastes being disposed of in commercial shallow land burial include trash and rubbish, ion-exchange resins (Epicor-II) and strippable coatings. The radwaste streams arising from cleanup activities currently under way are characterized and classified under the waste classification scheme of 10 CFR Part 61. It appears that much of the Epicor-II ion-exchange resin being disposed of in commerical land burial will be Class B and require stabilization if current radionuclide loading practices continue to be followed. Some of the trash and rubbish from the cleanup of the reactor building so far would be Class B. Strippable coatings being used at TMI-2 were tested for leachability of radionuclides and chelating agents, thermal stability, radiation stability, stability under immersion and biodegradability. Actual coating samples from reactor building decontamination testing were evaluated for radionuclide leaching and biodegradation.

Dougherty, D.; Adams, J. W.

1983-08-01T23:59:59.000Z

316

Decontamination of chemical and biological warfare (CBW) agents using an atmospheric pressure plasma jet (APPJ)  

Science Journals Connector (OSTI)

The atmospheric pressure plasma jet (APPJ) [A. Schütze et al. IEEE Trans. Plasma Sci. 26 1685 (1998)] is a nonthermal high pressure uniform glowplasmadischarge that produces a high velocity effluent stream of highly reactive chemical species. The discharge operates on a feedstock gas (e.g. He/O 2 /H 2 O ) which flows between an outer grounded cylindrical electrode and an inner coaxial electrode powered at 13.56 MHz rf. While passing through the plasma the feedgas becomes excited dissociated or ionized by electron impact. Once the gas exits the discharge volume ions and electrons are rapidly lost by recombination but the fast-flowing effluent still contains neutral metastable species (e.g. O 2 * He * ) and radicals (e.g. O OH). This reactive effluent has been shown to be an effective neutralizer of surrogates for anthrax spores and mustard blister agent. Unlike conventional wet decontamination methods the plasma effluent does not cause corrosion and it does not destroy wiring electronics or most plastics making it highly suitable for decontamination of sensitive equipment and interior spaces. Furthermore the reactive species in the effluent rapidly degrade into harmless products leaving no lingering residue or harmful by-products.

H. W. Herrmann; I. Henins; J. Park; G. S. Selwyn

1999-01-01T23:59:59.000Z

317

Decontamination and decommissioning surveillance and maintenance report for FY 1991. Environmental Restoration Program  

SciTech Connect

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.

Not Available

1991-12-01T23:59:59.000Z

318

Cold atmospheric pressure plasma and decontamination. Can it contribute to preventing hospital-acquired infections?  

Science Journals Connector (OSTI)

Summary Healthcare-associated infections (HCAIs) affect ?4.5 million patients in Europe alone annually. With the ever-increasing number of ‘multi-resistant’ micro-organisms, alternative and more effective methods of environmental decontamination are being sought as an important component of infection prevention and control. One of these is the use of cold atmospheric pressure plasma (CAPP) systems with clinical applications in healthcare facilities. \\{CAPPs\\} have been shown to demonstrate antimicrobial, antifungal and antiviral properties and have been adopted for other uses in clinical medicine over the past decade. \\{CAPPs\\} vary in their physical and chemical nature depending on the plasma-generating mechanism (e.g. plasma jet, dielectric barrier discharge, etc.). CAPP systems produce a ‘cocktail’ of species including positive and negative ions, reactive atoms and molecules (e.g. atomic oxygen, ozone, superoxide and oxides of nitrogen), intense electric fields, and ultraviolet radiation (UV). The effects of these ions have been studied on micro-organisms, skin, blood, and DNA; thus, a range of possible applications of \\{CAPPs\\} has been identified, including surface decontamination, wound healing, biofilm removal, and even cancer therapy. Here we evaluate plasma devices, their applications, mode of action and their potential role specifically in combating \\{HCAIs\\} on clinical surfaces.

N. O'Connor; O. Cahill; S. Daniels; S. Galvin; H. Humphreys

2014-01-01T23:59:59.000Z

319

DECONTAMINATION OF DREDGED MATERIAL FROM THE PORT OF NEW YORK AND NEW JERSEY.  

SciTech Connect

The Port of New York and New Jersey ranks first in the United States in volume of petroleum products handled each year. In addition, many refineries are in operation on the New Jersey side of the Port. These activities have led to the discharge of significant amounts of petroleum hydrocarbons into the waters of the New York/New Jersey region. Intense industrial and commercial activities have also brought about major inputs of other organic and inorganic contaminants as would be expected in an industrialized, heavily populated urban port. Sediments that then are contaminated are a major problem for the region since they can no longer be disposed of by the traditional method of ocean disposal following the dredging operations required for the efficient operation of the Port. Decontamination and beneficial reuse of the dredged materials is one component of a comprehensive dredged material management plan being developed by the US Army Corps of Engineers. A demonstration decontamination project extending from bench- to field-scale operations is now in progress in the Port, and its current status and relevance for other regions is summarized.

JONES,K.W.; STERN,E.A.; DONATO,K.R.; CLESCERI,N.L.

1999-06-01T23:59:59.000Z

320

DECONTAMINATION OF DREDGED MATERIAL FROM THE PORT OF NEW YORK AND NEW JERSEY  

SciTech Connect

The Port of New York and New Jersey ranks first in the US in volume of petroleum products handled each year. In addition, many refineries are in operation on the New Jersey side of the Port. These activities have led to the discharge of significant amounts of petroleum hydrocarbons into the waters of the New York/New Jersey region. Intense industrial and commercial activities have also brought about major inputs of other organic and inorganic contaminants as would be expected in an industrialized, heavily populated urban port. Sediments that then are contaminated are a major problem for the region since they can no longer be disposed of by the traditional method of ocean disposal following the dredging operations required for the efficient operation of the Port. Decontamination and beneficial reuse of the dredged materials is one component of a comprehensive dredged material management plan being developed by the US Army Corps of Engineers. A demonstration decontamination project extending from bench- to field-scale operations is now in progress in the Port, and its current status and relevance for other regions is summarized.

JONES,K.W.; STERN,E.A.; DONATO,K.R.; CLESCERI,N.L.

1999-06-01T23:59:59.000Z

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321

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

SciTech Connect

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

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

1994-02-01T23:59:59.000Z

322

Chemistry control and corrosion mitigation of heat transfer salts for the fluoride salt reactor (FHR)  

SciTech Connect

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)

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

323

Organic matter in the Paleogene west European rift: Bresse and Valence salt basins (France)  

SciTech Connect

The Bresse and Valence basins are two adjacent segments of the West European rift. They contain thick Paleogene halite sequences including intercalated and interfingering siliciclastic material and carbonate and sulfate deposits. Source rock samples in this study were mainly taken from the depocenters because of maximum sampling coverage. Organic matter (OM) is generally immature and occurs primarily within intercalated nonhalitic beds. The Bresse basin seems to contain more OM in (1) the Intermediate Salt Formation (Priabonian), composed of alternating laminated carbonate and halite beds; (2) the upper part of the Upper Salt Formation (clayey carbonate beds; Rupelian), affected by synsedimentary halite solution; and (3) the solution breccia which immediate overlies the salt sequence. In the Valence basin, the organic-rich layers are concentrated in the Subsalt Formation (carbonate beds; Priabonian), and the upper part of the Lower Salt Formation (laminates; Rupelian). In both basins, type III organic matter is associated with terrigenous facies. Type I is abundant in the Valence basin (laminites), and type II seems to be more abundant in the Bresse basin. The amount of OM varies considerably, and we suppose it is higher toward the basin margins. From studies made in evaporite basins in other region, which are also known to have significant amounts of organic matter, we find a similar range of organic composition. Such studies are of interest because of their petroleum potential and for understanding precise depositional environments and waste disposal problems (gas generation with local heat source).

Curial, A.; Dumas, D.; Moretto, R.

1988-08-01T23:59:59.000Z

324

Ethylenediamine salt of 5-nitrotetrazole and preparation  

DOE Patents (OSTI)

The ethylenediamine salt of 5-nitrotetrazole has been found to be useful as an explosive alone and in eutectic mixtures with ammonium nitrate and/or other explosive compounds. Its eutectic with ammonium nitrate has been demonstrated to behave in a similar manner to a monomolecular explosive such as TNT, and is less sensitive than the pure salt. Moreover, this eutectic mixture, which contains 87.8 mol% of ammonium nitrate, is close to the CO/sub 2/-balanced composition of 90 mol%, and has a relatively low melting point of 110.5 C making it readily castable. The ternary eutectic system containing the ethylenediamine salt of 5-nitrotetrazole, ammonium nitrate and ethylenediamine dinitrate has a eutectic temperature of 89.5 C and gives a measured detonation pressure of 24.8 GPa, which is 97.6% of the calculated value. Both the pure ethylenediamine salt and its known eutectic compounds behave in substantially ideal manner. Methods for the preparation of the salt are described.

Lee, K.; Coburn, M.D.

1984-05-17T23:59:59.000Z

325

Method for cleaning solution used in nuclear fuel reprocessing  

DOE Patents (OSTI)

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.

Tallent, O.K.; Crouse, D.J.; Mailen, J.C.

1980-12-17T23:59:59.000Z

326

Osmotic Pressure of Aqueous Chondroitin Sulfate Solution: A Molecular Modeling Investigation  

E-Print Network (OSTI)

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 ...

Bathe, Mark

327

Multi-parameter monitoring of a solution mining cavern collapse: first insight of precursors  

E-Print Network (OSTI)

Multi-parameter monitoring of a solution mining cavern collapse: first insight of precursors leveling; early warning system; environmental safety; salt cavern; near-surface geophysics. Mots clés

Paris-Sud XI, Université de

328

Method and apparatus for the in situ decontamination of underground water with the aid of solar energy  

DOE Patents (OSTI)

A method for the in situ decontamination of underground water containing -volatile contaminants comprising continuously contacting in situ underground water containing non-volatile contaminants with a liquid-absorbent material possessing high capillary activity, allowing the non-volatile contaminants to deposit in the material while the water moves upwardly through the material by capillary action, allowing substantially decontaminated water to be volatilized by impinging solar radiation, and then allowing the volatilized water to escape from the material into the atmosphere. An apparatus for the in situ decontamination of underground water containing non-volatile contaminants comprising at least one water-impermeable elongated conduit having an upper portion and first and second open ends and containing a homogeneous liquid-absorbent material possessing high capillary activity, means for supporting said conduit, and means for accelerating the escape of the volatilized decontamined water from the material, said means being detachably connected to the second end of the elongated conduit; wherein when underground water contaminated with non-volatile contaminants is continuously contacted in situ with the material contained in the first end of the conduit and the second end of the conduit is placed in contact with atmospheric air, non-volatile contaminants deposit in said material as the water moves upwardly through the material by capillary action, is then volatilized by impinging solar energy and escapes to the atmosphere.

Bench, Thomas R. (Pittsburgh, PA); McCann, Larry D. (Elizabeth, PA)

1989-01-01T23:59:59.000Z

329

Salt Wells Geothermal Project | Open Energy Information  

Open Energy Info (EERE)

Salt Wells Geothermal Project Salt Wells Geothermal Project Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Development Project: Salt Wells Geothermal Project Project Location Information Coordinates 39.580833333333°, -118.33444444444° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.580833333333,"lon":-118.33444444444,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

330

Geology of Damon Mound Salt Dome, Texas  

SciTech Connect

Geological investigation of the stratigraphy, cap-rock characteristics, deformation and growth history, and growth rate of a shallow coastal diapir. Damon Mound salt dome, located in Brazoria County, has salt less than 600 feet and cap rock less than 100 feet below the surface; a quarry over the dome provides excellent exposures of cap rock as well as overlying Oligocene to Pleistocene strata. These conditions make it ideal as a case study for other coastal diapirs that lack bedrock exposures. Such investigations are important because salt domes are currently being considered by chemical waste disposal companies as possible storage and disposal sites. In this book, the author reviews previous research, presents additional data on the subsurface and surface geology at Damon Mound, and evaluates Oligocene to post-Pleistocene diapir growth.

Collins, E.W.

