WorldWideScience

Sample records for radiochemical separation technology

  1. Development of Radiochemical Separation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Eil Hee; Kim, K. W.; Yang, H. B. (and others)

    2007-06-15

    This project of the second phase was aimed at the development of basic unit technologies for advanced partitioning, and the application tests of pre-developed partitioning technologies for separation of actinides by using a simulated multi-component radioactive waste containing Am, Np, Tc, U and so on. The goals for recovery yield of TRU, and for purity of Tc are high than 99% and about 99%, respectively. The work scopes and contents were as follows. 1). For the development of basic unit technologies for advanced partitioning. 1. Development of technologies for co-removal of TRU and for mutual separation of U and TRU with a reduction-complexation reaction. 2. Development of extraction system for high-acidity co-separation of An(+3) and Ln(+3) and its radiolytic evaluation. 3. Synthesis of extractants for the selective separation of An(+3) and its relevant extraction system development. 4. Development of a hybrid system for the recovery of noble metals and its continuous separation tests. 5. Development of electrolytic system for the decompositions of N-NO3 and N-NH3 compounds to nitrogen gas. 2). For the application test of pre-developed partitioning technologies for the separation of actinide elements in a simulated multi-component solution equivalent to HLW level. 1. Co-separation of Tc, Np and U by a (TBP-TOA)/NDD system. 2. Mutual-separation of Am, Cm and RE elements by a (Zr-DEHPA)/NDD system. All results will be used as the fundamental data for the development of advanced partitioning process in the future.

  2. Radiochemical separation of cadmium-109

    International Nuclear Information System (INIS)

    Egamediev, S.; Mukhtarov, A.; Nurbaeva, D.; Rakhmanov, A.

    2006-01-01

    chlorides with 6 M HCl from nitric acid solutions of Ag, Cu and Cd. Then the solution is filtered to remove silver. The filtrate is evaporated almost to dryness and the solid residue is dissolved in 2 M HCl. The solution obtained is passed through an anion-exchange column with DOWEX 1x8. Cadmium is retained on column at this concentration of HCl while Cu is completely eluted with 30 ml of 2 M HCl. Finally cadmium is eluted with 200 ml of 1 N HNO 3 , while the traces of silver remain on the column. Thus a pure solution of cadmium nitrate is obtained that can be evaporated to the desirable volume. Measuring the activity of the initial and obtained quantity of 109 Cd it is found that 80% of the total cadmium is recovered. Second method is based on the selective adsorption of silver on column containing 0.5 g of polyethenemonosulphide (PEMS or trade name TR-1) from nitric acid solutions of Ag, Cu, Zn and Cd. This sorbent has high adsorptive capacity to silver, its adsorptive capacity reaches to 1920 mg/g from 1.5 M nitric acid solutions. After adsorption of silver the solution obtained evaporated to dryness and the solid residue is dissolved in 0.5 M nitric acid containing 0.1 M hydrobromic acid. Then the solution obtained is percolated through the column, containing 5 ml of Dowex1x8 resin. The copper(II) and zinc are completely eluted with 70 ml of 0.5 M HNO 3 + 0.1 M HBr. The cadmium-109 is eluted with 50 ml of 3 M nitric acid. The obtained solution is evaporated to dryness and the dry residue is treated by evaporation with 2 ml of 12 M hydrochloric acid. After treatment the damp residue is dissolved in 0.1 M hydrochloric acid. The yield of cadmium-109 is higher than 90% and the radiochemical purity was more than 99.9%. These methods will be used for separation and purification of cadmium-109 to make of sealed sources for X-ray fluorescence analysis. The Science and Technologies Center at Cabinet of Ministers of Republic of Uzbekistan support this work (cont ract no.13

  3. Radiochemistry and radiochemical separations. A current bibliography

    International Nuclear Information System (INIS)

    Bujdoso, E.

    1999-01-01

    A current bibliography for years 1993-1996 with 159 references was compiled on radiochemistry and radiochemical separations based on the INIS Atomindex. The references are arranged in alphabetical order of first authors. (N.T.)

  4. Rapid radiochemical separation of zirconium-95 and niobium-95

    International Nuclear Information System (INIS)

    Downey, D.M.; McLaughlin, C.L.

    1983-01-01

    A rapid method for the quantitative separation of 95 Zr and 95 Nb has been developed. The method is based on the ion flotation of cationic zirconium complex ions with sodium lauryl sulfate (NaLS) from niobium which is masked with hydrogen peroxide. The separation was applied to mixtures of 95 Zr and 95 Nb initially in oxalic acid solution and quantitative recoveries of the radiochemically pure radioisotopes were obtained. (orig.)

  5. Rapid radiochemical separation of zirconium-95 and niobium-95

    Energy Technology Data Exchange (ETDEWEB)

    Downey, D.M.; McLaughlin, C.L.

    1983-01-01

    A rapid method for the quantitative separation of /sup 95/Zr and /sup 95/Nb has been developed. The method is based on the ion flotation of cationic zirconium complex ions with sodium lauryl sulfate (NaLS) from niobium which is masked with hydrogen peroxide. The separation was applied to mixtures of /sup 95/Zr and /sup 95/Nb initially in oxalic acid solution and quantitative recoveries of the radiochemically pure radioisotopes were obtained.

  6. Statistical processing of technological and radiochemical data

    International Nuclear Information System (INIS)

    Lahodova, Zdena; Vonkova, Kateřina

    2011-01-01

    The project described in this article had two goals. The main goal was to compare technological and radiochemical data from two units of nuclear power plant. The other goal was to check the collection, organization and interpretation of routinely measured data. Monitoring of analytical and radiochemical data is a very valuable source of knowledge for some processes in the primary circuit. Exploratory analysis of one-dimensional data was performed to estimate location and variability and to find extreme values, data trends, distribution, autocorrelation etc. This process allowed for the cleaning and completion of raw data. Then multiple analyses such as multiple comparisons, multiple correlation, variance analysis, and so on were performed. Measured data was organized into a data matrix. The results and graphs such as Box plots, Mahalanobis distance, Biplot, Correlation, and Trend graphs are presented in this article as statistical analysis tools. Tables of data were replaced with graphs because graphs condense large amounts of information into easy-to-understand formats. The significant conclusion of this work is that the collection and comprehension of data is a very substantial part of statistical processing. With well-prepared and well-understood data, its accurate evaluation is possible. Cooperation between the technicians who collect data and the statistician who processes it is also very important. (author)

  7. Radiochemical separation and their application to neutron activation analysis technique

    International Nuclear Information System (INIS)

    Turel, Z.R.

    2013-01-01

    The present paper discusses the development of some new, rapid and selective method for the radiochemical separation and estimation of elements such as, Co(II) 2-3 , Ir(III) 4 , Au(III) 5 , Pt(IV), Pd(II), Os(IV) 6 , Cu(II), Ag(I), Mo(VI), Ni(II), Zn(II), Cd(II), Hg(II), Cs(I), Sb(III), La(III), Sc(III) etc. using various reagents. Various parameters such as pH, time of equilibrium, effect of anions and cations, effect of reagent etc. has been determined employing tracers of the elements under consideration and will be discussed. The method is made highly selective by the use of appropriate masking agent. The stoichiometry of metal reagent is determined by the substoichiometric method. Some examples of multielemental radiochemical separation methods thus developed which have been applied in determining the elements by radiochemical thermal neutron activation analysis will be presented and discussed. The implications of the results on the reference system will also be accounted. Statistical evaluation with reference to accuracy, precision and sensitivity will also be presented

  8. Radiochemicals

    International Nuclear Information System (INIS)

    1980-01-01

    In this catalogue those radioactive chemicals for research are listed which are produced by the Radiochemical Centre Amersham and our laboratories at Brunswick. The dates given for each product can understandably only be limited within the framework of such a catalogue. Additional dates and references to application technique can be obtained from us any time. Our programme is continually updated by new products. If a compound not listed in the catalogue should be required we ask for inquiry. Our working team for special syntheses will try to produce it according to our possibilities and our requirements. (orig.) [de

  9. Quantitative radio-chemical separation of calcium, strontium and barium

    International Nuclear Information System (INIS)

    Dupuis, M.C.; Dupuis, M.; Le Nagard, M.; Michot, H.

    1965-01-01

    A method for separation of Ca 45 , Sr 89 and Ba 140 has been developed for the radiochemical determination of these isotopes in a solution of fission with a large concentration of mineral salts. After removal of most fission products by solvent extraction (TTA-MIBK) at different pH, the alkaline earths are extracted from the aqueous phase at pH 9. After recovery with diluted hydrochloric acid, the three elements are adsorbed on cationic resin Dowex 50 and eluted sequentially with ammonium α - Hydroxy iso-butyrate using gradient concentration and pH. Ca 45 and Sr 89 are measured by β - counting and Ba 140 by γ spectrometry. The chemical yield approximates 80 per cent for calcium, and 70 per cent for strontium and barium. The decontamination factor is 10 5 for most fission products. Four separations can be performed in twenty hours. (authors) [fr

  10. ESOL facility for the generation and radiochemical separation of short half-life fission products

    International Nuclear Information System (INIS)

    Gehrke, R.J.; Meikrantz, D.H.; Baker, J.D.; Anderl, R.A.; Novick, V.J.; Greenwood, R.C.

    1988-01-01

    A facility has been developed at the Idaho National Engineering Laboratory (INEL) for the generation and rapid radiochemical separation of short half-life mixed fission products. This facility, referred to as the Idaho Elemental Separation On Line (ESOL), consists of electro-plated sources of spontaneously fissioning 252 Cf with a helium jet transport arrangement to continuously deliver short half-life, mixed fission products to the radiochemistry laboratory for rapid, computer controlled, radiochemical separations. 18 refs., 13 figs

  11. Mercury determination in geological samples using radiochemical separation

    International Nuclear Information System (INIS)

    Goncalves, Cristina; Favaro, Deborah I.T.

    1997-01-01

    In this work, a radiochemical procedure is presented to increase the neutron activation analysis sensitivity. After irradiation, geological reference materials - Buffalo River Sediment (BRS- - NIST SRM 2704), Lake Sediment (BCR - CRM 280) and GXR-5 (USGS - AEG) - were leached with aqua regia in a Parr bomb placed in a domestic microwave oven and then bismuth diethyl dithiocarbamate was used to pre concentrate mercury by solvent extraction. This procedure eliminates the interference from 279 keV Se-75 photopeak and background radiation from 511 keV Cu-64 photopeak. (author). 15 refs., 2 figs., 1 tab

  12. Use of reference materials for quality control of elemental analysis by neutron activation with radiochemical separation

    International Nuclear Information System (INIS)

    Woittiez, J.R.W.

    1990-01-01

    This paper describes the use of certified reference materials to monitor the long-term quality of radiochemical separations. The practical limitations which determine the actual design of the quality control are discussed. The hypothesis that the high yield of the radiochemical separation will be constant with time has been checked and validated for the elements Zn, Fe, Co, Cd, Mo and to a lesser extent for W and Th using NBS SRM 1577A, BCR CRM 274 and IAEA RM A-11. This validation could not be made for the elements Cr, Au, and Ag. Especially for Cr there is a serious lack of appropiate certified reference materials. (orig.)

  13. Use of ethyl-α-isonitrosoacetoacetate in the rapid estimation and radiochemical separation of gold

    International Nuclear Information System (INIS)

    Sawant, A.D.; Haldar, B.C.

    1978-01-01

    The use of ethyl-α-isonitrosoacetoacetate in the rapid estimation and radiochemical separation of gold is reported. As low as 5.00 mg of Au can be estimated with an accuracy better than 1%. Decontamination values against platinum metals and other metals usually associated with Au are greater than 10 5 . Isotopes and results are tabulated. The time required for radiochemical separation is around 20 min and the recovery of Au is better than 80%. γ-activities were measured with a single channel analyser and NaI(Tl) detector. β-activities were counted on a thin end-window type GM counter. (T.I.)

  14. Radiochemical separation of Tb-149 after tandem accelerator production

    International Nuclear Information System (INIS)

    Sarkar, S.R.