1989-01-01T23:59:59.000Z

331

Molten nitrate salt technology development status report  

SciTech Connect

Recognizing thermal energy storage as potentially critical to the successful commercialization of solar thermal power systems, the Department of Energy (DOE) has established a comprehensive and aggressive thermal energy storage technology development program. Of the fluids proposed for heat transfer and energy storage molten nitrate salts offer significant economic advantages. The nitrate salt of most interest is a binary mixture of NaNO/sub 3/ and KNO/sub 3/. Although nitrate/nitrite mixtures have been used for decades as heat transfer and heat treatment fluids the use has been at temperatures of about 450/sup 0/C and lower. In solar thermal power systems the salts will experience a temperature range of 350 to 600/sup 0/C. Because central receiver applications place more rigorous demands and higher temperatures on nitrate salts a comprehensive experimental program has been developed to examine what effects, if any, the new demands and temperatures have on the salts. The experiments include corrosion testing, environmental cracking of containment materials, and determinations of physical properties and decomposition mechanisms. This report details the work done at Sandia National Laboratories in each area listed. In addition, summaries of the experimental programs at Oak Ridge National Laboratory, the University of New York, EIC Laboratories, Inc., and the Norwegian Institute of Technology on molten nitrate salts are given. Also discussed is how the experimental programs will influence the near-term central receiver programs such as utility repowering/industrial retrofit and cogeneration. The report is designed to provide easy access to the latest information and data on molten NaNO/sub 3//KNO/sub 3/ for the designers and engineers of future central receiver projects.

Carling, R.W.; Kramer, C.M.; Bradshaw, R.W.; Nissen, D.A.; Goods, S.H.; Mar, R.W.; Munford, J.W.; Karnowsky, M.M.; Biefeld, R.N.; Norem, N.J.

1981-03-01T23:59:59.000Z

332

Fast Spectrum Molten Salt Reactor Options  

SciTech Connect

During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

2011-07-01T23:59:59.000Z

333

Corrective Action Decision Document for Corrective Action Unit 254: Area 25 R-MAD Decontamination Facility, Nevada Test Site, Nevada  

SciTech Connect

This Corrective Action Decision Document identifies and rationalizes the US Department of Energy, Nevada Operations Office's selection of a recommended corrective action alternative (CAA) appropriate to facilitate the closure of Corrective Action Unit (CAU) 254, R-MAD Decontamination Facility, under the Federal Facility Agreement and Consent Order. Located in Area 25 at the Nevada Test Site in Nevada, CAU 254 is comprised of Corrective Action Site (CAS) 25-23-06, Decontamination Facility. A corrective action investigation for this CAS as conducted in January 2000 as set forth in the related Corrective Action Investigation Plan. Samples were collected from various media throughout the CAS and sent to an off-site laboratory for analysis. The laboratory results indicated the following: radiation dose rates inside the Decontamination Facility, Building 3126, and in the storage yard exceeded the average general dose rate; scanning and static total surface contamination surveys indicated that portions of the locker and shower room floor, decontamination bay floor, loft floor, east and west decon pads, north and south decontamination bay interior walls, exterior west and south walls, and loft walls were above preliminary action levels (PALs). The investigation-derived contaminants of concern (COCs) included: polychlorinated biphenyls, radionuclides (strontium-90, niobium-94, cesium-137, uranium-234 and -235), total volatile and semivolatile organic compounds, total petroleum hydrocarbons, and total Resource Conservation and Recovery Act (Metals). During the investigation, two corrective action objectives (CAOs) were identified to prevent or mitigate human exposure to COCs. Based on these CAOs, a review of existing data, future use, and current operations at the Nevada Test Site, three CAAs were developed for consideration: Alternative 1 - No Further Action; Alternative 2 - Unrestricted Release Decontamination and Verification Survey; and Alternative 3 - Unrestricted Release Decontamination and Verification Survey and Dismantling of Building 3126. These alternatives were evaluated based on four general corrective action standards and five remedy selection decision factors, and the preferred CAA chosen on technical merit was Alternative 2. This CAA was judged to meet all requirements for the technical components evaluated and applicable state and federal regulations for closure of the site, and reduce the potential for future exposure pathways.

U.S. Department of Energy, Nevada Operations Office

2000-06-01T23:59:59.000Z

334

Control of Soluble Salts in Farming and Gardening.  

E-Print Network (OSTI)

of Soluble Salts in Farming and Gardening This publication on soluble salts is dedicated to Dr. Paul Lyerl!. Resident Director of Texas A&M University Agricultural Research Center at El Paso. From his arrival at the Center in 1942 until his... 23 23 26 27 28 28 29 29 29 29 30 30 31 31 7- :.- 31 32 33 33 34 SUMMARY INTRODUCTION SOLUBLE SALTS IN WATERS AND SOILS Where Salts Come From Kinds and Amounts of Salt How Salt Problems Develop Definition of Terms...

Longenecker, D. E.; Lyerly, P. J.

1974-01-01T23:59:59.000Z

335

The Salt Industry at Sterling, Kansas  

E-Print Network (OSTI)

. Exhaust stean of the engine plant is ad- mitted to the first evaporator and warms the "brine, then passes to the second and warns it lesD and condenses, causing a partial vacuum in the first where the brine then boils violent- ly. The vapor thus... and is condensed by a jet condenser, whereupon the third boils. Each evaporator has its own electric prop- eller stirrers and its own electric elevator to remove the salt. Nearly all the handling is done by electric conveyors until the salt is discharged...

Horner, Robert Messenger

1914-01-01T23:59:59.000Z

336

The Effect of Salt Water on Rice.  

E-Print Network (OSTI)

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...

Fraps, G. S. (George Stronach)

1927-01-01T23:59:59.000Z

337

Interactions of Cl? and OH Radical in Aqueous Solution  

Science Journals Connector (OSTI)

There is a considerable controversy surrounding the nature of the Cl?/OH complex in aqueous solution, which appears as a byproduct of the irradiation of salt solutions in nuclear reactor operation, radioactive waste storage, medicine, and environmental problems. ... A similar process in the interfacial environment has been implicated in the production of molecular chlorine from sea salt aerosol, which ultimately could lead to enhanced ozone levels in the marine boundary layer. ... (2, 3) A detailed understanding of this reaction is hindered by uncertainty regarding the nature of the complex between OH and Cl? in aqueous environments. ...

Marat Valiev; Raffaella D’Auria; Douglas J. Tobias; Bruce C. Garrett

2009-07-10T23:59:59.000Z

338

Data summary report of commercial building experiments in Salt Lake City,  

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

Data summary report of commercial building experiments in Salt Lake City, Data summary report of commercial building experiments in Salt Lake City, UT from May 17 to June 10, 2002 Title Data summary report of commercial building experiments in Salt Lake City, UT from May 17 to June 10, 2002 Publication Type Report Year of Publication 2003 Authors Black, Douglas R., Tracy L. Thatcher, William W. Delp, Elisabeth A. Derby, Sheng-Chieh Chang, and Richard G. Sextro Abstract Under some circumstances, it may be desirable to provide all or part of a building with collective- protection against harmful chemical or biological (CB) agents. Collective-protection, as opposed to individual protection, uses the building -- its architecture, ventilation system, and control components -- to safeguard the health of the building occupants in the event of an indoor or outdoor release of toxic agents. In this study, we investigate the movement of tracer gases within a six-story building. The building was retrofitted to provide collective-protection on the upper two floors. To achieve this protection, the upper floors were over-pressurized using outside air that had passed through military specification carbon canisters and high-efficiency particulate air (HEPA) filters. The four lower floors were outside the collective-protection area and had a ventilation system that was retrofitted to provide response modes in the event of a CB release. These response modes (e.g. building flush and shelter in place) were designed to reduce the exposure of occupants on the lower floors without compromising the collective-protection zones. Over the course of four weeks, 16 tracer gas experiments were conducted to evaluate the collective- protection system (CPS) of the building's upper two floors and the ventilation response modes of the lower floors. Tracer gas concentrations were measured at a rate of 50 Hz in up to 30 locations in each experiment, which provided data with very high spatial and temporal resolution. Differential pressure and temperature measurements were also made throughout the building. Experiments showed that the CPS maintained a positive pressure differential between the upper two floors and the lower floors with various meteorological conditions and within specified settings of the HVAC fans serving the lower floors. However, the tracer experiments did show that a CB agent could enter the first zone of the decontamination areas on each CPS floor. Tracer gas analysis also showed that the shelter in place HVAC mode provided protection of lower floor occupants from an outdoor release by significantly lowering the air exchange rates on those floors. It was also determined that the efficacy of a flush mode triggered by an agent sensor depends greatly on the location of the sensor

339

Systems and strippable coatings for decontaminating structures that include porous material  

DOE Patents (OSTI)

Methods of removing contaminant matter from porous materials include applying a polymer material to a contaminated surface, irradiating the contaminated surface to cause redistribution of contaminant matter, and removing at least a portion of the polymer material from the surface. Systems for decontaminating a contaminated structure comprising porous material include a radiation device configured to emit electromagnetic radiation toward a surface of a structure, and at least one spray device configured to apply a capture material onto the surface of the structure. Polymer materials that can be used in such methods and systems include polyphosphazine-based polymer materials having polyphosphazine backbone segments and side chain groups that include selected functional groups. The selected functional groups may include iminos, oximes, carboxylates, sulfonates, .beta.-diketones, phosphine sulfides, phosphates, phosphites, phosphonates, phosphinates, phosphine oxides, monothio phosphinic acids, and dithio phosphinic acids.

Fox, Robert V. (Idaho Falls, ID); Avci, Recep (Bozeman, MT); Groenewold, Gary S. (Idaho Falls, ID)

2011-12-06T23:59:59.000Z

340

WVU cooperative agreement, decontamination systems information and research program, deployment support leading to implementation  

SciTech Connect

This program at West Virginia University is a Cooperative Agreement that focuses on R&D associated with hazardous waste remediation problems existing at DOE, Corps of Engineers, and private sector sites. The Agreement builds on a unique combination of resources coupling university researchers with DOE sponsored small businesses, leading toward field tests and large scale technology demonstrations of environmental technologies. Most of the Agreement`s projects are categorized in the Technology Maturity Levels under Gates 3-Advanced Development, Gate 4-Engineering Development, and Gate 5-Demonstration. The program includes a diversity of projects: subsurface contaminants; mixed wastes; mixed wastes/efficient separations; mixed wastes/characterization, monitoring, and sensor technologies; and decontamination and decommissioning/efficient separations.

Cook, E.E.

1996-12-31T23:59:59.000Z

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


341

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building  

SciTech Connect

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D&D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D&D plans for the turbine building were prepared from 1979 through 1990. D&D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D&D activities were completed with no radiation exposure to the workers. The D&D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

Arave, A.E.; Rodman, G.R.

1992-12-01T23:59:59.000Z

342

Final report of the decontamination and decommissioning of the BORAX-V facility turbine building  

SciTech Connect

The Boiling Water Reactor Experiment (BORAX)-V Facility Turbine Building Decontamination and Decommissioning (D D) Project is described in this report. The BORAX series of five National Reactor Testing Station (NRTS) reactors pioneered intensive work on boiling water reactor (BWR) experiments conducted between 1953 and 1964. Facility characterization, decision analyses, and D D plans for the turbine building were prepared from 1979 through 1990. D D activities of the turbine building systems were initiated in November of 1988 and completed with the demolition and backfill of the concrete foundation in March 1992. Due to the low levels of radioactivity and the absence of loose contamination, the D D activities were completed with no radiation exposure to the workers. The D D activities were performed in a manner that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) remain.

Arave, A.E.; Rodman, G.R.