    1996-01-01

    Full text: Terbium-149 is produced by the heavy ion induced reaction of the type 142 Nd( 12 C,5n) 149 Dy→ 149 Tb. This work concerns the separation of terbium from neodymium target, and other lanthanides produced by secondary reactions on neodymium target. Firstly, anion-exchange separation is carried out at room temperature using acid-alcohol media (90% methanol-10% 5M nitric acid) as eluent. But the separation is not satisfactory. To achieve satisfactory separation, cation exchange separation is performed under pressure at room temperature using 0.1 6M α-hydroxyisobutyric acid of pH 5 as eluent. The pressure is exerted from a nitrogen gas cylinder. The simplicity and efficacy of this method for the separation of terbium are discussed in comparison with the commercially available high performance liquid chromatography system

  15. Radiochemical determination and separation or total radium, 226Ra and 224Ra

    International Nuclear Information System (INIS)

    Suarez, J. A.; Gonzalez, J. A.; Pablo, M. A. de

    1987-01-01

    Radiochemical purification and separation of radium has been carried out and the determination of total radium solubilized in aqueous samples has been studied assuming that all the alpha emitters of the sample have their origin in the 226Ra and elements of its desintegration chain. Also, the activities of 22Ra and 226 Ra have been evaluated separately doing a measurement after the chemical separation of the radium and another one 10 days after. (Author) 9 refs

  16. Radiochemical separation and alpha-spectrometric determination of Americium in different matrixes

    International Nuclear Information System (INIS)

    Radenkovic, M.; Joksic, J.; Paligoric, D.

    2009-01-01

    A method of separation and alpha-spectrometric determination of americium, developed in VINCA Institute of Nuclear Sciences is described in the paper. The procedure is convenient to be used for 241 Am determination in environmental matrixes as well as samples of human origin if a very small concentrations are expected, using 243 Am as a tracer for radiochemical yield recovery. (author) [sr

  17. Investigation of quantitative separation of thorium, uranium, neptunium and plutonium from complex radiochemical mixtures

    International Nuclear Information System (INIS)

    Ushatskij, V.N.; Preobrazhenskaya, L.D.; Kolychev, V.B.; Gugel', E.S.

    1979-01-01

    Quantitative separation of actinides and their radiochemical purification with the aid of TBP with subsequent separation of thorium and quantitative separation of U, Np and Pu with the aid of D2EHPA have been studied. The method has been developed for quantitative extraction-chromatographic separation and radiochemical purification of nanogram amounts of U, Pu and microgram amounts of Th and Np from complex radiochemical mixtures containing both fragment radioisotopes and non-radioactive macrocomponents ( Fe,Al,Mg,Mn, Na and others). The method calls for application of one-extraction-chromatographic column with TBP and one column with D2EHPA. Thorium is separated at the first stage since it does not form complexes in a chloride solution during washing of the sorption column with 6. OM HCl. Npsup((4)) and Pusup((3)) required for separation are stabilized with the aid of hydrazine and hydroxylamine mixture. The yield of each of the above-cited actinide elements during the complete two-stage separation and at the stage of their separation varies within the range of 98.5-99.3%

  18. Application of radiochemical separation procedures to environmental and biological materials

    Energy Technology Data Exchange (ETDEWEB)

    Eakins, J D [UKAEA Atomic Energy Research Establishment, Harwell. Environmental and Medical Sciences Div.

    1984-06-15

    The measurement of low levels of radionuclides in environmental and biological materials often depends on separation of the nuclide of interest from a bulky matrix containing interfering radioelements. In such case, however sophisticated and elegant the counting technique, the quality of the final data will

  19. Radiochemical separation of mostly short-lived neutron activation products

    Czech Academy of Sciences Publication Activity Database

    Kučera, Jan; Kameník, Jan; Povinec, P. P.

    2017-01-01

    Roč. 311, č. 2 (2017), s. 1299-1307 ISSN 0236-5731. [1st International Conference on Radioanalytical and Nuclear chemistry (RANC). Budapest, 10.04.2016-15.04.2016] R&D Projects: GA ČR(CZ) GBP108/12/G108 Institutional support: RVO:61389005 Keywords : determination * Vanadium * Iodine * Manganese * Silicon * Mercury * Selenium * Th-232 anad U-238 * SuperNEMO experiment Subject RIV: CB - Analytical Chemistry, Separation OBOR OECD: Analytical chemistry Impact factor: 1.282, year: 2016

  20. Use of tetracycline as complexing agent in radiochemical separations

    International Nuclear Information System (INIS)

    Saiki, M.; Nastasi, M.J.C.; Lima, F.W.

    1981-01-01

    The use of the antibiotic agent tetracycline (TC) for analytical purposes in solvent extraction procedures is presented. Individual extraction curves for the lanthanides, zinc, scandium, uranium, thorium, neptunium and protactinium were obtained. Separation of those elements from one another, and of uranium from selenium, bromine, antimony, barium, tantalum and tungsten was carried out. In all cases benzyl alcohol was the diluent used to dissolve tetracycline hydrochloride. Sodium chloride was used as supporting electrolyte for the lanthanide separations and sodium perchlorate for the other elements mentioned. Stability or formation constants for the lanthanide complexes as well as for thorium complex with tetracycline were determined by using the methods of average number of ligands, the limiting value (for thorium), the two parameters and the weighted least squares. For the lanthanides, the stability constants of the complexes Ln(TC) 3 go from 9.35+-0.22 for lanthanum up to 10.84+-0.11 for lutetium. For the Th(TC) 4 complex the formation constant is equal to 24.6+-0.3. Radioisotopes of the respective elements were used as tracers for the determinations. (author)

  1. Ultratrace determination of platinum in biological materials via neutron activation and radiochemical separation

    International Nuclear Information System (INIS)

    Zeisler, R.; Greenberg, R.R.

    1982-01-01

    A neutron activation analysis scheme based upon a radiochemical separation of the activation products has been developed. The method utilizes the inherent sensitivity of the activation reaction 198 Pt(n,ν) 199 Pt and counting of the daughter nuclide 199 Au. This nuclide is radiochemically separated from interfering activities by homogeneous precipitation as elemental gold. The remaining interference of the secondary reaction 197 Au(n,ν) 198 Au(n,ν) 199 Au from gold in the samples is quantitatively assessed and corrected. During this process accurate gold concentrations in the samples are obtained at ultratrace levels. The analysis scheme is applied to gold and platinum determinations in biological Standard Reference Materials and human liver specimens. Gold and platinum are determined at concentrations of 5x10 - 11 g/g, and at higher levels. (author)

  2. Radiochemical separation of actinides for their determination in environmental samples and waste products

    Energy Technology Data Exchange (ETDEWEB)

    Gleisberg, B [Nuclear Engineering and Analytics Rossendorf, Inc. (VKTA), Dresden (Germany)

    1997-03-01

    The determination of low level activities of actinides in environmental samples and waste products makes high demands on radiochemical separation methods. Artificial and natural actinides were analyzed in samples form the surrounding areas of NPP and of uranium mines, incorporation samples, solutions containing radioactive fuel, solutions and solids resutling from the process, and in wastes. The activities are measured by {alpha}-spectrometry and {gamma}-spectrometry. (DG)

  3. Rapid radiochemical separation of short-lived radionuclides in neutron-activated samples

    International Nuclear Information System (INIS)

    Fardy, J.

    1985-11-01

    Radiochemical separation procedures based on the removal of metal ions by columns of C 18 -bonded silica gel after selective complexation are examined and the simplicity of the method demonstrated by its application to determination of Mn, Cu and Zn in neutron-activated biological material from the following solutions (pH 0-10, sulphate concentration 0,18M and 1,44M SO 4 ): 8-hydroxyquinoline (oxine), ammonium pyrrolidinedithiocarbamate (APDC), cupferron (CUP), 1-(2-pyridylazo)-2-naphthol (PAN), 1-(2'-thiazolylazo)-2-naphthol (TAN), 4-(2-pyridylazo) resorcinol (PAR), diethylammonium diethyldithiocarbamate (DDC), potassium ethyl xanthate (PEX), acetylacetone (AcAc) or thenoyltrifluoracetone (TTA). The method is rapid and reliable and readily adaptable in all radiochemical laboratories

  4. Some problems concenrning the use of automated radiochemical separation systems in destructive neutron activation analysis

    International Nuclear Information System (INIS)

    Nagy, L.G.; Toeroek, G.

    1977-01-01

    The present state of a long term program is reviewed. It was started to elaborate a remote controlled automated radiochemical processing system for the neutron activation analysis of biological materials. The system is based on wet ashing of the sample followed by reactive desorption of some volatile components. The distillation residue is passed through a series of columns filled with selective ion screening materials to remove the matrix activity. The solution is thus ''stripped'' from the interfering radioions, and it is processed to single-elements through group separations using ion-exchange chromatographic techniques. Some special problems concerning this system are treated. (a) General aspects of the construction of a (semi)automated radiochemical processing system are discussed. (b) Comparison is made between various technical realizations of the same basic concept. (c) Some problems concerning the ''reconstruction'' of an already published processing system are outlined. (T.G.)

  5. Development of radiochemical separation method for determination of toxic elements in biological samples

    International Nuclear Information System (INIS)

    Maihara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

    1990-01-01

    In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of H NO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-X8 resin column in 6 M HCl. The effluent was passed through a TDO, tin dioxide column which retains As and Se in 3 M HCl medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

  6. Development of a radiochemical separation method for toxic elements determination from biologic samples

    International Nuclear Information System (INIS)

    Malhara, V.A.; Vasconcellos, M.B.A.; Favaro, D.I.T.; Armelin, M.J.A.

    1990-01-01

    In order to determine Hg, Sb, As and Se in biological materials by neutron activation analysis, a radiochemical separation was developed. The chemical separation procedure used was based on the digestion of the irradiated sample in a mixture of HNO 3 and H 2 SO 4 in a teflon bomb, at 130 0 C for 1 to 4 hours. After the dissolution of organic matter, Hg and Sb were retained by a Dowex 2-XB resin column in 6M HCI. The efluent was passed through a TDO, tin dioxide column which retains As and Se in 3M HCI medium. Radioactive tracers of these elements were used to determine the yields of the separation process. Certified reference materials were analyzed to check the precision and accuracy of the method. (author)

  7. The study of radiochemical separation methods on gaseous Fission product krypton-88

    International Nuclear Information System (INIS)

    Yang Zhihong; Zhang Shengdong; Yang Lei; Ding Youqian; Sun Hongqing; Ma Peng

    2012-01-01

    Half-life of krypton-88 is 2.84 hours, high fission yields and a relatively large gamma branching ratio is had. The gas is short-lived fission products in burnup measurements. Only New fission products can extract from extraction in gas of fissile irradiation target. But krypton-88 with krypton-85, krypton-87, xenon -135, and xenon-138 is coexisted together, thus radiochemical separation must quickly taken. selected the irradiation time is 1-2 hours and cooling time is best 2 hours for sample preparation, krypton and xenon were separated using activated carbon adsorption, the ratio of krypton and xenon were measured by gamma spectroscopy. Then according to the ratio of krypton-85 and xenon-125 count rate coefficient around separation were calculated yield of krypton and decontamination factor of xenon and the final the yield of krypton-85 is calculated. (authors)

  8. Cyclotron production, radiochemical separation and quality control of platinum radiotracers for toxicological studies

    International Nuclear Information System (INIS)

    Bonardi, M.; Birattari, C.; Groppi, F.; Arginelli, D.; Gini, L.; Gallorini, M.

    1998-01-01

    The increasing concentration of Pt, Pd and Rh in the environment is mainly due to the release of these elements from the catalytic converters of the motorvehicles. This situation makes it necessary to carry out metallotoxicological experiments on both cell cultures and laboratory animals, in order to assess their impact on living organisms after a Long Term and Low Level Exposure (LLE). Both nuclear reactions nat Ir(p,xn) and nat Os(α,xn) were investigated in the energy range up to 45 MeV for protons and 38 MeV for alpha-particles, in order to optimize the irradiation parameters for the production of 188,189,191 Pt. Several sets of thin- and thick-target excitation functions were determined experimentally by cyclotron irradiation at both Milano and Ispra cyclotrons. This paper reports the irradiation parameters studied and adopted and two radiochemical procedures for the separation of radio-Pt from an Os target, as well as from ruthenium, iridium and gold impurities. These procedures were used to obtain very high specific activity Pt radionuclides in No Carrier Added (NCA) form. Radionuclidic, radiochemical and chemical purity measurements were carried out by the use of several techniques like γ-spectrometry, ion-exchange radio-chromatography, atomic absorption spectrometry and neutron activation analysis. (author)

  9. Determination of gold and platinum in biological materials by radiochemical neutron activation analysis using electrolytic separation of gold

    International Nuclear Information System (INIS)

    Reitz, B.; Heydorn, K.

    1993-01-01

    A new method is presented for the determination of Au and Pt in biological materials based on neutron activation analysis with radiochemical separation of gold. Separation of gold by electrolytic deposition on a niobium cathode ascertains thee highest radiochemical purity without any interference from calcium or other major elements. With 199 Au as indicator for platinum the gold content of the sample not only strongly affects the limit of detection, but also causes interference by double neutron capture. Replicate analyses of BCR Certified Reference Materials No. 184, 185 and 186 were carried out. (author) 18 refs.; 3 figs.; 2 tabs

  10. Radiochemical separation and effective dose estimation due to ingestion of 90Sr

    International Nuclear Information System (INIS)

    Ilic, Z.; Vidic, A.; Deljkic, D.; Sirko, D.; Zovko, E.; Samek, D.

    2009-01-01

    Since 2007. Institute for Public Health of Federation of Bosnia and Herzegovina-Radiation Protection Centre, within the framework of monitoring of radioactivity of environment carried out measurement of specific activity of 90 Sr content in selected food and water samples. The paper described the methods of measurement and radiochemical separation. Presented results, as average values of specific activity of 90 Sr, were used for estimation of effective dose due to ingestion of 90 Sr for 2007. and 2008. Estimated effective dose for 2007. due to ingestion of 90 Sr for adults was 1,36 μSv and 2,03 μSv for children (10 year old), and for 2008. 0,67 μSv (adults) and 1,01 μSv (children 10 year old). Estimated effective doses for 2007. and 2008. are varied because of different average specific activity radionuclide 90 Sr in selected samples of food, their number, species and origin. (author) [sr

  11. Automation of column-based radiochemical separations. A comparison of fluidic, robotic, and hybrid architectures

    Energy Technology Data Exchange (ETDEWEB)

    Grate, J.W.; O' Hara, M.J.; Farawila, A.F.; Ozanich, R.M.; Owsley, S.L. [Pacific Northwest National Laboratory, Richland, WA (United States)

    2011-07-01

    Two automated systems have been developed to perform column-based radiochemical separation procedures. These new systems are compared with past fluidic column separation architectures, with emphasis on using disposable components so that no sample contacts any surface that any other sample has contacted, and setting up samples and columns in parallel for subsequent automated processing. In the first new approach, a general purpose liquid handling robot has been modified and programmed to perform anion exchange separations using 2 mL bed columns in 6 mL plastic disposable column bodies. In the second new approach, a fluidic system has been developed to deliver clean reagents through disposable manual valves to six disposable columns, with a mechanized fraction collector that positions one of four rows of six vials below the columns. The samples are delivered to each column via a manual 3-port disposable valve from disposable syringes. This second approach, a hybrid of fluidic and mechanized components, is a simpler more efficient approach for performing anion exchange procedures for the recovery and purification of plutonium from samples. The automation architectures described can also be adapted to column-based extraction chromatography separations. (orig.)

  12. Radiochemical procedures

    International Nuclear Information System (INIS)

    Lyon, W.S.

    1982-01-01

    The modern counting instrumentation has largely obviated the need for separation processes in the radiochemical analysis but problems in low-level radioactivity measurement, environmental-type analyses, and special situations caused in the last years a renaissance of the need for separation techniques. Most of the radiochemical procedures, based on the classic works of the Manhattan Project chemists of the 1940's, were published in the National Nuclear Energy Series (NNES). Improvements such as new solvent extraction and ion exchange separations have been added to these methods throughout the years. Recently the Los Alamos Group have reissued their collected Radiochemical Procedures containing a short summary and review of basic inorganic chemistry - 'Chemistry of the Elements on the Basis of Electronic Configuration'. (A.L.)

  13. radiochemical study on the medically and technology radionuclides of some lanthanides

    International Nuclear Information System (INIS)

    Aglan, H.A.E.

    2010-01-01

    In this work, trials for the production of the medically and technologically interesting 139 Ce and 142 Pr radionuclides through cyclotron irradiations using protons and alpha particles were studied. The radiochemical separation of no-carrier-added cerium from proton irradiated lanthanum was studied by solvent extraction using DEE, TBP and TPPO, the latter reagent being employed for the first time for separation of radio cerium from bulk of lanthanum. Distribution coefficients of cerium and lanthanum were investigated as a function of equilibrium time and HNO 3 concentration. A mixture of 0.05 M K 2 Cr 2 O 7 and 0.1 M H 2 SO 4 was used as an oxidizing agent to improve the separation efficiency of cerium. A comparative study of the three extractants released that DEE is the best for separation of cerium from bulk of lanthanum oxide. The target was prepared by pressing. The production of 139 Ce of high radionuclidic and chemical purity via irradiation of lanthanum oxide target at MGC-20 cyclotron with protons of energy 14.5 is described. The experimental yield was found to be 153 kBq/μAh .The adsorption behaviour of La/Ce system on Dowex 50W-X8 in different media, namely, nitric acid, acetate buffer and citrate buffer was studied as a function of the concentration of nitric acid and buffer ph. In addition, in cation-exchange column chromatography experiments, three different eluants, namely, citrate buffer of ph 5.5, 0.1 M EDTA and 0.2 M α-HIBA, were employed for separation of Ce (III) from La (III). The optimum conditions for improvement of radiochemical separation of no-carrier-added 139 Ce from proton irradiated lanthanum were applied using the most suitable chelating agent 0.2 M α-HIBA. The purification of 139 Ce from macro amount of La (III) was done using two columns in a sequence. The experimental yield was found to be 200 kBq/μAh.

  14. Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype

    International Nuclear Information System (INIS)

    Duarte A, C.; Alanis M, J.; Gutierrez R, C.

    2002-01-01

    In this work an obtention process of phosphorus 32 ( 32 P) in orthophosphoric acid form (H 3 32 PO 4 ) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

  15. Radiochemical separations of hafnium, tantalum, and germanium from tungsten and selenium irradiated by 14 MeV neutrons

    International Nuclear Information System (INIS)

    Blachot, J.; Benabed, A.; Herment, J.; Monnand, E.

    1968-01-01

    Radiochemical separations of Hf, Ta and Ge from W and Se respectively, after 14 MeV-neutron irradiation. A new isotope: 79 Ge with a half-live of 50 ± 5 s and emitter of a 230 keV γ transition is observed. (authors) [fr

  16. Radiochemical studies on the separation of iodine-131 and radioiodination of some organic compounds

    International Nuclear Information System (INIS)

    Mohamed, M.A.I.

    2010-01-01

    its retardation factor (R f ). The second technique is the purification of the labeled compounds by means of high pressure liquid chromatography (HPLC). On the reverse phase RP-18, column eluted with an appropriate solvent where each compound is identified by its retention time (R t ).Chapter III :It deals with the idea of separation of iodine-131 from tellurium targets using the dry distillation method. The factors affecting the production and separation of 131 I were studied such as the oven temperature; the distillation time and the sodium hydroxide concentration, the following flow sheet summarizes the production process. The quality control tests were carried out on the final product (Na 131 I). They were 99.9%, 98.7% for radionuclidic purity and radiochemical purity, respectively and the chemical purity of Te in the final radioiodine was 0.8μg/ml.

  17. Comparison of alkali fusion and acid digestion methods for radiochemical separation of Uranium from dietary samples

    International Nuclear Information System (INIS)

    Kamesh Viswanathan, B.; Arunachalam, Kantha D.; Sathesh Kumar, A.; Jayakrishana, K.; Shanmugamsundaram, H.; Rao, D.D.

    2014-01-01

    Several methods exist for separation and measurement of uranium in dietary samples such as neutron activation analysis (NAA), alpha spectrometric determination, inductively coupled plasma mass spectrometry (ICP-MS) and fluorimetry. For qualitative determination of activity, NAA and alpha spectrometry are said to be superior to evaluate the isotopes of uranium ( 238 U, 234 U and 235 U). In case of alpha spectrometry, the samples have to undergo radiochemical analysis for separation from other elements for uranium detection. In our studies, uranium was determined in food matrices by acid digestion (AD) and alkali fusion (AF) methods. The recovery yield of uranium in food matrices was compared in order to get consistent yield. The average activity levels of 238 U and 234 U in food samples were calculated based on recovery yield of 232 U in the samples. The average recovery of 232 U in AD method was 22 ± 8% and in AF method, it was 14.9 ± 1.3%. The spread is more in AD method than the AF method from their mean. The lowest recovery of 232 U was found in AF method. This is due to the interference of other elements in the sample during electroplating. Experimental results showed that the uranium separation by AD method has better recovery than the AF method. The consistency in recovery of 232 U was better for AF method, which was lower than the AD method. However, overall for both the methods, the recovery can be termed as poor and need rigorous follow up studies for consistently higher recoveries (>50%) in these type of biological samples. There are reports indicating satisfactory recoveries of around 80% with 232 U as tracer in the food matrices

  18. Proceedings of DAE-BRNS biennial symposium on emerging trends in separation science and technology

    International Nuclear Information System (INIS)

    Pathak, P.N.; Mohapatra, P.K.; Goswami, A.

    2012-01-01

    The symposium on emerging trends in separation science and technology was held during 27 February -1 March, 2012. An attempt has been made to cover a wide range of topics in the symposium including design and synthesis of solvents/resins, development of separation equipment's, separation the nuclear fuel cycle, emerging separation technologies, electrochemical and pyrochemical separations, treatment of industrial effluents, isotope separations, membrane science and technology, radiochemical separations, water treatment and recycling, bioremediation and speciation. Papers relevant to INIS are indexed separately

  19. Radiochemical Separation and Quantification of Tritium in Metallic Radwastes Generated from CANDU Type NPP - 13279

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, H.J.; Choi, K.C.; Choi, K.S.; Park, T.H.; Park, Y.J.; Song, K. [Korea Atomic Energy Research Institute, P.O. Box 105, Yuseong, Daejeon, 305-330 (Korea, Republic of)

    2013-07-01

    As a destructive quantification method of {sup 3}H in low and intermediate level radwastes, bomb oxidation, sample oxidation, and wet oxidation methods have been introduced. These methods have some merits and demerits in the radiochemical separation of {sup 3}H radionuclides. That is, since the bomb oxidation and sample oxidation methods are techniques using heating at high temperature, the separation methods of the radionuclides are relatively simple. However, since {sup 3}H radionuclide has a property of being diffused deeply into the inside of metals, {sup 3}H which is distributed on the surface of the metals can only be extracted if the methods are applied. As an another separation method, the wet oxidation method makes {sup 3}H oxidized with an acidic solution, and extracted completely to an oxidized HTO compound. However, incomplete oxidized {sup 3}H compounds, which are produced by reactions of acidic solutions and metallic radwastes, can be released into the air. Thus, in this study, a wet oxidation method to extract and quantify the {sup 3}H radionuclide from metallic radwastes was established. In particular, a complete extraction method and complete oxidation method of incomplete chemical compounds of {sup 3}H using a Pt catalyst were studied. The radioactivity of {sup 3}H in metallic radwastes is extracted and measured using a wet oxidation method and liquid scintillation counter. Considering the surface dose rate of the sample, the appropriate size of the sample was determined and weighed, and a mixture of oxidants was added to a 200 ml round flask with 3 tubes. The flask was quickly connected to the distilling apparatus. 20 mL of 16 wt% H{sub 2}SO{sub 4} was given into the 200-ml round flask through a dropping funnel while under stirring and refluxing. After dropping, the temperature of the mixture was raised to 96 deg. C and the sample was leached and oxidized by refluxing for 3 hours. At that time, the incomplete oxidized {sup 3}H compounds were

  20. Cadmium determination in biological samples using neutron activation analysis with radiochemical separations

    International Nuclear Information System (INIS)

    Munoz A, Luis; Gras R, Nuri

    2005-01-01

    Chile has 7500 km of coastline on the Southern Pacific ocean,with about 4500 km of continental coastline that contains a variety of different geographical zones.This variety means that there is a great diversity of marine resources such as fish, shellfish and seaweeds. The utilization of these resources has been increasing in recent years making this sector an economically important one. The catch as of May 2002 came to 1.9 million tons and exports of the different species amounted to US$611.5 million as of April.But this important economic resource is being threatened by the technical demands imposed by importing countries, mainly the specific requirements for sanitary certification for fishery export products, depending on the markets of destination. The chemical element cadmium is one of the most strictly controlled elements due some shellfish accumulate a large amount of this element and to its high toxicity. The Chilean standard's analytical procedures for cadmium determination in hydro biological products, which must be met by laboratories that certify and control these products for export, are now being evaluated. Through its Chemical Metrology Unit, the Chilean Nuclear Energy Commission is strongly supporting this sector by preparing the secondary reference or control materials, and it has developed and implemented nuclear analytical methods for the certification of these materials, which will be used mostly in collaborative studies. This work describes the methodology developed for the determination of cadmium in biological samples, particularly in shellfish and fish. The method is based on neutron activation analysis with radiochemical separations, using the radioisotopes 115 Cd and 115m In, generated in the samples by bombarding with neutrons in a nuclear reactor. The samples were digested at 110 o C with H 2 SO 4 and H 2 O 2 and then the radioactive cadmium element was separated from the other elements present in the samples using a Bio Rad AG 2-X8

  1. Separation science and technology

    International Nuclear Information System (INIS)

    Smith, B.F.; Sauer, N.; Chamberlin, R.M.; Gottesfeld, S.; Mattes, B.R.; Li, D.Q.; Swanson, B.