1992-12-01T23:59:59.000Z

343

Decontamination of Radioactive Cesium Released from Fukushima Daiichi Nuclear Power Plant - 13277  

SciTech Connect

Peculiar binding of Cesium to the soil clay minerals remained the major obstacle for the immediate Cs-decontamination of soil and materials containing clay minerals like sludge. Experiments for the removal of Cesium from soil and ash samples from different materials were performed in the lab scale. For soil and sludge ash formed by the incineration of municipal sewage sludge, acid treatment at high temperature is effective while washing with water removed Cesium from ashes of plants or burnable garbage. Though total removal seems a difficult task, water-washing of wood-ash or garbage-ash at 40 deg. C removes >90% radiocesium, while >60% activity can be removed from soil and sludge-ash by acid washing at 95 deg. C. (authors)

Parajuli, Durga; Minami, Kimitaka; Tanaka, Hisashi; Kawamoto, Tohru [Nanosystem Research Institute, National Institute of Advanced Industrial Science and Technology - AIST (Japan)] [Nanosystem Research Institute, National Institute of Advanced Industrial Science and Technology - AIST (Japan)

2013-07-01T23:59:59.000Z

344

Apparatus for measuring the decontamination factor of a multiple filter air-cleaning system  

DOE Patents (OSTI)

An apparatus for measuring the overall decontamination factors of first and second filters located in a plenum. The first filter separates the plenum's upstream and intermediate chambers. The second filter separates the plenum's intermediate and downstream chambers. The apparatus comprises an aerosol generator that generates a challenge aerosol. An upstream collector collects unfiltered aerosol which is piped to first and second dilution stages and then to a laser aerosol spectrometer. An intermediate collector collects challenge aerosol that penetrates the first filter. The filtered aerosol is piped to the first dilution stage, diluted, and then piped to the laser aerosol spectrometer which detects single particles. A downstream collector collects challenge aerosol that penetrates both filters. The twice-filtered aerosol is piped to the aerosol spectrometer. A pump and several valves control the movement of aerosol within the apparatus.

Ortiz, J.P.

1985-07-03T23:59:59.000Z

345

Cost-benefits of a mobile, trailer-contained, vibratory finishing decontamination facility  

SciTech Connect

The objective of this study was to determine the cost-benefits of a vibratory finishing process, developed at Pacific Northwest Laboratory (PNL), which has been used successfully to remove a variety of transuranic (TRU) contaminants from surfaces of metallic and nonmetallic wastes. Once TRU contaminants are removed, the metallic and nonmetallic materials can be disposed of as low-level waste (LLW). Otherwise, these materials would be disposed of in geologic repositories. This study provides an economic evaluation of the vibratory finishing process as a possible method for use in decontaminating and decommissioning retired facilities at Hanford and oher sites. Specifically, the economic evaluation focuses on a scoping design for a mobile, trailer-contained facility, which could be used in the field in conjunction with decontamination and decommissioning operations. The capital cost of the mobile facility is estimated to be about $1.09 million including contingency and working capital. Annual operating costs, including disposal costs, are estimated to be $440,000 for processing about 6340 ft/sup 3//yr of pre-sectioned, TRU-contaminated material. Combining the operating cost and the capital cost, annualized at a discount rate of 10%, the total annual cost estimate is $602,000. The unit cost for vibratory finishing is estimated to be about $11/ft/sup 3/ of original reference glove box volume (Abrams et at. 1980). All costs are in first quarter 1981 dollars. Although not directly comparable, the unit cost for the vibratory finishing process is very favorable when considered beside typical, substantially higher, unit costs for processing and geologically disposing of TUR-contaminated materials. The probable accuracy of this study cost estimate is about +- 30%. It is therefore recommended that a detailed cost estimate be prepared if a mobile facility is designed.

Hazelton, R.F.; McCoy, M.W.

1982-07-01T23:59:59.000Z

346

State and Local Solution Center: Financing Solutions  

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

Technical Assistance Technical Assistance Resources Printable Version Share this resource Send a link to State and Local Solution Center: Financing Solutions to someone by E-mail Share State and Local Solution Center: Financing Solutions on Facebook Tweet about State and Local Solution Center: Financing Solutions on Twitter Bookmark State and Local Solution Center: Financing Solutions on Google Bookmark State and Local Solution Center: Financing Solutions on Delicious Rank State and Local Solution Center: Financing Solutions on Digg Find More places to share State and Local Solution Center: Financing Solutions on AddThis.com... Strategic Energy Planning Energy Policies & Programs Financing Financing Overview Financing Program Market Segments Energy Data Management Energy Technologies

347

Accelerators for Subcritical Molten-Salt Reactors  

SciTech Connect

Accelerator parameters for subcritical reactors have usually been based on using solid nuclear fuel much like that used in all operating critical reactors as well as the thorium burning accelerator-driven energy amplifier proposed by Rubbia et al. An attractive alternative reactor design that used molten salt fuel was experimentally studied at ORNL in the 1960s, where a critical molten salt reactor was successfully operated using enriched U235 or U233 tetrafluoride fuels. These experiments give confidence that an accelerator-driven subcritical molten salt reactor will work better than conventional reactors, having better efficiency due to their higher operating temperature, having the inherent safety of subcritical operation, and having constant purging of volatile radioactive elements to eliminate their accumulation and potential accidental release in dangerous amounts. Moreover, the requirements to drive a molten salt reactor can be considerably relaxed compared to a solid fuel reactor, especially regarding accelerator reliability and spallation neutron targetry, to the point that much of the required technology exists today. It is proposed that Project-X be developed into a prototype commercial machine to produce energy for the world by, for example, burning thorium in India and nuclear waste from conventional reactors in the USA.

Johnson, Roland (Muons, Inc.) [Muons, Inc.

2011-08-03T23:59:59.000Z

348

STANDARD OPERATING PROCEDURE HEAVY METAL SALTS (selected)  

E-Print Network (OSTI)

MSDS ___Special training provided by the department/supervisor ___Review of the OSHA Lab Standard ___Review of the departmental safety manual ___Review of the Chemical Hygiene Plan ___Safety meetings12.1 STANDARD OPERATING PROCEDURE for HEAVY METAL SALTS (selected) Location

Pawlowski, Wojtek

349

Solar with a Grain of Salt  

Science Journals Connector (OSTI)

...zone, and a bot-tom storage zone. The upper zone...electricity. Hot water is pumped out of the bottom zone...sequentially on the top of the storage zone. Howard C. Bryant...leached salts to the storage zone. One way to do...says French, but the seawater itself is turbid and...

THOMAS H. MAUGH II

1982-06-11T23:59:59.000Z

350

NOVEL GRAPHITE SALTS OF HIGH OXIDIZING POTENTIAL  

E-Print Network (OSTI)

hr volatiles none AsFS AsFS > CF4 AsFS AsFS AsFS C13.l AsF 6C16.l AsF 6 C24.3AsF6·l/2 F2 > CF4> CF4 > CF4 Table VI-7. Graphite hexafluoroarsenate salts +

McCarron III, Eugene Michael

2010-01-01T23:59:59.000Z

351

Salt repository project closeout status report  

SciTech Connect

This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs.

NONE

1988-06-01T23:59:59.000Z

352

Salt Wells, Eight Mile Flat | Open Energy Information  

Open Energy Info (EERE)

Salt Wells, Eight Mile Flat Salt Wells, Eight Mile Flat Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Salt Wells, Eight Mile Flat Abstract Abstract unavailable. Author Nevada Bureau of Mines and Geology Published Online Nevada Encyclopedia, 2009 DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for Salt Wells, Eight Mile Flat Citation Nevada Bureau of Mines and Geology. Salt Wells, Eight Mile Flat [Internet]. 2009. Online Nevada Encyclopedia. [updated 2009/03/24;cited 2013/08/07]. Available from: http://www.onlinenevada.org/articles/salt-wells-eight-mile-flat Related Geothermal Exploration Activities Activities (1) Areas (1) Regions (0) Development Wells At Salt Wells Area (Nevada Bureau of Mines and Geology, 2009) Salt Wells Geothermal Area

353

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

354

Brine Migration Experimental Studies for Salt Repositories | Department of  

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

Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Brine Migration Experimental Studies for Salt Repositories Experiments were used to examine water content in Permian salt samples (Salado Formation) collected from the WIPP site. The profile of water release and movement is recognized as a function of temperature from 30 to 275 oC using classical gravimetric methods to measure weight loss as a result of heating. The amount of water released from heating the salt was found to be correlated with the salts accessory mineral content (clay, other secondary minerals lost up to 3 wt % while pure halite salt lost less than 0.5 wt % water). Water released from salt at lower temperature was reversible and is attributed to clay hydration and dehydration processes. The analysis

355

Sandia National Laboratories: New Liquid Salt Electrolytes Could...  

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

ClimateECEnergyNew Liquid Salt Electrolytes Could Lead to Cost-Effective Flow Batteries New Liquid Salt Electrolytes Could Lead to Cost-Effective Flow Batteries Sandia Tool...

356

Corrosion Studies in High-Temperature Molten Salt Systems for...  

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

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...

357

Ketone Production from the Thermal Decomposition of Carboxylate Salts  

E-Print Network (OSTI)

The MixAlco process uses an anaerobic, mixed-culture fermentation to convert lignocellulosic biomass to carboxylate salts. The fermentation broth must be clarified so that only carboxylate salts, water, and minimal impurities remain. Carboxylate...

Landoll, Michael 1984-

2012-08-15T23:59:59.000Z

358

Energy Efficient Buildings, Salt Lake County, Utah  

SciTech Connect

Executive Summary Salt Lake County's Solar Photovoltaic Project - an unprecedented public/private partnership Salt Lake County is pleased to announce the completion of its unprecedented solar photovoltaic (PV) installation on the Calvin R. Rampton Salt Palace Convention Center. This 1.65 MW installation will be one the largest solar roof top installations in the country and will more than double the current installed solar capacity in the state of Utah. Construction is complete and the system will be operational in May 2012. The County has accomplished this project using a Power Purchase Agreement (PPA) financing model. In a PPA model a third-party solar developer will finance, develop, own, operate, and maintain the solar array. Salt Lake County will lease its roof, and purchase the power from this third-party under a long-term Power Purchase Agreement contract. In fact, this will be one of the first projects in the state of Utah to take advantage of the recent (March 2010) legislation which makes PPA models possible for projects of this type. In addition to utilizing a PPA, this solar project will employ public and private capital, Energy Efficiency and Conservation Block Grants (EECBG), and public/private subsidized bonds that are able to work together efficiently because of the recent stimulus bill. The project also makes use of recent changes to federal tax rules, and the recent re-awakening of private capital markets that make a significant public-private partnership possible. This is an extremely innovative project, and will mark the first time that all of these incentives (EECBG grants, Qualified Energy Conservation Bonds, New Markets tax credits, investment tax credits, public and private funds) have been packaged into one project. All of Salt Lake County's research documents and studies, agreements, and technical information is available to the public. In addition, the County has already shared a variety of information with the public through webinars, site tours, presentations, and written correspondence.

Barnett, Kimberly

2012-04-30T23:59:59.000Z

359

The Salt or Sodium Chloride Content of Feeds  

E-Print Network (OSTI)

1 EXAS AGRICULTURAL EXPERIMENT STATION AGRICULTURAL AND MECHANICAL COLLEGE OF TEXAS W. B. BIZZELL, Preeident BULLETIN NO. 271 OCTOBER, 1920 DIVISION OF CHEMISTRY THE SALT OR SODIUM CHLORIDE CONTENT OF FEEDS B. YOUNGBLOOD, DIRECTOK COLLEGE.... ............... Salt content of feecls.. ......... Salt content of mixed feeds.. ................... Summary ancl conclusions. Page. l1 [Blank Page in Original Bulletin] BULLETIN XO. 271. OCTOBE- '"On THE SALT OR SODIUM CHLORIDE CONTENT OF FEI The Texas feed...

Fraps, G. S. (George Stronach); Lomanitz, S. (Sebastian)

1920-01-01T23:59:59.000Z

360

Interactions among Plant Species and Microorganisms in Salt Marsh Sediments  

Science Journals Connector (OSTI)

...a New England salt marsh. Ecology 72: 138-148...L. Melville, and R. L. Peterson. 1994...Broome, and S. R. Shafer. 1993...mycorrhizae in salt marshes in North Carolina...a New England salt marsh. J. Ecol. 86: 285-292. 30 Linderman, R. G. 1988. Mycorrhizal...

David J. Burke; Erik P. Hamerlynck; Dittmar Hahn

2002-03-01T23:59:59.000Z

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


361

Self-potential monitoring of a salt plume  

Science Journals Connector (OSTI)

...salt-migration process. By this we...salt-migration process needs to be much...salt migration process is relatively...written as a MATLAB routine. The...The numerical simulation was used to compute...gradient in the chemical potential of...digitaledition.pdf .. Fournier...

P. Martínez-Pagán; A. Jardani; A. Revil; A. Haas

362

Production of carboxylic acid and salt co-products  

DOE Patents (OSTI)

This invention provide processes for producing carboxylic acid product, along with useful salts. The carboxylic acid product that is produced according to this invention is preferably a C.sub.2-C.sub.12 carboxylic acid. Among the salts produced in the process of the invention are ammonium salts.

Hanchar, Robert J.; Kleff, Susanne; Guettler, Michael V.

2014-09-09T23:59:59.000Z

363

Occurrence of gypsum in Gulf coast salt domes  

Science Journals Connector (OSTI)

...Occurrence of gypsum in Gulf coast salt domes Barton Donald Clinton...OF GYPSUM IN THE GULF COAST SALT DOMES. Sir: On accountof thepaucityof...concerningtheoccurrenceof gypsumandanhydriteon the salt domes. The followingremarksmay...5o-footsill of saltat 3,350feetat Palangana,possiblyalsoStrattonRidge...

Donald Clinton Barton

364

Structural restoration of Louann Salt and overlying sediments, De Soto Canyon Salt Basin, northeastern Gulf of Mexico  

E-Print Network (OSTI)

The continental margin of the northeastern Gulf of Mexico is suited for seismic stratigraphic analysis and salt tectonism analysis. Jurassic strata include the Louann Salt on the continental shelf and upper slope of the Destin Dome OCS area...

Guo, Mengdong

2012-06-07T23:59:59.000Z

365

Flow, Salts, and Trace Elements in the Rio Grande: A Review  

E-Print Network (OSTI)

must then focus on either in- creasing salt removal, minimizing salt inflow into the Rio Grande, or reducing evaporative losses of water, which concentrate salts. Although techniques to remove salts such as reverse os- mosis and electrodialysis exist...

Miyamoto, S.; Fenn, L. B.; Swietlik, D.

1995-01-01T23:59:59.000Z

366

Seismic stratigraphy and salt tectonics of the Alaminos Canyon area, Gulf of Mexico.  

E-Print Network (OSTI)

morphology, salt structure, and suprasalt sediments indicate the majority of the slope is covered by a shallow salt canopy. The salt structure map indicates that the Alaminos Canyon study area represents a transition from a semi-continuous salt sheet...

Mechler, Suzanne Marie

2012-06-07T23:59:59.000Z

367

SEDIMENT DECONTAMINATION TREATMENT TRAIN: COMMERCIAL-SCALE DEMONSTRATION FOR THE PORT OF NEW YORK/NEW JERSEY  

SciTech Connect

Decontamination and beneficial use of dredged material is a component of a comprehensive Dredged Material Management Plan for the Port of New York and New Jersey. The authors describe here a regional contaminated sediment decontamination program that is being implemented to meet the needs of the Port. The components of the train include: (1) dredging and preliminary physical processing (materials handling), (2) decontamination treatment, (3) beneficial use, and (4) public outreach. Several types of treatment technologies suitable for use with varying levels of sediment contamination have been selected based on the results of bench- and pilot-scale tests. This work is being conducted under the auspices of the Water Resources Development Act (WRDA). The use of sediment washing is suitable for sediments with low to moderate contamination levels, typical of industrialized waterways. BioGenesis Enterprises and Roy F. Weston, Inc. performed the first phase of an incremental decontamination demonstration with the goal of decontaminating 700 cubic yards (cy) (pilot-scale) for engineering design and cost economics information for commercial scale operations. This pilot test was completed in March, 1999. The next phase will scale-up to operation of a commercial facility capable of treating 40 cy/hr. It is anticipated that this will be completed by January 2000 (250,000 cy/yr). Manufactured topsoil is one beneficial use product from this process. Tests of two high-temperature treatment technologies are also in progress. They are well suited to produce almost complete destruction of organic compounds in moderate to highly contaminated dredged materials and for production of high-value beneficial reuse products. The Institute of Gas Technology is demonstrating a natural gas-fired thermochemical manufacturing process with an initial treatment capacity of 30,000 cy/yr into operation by the fall of 1999. Design and construction of a 100,000 cy/yr facility will be based on the operational results obtained from the demonstration facility. The decontaminated dredged material will be converted to a construction-grade cement. Prior bench- and pilot-scale tests showed that this treatment removes 99.99% of the organic contaminants and immobilizes the metals. The Westinghouse Science and Technology Center has demonstrated use of a high-temperature plasma to achieve 99.99% removal efficiencies for organic contaminants while immobilizing metals in a glass matrix. It was shown that a glass product such as tiles or fibers can be produced and that it can be used for manufacturing high quality glass tiles on a commercial scale.

JONES,K.W.; STERN,E.A.; DONATO,K.R.; CLESCERI,N.L.

1999-07-01T23:59:59.000Z

368

Enrichment and Association of Bacteria and Particulates in Salt Marsh Surface Water  

Science Journals Connector (OSTI)

...Sippewissett salt marsh, Falmouth, Massachusetts, and Palo Alto salt marsh...Sippewissett salt marsh, Falmouth, Massachusetts, and Palo Alto salt marsh...Sippewissett salt marsh, Falmouth, Massachusetts, and Palo Alto salt marsh...largely attributed to intense solar radiation. There have been...

R. W. Harvey; L. Y. Young

1980-04-01T23:59:59.000Z

369

Salt River Electric - Residential Energy Efficiency Rebate Program |  

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

Salt River Electric - Residential Energy Efficiency Rebate Program Salt River Electric - Residential Energy Efficiency Rebate Program Salt River Electric - Residential Energy Efficiency Rebate Program < Back Eligibility Residential Savings Category Home Weatherization Commercial Weatherization Sealing Your Home Heating & Cooling Construction Commercial Heating & Cooling Design & Remodeling Other Ventilation Heat Pumps Program Info State Kentucky Program Type Utility Rebate Program Rebate Amount Varies by technology Provider Salt River Electric Cooperative Salt River Electric serves as the rural electric provider in Kentucky's Bullitt, Nelson, Spencer, and Washington counties. Residential customers are eligible for a variety of cash incentives for energy efficiency. The Touchstone Energy Home Program provides a rebate of up to $250 to customers

370

CATALYTIC GASIFICATION OF COAL USING EUTECTIC SALT MIXTURES  

SciTech Connect

The Gas Research Institute (GRI) estimates that by the year 2010, 40% or more of U.S. gas supply will be provided by supplements including substitute natural gas (SNG) from coal. These supplements must be cost competitive with other energy sources. The first generation technologies for coal gasification e.g. the Lurgi Pressure Gasification Process and the relatively newer technologies e.g. the KBW (Westinghouse) Ash Agglomerating Fluidized-Bed, U-Gas Ash Agglomerating Fluidized-Bed, British Gas Corporation/Lurgi Slagging Gasifier, Texaco Moving-Bed Gasifier, and Dow and Shell Gasification Processes, have several disadvantages. These disadvantages include high severities of gasification conditions, low methane production, high oxygen consumption, inability to handle caking coals, and unattractive economics. Another problem encountered in catalytic coal gasification is deactivation of hydroxide forms of alkali and alkaline earth metal catalysts by oxides of carbon (CO{sub x}). To seek solutions to these problems, a team consisting of Clark Atlanta University (CAU, a Historically Black College and University, HBCU), the University of Tennessee Space Institute (UTSI) and Georgia Institute of Technology (Georgia Tech) proposed to identify suitable low melting eutectic salt mixtures for improved coal gasification. The research objectives of this project were to: Identify appropriate eutectic salt mixture catalysts for coal gasification; Assess agglomeration tendency of catalyzed coal; Evaluate various catalyst impregnation techniques to improve initial catalyst dispersion; Determine catalyst dispersion at high carbon conversion levels; Evaluate effects of major process variables (such as temperature, system pressure, etc.) on coal gasification; Evaluate the recovery, regeneration and recycle of the spent catalysts; and Conduct an analysis and modeling of the gasification process to provide better understanding of the fundamental mechanisms and kinetics of the process.

Dr. Yaw D. Yeboah; Dr. Yong Xu; Dr. Atul Sheth; Dr. Pradeep Agrawal

2001-12-01T23:59:59.000Z

371

Salt River Project | Open Energy Information  

Open Energy Info (EERE)

Project Project Jump to: navigation, search Name Salt River Project Place Tempe, Arizona Utility Id 16572 Utility Location Yes Ownership P NERC Location WECC NERC WECC Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Buying Transmission Yes Activity Distribution Yes Activity Wholesale Marketing Yes Activity Bundled Services Yes Alt Fuel Vehicle Yes Alt Fuel Vehicle2 Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] SGIC[2] Energy Information Administration Form 826[3] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Salt River Project Smart Grid Project was awarded $56,859,359 Recovery Act Funding with a total project value of $114,003,719.

372

Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance To The  

Open Energy Info (EERE)

Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance To The 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, search GEOTHERMAL ENERGYGeothermal Home Journal Article: Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance To The Hydrocarbon Exploration In The Tuz Golu (Salt Lake) Basin, Central Anatolia, Turkey Details Activities (0) Areas (0) Regions (0) Abstract: Due to activitiy of the Aksaray and Ecemis Faults, volcanic intrusion and westward movement of the Anatolian plate, diapiric salt structures were occurred in the Tuz Golu (Salt Lake) basin in central Anatolia, Turkey. With the collisions of the Arabian and Anatolian plates during the late Cretaceous and Miocene times, prominent ophiolitic

373

WIPP Shares Expertise with Salt Club Members | Department of Energy  

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

Shares Expertise with Salt Club Members Shares Expertise with Salt Club Members WIPP Shares Expertise with Salt Club Members November 26, 2013 - 12:00pm Addthis Carlsbad Field Office’s Abe Van Luik, third from right, examines rock salt taken from the Morsleben mine in Germany. Carlsbad Field Office's Abe Van Luik, third from right, examines rock salt taken from the Morsleben mine in Germany. CARLSBAD, N.M. - EM's Carlsbad Field Office (CBFO) participated in the second meeting of the Nuclear Energy Agency's (NEA) Salt Club and the 4th U.S.-German Workshop on Salt Repository Research, Design & Operation in Berlin. CBFO, which has responsibility for the Waste Isolation Pilot Plant (WIPP) and the National Transuranic (TRU) Program, was represented by International Programs and Policy Advisor Dr. Abe Van Luik.

374

Salt Waste Contractor Reaches Contract Milestone | Department of Energy  

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

Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone Salt Waste Contractor Reaches Contract Milestone April 29, 2013 - 12:00pm Addthis Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. Robert Brown, SRR tank farm operator, performs daily inspections of a salt disposition process facility. The inspections and improvement upgrades have resulted in continued successful operations. AIKEN, S.C. - The liquid waste cleanup contractor for the EM program at the Savannah River Site (SRS) recently surpassed a 2013 contract milestone by processing more than 600,000 gallons of salt waste. Savannah River Remediation (SRR) salt disposition process facilities

375

Molten Salt Heat Transfer Fluid (HTF)  

Sandia has developed a heat transfer fluid (HTF) for use at elevated temperatures that has a lower freezing point than any molten salt mixture available commercially. This allows the HTF to be used in applications in which the expensive parasitic energy costs necessary for freeze protection can be significantly reduced. The higher operating temperature limit significantly increases power cycle efficiency and overall power plan sun-to-net electric efficiency....

2013-03-12T23:59:59.000Z

376

Unravelling the Structure of Magnus’ Pink Salt  

Science Journals Connector (OSTI)

Two classic examples of colorful Pt complexes featuring metallophilic interactions are Magnus’ salts, which have a long history of eluding structural characterization. ... The complete 14N WURST-CPMG and BRAIN-CP/WURST-CPMG NMR spectra were generated by mirroring the low-frequency (right) portion of the powder pattern about ? = 0 ppm, as described previously. ... The microscope was equipped with a 32× Schwarzschild objective and a liquid nitrogen cooled mercury cadmium telluride detector. ...

Bryan E. G. Lucier; Karen E. Johnston; Wenqian Xu; Jonathan C. Hanson; Sanjaya D. Senanayake; Siyu Yao; Megan W. Bourassa; Monika Srebro; Jochen Autschbach; Robert W. Schurko

2013-12-13T23:59:59.000Z

377

Stationary phase deposition based on onium salts  

DOE Patents (OSTI)

Onium salt chemistry can be used to deposit very uniform thickness stationary phases on the wall of a gas chromatography column. In particular, the stationary phase can be bonded to non-silicon based columns, especially microfabricated metal columns. Non-silicon microfabricated columns may be manufactured and processed at a fraction of the cost of silicon-based columns. In addition, the method can be used to phase-coat conventional capillary columns or silicon-based microfabricated columns.