    1998-01-01

    The focus of this project is the demonstration and advancement of membrane-based separation and destruction technologies. The authors are exploring development of membrane systems for gas separations, selective metal ion recovery, and for separation or destruction of hazardous organics. They evaluated existing polymers and polymer formulations for recovery of toxic oxyanionic metals such as chromate and arsenate from selected waste streams and developed second-generation water-soluble polymeric systems for highly selective oxyanion removal and recovery. They optimized the simultaneous removal of radioactive strontium and cesium from aqueous solutions using the new nonhazardous separations agents, and developed recyclable, redox-active extractants that permitted recovery of the radioactive ions into a minimal waste volume. They produced hollow fibers and fabricated prototype hollow-fiber membrane modules for applications to gas separations and the liquid-liquid extraction and recovery of actinides and nuclear materials from process streams. They developed and fabricated cyclodextrin-based microporous materials that selectively absorb organic compounds in an aqueous environment; the resultant products gave pure water with organics at less than 0.05 parts per billion. They developed new, more efficient, membrane-based electrochemical reactors for use in organic destruction in process waste treatment. They addressed the need for advanced oxidation technologies based on molecular-level materials designs that selectively remove or destroy target species. They prepared and characterized surface-modified TiO 2 thin films using different linking approaches to attach ruthenium photosensitizers, and they started the measurement of the photo-degradation products generated using surface modified TiO 2 films in reaction with chlorophenol

  2. Utility of reversed phase high performance liquid chromatography for on-line yield determination of radiochemical separations: Studies with cobalt

    International Nuclear Information System (INIS)

    Subramanian, S.; Woittiez, J.R.W.

    1993-01-01

    This article indicates the potentials of high performance liquid chromatography (HPLC) as a radiochemical technique for multielement separation of neutron irradiated samples. The focus lies on the convenience to use the detector signal of the eluted components to indicate the chemical yield of the analyte, which has often proved to be a crucial step in radiochemical separations. Two signals have been utilized. The UV signal of the metal-ligand complexes separated by reversed phase HPLC and the radioactive response as a result of sample irradiation of carrier-tracer addition. Change in ratio is discussed between the two signals, if any, for a specific sample. Losses of metal as much as 65% were simulated and corrected using the individual UV response. The method promises improved accuracy for elemental analysis despite losses suffered during the various chemical steps. The procedure omits the necessity of additional analytical steps for yield determination. The present article aims at the chromatographic part of the study. Cobalt as cobalt diethyldithiocarbamate has been used to demonstrate the viability of the concept. The separation was developed on c C18 reverse phase analytical column and optimized on a semi preparative one

  3. Innovative Separations Technologies

    Energy Technology Data Exchange (ETDEWEB)

    J. Tripp; N. Soelberg; R. Wigeland

    2011-05-01

    Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material properties, and engineering. Technology options are available to meet a variety of processing goals. A decision about which reprocessing method is best depends significantly on the process attributes considered to be a priority. New methods of reprocessing that could provide advantages over the aqueous Plutonium Uranium Reduction Extraction (PUREX) and Uranium Extraction + (UREX+) processes, electrochemical, and other approaches are under investigation in the Fuel Cycle Research and Development (FCR&D) Separations Campaign. In an attempt to develop a revolutionary approach to UNF recycle that may have more favorable characteristics than existing technologies, five innovative separations projects have been initiated. These include: (1) Nitrogen Trifluoride for UNF Processing; (2) Reactive Fluoride Gas (SF6) for UNF Processing; (3) Dry Head-end Nitration Processing; (4) Chlorination Processing of UNF; and (5) Enhanced Oxidation/Chlorination Processing of UNF. This report provides a description of the proposed processes, explores how they fit into the Modified Open Cycle (MOC) and Full Recycle (FR) fuel cycles, and identifies performance differences when compared to 'reference' advanced aqueous and fluoride volatility separations cases. To be able to highlight the key changes to the reference case, general background on advanced aqueous solvent extraction, advanced oxidative processes (e.g., volumetric oxidation, or 'voloxidation,' which is high temperature reaction of oxide UNF with oxygen, or modified using other oxidizing and reducing gases), and fluorination and chlorination processes is provided.

  4. Innovative Separations Technologies

    International Nuclear Information System (INIS)

    Tripp, J.; Soelberg, N.; Wigeland, R.

    2011-01-01

    Reprocessing used nuclear fuel (UNF) is a multi-faceted problem involving chemistry, material properties, and engineering. Technology options are available to meet a variety of processing goals. A decision about which reprocessing method is best depends significantly on the process attributes considered to be a priority. New methods of reprocessing that could provide advantages over the aqueous Plutonium Uranium Reduction Extraction (PUREX) and Uranium Extraction + (UREX+) processes, electrochemical, and other approaches are under investigation in the Fuel Cycle Research and Development (FCR and D) Separations Campaign. In an attempt to develop a revolutionary approach to UNF recycle that may have more favorable characteristics than existing technologies, five innovative separations projects have been initiated. These include: (1) Nitrogen Trifluoride for UNF Processing; (2) Reactive Fluoride Gas (SF6) for UNF Processing; (3) Dry Head-end Nitration Processing; (4) Chlorination Processing of UNF; and (5) Enhanced Oxidation/Chlorination Processing of UNF. This report provides a description of the proposed processes, explores how they fit into the Modified Open Cycle (MOC) and Full Recycle (FR) fuel cycles, and identifies performance differences when compared to 'reference' advanced aqueous and fluoride volatility separations cases. To be able to highlight the key changes to the reference case, general background on advanced aqueous solvent extraction, advanced oxidative processes (e.g., volumetric oxidation, or 'voloxidation,' which is high temperature reaction of oxide UNF with oxygen, or modified using other oxidizing and reducing gases), and fluorination and chlorination processes is provided.

  5. Radiochemical separation of {sup 231}Pa from siliceous cake prior to its determination by gamma ray spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Dalvi, Aditi A. [Bhabha Atomic Research Centre, Mumbai (India). Analytical Chemistry Div.; Homi Bhabha National Institute, Mumbai (India); Verma, Rakesh

    2017-07-01

    A simple and fast radiochemical method for the separation of protactinium ({sup 231}Pa) from siliceous cake for its determination by gamma ray spectrometry is described. The method involves (a) a novel approach, the fusion of the siliceous cake with sodium peroxide, (b) the dissolution of the fused mass in nitric acid and (c) the co-precipitation of {sup 231}Pa with manganese dioxide formed in-situ by the addition of solid manganous sulfate and potassium permanganate to the solution. The fusion, effected in a single step, is simpler and highly effective in comparison to methods reported hitherto in literature. The radiochemical yield of {sup 231}Pa, determined using 311.9 keV gamma ray of {sup 233}Pa radiotracer is quantitative (∝90%). The decontamination factors calculated using gamma ray spectrometry and energy dispersive X-ray fluorescence measurements show that the separation from the interfering radionuclides is high whereas separation from major and minor elements is good. Separation by ion-exchange method in hydrochloric acid, hydrofluoric acid and oxalic acid media have comparatively much lower yields. The concentration of {sup 231}Pa in the siliceous cake measured using interference-free 283.6 keV gamma ray was found to be (6.4 ± 0.33) μg kg{sup -1}. The measured concentration of {sup 231}Pa was well above the limit of quantitation whereas the coefficient of variation was ∝5%. The improvement in the limit of detection was due to the reduction in spectral background. Systematic evaluation of various uncertainty parameters showed that the major contributors to the combined uncertainty were efficiency of the high purity germanium detector and the counting statistics. The present sample decomposition and separation methods are robust, simple to perform and can be effectively used for the determination and hence source prospecting of protactinium.

  6. Development of a rapid radiochemical procedure for the separation of /sup 235m/U from 239Pu

    International Nuclear Information System (INIS)

    Attrep, M. Jr.; Efurd, D.W.; Roensch, F.R.

    1987-01-01

    We have developed a rapid radiochemical procedure for the isolation and purification of /sup 235m/U (t/sub 1/2/ = 26 minutes) from 239 Pu samples up to 250 mg. Purpose of developing the procedure was to measure the thermal neutron fission cross section of the isomeric meta state of 235 U. We used rapid small-scale anion exchange columns that absorbed uranium in concentrated HBr but did not absorb plutonium. Uranium was easily eluted with very dilute HF. The separation time required 25 to 35 minutes. We were able to attain a separation factor of uranium from plutonium of approximately 1 x 10 10 with samples ranging from 1 x 10 10 to 3 x 10 11 . The ratio of the fission cross sections for the meta to ground state was measured to be 1.42. 4 figs., 1 tab

  7. Separation procedure for the determination of Ag, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Haas, H F; Krivan, V

    1986-05-01

    A simple separation procedure for the determination of Ag, Au, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis was developed. It enables the separation of the indicator radionuclides sup(110m)Ag, /sup 198/Au, /sup 115/Cd, /sup 203/Hg and /sup 65/Zn in a group with yields >99% and is well suited for the separation of /sup 203/Hg from /sup 75/Se and /sup 65/Zn from /sup 46/Sc. The separation of these radionuclides is often necessary because of the occurrence of instrumental interferences in the instrumental neutron activation analysis. Simultaneously, the limits of detection for Ag, Au and Cd can significantly be improved. The method is based on the decomposition of the sample in the mixture of HNO/sub 3//HCl/H/sub 2/O/sub 2/ and on the separation of Ag, Au, Cd, Hg and Zn on Dowex 1X8 from a sample solution being 1.5 M with HCl. The applicability of this method is demonstrated by the analysis of lichens and several kinds of fungi. For the experimental conditions used, the limits of detection are of the order of magnitude of 10 ng/g.

  8. Determination of Sr, Ba, Rb, and Cs in biological reference materials using a radiochemical NAA group separation procedure

    International Nuclear Information System (INIS)

    Mizera, J.; Randa, Z.

    2008-01-01

    Strontium, barium, rubidium, and cesium in selected, predominantly biological, reference materials (NIST 1515, 1547, 1549, 1566a, 1571, 1577b, 2704, CTA-OTL-1, and Bowen's Kale) were determined using neutron activation analysis (NAA) in two different analytical modes - instrumental NAA with epithermal neutrons (ENAA), and NAA with radiochemical group separation of Sr-Ba and Rb-Cs (RNAA). The ENAA mode was based on long-term (5 h) irradiation of samples in a Cd shielding. The RNAA procedure was based on long-term (20 h) irradiation of samples, their decomposition / dissolution by alkaline-oxidative fusion, and precipitation of Sr and Ba sulfates, and sorption of Rb and Cs onto ammonium phosphomolybdate (APM). Both methods provided element contents in the analyzed reference materials consistent with certified and/or literature values. (author)

  9. Radiochemical determination and separation or total radium, 226Ra and 224Ra; Analisis Radioquimico de Radio total, Radio-226 y Radio-224

    Energy Technology Data Exchange (ETDEWEB)

    Suarez, J A; Gonzalez, J A; Pablo, M A. de

    1987-07-01

    Radiochemical purification and separation of radium has been carried out and the determination of total radium solubilized in aqueous samples has been studied assuming that all the alpha emitters of the sample have their origin in the 226Ra and elements of its desintegration chain. Also, the activities of 22Ra and 226 Ra have been evaluated separately doing a measurement after the chemical separation of the radium and another one 10 days after. (Author) 9 refs.

  10. Studies on the radiochemical separation of Ga(III) from Zn(II)

    International Nuclear Information System (INIS)

    Chirayil, Viju; Vimalnath, K.V.; Jagadeesan, K.C.; Thakare, S.V.; Dhami, P.S.; Jagesia, Poonam; Dakshinamoorthy, A.

    2007-01-01

    The 67 Ga, produced in cyclotron from zinc target is widely used in tumor imaging in the form of gallium citrate. A method to separate gallium from zinc is developed using cation exchange chromatography. Reactor produced 65 Zn and 72 Ga were used to study the separation characteristics for further applicability in cyclotron production of 67 Ga. Zinc forms a stable cationic complex with NH 3 , whereas, Gallium forms anionic gallate (Ga(OH) 4 )- at pH 9.3. Zinc is quantitatively taken up by the cation exchange resin (Tulsion T-42) in NH 4 + form, thus effecting a simple rapid one step separation between Zn and Ga. (author)

  11. Rapid radiochemical ion-exchange separation of iodine from tellurium: a novel radioiodine-132 generator

    Energy Technology Data Exchange (ETDEWEB)

    Abrao, A

    1975-01-01

    Tellurium ions form a soluble cationic complex with thiourea in acid medium. The cationic tellurium-thiourea species is strongly absorbed on a cationic ion exchanger. The retention of tellurium on the resin enables many interesting separation schemes for tellurium from various ions. With special interest, the separation of iodine from tellurium was studied. An efficient and convenient iodine-132 generator is described, in which the radio-iodine is eluted with water or 9 g/1 NaCl, when desired.

  12. A rapid radiochemical ion-exchange separation of iodine from tellurium: a novel radioiodine-132 generator

    International Nuclear Information System (INIS)

    Abrao, A.

    1975-01-01

    Tellurium ions form a soluble cationic complex with thiourea in acid medium. The cationic tellurium-thiourea species is strongly absorbed on a cationic ion exchanger. The retention of tellurium on the resin enables many interesting separation schemes for tellurium from various ions. With special interest, the separation of iodine from tellurium was studied. An efficient and convenient iodine-132 generator is described, in which the radio-iodine is eluted with water or 9 g/1 NaCL, when desired

  13. Automated ion-exchange system for the radiochemical separation of the noble metals

    International Nuclear Information System (INIS)

    Parry, S.J.

    1980-01-01

    Ion-exchange separation is particularly suitable for mechanisation and automated ion exchange has been applied to the activation analysis of biological and environmental samples. In this work a system has been designed for experimental studies, which can be adapted for different modes of operation. The equipment is based on a large-volume sampler for the automatic presentation of 500 ml of liquid to a sampling probe. The sample is delivered to the ion-exchange column by means of a peristaltic pump. The purpose of this work was to automate a procedure for separating the noble metals from irradiated geological samples, for neutron-activation analysis. The process of digesting the rock sample is carried out manually in 30 min and is not suited to unattended operation. The volume of the resulting liquid sample may be 100 ml and so the manual separation step may take as long as 1.25 h per sample. The reason for automating this part of the procedure is to reduce the separation time for a group of five samples and consequently to improve the sensitivity of the analysis for radionuclides with short half-lives. This paper describes the automatic ion-exchange system and the ways in which it can be used. The mode of operation for the separation of the noble metals is given in detail. The reproducibility of the system has been assessed by repeated measurements on a standard reference matte. (author)

  14. Separation technology 2005; Separasjonsteknologi 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The conference comprises 13 presentations on the topics of separation technology aspects with emphasis on technology assessment. Some topics of particular interest are emulsion stabilization, sand technology and handling, water handling and reservoir injection, technical equipment and compression and pressure aspects.

  15. Innovation in metrology: fast automated radiochemical separation and measurement for strontium 89 and 90

    Energy Technology Data Exchange (ETDEWEB)

    Augeray, C.; Galliez, K.; Mouton, M.; Tarlette, L.; Loyen, J.; Fayolle, C.; Gleizes, M. [Institut de Radioprotection et de Surete Nucleaire - IRSN (France)

    2014-07-01

    Measuring radioactivity in the food and for radiological monitoring of the environment around Nuclear Facilities or mining sites requires the quantification of the radioactive isotopes present in the different compartments (liquids or solids), especially of the beta emitters. Strontium 89 and 90, both pure beta emitters are radioactive isotopes of interest. Because of their toxicity and the similarity of their chemical and physical behavior with calcium, these elements may be found through the food chain. After the Fukushima accident, the necessity of quantifying quickly radioactive isotopes such as strontium 89 and 90 appeared. The technique we are going to present concerns the determination of the activity concentration of strontium 89 and 90 in water, according to the {sup 89}Sr/{sup 90}Sr ratio. It consists of two stages: the chemical separation by ionic chromatography and the measurement of the activity concentration of strontium 89 and 90 by Cerenkov Effect. The automated separation has been developed and allows isolating the isotopes of strontium in particular the radioactive ones: strontium 89 and 90. The separation can be done within one hour. It was realized from the adaptation of existing analytical chemistry equipments with on-line couplings. The protocol of separation is based on the use of ions exchange columns of Ionic chromatography not as a separation and measurement technique of the cation but only as a separation technique. At the release time of the ion to be quantified, a fraction collector allows its recovery. The test portion is then analyzed with a liquid scintillation counter (LSC). The activity concentration is measured by Cerenkov Effect on a quenched sample. The quenching is realized by applying a thin colored film on the sample vial. This color quench is used to make strontium 90 counts disappear on the LS spectrum. This way, only yttrium 90 ingrowth and strontium 89 decay are measured (E{sup 90}Sr < E{sup 89}Sr < E{sup 90}Y

  16. Acoustic Separation Technology; FINAL

    International Nuclear Information System (INIS)

    Fred Ahrens; Tim Patterson

    2002-01-01

    Today's restrictive environmental regulations encourage paper mills to close their water systems. Closed water systems increase the level of contaminants significantly. Accumulations of solid suspensions are detrimental to both the papermaking process and the final products. To remove these solids, technologies such as flotation using dissolved air (DAF), centrifuging, and screening have been developed. Dissolved Air Flotation systems are commonly used to clarify whitewater. These passive systems use high pressure to dissolve air into whitewater. When the pressure is released, air micro-bubbles form and attach themselves to fibers and particles, which then float to the surface where they are mechanically skimmed off. There is an economic incentive to explore alternatives to the DAF technology to drive down the cost of whitewater processing and minimize the use of chemicals. The installed capital cost for a DAF system is significant and a typical DAF system takes up considerable space. An alternative approach, which is the subject of this project, involves a dual method combining the advantages of chemical flocculation and in-line ultrasonic clarification to efficiently remove flocculated contaminants from a water stream

  17. Radiochemical studies of the separation of some chloro-complexes of tin, antimony, cadmium and indium

    International Nuclear Information System (INIS)

    Ramamoorthy, N.; Mani, R.S.

    1976-01-01

    Radioisotopes of tin, antimony, cadmium and indium such as tin-113, antimony-124, antimony-125, cadmium-109, cadmium-115, indium-113m and indium-111 find extensive applications as tracers in various fields. These isotopes are produced by irradiation of targets in a reactor or a cyclotron. It is usually observed that in addition to the nuclear reactions giving rise to the desired isotopes, side reactions also take place giving rise to radionuclidic contaminants. Thus, antimony-125, indium-114m and indium-114 will be present in the cyclotron produced indium-111. The authors have studied column chromatography over hydrous zirconia for the separation of antimony from tin and indium, and cadmium from indium. These studies have thrown light on the role and behaviour of antimony-125 present as an impurity in tin-113 during the preparation of tin-113-indium-113m generators and have indicated methods for the preparation of 115 Cd-sup(115m)In generators and for separation of 111 In from proton irradiated cadmium targets. (Authors)

  18. Study of the isotopic exchange associated with ionic exchange for the radiochemical separation of 233-Th

    International Nuclear Information System (INIS)

    Sepulveda Munita, C.J.A.

    1983-01-01

    The isotopic ion exchange procedure is applied in order to establish an analytical method for the determination of thorium by means of the 233 Th activity, when the presence of interfering elements does not allow a direct non-destructive activation analysis. The separation is based on the retention of 233 Th by a thorium saturated resin, due to the isotopic exchange effect, and subsequent elution of the interfering radioisotopes with a solution of thorium in diluted hydrochloric acid. The interfering elements were those which either present a great affinity for the resin or emit gamma rays with energies close to that of 233 Th (86.6 KeV), when a NaI(Tl) detector is used to obtain the gama-ray spectra of the irradiated samples. The equilibrium time for the thorium isotopic ion exchange and the distribution coefficients for the interfering elements were determined by using Bio-Rad AG 50W resins (100-200 mesh), with 4% to 8% of divinylbenzene. The best separation conditions were established in terms of the thorium and hydrochloric acid concentrations in the solution, the resin cross-linking degree, and the solution flow through the resin. The analytical method was applied to the determination of thorium in samples of ammonium diuranate as well in standard rock samples from the United States Geological Survey. The sensitivity, precision and accuracy of the method are also discussed. (Author) [pt

  19. Radiochemical separation from111In from Cd and Cu by Ion exchange chromatography

    International Nuclear Information System (INIS)

    Yavari, R.; Khanchi, A. R.; Rafii, H.; Maragheh, M. G.; Farajzadeh, M. A.

    2005-01-01

    In this work, during the nuclear reaction of nat Cd (p, xn) 111 In, the irradiated cadmium target was dissolved in 3 M nitric acid. It was passed through a cation exchange column, containing 4 g. of AG 5OW-X8, and then was separated from cadmium and copper impurities by using a simple two stage procedure. At the first stage, cadmium was eluted with acetone-water-hydrobromic acid solution. At the second stage, indium was eluted with acetone-water-hydrochloric acid solution. The effluent was evaporated to dry and the residue was dissolved in 0.01M hydrochloric acid. The overall yield of the procedure was 95 ± 1 percent and the amount of cadmium and copper contamination were 0.3 and 0.1 ppm, respectively

  20. Production and radiochemical separation of 203Pb radioisotope for nuclear medicine

    International Nuclear Information System (INIS)

    Szuecs, Z.; Takacs, S.; Andrasi, D.; Kovacs, B.

    2012-01-01

    Complete text of publication follows. The heavy metal pollution due to their industrial production, waste repository or accident as the cyanide spill in river Tisza in 2002, increase the scientific interest for using an ideal trace isotope for monitoring these type of events. The lead is one of the most toxic and commonly used heavy metal, its poisoning is often deadly because very difficult to recognize and identify. The neuro-scientific study of biodegradation effect of lead could be an impressive scientific field of application of 203 Pb radioisotope. However the targeted radionuclide therapy especially the α-emitting radioisotope therapy is also strongly interested to find an ideal tracer for the 213 Bi and 212 Pb therapy. Therefore the 203 Pb is a potential radioisotope for this role due to its radiation behaviour and as heavy metal element. The 203 Tl(p,n) 203 Pb nuclear reaction was chosen for the production. The irradiation was done at the compact cyclotron of Atomki with proton beam 14.5 MeV energy and beam current of 7 μAs. The thickness of the target material was 840 μm, the irradiation time was 3 hours and the produced activity was 40 MBq at EOB. It corresponds to 1.87 MBq/μAh physical yield of the reaction which correlating with the cross section curve. A new technique was developed for target preparation. The metal Tl was pressed into a copper backing and covered with a HAWAR foil with thickness of 11 μm. The covering foil saved the surface of the Tl from the oxidation and also transferred the dissipating heat to the cooling He gas. The back side of the target was cooled with pressured cold water. The irradiated Tl target was pressed out from the copper backing, which had only the thickness of 0.2 mm. Then the Thallium was dissolved in nitric acid. The excess acid was evaporated slowly. The nitrate form was transferred to chloride form by 8 mol/dm 3 HCl and the Thallium was kept in 3+ oxidation stage by hydrogen peroxide. The separation was

  1. Green methods for the radiochemical separations of no-carrier-added 61Cu, 62Zn from 7Li irradiated cobalt target

    International Nuclear Information System (INIS)

    Moumita Maiti; Kaustab Ghosh; Susanta Lahiri

    2015-01-01

    A nat Co target was irradiated with 47 MeV 7 Li beam to produce no-carrier-added 61 Cu, 62 Zn in the target matrix. Two new green radiochemical methods were developed for separation of 61 Cu and 62 Zn from the target matrix, (i) liquid-liquid extraction (LLX) technique using room temperature ionic liquid (RTIL) 1-butyl-3-methylimidazolium hexafluorophosphate ([C 4 mim][PF 6 ]) and ammonium pyrrolidinedithiocarbamate (APDC) (ii) adsorption on calcium alginate beads. (author)

  2. Center for Advanced Separation Technology

    Energy Technology Data Exchange (ETDEWEB)

    Honaker, Rick

    2013-09-30

    The U.S. is the largest producer of mining products in the world. In 2011, U.S. mining operations contributed a total of $232 billion to the nation’s GDP plus $138 billion in labor income. Of this the coal mining industry contributed a total of $97.5 billion to GDP plus $53 billion in labor income. Despite these contributions, the industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Originally set up by Virginia Tech and West Virginia University, CAST is now a five-university consortium – Virginia Tech, West Virginia University, University of Kentucky, University of Utah and Montana Tech, - that is supported through U.S. DOE Cooperative Agreement No. DE-FE0000699, Center for Advanced Separation Technology. Much of the research to be conducted with Cooperative Agreement funds will be longer term, high-risk, basic research and will be carried out in two broad areas: Advanced Pre-Combustion Clean Coal Technologies and Gas-Gas Separations. Distribution of funds is handled via competitive solicitation of research proposals through Site Coordinators at the five member universities. These were reviewed and the selected proposals were forwarded these to the DOE/NETL Project Officer for final review and approval. The successful projects are listed below by category, along with abstracts from their final reports.