Wheeler, David R. (Albuquerque, NM); Lewis, Patrick R. (Albuquerque, NM); Dirk, Shawn M. (Albuquerque, NM); Trudell, Daniel E. (Albuquerque, NM)

2008-01-01T23:59:59.000Z

378

Salt Lake County Residential Solar Financing Study  

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

As part of our engagement with the National Renewable Energy Laboratories conducting the Salt Lake County Solar America Residential Finance Study, we have drafted this report summarizing the tools and mechanisms available for residential solar projects. These include the financial incentives available, possible financing models that could be used in the County, and a review of the community-scale solar project in St. George, Utah. We have also provided cost estimates for each system.

379

FINAL REPORT U.S. Department of Energy Waste Volume Reduction Using Surface Characterization and Decontamination by  

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

REPORT REPORT U.S. Department of Energy Waste Volume Reduction Using Surface Characterization and Decontamination by Laser Ablation Principal Investigator: Michael J. Pellin Institution: Argonne National Laboratory Collaborators: Michael R, Savina, Claude B. Reed, Zhiyue Xu, Yong Wang Institutions: Argonne National Laboratory Project Number: 60283 Grant Number: W-31-109-ENG-38 Grant Project Officers: C. Miller Project Duration: October 1, 1997 - October 1, 2000 2 Table of Contents Table of Contents............................................................................................................................ 2 Executive Summary ........................................................................................................................ 3 Research Objectives........................................................................................................................

380

New public information resources on salt caverns.  

SciTech Connect

For the past decade, interest has been growing in using underground salt caverns for disposing of wastes. The Railroad Commission of Texas has permitted a few caverns for disposal of nonhazardous oil field waste (NOW) and one cavern for disposal of naturally occurring radioactive materials (NORM) from oil field activities. Several salt caverns in Canada have also been permitted for disposal of NOW. In addition, oil and gas agencies in Louisiana and New Mexico are developing cavern disposal regulations. The US Department of Energy (DOE) has funded several studies to evaluate the technical feasibility, legality, economic viability, and risk of disposing of NOW and NORM in caverns. The results of these studies have been disseminated to the scientific and regulatory communities. However, as use of caverns for waste disposal increases, more government and industry representatives and members of the public will become aware of this practice and will need adequate information about how disposal caverns operate and the risks they pose. In anticipation of this need, DOE has funded Argonne National Laboratory to develop a salt cavern public outreach program. Key components of this program are an informational brochure designed for nontechnical persons and a website that provides greater detail on cavern operations and allows downloadable access to the reports on the topic funded by DOE. This paper provides an overview of the public outreach program.

Tomasko, D.; Veil, J. A.

1999-08-25T23:59:59.000Z

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


381

New public information resources on salt caverns.  

SciTech Connect

For the past decade, interest has been growing in using underground salt caverns for disposing of wastes. The Railroad Commission of Texas has permitted a few caverns for disposal of nonhazardous oil field waste (NOW) and one cavern for disposal of naturally occurring radioactive materials (NORM) from oil field activities. Several salt caverns in Canada have also been permitted for disposal of NOW. In addition, oil and gas agencies in Louisiana and New Mexico are developing cavern disposal regulations. The US Department of Energy (DOE) has funded several studies to evaluate the technical feasibility, legality, economic viability, and risk of disposing of NOW and NORM in caverns. The results of these studies have been disseminated to the scientific and regulatory communities. However, as use of caverns for waste disposal increases, more government and industry representatives and members of the public will become aware of this practice and will need adequate information about how disposal caverns operate and the risks they pose. In anticipation of this need, DOE has fi.mded Argonne National Laboratory to develop a salt cavern public outreach program. Key components of this program are an informational brochure designed for nontechnical persons and a website that provides greater detail on cavern operations and allows downloadable access to the reports on the topic funded by DOE. This paper provides an overview of the public outreach program.

Tomasko, D.; Veil, J. A.

1999-08-25T23:59:59.000Z

382

Evaluation of nuclear facility decommissioning projects. Three Mile Island Unit 2 reactor building decontamination. Summary status report. Volume 2  

SciTech Connect

This document summarizes information relating to decontamination of the Three Mile Island Unit 2 (TMI-2) reactor building. The report covers activities for the period of June 1, 1979 through March 29, 1985. The data collected from activity reports, reactor containment entry records, and other sources were entered into a computerized data system which permits extraction/manipulation of specific information which can be used in planning for recovery from an accident similar to that experienced at TMI-2 on March 28, 1979. This report contains summaries of man-hours, manpower, and radiation exposures incurred during decontamination of the reactor building. Support activities conducted outside of radiation areas are excluded from the scope of this report. Computerized reports included in this document are: a chronological summary listing work performed relating to reactor building decontamination for the period specified; and summary reports for each major task during the period. Each task summary is listed in chronological order for zone entry and subtotaled for the number of personnel entries, exposures, and man-hours. Manually-assembled table summaries are included for: labor and exposures by department and labor and exposures by major activity.

Doerge, D.H.; Miller, R.L.; Scotti, K.S.

1986-05-01T23:59:59.000Z

383

Y-12 Plant decontamination and decommissioning technology logic diagram for Building 9201-4. Volume 2: Technology logic diagram  

SciTech Connect

The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 (TLD) was developed to provide a decision-support tool that relates decontamination and decommissioning (D and D) problems at Bldg. 9201-4 to potential technologies that can remediate these problems. This TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to D and D and waste management (WM) activities. It is essential that follow-on engineering studies be conducted to build on the output of this project. These studies will begin by selecting the most promising technologies identified in the TLD and by finding an optimum mix of technologies that will provide a socially acceptable balance between cost and risk. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 2 has been divided into five sections: Characterization, Decontamination, Dismantlement, Robotics/Automation, and Waste Management. Each section contains logical breakdowns of the Y-12 D and D problems by subject area and identifies technologies that can be reasonably applied to each D and D challenge.

NONE

1994-09-01T23:59:59.000Z

384

Chemistry and mechanism of molten-salt catalysts in coal-gasification processes. Final report, January 1984-January 1985  

SciTech Connect

Alkali metal salts have been recognized as effective catalysts in coal gasification. However, the presence of reducing gases, in particular carbon monoxide, has recently been shown to have serious inhibitory effects on the catalyst performance. This program has addressed the question of the chemical interactions between carbon monoxide gas containing mixtures and the salt catalysts in liquid form by probing the solution chemistry by dynamic electrochemical techniques. The results of this study show that oxalate ions are formed by the reaction between carbonate ions and carbon monoxide gas. At temperatures above 700/sup 0/C, sulfate ions are directly attacked by carbon monoxide. The oxalate ions are electroactive and their electrochemistry has been studied and found to involve adsorption of oxalate and formation of reactive intermediates. The pathway likely involves an ECE sequence. The formation of active adsorbed species such as oxalate or sulfides at high temperature may be the means by which catalytic function of the salts is inhibited.

White, S.H.; Twardoch, U.M.

1985-02-01T23:59:59.000Z

385

A hypothesis concerning the distribution of salt and salt structures in the Gulf of Mexico  

E-Print Network (OSTI)

A IIYPO'rklESIS CO/iCI, RI~ IG TktE DISTRIIoUTIO l OE SALT I'D cAET STRU TURES Rci TIIE GU:I 0= VEXICO A Thesis by JOIIN 'O'OODYJ ORTII A ?TOINE Subrnitte. ' to th, Graouate CoU~ Se Texas A i~. '4 University in partial fv~t'Ub~s "u o I... the reouirernent 'or th ~ cl . . gree o', ' i%I A S T E R 0 E S C IF. U C E ivla y 1 9 I 6 Mr jo? Subject: Geolnsical Oceanography A HYPOTHESIS CONCERNING THE DISTRIBUTION OF SALT AND SALT STRUCTURES IN THE GULF OF MEXICO A Thesis by JOHN WOODWORTH ANTOINE...

Antoine, John Woodworth

2012-06-07T23:59:59.000Z

386

Treatment requirements for decontamination of ORNL low-level liquid waste  

SciTech Connect

Experimental studies have been made to provide data for the development of improved processes for decontaminating low-level liquid wastes (LLLWs) that exist and continue to be generated at Oak Ridge National Laboratory. The concept underlying this work is that there is a net benefit if the major radionuclides ({sup 137}Cs, {sup 134}Cs, {sup 90}Sr, and actinides) can be separated into small volumes, thereby reducing the activity of the bulk of the waste so that it can be disposed of or managed at a lower total cost. Data-base calculations on the LLLW supernate and sludges contained in the active Melton Valley Storage Tanks and evaporator storage and service tanks are essential in order to define and determine the extent of the problem. These calculations indicate to what extent alpha- and beta-gamma-emitting radionuclides must be removed and/or treated before final disposition of the waste can be made. They also show that many of the inorganic constitutents (e.g., regulated metals and nitrate) and minor radionuclides such as {sup 14}C and actinides (in terms of quantity present) must be removed before the LLLW can be disposed of as either liquid to the environment or solidified and disposed of as solid NUS Class L-1 or L-2 LLW. 25 refs., 31 tabs.

Lee, D.D.; Campbell, D.O.

1991-10-01T23:59:59.000Z

387

Proceedings of the workshop on transite decontamination dismantlement and recycle/disposal  

SciTech Connect

On February 3--4, 1993, a workshop was conducted to examine issues associated with the decontamination, dismantlement, and recycle/disposal of transite located at the US Department of Energy Fernald site near Cincinnati, OH. The Fernald Environmental Management Project (FEMP) is a Superfund Site currently undergoing remediation. A major objective of the workshop was to assess the state-of-the-art of transite remediation, and generate concepts that could be useful to the Fernald Environmental Restoration Management Co. (FERMCO) for remediation of transite. Transite is a building material consisting of asbestos fiber and cement and may be radioactively contaminated as a result of past uranium processing operations at the FEMP. Many of the 100 buildings within the former uranium production area were constructed of transite siding and roofing and consequently, over 180,000 m{sup 2} of transite must be disposed or recycled. Thirty-six participants representing industry, academia, and government institutions such as the EPA and DOE assembled at the workshop to present their experience with transite, describe work in progress, and address the issues involved in remediating transite.

Not Available

1993-12-31T23:59:59.000Z

388

Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas  

SciTech Connect

This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

389

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory  

SciTech Connect

The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

Fellhauer, C.R.; Boing, L.E. [Argonne National Lab., IL (United States); Aldana, J. [NES, Inc., Danbury, CT (United States)

1997-03-01T23:59:59.000Z

390

Engineering evaluation/cost analysis for decontamination at the St. Louis Downtown Site, St. Louis, Missouri  

SciTech Connect

The US Department of Energy (DOE) is implementing a cleanup program for three groups of properties in the St. Louis, Missouri, area: the St. Louis Downtown Site (SLDS), the St. Louis Airport Site (SLAPS) and vicinity properties, and the Latty Avenue Properties, including the Hazelwood Interim Storage Site (HISS). The general location of these properties is shown in Figure 1; the properties are referred to collectively as the St. Louis Site. None of the properties are owned by DOE, but each property contains radioactive residues from federal uranium processing activities conducted at the SLDS during and after World War 2. The activities addressed in this environmental evaluation/cost analysis (EE/CA) report are being proposed as interim components of a comprehensive cleanup strategy for the St. Louis Site. As part of the Department's Formerly Utilized Sites Remedial Action Program (FUSRAP), DOE is proposing to conduct limited decontamination in support of proprietor-initiated activities at the SLDS, commonly referred to as the Mallinckrodt Chemical Works. The primary goal of FUSRAP activity at the SLDS is to eliminate potential environmental hazards associated with residual contamination resulting from the site's use for government-funded uranium processing activities. 17 refs., 3 figs., 5 tabs.

Picel, M.H.; Hartmann, H.M.; Nimmagadda, M.R. (Argonne National Lab., IL (USA)); Williams, M.J. (Bechtel National, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

391

A Simplified Solution For Gas Flow During a Blow-out in an H2 or Air Storage Cavern  

E-Print Network (OSTI)

and hydrogen storage in salt caverns. Compressed Air Energy Storage (CAES) is experiencing a rise in interest-form solutions of the blow-out problem. These solutions are applied to the cases of compressed air storageA Simplified Solution For Gas Flow During a Blow-out in an H2 or Air Storage Cavern Pierre BĂ©rest

Boyer, Edmond

392

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

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

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

2011-01-01T23:59:59.000Z

393

Destruction of XM-46 (aka LGP-1846) using the Molten Salt Destruction Process  

SciTech Connect

The experimental work done on the destruction of the liquid gun propellant XM-46 (or LGP-1846) using the Molten Salt Destruction (MSD) Process at the Lawrence Livermore National Laboratory (LLNL) for the US Army is described in this report. The current methods of disposal of large quantities of high explosives (HE), propellants and wastes containing energetic materials by open burning or open detonation (OB/OD), or by incineration, are becoming undesirable. LLNL is developing MSD as an alternative to OB/OD and incineration of energetic materials. A series of 18 continuous experimental runs were made wherein a solution of XM-46 and water was injected into a bed of molten salt comprising the carbonates of sodium, potassium and lithium, along with air. The results from these experiments, described in detail in the main body of this report, show that: XM-46 can be safely and completely destroyed in a bed of molten salt at temperatures well below those needed for incineration. Under optimum operating conditions, less than 1% of the chemically bound nitrogen in the XM-46 is converted to NO{sub x}, and less than 1% carbon is converted to CO. There exist, however, a number of technical uncertainties: We need to understand better why nitrates build up in the salt bath, and what we can do to reduce this amount. We need to understand the mechanism of XM-46 oxidation and ways to minimize the formation of CO and NO{sub x}. In addition, we would like to find out ways by which a more concentrated solution of XM-46 can be introduced into the reactor, so as to increase the throughputs.

Upadhye, R.S.; Watkins, B.E.

1994-03-01T23:59:59.000Z

394

Development of Molten-Salt Heat Transfer Fluid Technology for Parabolic Trough Solar Power Plants - Public Final Technical Report  

SciTech Connect

Executive Summary This Final Report for the "Development of Molten-Salt Heat Transfer Fluid (HTF) Technology for Parabolic Trough Solar Power Plants” describes the overall project accomplishments, results and conclusions. Phase 1 analyzed the feasibility, cost and performance of a parabolic trough solar power plant with a molten salt heat transfer fluid (HTF); researched and/or developed feasible component options, detailed cost estimates and workable operating procedures; and developed hourly performance models. As a result, a molten salt plant with 6 hours of storage was shown to reduce Thermal Energy Storage (TES) cost by 43.2%, solar field cost by 14.8%, and levelized cost of energy (LCOE) by 9.8% - 14.5% relative to a similar state-of-the-art baseline plant. The LCOE savings range met the project’s Go/No Go criteria of 10% LCOE reduction. Another primary focus of Phase 1 and 2 was risk mitigation. The large risk areas associated with a molten salt parabolic trough plant were addressed in both Phases, such as; HTF freeze prevention and recovery, collector components and piping connections, and complex component interactions. Phase 2 analyzed in more detail the technical and economic feasibility of a 140 MWe,gross molten-salt CSP plant with 6 hours of TES. Phase 2 accomplishments included developing technical solutions to the above mentioned risk areas, such as freeze protection/recovery, corrosion effects of applicable molten salts, collector design improvements for molten salt, and developing plant operating strategies for maximized plant performance and freeze risk mitigation. Phase 2 accomplishments also included developing and thoroughly analyzing a molten salt, Parabolic Trough power plant performance model, in order to achieve the project cost and performance targets. The plant performance model and an extensive basic Engineering, Procurement, and Construction (EPC) quote were used to calculate a real levelized cost of energy (LCOE) of 11.50˘/kWhe , which achieved the Phase 2 Go/No Go target of less than 0.12˘/kWhe. Abengoa Solar has high confidence that the primary risk areas have been addressed in the project and a commercial plant utilizing molten salt is economically and technically feasible. The strong results from the Phase 1 and 2 research, testing, and analyses, summarized in this report, led Abengoa Solar to recommend that the project proceed to Phase 3. However, a commercially viable collector interconnection was not fully validated by the end of Phase 2, combined with the uncertainty in the federal budget, forced the DOE and Abengoa Solar to close the project. Thus the resources required to construct and operate a molten salt pilot plant will be solely supplied by Abengoa Solar.

Grogan, Dylan C. P.

2013-08-15T23:59:59.000Z

395

Corrective Action Investigation Plan for Corrective Action Unit 252: Area 25 Engine Test Stand 1 Decontamination Pad, Nevada Test Site, Nevada  

SciTech Connect

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit 252 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 252 consists of Corrective Action Site (CAS) 25-07-02, Engine Test Stand-1 (ETS-1) Decontamination Pad. Located in Area 25 at the intersection of Road H and Road K at the Nevada Test Site, ETS-1 was designed for use as a mobile radiation checkpoint and for vehicle decontamination. The CAS consists of a concrete decontamination pad with a drain, a gravel-filled sump, two concrete trailer pads, and utility boxes. Constructed in 1966, the ETS-1 facility was part of the Nuclear Rocket Development Station (NRDS) complex and used to test nuclear rockets. The ETS-1 Decontamination Pad and mobile radiation check point was built in 1968. The NRDS complex ceased primary operations in 1973. Based on site history, the focus of the field investigation activities will be to determine if any primary contaminants of potential concern (COPCs) (including radionuclides, total volatile organic compounds, total semivolatile organic compounds, total petroleum hydrocarbons as diesel-range organics, Resource Conservation and Recovery Act metals, total pesticides, and polychlorinated biphenyls) are present at this site. Vertical extent of migration of suspected vehicle decontamination effluent COPCs is expected to be less than 12 feet below ground surface. Lateral extent of migration of COPCs is expected to be limited to the sump area or near the northeast corner of the decontamination pad. Using a biased sampling approach, near-surface and subsurface sampling will be conducted at the suspected worst-case areas including the sump and soil near the northeast corner of the decontamination pad. The results of this field investigation will support a defensible e valuation of corrective action alternatives in the corrective action decision document.

U.S. Department of Energy, Nevada Operations Office

1999-08-20T23:59:59.000Z

396

Independent Oversight Assessment, Salt Waste Processing Facility Project -  

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

Salt Waste Processing Facility Salt Waste Processing Facility Project - January 2013 Independent Oversight Assessment, 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 of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent assessment of nuclear safety culture at the Salt Waste Processing Facility (SWPF) Project. The primary objective of the evaluation was to provide information regarding the status of the safety culture at the SWPF Project. The data collection phase of the assessment occurred during August - September 2012. Independent Oversight Assessment, Salt Waste Processing Facility Project -

397

Disposing of nuclear waste in a salt bed  

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

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

398

Salt tectonics, patterns of basin fill, and reservoir distribution  

SciTech Connect

Salt structures, which develop due to sediment loading, gravity creep, and/or buoyance, include boundary-fault grabens and half grabens, rollers, anticlines, domes and walls, diapirs, sills, massifs, and compressional toe structure. Associated features include fault systems and turtle structures. Of these, six directly relate to basin fill and all directly influence the distribution of reservoir facies. Salt structuring is initiated by sedimentation, which in turn is localized by salt withdrawal. Withdrawal produces individual salt structures, migrating sills, dissected massifs, and regional depocenters bordered by salt walls. Composite withdrawals dictate the patterns of basin fill. Relative rates of structural growth and sedimentation control the distribution of reservoir facies. When growth dominates, sands are channeled into lows. When sedimentation dominates and maintains flat surfaces, facies distribution is not impacted except where faulting develops. This paper presents techniques for using seismic data to determine the controls on salt structural growth and sedimentation and the patterns of basin fill and reservoir distribution.

Yorston, H.J.; Miles, A.E.

1988-01-01T23:59:59.000Z

399

Supai salt karst features: Holbrook Basin, Arizona  

SciTech Connect

More than 300 sinkholes, fissures, depressions, and other collapse features occur along a 70 km (45 mi) dissolution front of the Permian Supai Formation, dipping northward into the Holbrook Basin, also called the Supai Salt Basin. The dissolution front is essentially coincident with the so-called Holbrook Anticline showing local dip reversal; rather than being of tectonic origin, this feature is likely a subsidence-induced monoclinal flexure caused by the northward migrating dissolution front. Three major areas are identified with distinctive attributes: (1) The Sinks, 10 km WNW of Snowflake, containing some 200 sinkholes up to 200 m diameter and 50 m depth, and joint controlled fissures and fissure-sinks; (2) Dry Lake Valley and contiguous areas containing large collapse fissures and sinkholes in jointed Coconino sandstone, some of which drained more than 50 acre-feet ({approximately}6 {times} 10{sup 4} m{sup 3}) of water overnight; and (3) the McCauley Sinks, a localized group of about 40 sinkholes 15 km SE of Winslow along Chevelon Creek, some showing essentially rectangular jointing in the surficial Coconino Formation. Similar salt karst features also occur between these three major areas. The range of features in Supai salt are distinctive, yet similar to those in other evaporate basins. The wide variety of dissolution/collapse features range in development from incipient surface expression to mature and old age. The features began forming at least by Pliocene time and continue to the present, with recent changes reportedly observed and verified on airphotos with 20 year repetition. The evaporate sequence along interstate transportation routes creates a strategic location for underground LPG storage in leached caverns. The existing 11 cavern field at Adamana is safely located about 25 miles away from the dissolution front, but further expansion initiatives will require thorough engineering evaluation.

Neal, J.T.

1994-12-31T23:59:59.000Z

400

Consolidation and permeability of salt in brine  

SciTech Connect

The consolidation and loss of permeability of salt crystal aggregates, important in assessing the effects of water in salt repositories, has been studied as a function of several variables. The kinetic behavior was similar to that often observed in sintering and suggested the following expression for the time dependence of the void fraction: phi(t) = phi(0) - (A/B)ln(1 + Bt/z(0)/sup 3/), where A and B are rate constants and z(0) is initial average particle size. With brine present, A and phi(0) varied linearly with stress. The initial void fraction was also dependent to some extent on the particle size distribution. The rate of consolidation was most rapid in brine and least rapid in the presence of only air as the fluid. A brine containing 5 m MgCl/sub 2/ showed an intermediate rate, presumably because of the greatly reduced solubility of NaCl. A substantial wall effect was indicated by an observed increase in the void fraction of consolidated columns with distance from the top where the stress was applied and by a dependence of consolidation rate on the column height and radius. The distance through which the stress fell by a factor of phi was estimated to change inversely as the fourth power of the column diameter. With increasing temperature (to 85/sup 0/C), consolidation proceeded somewhat more rapidly and the wall effect was reduced. The permeability of the columns dropped rapidly with consolidation, decreasing with about the sixth power of the void fraction. In general, extrapolation of the results to repository conditions confirms the self-sealing properties of bedded salt as a storage medium for radioactive waste.

Shor, A.J.; Baes, C.F. Jr.; Canonico, C.M.

1981-07-01T23:59:59.000Z

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


401

Experimental studies of actinides in molten salts  

SciTech Connect

This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen-containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of actinide elements and compounds, and measurements of various properties of the molten volts. Property measurements discussed are phase relationships, vapor pressure, density, viscosity, absorption spectra, electromotive force, and conductance. 188 refs., 17 figs., 6 tabs.

Reavis, J.G.

1985-06-01T23:59:59.000Z

402

Salt River Project electric vehicle program  

SciTech Connect

Electric vehicles (EV) promise to be a driving force in the future of America. The quest for cleaner air and efforts to trim the nation's appetite for foreign oil are among the reasons why. America's EV future is rapidly approaching, with major automakers targeting EV mass production and sales before the end of the decade. This article describes the Salt River Project (SRP), a leader among electric utilities involved in EV research and development (R and D). R and D efforts are underway to plan and prepare for a significant number of EVs in SRP's service territory and to understand the associated recharging requirements for EVs.

Morrow, K.P.

1994-11-01T23:59:59.000Z

403

Delivery system for molten salt oxidation of solid waste  

DOE Patents (OSTI)

The present invention is a delivery system for safety injecting solid waste particles, including mixed wastes, into a molten salt bath for destruction by the process of molten salt oxidation. The delivery system includes a feeder system and an injector that allow the solid waste stream to be accurately metered, evenly dispersed in the oxidant gas, and maintained at a temperature below incineration temperature while entering the molten salt reactor.