  3. Determination of trace amounts of uranium in silicate materials by means of neutron activation analysis involving rapid radiochemical separation

    International Nuclear Information System (INIS)

    Ebihara, M.; Tomura, Kenji; Masutani, M.

    1987-01-01

    Uranium is determined in silicate materials such as standard rocks and a meteorite by radiochemical neutron activation analysis. The gamma-ray intensity of 239 U was measured with a planar type pure germanium detector system. The obtained data are mostly consistent with the literature values. Compared with a non-destructive method, the present method was found to improve the sensitivity by at least a factor of ten. Several errors which might be involved in the authors' RNAA procedures were examined and their degrees were evaluated. (author)

  4. 14th radiochemical conference. Booklet of abstracts

    International Nuclear Information System (INIS)

    2002-03-01

    The contributions dealt with the following topics: Radionuclides in the environment, radioecology; Nuclear analytical methods; Chemistry of actinide and trans-actinide elements; Ionizing radiation in science, technology, and arts and cultural heritage preservation; Production and application of radionuclides; Separation methods, speciation; Chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management; and Nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds. Of the verbal and poster presentation, 192 have been input to INIS. (P.A.)

  5. Separators - Technology review: Ceramic based separators for secondary batteries

    Energy Technology Data Exchange (ETDEWEB)

    Nestler, Tina; Schmid, Robert; Münchgesang, Wolfram; Bazhenov, Vasilii; Meyer, Dirk C. [Technische Universität Bergakademie Freiberg, Institut für Experimentelle Physik, Leipziger Str. 23, 09596 Freiberg (Germany); Schilm, Jochen [Fraunhofer-Institut für Keramische Technologien und Systeme IKTS, Winterbergstraße 28, 01277 Dresden (Germany); Leisegang, Tilmann [Fraunhofer-Technologiezentrum Halbleitermaterialien THM, Am St.-Niclas-Schacht 13, 09599 Freiberg (Germany)

    2014-06-16

    Besides a continuous increase of the worldwide use of electricity, the electric energy storage technology market is a growing sector. At the latest since the German energy transition ('Energiewende') was announced, technological solutions for the storage of renewable energy have been intensively studied. Storage technologies in various forms are commercially available. A widespread technology is the electrochemical cell. Here the cost per kWh, e. g. determined by energy density, production process and cycle life, is of main interest. Commonly, an electrochemical cell consists of an anode and a cathode that are separated by an ion permeable or ion conductive membrane - the separator - as one of the main components. Many applications use polymeric separators whose pores are filled with liquid electrolyte, providing high power densities. However, problems arise from different failure mechanisms during cell operation, which can affect the integrity and functionality of these separators. In the case of excessive heating or mechanical damage, the polymeric separators become an incalculable security risk. Furthermore, the growth of metallic dendrites between the electrodes leads to unwanted short circuits. In order to minimize these risks, temperature stable and non-flammable ceramic particles can be added, forming so-called composite separators. Full ceramic separators, in turn, are currently commercially used only for high-temperature operation systems, due to their comparably low ion conductivity at room temperature. However, as security and lifetime demands increase, these materials turn into focus also for future room temperature applications. Hence, growing research effort is being spent on the improvement of the ion conductivity of these ceramic solid electrolyte materials, acting as separator and electrolyte at the same time. Starting with a short overview of available separator technologies and the separator market, this review focuses on ceramic

  6. Separators - Technology review: Ceramic based separators for secondary batteries

    Science.gov (United States)

    Nestler, Tina; Schmid, Robert; Münchgesang, Wolfram; Bazhenov, Vasilii; Schilm, Jochen; Leisegang, Tilmann; Meyer, Dirk C.

    2014-06-01

    Besides a continuous increase of the worldwide use of electricity, the electric energy storage technology market is a growing sector. At the latest since the German energy transition ("Energiewende") was announced, technological solutions for the storage of renewable energy have been intensively studied. Storage technologies in various forms are commercially available. A widespread technology is the electrochemical cell. Here the cost per kWh, e. g. determined by energy density, production process and cycle life, is of main interest. Commonly, an electrochemical cell consists of an anode and a cathode that are separated by an ion permeable or ion conductive membrane - the separator - as one of the main components. Many applications use polymeric separators whose pores are filled with liquid electrolyte, providing high power densities. However, problems arise from different failure mechanisms during cell operation, which can affect the integrity and functionality of these separators. In the case of excessive heating or mechanical damage, the polymeric separators become an incalculable security risk. Furthermore, the growth of metallic dendrites between the electrodes leads to unwanted short circuits. In order to minimize these risks, temperature stable and non-flammable ceramic particles can be added, forming so-called composite separators. Full ceramic separators, in turn, are currently commercially used only for high-temperature operation systems, due to their comparably low ion conductivity at room temperature. However, as security and lifetime demands increase, these materials turn into focus also for future room temperature applications. Hence, growing research effort is being spent on the improvement of the ion conductivity of these ceramic solid electrolyte materials, acting as separator and electrolyte at the same time. Starting with a short overview of available separator technologies and the separator market, this review focuses on ceramic-based separators

  7. Separation process using microchannel technology

    Science.gov (United States)

    Tonkovich, Anna Lee [Dublin, OH; Perry, Steven T [Galloway, OH; Arora, Ravi [Dublin, OH; Qiu, Dongming [Bothell, WA; Lamont, Michael Jay [Hilliard, OH; Burwell, Deanna [Cleveland Heights, OH; Dritz, Terence Andrew [Worthington, OH; McDaniel, Jeffrey S [Columbus, OH; Rogers, Jr; William, A [Marysville, OH; Silva, Laura J [Dublin, OH; Weidert, Daniel J [Lewis Center, OH; Simmons, Wayne W [Dublin, OH; Chadwell, G Bradley [Reynoldsburg, OH

    2009-03-24

    The disclosed invention relates to a process and apparatus for separating a first fluid from a fluid mixture comprising the first fluid. The process comprises: (A) flowing the fluid mixture into a microchannel separator in contact with a sorption medium, the fluid mixture being maintained in the microchannel separator until at least part of the first fluid is sorbed by the sorption medium, removing non-sorbed parts of the fluid mixture from the microchannel separator; and (B) desorbing first fluid from the sorption medium and removing desorbed first fluid from the microchannel separator. The process and apparatus are suitable for separating nitrogen or methane from a fluid mixture comprising nitrogen and methane. The process and apparatus may be used for rejecting nitrogen in the upgrading of sub-quality methane.

  8. Automation of radiochemical analysis by flow injection techniques. Am-Pu separation using TRU-resinTM sorbent extraction column

    International Nuclear Information System (INIS)

    Egorov, O.; Washington Univ., Seattle, WA; Grate, J.W.; Ruzicka, J.

    1998-01-01

    A rapid automated flow injection analysis (FIA) procedure was developed for efficient separation of Am and Pu from each other and from interfering matrix and radionuclide components using a TRU-resin TM column. Selective Pu elution is enabled via on-column reduction. The separation was developed using on-line radioactivity detection. After the separation had been developed, fraction collection was used to obtain the separated fractions. In this manner, a FIA instrument functions as an automated separation workstation capable of unattended operation. (author)

  9. Radiochemical methods

    International Nuclear Information System (INIS)

    Geary, W.J.

    1986-01-01

    This little volume is one of an extended series of basic textbooks on analytical chemistry produced by the Analytical Chemistry by Open Learning project in the UK. Prefatory sections explain its mission, and how to use the Open Learning format. Seventeen specific sections organized into five chaptrs begin with a general discussion of nuclear properties, types, and laws of nuclear decay and proceeds to specific discussions of three published papers (reproduced in their entirety) giving examples of radiochemical methods which were discussed in the previous chapter. Each section begins with an overview, contains one or more practical problems (called self-assessment questions or SAQ's), and concludes with a summary and a list of objectives for the student. Following the main body are answers to the SAQ's, and several tables of physical constants, SI prefixes, etc. A periodic table graces the inside back cover

  10. Nuclear Wastes: Technologies for Separations and Transmutation

    National Research Council Canada - National Science Library

    .... The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted...

  11. Hanford radiochemical site decommissioning demonstration program

    International Nuclear Information System (INIS)

    Nelson, D.C.

    1971-01-01

    A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given

  12. Radiochemical separation and ICP-AES determination of some common metallic elements in ThO2 matrix

    International Nuclear Information System (INIS)

    Adya, V.C.; Hon, N.S.; Bangia, T.R.; Sastry, M.D.; Iyer, R.H.

    1997-01-01

    Radioactive tracer and also ICP-AES studies have been carried out to determine Al, Cd, Ca, Cr, Co, Cu, Mn, Mo and Pd in ThO 2 matrix after chemical separation. Di-2-ethyl-hexyl phosphoric acid/xylene/HNO 3 extraction system was used for quantitative separation of thorium. The recovery of elements as determined by tracers and ICP-AES was found to be quantitative within experimental error. (author). 3 refs., 1 tab

  13. Obtention process of phosphorus 32 starting from commercial sulfur and design and construction of the radiochemical separation prototype; Proceso de obtencion de fosforo-32 a partir de azufre comercial y diseno y construccion del prototipo de separacion radioquimica

    Energy Technology Data Exchange (ETDEWEB)

    Duarte A, C.; Alanis M, J.; Gutierrez R, C. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    In this work an obtention process of phosphorus 32 ({sup 32} P) in orthophosphoric acid form (H{sub 3}{sup 32}PO{sub 4}) is described starting from commercial sulfur. Also the design and construction of the experimental prototype used in the radiochemical separation and their results in three tests carried out is reported. (Author)

  14. Radiochemical studies in chemical separation and spectrographic determination of rare earths in thorium oxide matrix (Preprint No. RA.06)

    International Nuclear Information System (INIS)

    Adya, V.C.; Dhawale, B.A.; Rajeshwari, B.; Bangia, T.R.; Sastry, M.D.

    1989-01-01

    A chemical separation procedure was standardised for the separation of traces of rare earths from ThO 2 matrix using HDEHP (Di 2-ethyl hexyl phosphoric acid). The studies were carried out using both nitric acid and hydrochloric acid medium in different concentrations. The extraction studies were also carried out using radioactive isotopes of rare earths viz. 141 Ce, 152-154 Eu, 153 Gd, 170 Tm etc. The extraction was effective in both media. In 0.1 M HDEHP/xylene and 3 M HNO 3 , Ce was partially extracted into organic phase. So HCl/xylene medium was chosen for extraction purposes. The recovery was confirmed by both gamma counting and emission spectropgraphic method. It was found to be quantitative within experimental error. The separation procedure development here was used for determination of rare earths in thorium oxide matrix by emission spectrographic method. (author)

  15. Comparison of the radiochemical separation procedures od plutonium applied for its determination in the environmental samples using alpha spectrometry

    International Nuclear Information System (INIS)

    Komosa, A.; Michalik, S.

    2006-01-01

    Alpha spectrometry of the plutonium isotopes can be performed only after the perfect plutonium separation from other components of the matrix. So, till now numerous procedures have been elaborated and tested. The communication presents comparison of the plutonium content determination in soil, bones, eggshells and in the reference materials obtained by alpha spectrometry combined with two different separation procedures. The samples were mineralized in the concentrated HCl or HF prior to plutonium electrodeposition or coprecipitation with NdF 3 . Some other details were also tested in various variants. Quality of the spectra is discussed in terms of all these pre-treatment methods

  16. A radiochemical separation of spallogenic 88Zr in the carrier-free state for radioisotopic photoneutron sources

    International Nuclear Information System (INIS)

    Whipple, R.E.; Grant, P.M.; Daniels, R.J.; Daniels, W.R.; O'Brien, H.A.Jr.

    1976-01-01

    As the precursor of its 88 Y daughter, 88 Zr could be advantageously included in the active component of the 88 Y-Be photoneutron source for several reasons. The spallation of Mo targets with medium-energy protons at LAMPF procedure has been developed to separate radiozirconium from the target material and various spallogenic impurities. 88 Zr can consequently be obtained carrier-free and in quantitative yield. (author)

  17. Development of radiochemical property analysis and handling technology of long-lived radionuclide

    International Nuclear Information System (INIS)

    Park, Jin Ho; Choung, W. M.; Lee, K. I.; Woo, M. S.; Hwang, D. S.; Kim, Y. K.; Choi, Y. D.; Jung, K. C.; Kim, B. H.; Jung, J. Y.

    1997-08-01

    The goals of this research are completion of detail design of wet type lead cell for radioactive test of partitioning process, and possession of technologies to operate and handle safely process equipments in hot cells. The main contents in this research are as follows: 1) For analysis of radiolysis property of extractants in high level radioactive atmosphere, three extractants (DEHPA, DIDPA, TBP) were irradiated, and degradation phenomena was investigated. 2) For development of radioactive analysis technologies of sample solution, property tests of ion chromatography (NovaPac C-18) and activity measuring tests of Cs-137 with collimator, and design/application tests of collimator were performed. 3) Wet type lead cells (α-γ cell, 2 sets) and auxiliary facilities were designed, and tong manipulator and special tools were designed and fabricated, performed test operation. 4) For getting of MA fuel basic data, a review on process technologies for MA fuel production was performed. (author). 55 refs., 10 tabs., 46 figs

  18. Separation science and technology: an ORNL perspective

    International Nuclear Information System (INIS)

    Pruett, D.J.

    1986-05-01

    This report was prepared as a summary of a fourfold effort: (1) to examine schemes for defining and categorizing the field of separation science and technology; (2) to review several of the major categories of separation techniques in order to determine the most recent developments and future research needs; (3) to consider selected problems and programs that require advances in separation science and technology as a part of their solution; and (4) to propose suggestions for new directions in separation research at Oak Ridge National Laboratory (ORNL)

  19. Separation of plutonium on the anion exchanger BIO-RAD 1-X2 and its application to radiochemical analysis

    Energy Technology Data Exchange (ETDEWEB)

    Bajo, S.; Gann, C.; Eikenberg, J.; Wyer, L.; Beer, H.; Ruethi, M.; Jaeggi, M.; Zumsteg, I

    2007-12-15

    The element Pu (Z = 94) is a member of the actinide series of the elements (Z = 89 -103). The actinides have similar chemical properties and are also similar to the lanthanides (Z = 57 -71). Sixteen isotopes of Pu have been synthesized, all of which are radioactive. The Pu present in the environment originates from the atmospheric nuclear tests from 1950 to 1963, which produced the so-called 'global fallout'. As a result, 6.5 {center_dot} 10{sup 15} Bq {sup 239}Pu (2.8 tons), 4.4 {center_dot} 10{sup 15} Bq {sup 240}Pu (0.52 tons), and 3.7 {center_dot} 10{sup 4} Bq {sup 241}Pu (0.04 tons) were dispersed over the world. A contribution also to the global fallout was the ignition of the satellite SWAP 9A in the atmosphere in 1964, equipped with a battery powered by 6.3 {center_dot} 10{sup 14} Bq (1 kg) of {sup 238}Pu. In addition to these sources, nuclear reactors, reprocessing plants and radioactive waste facilities may contribute with their emissions to increase locally the Pu concentration in their environment. In the PSI laboratory, we are confronted with the determination of traces of {sup 238}Pu, {sup 239}Pu and {sup 240}Pu in environmental and biological materials. Because of the low quantity of Pu in the analyzed samples, which is usually below 100 mBq, it is mandatory to separate the Pu from all other accompanying elements. The separated Pu is then measured by alpha spectrometry. In this work, the anion exchanger BIO-RAD AG 1 is extensively used for the separation of Pu from different matrices. This exchanger is superior when only Pu is determined in the sample. In addition, it is also very suitable when other actinides, such as Am and Cm, are also determined. No preconcentration step is necessary for the Pu separation. The resins introduced by the company Eichrom Industries in the 90's, which allow the separation of the actinides from the major environmental elements and from each other, requires relatively small volumes of sample solution

  20. Separation of plutonium on the anion exchanger BIO-RAD 1-X2 and its application to radiochemical analysis

    International Nuclear Information System (INIS)

    Bajo, S.; Gann, C.; Eikenberg, J.; Wyer, L.; Beer, H.; Ruethi, M.; Jaeggi, M.; Zumsteg, I.

    2007-12-01

    The element Pu (Z = 94) is a member of the actinide series of the elements (Z = 89 -103). The actinides have similar chemical properties and are also similar to the lanthanides (Z = 57 -71). Sixteen isotopes of Pu have been synthesized, all of which are radioactive. The Pu present in the environment originates from the atmospheric nuclear tests from 1950 to 1963, which produced the so-called 'global fallout'. As a result, 6.5 · 10 15 Bq 239 Pu (2.8 tons), 4.4 · 10 15 Bq 240 Pu (0.52 tons), and 3.7 · 10 4 Bq 241 Pu (0.04 tons) were dispersed over the world. A contribution also to the global fallout was the ignition of the satellite SWAP 9A in the atmosphere in 1964, equipped with a battery powered by 6.3 · 10 14 Bq (1 kg) of 238 Pu. In addition to these sources, nuclear reactors, reprocessing plants and radioactive waste facilities may contribute with their emissions to increase locally the Pu concentration in their environment. In the PSI laboratory, we are confronted with the determination of traces of 238 Pu, 239 Pu and 240 Pu in environmental and biological materials. Because of the low quantity of Pu in the analyzed samples, which is usually below 100 mBq, it is mandatory to separate the Pu from all other accompanying elements. The separated Pu is then measured by alpha spectrometry. In this work, the anion exchanger BIO-RAD AG 1 is extensively used for the separation of Pu from different matrices. This exchanger is superior when only Pu is determined in the sample. In addition, it is also very suitable when other actinides, such as Am and Cm, are also determined. No preconcentration step is necessary for the Pu separation. The resins introduced by the company Eichrom Industries in the 90's, which allow the separation of the actinides from the major environmental elements and from each other, requires relatively small volumes of sample solution. This report describes the extensive utilization of the classical anion exchanger BIO-RAD 1-X2 in 8 molar nitric

  1. Determination of 63Ni and 55Fe in nuclear waste samples using radiochemical separation and liquid scintillation counting

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Frøsig Østergaard, L.; Nielsen, S.P.

    2005-01-01

    An analytical method for the determination of Ni-63 and Fe-55 in nuclear waste samples such as graphite, heavy concrete, aluminium and lead was developed. Different decomposition methods (i.e. ashing, acid digestion and alkali fusion) were investigated for the decomposition of the samples...... by extraction chromatography. The purified Ni-63 and Fe-55 was then measured by liquid scintillation counting. The chemical yields of the separation procedures for Fe-55 and Ni-63 are above 90% and the decontamination factors for all interfering radionuclides are more than 10(5). The detection limits...

  2. Cesium and Strontium Separation Technologies Literature Review

    Energy Technology Data Exchange (ETDEWEB)

    T. A. Todd; T. A. Todd; J. D. Law; R. S. Herbst

    2004-03-01

    Integral to the Advanced Fuel Cycle Initiative (AFCI) Program’s proposed closed nuclear fuel cycle, the fission products cesium and strontium in the dissolved spent nuclear fuel stream are to be separated and managed separately. A comprehensive literature survey is presented to identify cesium and strontium separation technologies that have the highest potential and to focus research and development efforts on these technologies. Removal of these high-heat-emitting fission products reduces the radiation fields in subsequent fuel cycle reprocessing streams and provides a significant short-term (100 yr) heat source reduction in the repository. This, along with separation of actinides, may provide a substantial future improvement in the amount of fuel that could be stored in a geologic repository. The survey and review of the candidate cesium and strontium separation technologies are presented herein. Because the AFCI program intends to manage cesium and strontium together, technologies that simultaneously separate both elements are of the greatest interest, relative to technologies that separate only one of the two elements.

  3. 13th Radiochemical Conference. Booklet of Abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors` abstracts. (P.A.)

  4. 13th Radiochemical Conference. Booklet of Abstracts

    International Nuclear Information System (INIS)

    1998-04-01

    The Conference included the following sessions: (i) Opening plenary presentations (6 contributions); (ii) Chemistry of natural radionuclides, discovery of radium and polonium (6 verbal presentations + 5 poster presentations); (iii) Radionuclides in the environment, radioecology (29 + 48); (iv) Activation analysis and other radioanalytical methods (36 + 49); (v) Ionizing radiation in science and technology (12 + 12); (vi) Chemistry of actinide and trans-actinide elements (11 + 14); (vii) Separation methods, speciation (18 + 41); (viii) Production and application of radionuclides (14 + 29); and (ix) Radiochemical problems in nuclear waste management (12 + 22). The majority of verbal presentations has been input to INIS, mostly in the form of the full authors' abstracts. (P.A.)

  5. Zirconium-titanium-phosphate nanoparticles. Triton X-100 based size modification, characterization and application in radiochemical separation

    Energy Technology Data Exchange (ETDEWEB)

    Chakraborty, R.; Sen, B.; Chattopadhyay, P. [Burdwan Univ. (India). Dept. of Chemistry

    2014-07-01

    Zirconium-titanium-phosphate nanoparticles (ZTP) of different sizes were synthesized using tritron X-100 (polyethylene glycol-p-isooctylphenyl ether) surfactant. The materials were characterized by FTIR and powdered X-ray diffraction (XRD). The structural and morphological details of the material were obtained by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). The SEM study was followed by energy dispersive spectroscopic analysis (EDS) for elemental analysis of the sample. The important peaks of the XRD spectra were analyzed to determine the probable composition of the material. The particle sizes were determined by dynamic light scattering (DLS) method. Ion exchange capacity was measured for different metal ions with sizes of the ZTP nanoparticles and size-dependent ion exchange property of the material was investigated thoroughly. The nanomaterial of the smallest size of around 5 nm was employed to separate carrier-free {sup 137m}Ba from {sup 137}Cs in column chromatographic technique using 1.0 M HNO{sub 3} as eluting agent at pH = 5. (orig.)

  6. 11th radiochemical conference

    International Nuclear Information System (INIS)

    Prasil, Z.

    1987-01-01

    The conference met in four sesions which discussed: Separation methods, Radioanalytical methods, Labelled compounds and Miscellaneous. The first session discussed extraction methods, ion exchange and chromatographic separation of radioisotopes. The second session heard papers on the application of these methods, e.g., in geochemistry, on the use of radioactive tracers in radiochemical analysis and the use of activation analysis in the determination of trace elements. The third session heard papers on the preparation of labelled organic compounds with isotopes 3 H, 14 C, radioiodine and 32 P, on the preparation of RIA kits and on the chemistry and radiopharmacology of technetium compounds. The other contributions which could not be heard in any of the three sessions discussed, e.g., the preparation of elements on the cyclotron and microtron, the production of a new 99m Tc-generator, the participation of the IAEA in processing low- and medium-level radioactive wastes, etc. (E.S.)

  7. Ga2O for target, solvent extraction for radiochemical separation and SnO2 for the preparation of a 68Ge/68Ga generator

    International Nuclear Information System (INIS)

    Aardaneh, K.; Walt, T.N. van der

    2006-01-01

    The target for the production of 68 Ge consists of a disc of gallium suboxide, Ga 2 O, with a 19 mm diameter. The suboxide was primarily prepared by repeatedly mixing metallic Ga and Ga 2 O 3 at 700 deg C. The target (2.4 g) was quite stable under a long-time irradiation with a 34 MeV proton beam at a current of ∼80 μA. The dissolution of the target was performed using 12M sulphuric acid solution, assisted with the dropwise addition of 30% H 2 O 2 solution, and took less than 4 hours. A solvent extraction method, using a 9M H 2 SO 4 - 0.3M HCl/CCl 4 system, was employed for the radiochemical separation of 68 Ge from Ga and Zn radionuclides, while 0.05M HCl was used for the back extraction of 68 Ge from the organic phase. The 68 Ge obtained in the dilute HCl was directly loaded onto a column containing either a hydrous tin dioxide or a crystalline tin dioxide, obtained by calcinations of the hydrous oxide at 450, 700, and 900 deg C. The calcinated hydrous tin dioxide at 900 deg C showed the highest crystallinity and highest 68 Ga elution yield and was selected for use in the generator. The 68 Ga elution from the column generator packed with 2 g of tin dioxide, using 3 ml of 1M HCl, and yielded an average of 65%. The breakthrough of 68 Ge was 6.1 x 10 -4 %. (author)

  8. Dry separation technology of transuranic elements

    International Nuclear Information System (INIS)

    Inoue, Tadashi

    1999-01-01

    The separation principle of transuranic elements (TRU) by a dry method, the separation technique of TRU from a high level waste solution and a dry recycle technology of LWR and FBR fuel cycle are explained. The dry method used molten salt and liquid metal. TRU and the rare earth elements in the molten salt (LiCl-KCl, LiCl-KCl/Cd and LiCl-KCl/Bi system) were separated by two methods such as the electrolytic refining and the reduction-extraction method. The former method separated 98% U, Np and Pu, but low Am. The latter method was able to separate more than 99.9% Np and Pu and 99.7% Am. (S.Y.)