Brummond, William A. (Livermore, CA); Squire, Dwight V. (Livermore, CA); Robinson, Jeffrey A. (Manteca, CA); House, Palmer A. (Walnut Creek, CA)

2002-01-01T23:59:59.000Z

404

Integrated demonstration of molten salt oxidation with salt recycle for mixed waste treatment  

SciTech Connect

Molten Salt Oxidation (MSO) is a thermal, nonflame process that has the inherent capability of completely destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility and constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are performed under carefully controlled (experimental) conditions. The system consists of a MSO processor with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. This integrated system was designed and engineered based on laboratory experience with a smaller engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. In this paper we present design and engineering details of the system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is identification of the most suitable waste streams and waste types for MSO treatment.

Hsu, P.C.

1997-11-01T23:59:59.000Z

405

Columbus Salt Marsh Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Columbus Salt Marsh Geothermal Area Columbus Salt Marsh Geothermal Area (Redirected from Columbus Salt Marsh Area) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Columbus Salt Marsh Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (3) 10 References Area Overview Geothermal Area Profile Location: California Exploration Region: Walker-Lane Transition Zone Geothermal Region GEA Development Phase: 2008 USGS Resource Estimate Mean Reservoir Temp: Estimated Reservoir Volume: Mean Capacity: Click "Edit With Form" above to add content History and Infrastructure

406

salt-water pumped-storage hydroelectric plant  

Science Journals Connector (OSTI)

salt-water pumped-storage hydroelectric plant, saltwater pumped-storage hydroelectric station, seawater pumped-storage hydroelectric plant, seawater pumped-storage hydroelectric station ? Salzwasser-...

2014-08-01T23:59:59.000Z

407

Independent Oversight Review, Savannah River Site Salt Waste...  

Energy Savers (EERE)

Waste Treatment and Immobilization Plant - May 2013 Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project - February 2013 CRAD,...

408

Sedimentation and resuspension in a New England salt marsh  

Science Journals Connector (OSTI)

Particulate matter in a salt marsh can undergo repeated sedimentation and resuspension. Sedimentation measured with sediment traps, increases ... suggests that sedimentation is more than offset by resuspension. Resuspension

Thomas E. Jordan; Ivan Valiela

1983-01-23T23:59:59.000Z

409

Method for the production of uranium chloride salt  

DOE Patents (OSTI)

A method for the production of UCl.sub.3 salt without the use of hazardous chemicals or multiple apparatuses for synthesis and purification is provided. Uranium metal is combined in a reaction vessel with a metal chloride and a eutectic salt- and heated to a first temperature under vacuum conditions to promote reaction of the uranium metal with the metal chloride for the production of a UCl.sub.3 salt. After the reaction has run substantially to completion, the furnace is heated to a second temperature under vacuum conditions. The second temperature is sufficiently high to selectively vaporize the chloride salts and distill them into a condenser region.

Westphal, Brian R.; Mariani, Robert D.

2013-07-02T23:59:59.000Z

410

Project Profile: Molten Salt-Carbon Nanotube Thermal Storage  

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

Texas Engineering Experiment Station (TEES), under the Thermal Storage FOA, created a composite thermal energy storage material by embedding nanoparticles in a molten salt base material.

411

Notice of Availability of Section 3116 Determination for Salt...  

Office of Environmental Management (EM)

in the SPA SEIS, short- term impacts are incurred during operation of the salt waste processing facilities, and long-term impacts are those resulting from release of...

412

Fundamental Corrosion Studies in High-Temperature Molten Salt...  

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

Studies in High-Temperature Molten Salt Systems for CSP Applications Savannah River National Laboratory April 15, 2013 | Garcia-Diaz * The overall project approach will combine...

413

Corrosion Studies in High-Temperature Molten Salt Systems for...  

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

Studies in High-Temperature Molten Salt Systems for CSP Applications Savannah River National Laboratory Garcia-Diaz A 1152013:Garcia-Diaz * The overall project approach will...

414

Multispectral Imaging At Columbus Salt Marsh Area (Shevenell...  

Open Energy Info (EERE)

Area (Shevenell, Et Al., 2008) Exploration Activity Details Location Columbus Salt Marsh Area Exploration Technique Multispectral Imaging Activity Date Usefulness useful...

415

Fundamental Corrosion Studies in High-Temperature Molten Salt...  

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

Molten Salt Systems for CSP Applications - FY13 Q1 Advanced Ceramic Materials and Packaging Technologies for Realizing Sensors for Concentrating Solar Power Systems...

416

Molten salt bath circulation design for an electrolytic cell  

DOE Patents (OSTI)

An electrolytic cell for reduction of a metal oxide to a metal and oxygen has an inert anode and an upwardly angled roof covering the inert mode. The angled roof diverts oxygen bubbles into an upcomer channel, thereby agitating a molten salt bath in the upcomer channel and improving dissolution of a metal oxide in the molten salt bath. The molten salt bath has a lower velocity adjacent the inert anode in order to minimize corrosion by substances in the bath. A particularly preferred cell produces aluminum by electrolysis of alumina in a molten salt bath containing aluminum fluoride and sodium fluoride. 4 figs.

Dawless, R.K.; LaCamera, A.F.; Troup, R.L.; Ray, S.P.; Hosler, R.B.

1999-08-17T23:59:59.000Z

417

THE PARTIAL EQUIVALENT VOLUMES OF SALTS IN SEAWATER  

Science Journals Connector (OSTI)

of the major salts in seawater have been mcasurcd over the salinity ... model of seawater by considering seawater .... mained essentially constant during storage.

418

Waste Isolation Pilot Plant's Excavated Salt Agreement Supports...  

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

result in large volumes of excavated salt. Seeking an innovative alternative to landfill disposal, EM's Carlsbad Field Office (CBFO) reached an agreement with Magnum...

419

Sustainable Energy Source for Water Pumping at Puttalam Salt Limited.  

E-Print Network (OSTI)

?? The cost of grid based electrical and diesel sea water pumping to salt fields is one of the major cost components out of the… (more)

Kamaldeen, Mohammed Rizwan

2014-01-01T23:59:59.000Z

420

Hybrid Molten Salt Reactor (HMSR): Method and System to fully...  

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

Hybrid Molten Salt Reactor (HMSR): Method and System to fully fission actinides for electric power production without fuel enrichment, fabrication, or reprocessing A method for...

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


421

Accelerating Solutions  

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

Solutions From vehicles on the road to the energy that powers them, Oak Ridge National Laboratory innovations are advancing American transportation. Oak Ridge National Laboratory is making an impact on everyday America by enhancing transportation choices and quality of life. Through strong collaborative partnerships with industry, ORNL research and development efforts are helping accelerate the deployment of a new generation of energy efficient vehicles powered by domestic, renewable, clean energy. EPA ultra-low sulfur diesel fuel rule ORNL and the National Renewable Energy Laboratory co-led a comprehensive research and test program to determine the effects of diesel fuel sulfur on emissions and emission control (catalyst) technology. In the course of this program, involving

422

Excavation Damaged Zones In Rock Salt Formations  

SciTech Connect

Salt formations have long been proposed as potential host rocks for nuclear waste disposal. After the operational phase of a repository the openings, e.g., boreholes, galleries, and chambers, have to be sealed in order to avoid the release of radionuclides into the biosphere. For optimising the sealing techniques knowledge about the excavation damaged zones (EDZ) around these openings is essential. In the frame of a project performed between 2004 and 2007, investigations of the EDZ evolution were performed in the Stassfurt halite of the Asse salt mine in northern Germany. Three test locations were prepared in the floor of an almost 20 year old gallery on the 800-m level of the Asse mine: (1) the drift floor as existing, (2) the new drift floor shortly after removing of a layer of about 1 m thickness of the floor with a continuous miner, (3) the new drift floor 2 years after cutting off the 1-m layer. Subject of investigation were the diffusive and advective gas transport and the advective brine transport very close to the opening. Spreading of the brine was tracked by geo-electric monitoring in order to gain information about permeability anisotropy. Results obtained showed that EDZ cut-off is a useful method to improve sealing effectiveness when constructing technical barriers. (authors)

Jockwer, N.; Wieczorek, K. [Gesellschaft fur Anlagen- und Reaktorsicherheit (GRS) mbH, Braunschweig (Germany)

2008-07-01T23:59:59.000Z

423

Preliminary Evaluation of Cesium Distribution for Wet Sieving Process Planned for Soil Decontamination in Japan - 13104  

SciTech Connect

For the purpose of decontaminating radioactive cesium from a huge amount of soil, which has been estimated to be 1.2x10{sup 8} m{sup 3} by excavating to a 5-cm depth from the surface of Fukushima Prefecture where a severe nuclear accident occurred at TEPCO's power generating site and has emitted a significant amount of radioactive materials, mainly radioactive cesium, a wet sieving process was selected as one of effective methods available in Japan. Some private companies have demonstrated this process for soil treatment in the Fukushima area by testing at their plants. The results were very promising, and a full-fledged application is expected to follow. In the present study, we spiked several aqueous samples containing soil collected from an industrial wet sieving plant located near our university for the recycling of construction wastes with non-radioactive cesium hydroxide. The present study provides scientific data concerning the effectiveness in volume reduction of the contaminated soil by a wet sieving process as well as the cesium distribution between the liquid phase and clay minerals for each sub-process of the full-scale one, but a simulating plant equipped with a process of coagulating sedimentation and operational safety fundamentals for the plant. Especially for the latter aspect, the study showed that clay minerals of submicron size strongly bind a high content of cesium, which was only slightly removed by coagulation with natural sedimentation (1 G) nor centrifugal sedimentation (3,700 G) and some of the cesium may be transferred to the effluent or recycled water. By applying ultracentrifugation (257,000 G), most of submicron clay minerals containing cesium was removed, and the cesium amount which might be transferred to the effluent or recycled water, could be reduced to less than 2.3 % of the original design by the addition of a cesium barrier consisting of ultracentrifugation or a hollow fiber membrane. (authors)

Enokida, Y.; Tanada, Y.; Hirabayashi, D. [Graduate School of Engineering, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan)] [Graduate School of Engineering, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan); Sawada, K. [EcoTopia Science Institute, Nagoya University, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan)] [EcoTopia Science Institute, Nagoya University, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan)

2013-07-01T23:59:59.000Z

424

Decontamination of soil washing wastewater using solar driven advanced oxidation processes  

Science Journals Connector (OSTI)

Decontamination of soil washing wastewater was performed using two different solar driven advanced oxidation processes (AOPs): the photo-Fenton reaction and the cobalt/peroxymonosulfate/ultraviolet (Co/PMS/UV) process. Complete sodium dodecyl sulphate (SDS), the surfactant agent used to enhance soil washing process, degradation was achieved when the Co/PMS/UV process was used. In the case of photo-Fenton reaction, almost complete SDS degradation was achieved after the use of almost four times the actual energy amount required by the Co/PMS/UV process. Initial reaction rate in the first 15 min (IR15) was determined for each process in order to compare them. Highest IR15 value was determined for the Co/PMS/UV process (0.011 mmol/min) followed by the photo-Fenton reaction (0.0072 mmol/min) and the dark Co/PMS and Fenton processes (IR15 = 0.002 mmol/min in both cases). Organic matter depletion in the wastewater, as the sum of surfactant and total petroleum hydrocarbons present (measured as chemical oxygen demand, COD), was also determined for both solar driven processes. It was found that, for the case of COD, the highest removal (69%) was achieved when photo-Fenton reaction was used whereas Co/PMS/UV process yielded a slightly lower removal (51%). In both cases, organic matter removal achieved was over 50%, which can be consider proper for the coupling of the tested \\{AOPs\\} with conventional wastewater treatment processes such as biodegradation.

Erick R. Bandala; Yuridia Velasco; Luis G. Torres

2008-01-01T23:59:59.000Z

425

Savannah River Site- Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

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

This is a presentation outlining the Salt Waste Processing Facility process, major risks, approach for conducting reviews, discussion of the findings, and conclusions.

426

From pre-salt sources to post-salt traps: A specific petroleum system in Congo coastal basin  

SciTech Connect

The Bas Congo basin extends from Gabon to Angola and is a prolific oil province where both pre-salt and post salt sources and reservoirs have been found. In the northern part of the basin referred to as the Congo coastal basin, the proven petroleum system is more specific: mature source rocks are found only in pre-salt series whereas by contrast 99 % proven hydrocarbon reserves am located in post-salt traps. Such a system is controlled by the following factors: Source rocks are mostly organic rich shales deposited in a restricted environment developed in a rift prior to the Atlantic Ocean opening; Migration from pre-salt sources to post-salt traps is finalized by local discontinuities of the regional salt layer acting otherwise as a tight seal; Post-salt reservoirs are either carbonates or sands desposited in the evolutive shelf margin developped during Upper Cretaceous; Geometric traps are linked to salt tectonics (mostly turtle-shaped structures); Regional shaly seals are related to transgressive shales best developped during high rise sea level time interval. Stratigraphically, the age of hydrocarbon fields trends are younger and younger from West to East: lower Albian in Nkossa, Upper Albian and lower Cenomanian in Likouala, Yanga, Sendji, Upper Cenomanian in Tchibouela, Turonian in Tchendo, Turanian and Senonian in Emeraude.

Vernet, R.

1995-08-01T23:59:59.000Z

427

Treatment plan for aqueous/organic/decontamination wastes under the Oak Ridge Reservation FFCA Development, Demonstration, Testing, and Evaluation Program  

SciTech Connect

The U.S. Department of Energy (DOE) Oak Ridge Operations Office and the U.S. Environmental Protection Agency (EPA)-Region IV have entered into a Federal Facility Compliance Agreement (FFCA) which seeks to facilitate the treatment of low-level mixed wastes currently stored at the Oak Ridge Reservation (ORR) in violation of the Resource, Conservation and Recovery Act Land Disposal Restrictions. The FFCA establishes schedules for DOE to identify treatment for wastes, referred to as Appendix B wastes, that current have no identified or existing capacity for treatment. A development, demonstration, testing, and evaluation (DDT&E) program was established to provide the support necessary to identify treatment methods for mixed was meeting the Appendix B criteria. The Program has assembled project teams to address treatment development needs for major categories of the Appendix B wastes based on the waste characteristics and possible treatment technologies. The Aqueous, Organic, and Decontamination (A/O/D) project team was established to identify pretreatment options for aqueous and organic wastes which will render the waste acceptable for treatment in existing waste treatment facilities and to identify the processes to decontaminate heterogeneous debris waste. In addition, the project must also address the treatment of secondary waste generated by other DDT&E projects. This report details the activities to be performed under the A/O/D Project in support of the identification, selection, and evaluation of treatment processes. The goals of this plan are (1) to determine the major aqueous and organic waste streams requiring treatment, (2) to determine the treatment steps necessary to make the aqueous and organic waste acceptable for treatment in existing treatment facilities on the ORR or off-site, and (3) to determine the processes necessary to decontaminate heterogeneous wastes that are considered debris.

Backus, P.M.; Benson, C.E.; Gilbert, V.P.

1994-08-01T23:59:59.000Z

428

Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4. Volume 1: Technology evaluation  

SciTech Connect

During World War 11, the Oak Ridge Y-12 Plant was built as part of the Manhattan Project to supply enriched uranium for weapons production. In 1945, Building 9201-4 (Alpha-4) was originally used to house a uranium isotope separation process based on electromagnetic separation technology. With the startup of the Oak Ridge K-25 Site gaseous diffusion plant In 1947, Alpha-4 was placed on standby. In 1953, the uranium enrichment process was removed, and installation of equipment for the Colex process began. The Colex process--which uses a mercury solvent and lithium hydroxide as the lithium feed material-was shut down in 1962 and drained of process materials. Residual Quantities of mercury and lithium hydroxide have remained in the process equipment. Alpha-4 contains more than one-half million ft{sup 2} of floor area; 15,000 tons of process and electrical equipment; and 23,000 tons of insulation, mortar, brick, flooring, handrails, ducts, utilities, burnables, and sludge. Because much of this equipment and construction material is contaminated with elemental mercury, cleanup is necessary. The goal of the Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 is to provide a planning document that relates decontamination and decommissioning and waste management problems at the Alpha-4 building to the technologies that can be used to remediate these problems. The Y-12 Plant Decontamination and Decommissioning Technology Logic Diagram for Building 9201-4 builds on the methodology transferred by the U.S. Air Force to the Environmental Management organization with DOE and draws from previous technology logic diagram-efforts: logic diagrams for Hanford, the K-25 Site, and ORNL.

NONE

1994-09-01T23:59:59.000Z

429

Decontamination of metals by melt refining/slagging. An annotated bibliography: Update on stainless steel and steel  

SciTech Connect

The following presentation is an update to a previous annotation, i.e., WINCO-1138. The literature search and annotated review covers all metals used in the nuclear industries but the emphasis of this update is directed toward work performed on mild steels. 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 problems, Lockheed Idaho Technologies Co (LITCO) 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 wide 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--2,000 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 and Pit 9/RWMC boxes. This report is the result of the literature search conducted to establish a basis for experimental melt/slag program development. The program plan will be jointly developed by Montana Tech and LITCO.

Worchester, S.A.; Twidwell, L.G.; Paolini, D.J.; Weldon, T.A. [Montana Tech of the Univ., of Montana (United States); Mizia, R.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-01-01T23:59:59.000Z

430

New information on disposal of oil field wastes in salt caverns  

SciTech Connect

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

Veil, J.A.

1996-10-01T23:59:59.000Z

431

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

SciTech Connect

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

Veil, J.A.

1996-10-01T23:59:59.000Z

432

Evaluation of gas-phase technetium decontamination and safety related experiments during FY 1994. A report of work in progress  

SciTech Connect

Laboratory activities for FY94 included: evaluation of decontamination of Tc by gas-phase techniques, evaluation of diluted ClF{sub 3} for removing U deposits, evaluation of potential hazard of wet air inlekage into a vessel containing ClF{sub 3}, planning and preparation for experiments to assess hazard of rapid reaction of ClF{sub 3} and hydrated UO{sub 2}F{sub 2} or powdered Al, and preliminary evaluation of compatibility of Tenic valve seat material.

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

1995-05-01T23:59:59.000Z

433

Populations of Methanogenic Bacteria in a Georgia Salt Marsh  

Science Journals Connector (OSTI)

...28. Oremland, R. S., L. M. Marsh, and S. Polcin...reduction in anoxic, salt marsh sediments. Nature...29. Oremland, R. S., and S. Polcin...Pomeroy, L. R., and R. G. Wiegert. 1981. The ecology of a salt marsh. Springer-Verlag...

Michael J. Franklin; William J. Wiebe; William B. Whitman

1988-05-01T23:59:59.000Z

434

Alternative Waste Forms for Electro-Chemical Salt Waste  

SciTech Connect

This study was undertaken to examine alternate crystalline (ceramic/mineral) and glass waste forms for immobilizing spent salt from the Advanced Fuel Cycle Initiative (AFCI) electrochemical separations process. The AFCI is a program sponsored by U.S. Department of Energy (DOE) to develop and demonstrate a process for recycling spent nuclear fuel (SNF). The electrochemical process is a molten salt process for the reprocessing of spent nuclear fuel in an electrorefiner and generates spent salt that is contaminated with alkali, alkaline earths, and lanthanide fission products (FP) that must either be cleaned of fission products or eventually replaced with new salt to maintain separations efficiency. Currently, these spent salts are mixed with zeolite to form sodalite in a glass-bonded waste form. The focus of this study was to investigate alternate waste forms to immobilize spent salt. On a mole basis, the spent salt is dominated by alkali and Cl with minor amounts of alkaline earth and lanthanides. In the study reported here, we made an effort to explore glass systems that are more compatible with Cl and have not been previously considered for use as waste forms. In addition, alternate methods were explored with the hope of finding a way to produce a sodalite that is more accepting of as many FP present in the spent salt as possible. This study was done to investigate two different options: (1) alternate glass families that incorporate increased concentrations of Cl; and (2) alternate methods to produce a mineral waste form.

Crum, Jarrod V.; Sundaram, S. K.; Riley, Brian J.; Matyas, Josef; Arreguin, Shelly A.; Vienna, John D.

2009-10-28T23:59:59.000Z

435

SALT DAMAGE CRITERION PROOF-OF-CONCEPT RESEARCH  

SciTech Connect

The purpose of this study was to conduct a field-scale application demonstrating the use of continuum damage mechanics to determine the minimum allowable operating pressure of compressed natural gas storage caverns in salt formations. A geomechanical study was performed of two natural gas storage caverns (one existing and one planned) utilizing state-of-the-art salt mechanics to assess the potential for cavern instability and collapse. The geomechanical study consisted primarily of laboratory testing, theoretical development, and analytical/numerical tasks. A total of 50 laboratory tests was performed on salt specimens to aid in the development and definition of the material model used to predict the behavior of rock salt. Material model refinement was performed that improved the predictive capability of modeling salt during damage healing, recovery of work-hardened salt, and the behavior of salt at stress states other than triaxial compression. Results of this study showed that the working gas capacity of the existing cavern could be increased by 18 percent and the planned cavern could be increased by 8 percent using the proposed method compared to a conventional stress-based method. Further refinement of the continuum damage model is recommended to account for known behavior of salt at stress conditions other than triaxial compression that is not characterized accurately by the existing model.

Kerry L. DeVries; Kirby D. Mellegard; Gary D. Callahan

2002-11-01T23:59:59.000Z

436

Influence of Salt Purity on Na+ and Palmitic Acid Interactions  

E-Print Network (OSTI)

frequency generation (VSFG) spectroscopy. Ultrapure (UP) and ACS grade NaCl salts are used for aqueous the interfacial water structure. These results suggest that the alkali salt grade even after pretreatment to many chemical, biochemical, and atmospheric processes.1-8 Particularly, Na+ and K+ , as the two most

437

Molten salts and nuclear energy production Christian Le Bruna*  

E-Print Network (OSTI)

Molten salts and nuclear energy production Christian Le Bruna* a Laboratoire de Physique or chlorides) have been taken in consideration very soon in nuclear energy production researches with solid fuels, liquid fuel in molten salt reactor, solvents for spent nuclear solid fuel in the case

Boyer, Edmond

438

Detection and removal of molten salts from molten aluminum alloys  

SciTech Connect

Molten salts are one source of inclusions and defects in aluminum ingots and cast shapes. A selective adsorption media was used to remove these inclusions and a device for detection of molten salts was tested. This set of experiments is described and the results are presented and analyzed.

K. Butcher; D. Smith; C. L. Lin; L. Aubrey

1999-08-02T23:59:59.000Z

439

Brachybacterium squillarum sp. nov., isolated from salt-fermented seafood  

E-Print Network (OSTI)

Brachybacterium squillarum sp. nov., isolated from salt-fermented seafood Seong-Kyu Park, Min salt-fermented seafood in Korea. The organism grew in 0­10 % (w/v) NaCl and at 25­37 6C, with optimal

Bae, Jin-Woo

440

Kocuria salsicia sp. nov., isolated from salt-fermented seafood  

E-Print Network (OSTI)

Kocuria salsicia sp. nov., isolated from salt- fermented seafood Ji-Hyun Yun,1 Seong Woon Roh,1 salt-fermented seafood in Korea. It was a Gram- positive, non-motile, coccus-shaped bacterium-fermented seafood (`gajami-sikhae') from Korea. Following isolation on marine agar 2216 (MA, BBL) at 30 uC, a pure

Bae, Jin-Woo

Note: This page contains sample records for the topic "decontaminated salt solution" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Salt tectonics, patterns of basin fill, and reservoir distribution  

SciTech Connect

Salt structures, which develop due to sediment loading, gravity creep, and/or buoyancy, include boundary-fault grabens and half grabens, rollers, anticlines, domes and walls, diapirs, sills, massifs, and compressional toe structures. Associated features include fault systems and turtle structures. Of these, six directly relate to basin fill and all directly influence the distribution of reservoir facies. Salt structuring is initiated by sedimentation, which in turn is localized by salt withdrawal. Withdrawal produces individual salt structures, migrating sills, dissected massifs, and regional depocenters bordered by salt walls. Composite withdrawals dictate the patterns of basin fill. Relative rates of structural growth and sedimentation control the distribution of reservoir facies. When growth dominates, sands are channeled into lows. When sedimentation dominates and maintains flat surfaces, facies distribution is not impacted except where faulting develops. Turtle structures, developed by the inversion of peripheral synclines, can move sands into favorable structural position and/or serve as platforms for carbonate reservoir devel