  9. Development of a purification technology for treatment of medium- and low-activity radioactive waste of radiochemical production from Co-60 and Cs-137

    Directory of Open Access Journals (Sweden)

    Apalkov Gleb

    2016-01-01

    Full Text Available The technological flowchart of purification of medium- and low-activity waste from Co-60 and Cs-137 is developed and introduced. The developed purification scheme has been successfully tested using genuine medium- and low-level liquid radioactive waste of radiochemical production containing complexing and colloid forming components complexons, surfactants. The optimal conditions of the presented method of purification ensure reduction of the residual specific activity of 60Co and 137Cs radionuclides in the solution to less than 0,9 Bq per litre.

  10. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2005-11-04

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  11. Crosscutting Technology Development at the Center for Advanced Separation Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2006-09-30

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  12. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2006-05-15

    This Technical Progress Report describes progress made on the twenty nine subprojects awarded in the second year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  13. Separations Technology for Clean Water and Energy

    Energy Technology Data Exchange (ETDEWEB)

    Jarvinen, Gordon D [Los Alamos National Laboratory

    2012-06-22

    Providing clean water and energy for about nine billion people on the earth by midcentury is a daunting challenge. Major investments in efficiency of energy and water use and deployment of all economical energy sources will be needed. Separations technology has an important role to play in producing both clean energy and water. Some examples are carbon dioxide capture and sequestration from fossil energy power plants and advanced nuclear fuel cycle scemes. Membrane separations systems are under development to improve the economics of carbon capture that would be required at a huge scale. For nuclear fuel cycles, only the PUREX liquid-liquid extraction process has been deployed on a large scale to recover uranium and plutonium from used fuel. Most current R and D on separations technology for used nuclear fuel focuses on ehhancements to a PUREX-type plant to recover the minor actinides (neptunium, americiu, and curium) and more efficiently disposition the fission products. Are there more efficient routes to recycle the actinides on the horizon? Some new approaches and barriers to development will be briefly reviewed.

  14. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Hugh W. Rimmer

    2004-05-12

    This Technical Progress Report describes progress made on the seventeen subprojects awarded in the first year of Cooperative Agreement DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices. Due to the time taken up by the solicitation/selection process, these cover the initial 6-month period of project activity only. The U.S. is the largest producer of mining products in the world. In 1999, U.S. mining operations produced $66.7 billion worth of raw materials that contributed a total of $533 billion to the nation's wealth. Despite these contributions, the mining industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Originally set up by Virginia Tech and West Virginia University, this endeavor has been expanded into a seven-university consortium--Virginia Tech, West Virginia University, University of Kentucky, University of Utah, Montana Tech, New Mexico Tech and University of Nevada, Reno--that is supported through U.S. DOE Cooperative Agreement No. DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. Much of the research to be conducted with Cooperative Agreement funds will be longer-term, high-risk, basic research and will be carried out in five broad areas: (1) Solid-solid separation (2) Solid-liquid separation (3) Chemical/Biological Extraction (4) Modeling and Control, and (5) Environmental Control.

  15. CROSSCUTTING TECHNOLOGY DEVELOPMENT AT THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2005-01-20

    The U.S. is the largest producer of mining products in the world. In 2003, U.S. mining operations produced $57 billion worth of raw materials that contributed a total of $564 billion to the nation's wealth. Despite these contributions, the mining industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Much of the research to be conducted with Cooperative Agreement funds will be longer-term, high-risk, basic research and will be carried out in five broad areas: (1) Solid-solid separation; (2) Solid-liquid separation; (3) Chemical/Biological Extraction; (4) Modeling and Control; and (5) Environmental Control.

  16. CENTER FOR ADVANCED SEPARATION TECHNOLOGY (CAST) PROGRAM

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Roe-Hoan; Hull, Christopher

    2014-09-30

    The U.S. is the largest producer of mining products in the world. In 2011, U.S. mining operations contributed a total of $232 billion to the nation’s GDP plus $138 billion in labor income. Of this the coal mining industry contributed a total of $97.5 billion to GDP plus $53 billion in labor income. Despite these contributions, the industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations.

  17. Radiochemical Processing Laboratory (RPL)

    Data.gov (United States)

    Federal Laboratory Consortium — The Radiochemical Processing Laboratory (RPL)�is a scientific facility funded by DOE to create and implement innovative processes for environmental clean-up and...

  18. Radiochemical procedures and techniques

    International Nuclear Information System (INIS)

    Flynn, K.

    1975-04-01

    A summary is presented of the radiochemical procedures and techniques currently in use by the Chemistry Division Nuclear Chemistry Group at Argonne National Laboratory for the analysis of radioactive samples. (U.S.)

  19. Crosscutting Technology Development at the Center for Advanced Separation Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Christopher Hull

    2009-10-31

    The U.S. is the largest producer of mining products in the world. In 2003, U.S. mining operations produced $57 billion worth of raw materials that contributed a total of $564 billion to the nation's wealth. Despite these contributions, the mining industry has not been well supported with research and development funds as compared to mining industries in other countries. To overcome this problem, the Center for Advanced Separation Technologies (CAST) was established to develop technologies that can be used by the U.S. mining industry to create new products, reduce production costs, and meet environmental regulations. Originally set up by Virginia Tech and West Virginia University, this endeavor has been expanded into a seven-university consortium -- Virginia Tech, West Virginia University, University of Kentucky, University of Utah, Montana Tech, New Mexico Tech and University of Nevada, Reno - that is supported through U.S. DOE Cooperative Agreement No. DE-FC26-02NT41607: Crosscutting Technology Development at the Center for Advanced Separation Technologies. Much of the research to be conducted with Cooperative Agreement funds will be longer-term, high-risk, basic research and will be carried out in five broad areas: (1) Solid-solid separation; (2) Solid-liquid separation; (3) Chemical/biological extraction; (4) Modeling and control; and (5) Environmental control. Distribution of funds is handled via competitive solicitation of research proposals through Site Coordinators at the seven member universities. These were first reviewed and ranked by a group of technical reviewers (selected primarily from industry). Based on these reviews, and an assessment of overall program requirements, the CAST Technical Committee made an initial selection/ranking of proposals and forwarded these to the DOE/NETL Project Officer for final review and approval. The successful projects are listed by category, along with brief abstracts of their aims and objectives.

  20. Radiochemical analysis of phosphorus in milk samples

    International Nuclear Information System (INIS)

    Oliveira, R.M. de; Cunha, I.I.L.

    1991-01-01

    The determination of phosphorus in milk samples by thermal neutron activation analysis employing radiochemical separation is described. The radiochemical separation consists of the simultaneous irradiation of samples and standards, dissolution of the milk samples in a perchloric acid and nitric acid mixture, addition of zinc hold-back carrier, precipitation of phosphorus as ammonium phospho molybdate (A.M.P.) and sample counting in a Geiger-Mueller detector. The analysis sources of error were studied and the established method was applied to phosphorus analyses in commercial milk samples. (author)

  1. Innovative developments in uranium separation and concentration technology abroad

    International Nuclear Information System (INIS)

    Liang Jinlong; Zhou Mingsheng; Fang Wei; Sun Yuxiang

    2014-01-01

    Significance of deeply study the innovative developments in Uranium separation and concentration technology abroad was discussed. Development history and innovativeness of eight species of key equipments for separation and concentration were summarized for the first time. Principle and application of seven Uranium separation and concentration technology were analyzed systematically. It is expounded in the paper that high parameter, intelligent and low carbon were three development trends of Uranium separation and concentration technology. (authors)

  2. Sixth symposium on separation science and technology for energy applications

    International Nuclear Information System (INIS)

    Bell, J.T.; Watson, J.S.

    1990-01-01

    This meeting contained sessions on: membranes: liquid-phase and low-temperature gas-phase separations; separations in hazardous waste management; solvent extraction; membranes: high-temperature gas-phase separations; adsorption and chromatography; and novel separations in nuclear and isotope technologies

  3. Factors influencing adoption of manure separation technology in the Netherlands

    NARCIS (Netherlands)

    Gebrezgabher, Solomie; Meuwissen, M.P.M.; Kruseman, G.; Lakner, D.; Oude Lansink, A.G.J.M.

    2015-01-01

    Manure separation technologies are essential for sustainable livestock operations in areas with high livestock density as these technologies result in better utilization of manure and reduced environmental impact. Technologies for manure separation have been well researched and are ready for use.

  4. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

    International Nuclear Information System (INIS)

    Strisovska, J.

    2013-01-01

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237 Np a 241 Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239 Np a 237 Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242 Pu and 239 Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239 Np was obtained by separation from the parent radionuclide 2 43 Am, which is in radioactive equilibrium to 239 Np. The average yield of chemical separation was 69,3% for 239 Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240 Pu (95,0 ± 3,5)% and 237 Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  5. Radiochemical separations of target-like reaction products from Au-, Pt-, and Th-targets after irradiation with GeV protons

    International Nuclear Information System (INIS)

    Szweryn, B.; Bruechle, W.; Schausten, B.; Schaedel, M.

    1988-08-01

    Chemical separation procedures for separations of reaction products after spallation reactions with 2.6 GeV protons and heavy element targets are presented. To determine independent cross sections of individual isotopes the elements Au, Pt, Ir, Os, Re, W, Ta, Hf, (Lu, Yb, Tm, Er), (Gd, Eu, Sm), were separated from gold targets, Pt, Ir, Os, W, Ta, Hf, (Lu, Yb, Tm, Er), (Gd, Eu, Sm) from a platinum target and Au, Tl from a thorium target. (orig.)

  6. Advantage of chromatographic resin over the conventional nitrate radiochemical separation for 89,90Sr in milk in case of radiological emergency

    International Nuclear Information System (INIS)

    Mehenderge, S.T.; Sudheendran, V.; Rao, D.D.; Hegde, A.G.

    2010-01-01

    The paper presents the comparative evaluation of both the methods. Sr-spec was used for analysing 24 milk powder samples and 15 milk powder samples were analysed using by conventional separation method in an IAEA method validation study

  7. Safety assessment for TA-48 radiochemical operations

    International Nuclear Information System (INIS)

    1994-08-01

    The purpose of this report is to document an assessment performed to evaluate the safety of the radiochemical operations conducted at the Los Alamos National Laboratory operations area designated as TA-48. This Safety Assessment for the TA-48 radiochemical operations was prepared to fulfill the requirements of US Department of Energy (DOE) Order 5481.1B, ''Safety Analysis and Review System.'' The area designated as TA-48 is operated by the Chemical Science and Technology (CST) Division and is involved with radiochemical operations associated with nuclear weapons testing, evaluation of samples collected from a variety of environmental sources, and nuclear medicine activities. This report documents a systematic evaluation of the hazards associated with the radiochemical operations that are conducted at TA-48. The accident analyses are limited to evaluation of the expected consequences associated with a few bounding accident scenarios that are selected as part of the hazard analysis. Section 2 of this report presents an executive summary and conclusions, Section 3 presents pertinent information concerning the TA-48 site and surrounding area, Section 4 presents a description of the TA-48 radiochemical operations, and Section 5 presents a description of the individual facilities. Section 6 of the report presents an evaluation of the hazards that are associated with the TA-48 operations and Section 7 presents a detailed analysis of selected accident scenarios

  8. Separation Technology - Making a difference in biorefineries

    NARCIS (Netherlands)

    Kiss, Anton Alexandru; Lange, Jean Paul; Schuur, Boelo; Brilman, Derk Willem Frederik; van der Ham, Aloysius G.J.; Kersten, Sascha R.A.

    2016-01-01

    In the quest for a sustainable bio-based economy, biorefineries play a central role as they involve the sustainable processing of biomass into marketable products and energy. This paper aims to provide a perspective on applications of separations that can make a great difference in biorefineries, by

  9. Membrane-based technologies for biogas separations.

    Science.gov (United States)

    Basu, Subhankar; Khan, Asim L; Cano-Odena, Angels; Liu, Chunqing; Vankelecom, Ivo F J

    2010-02-01

    Over the past two decades, membrane processes have gained a lot of attention for the separation of gases. They have been found to be very suitable for wide scale applications owing to their reasonable cost, good selectivity and easily engineered modules. This critical review primarily focuses on the various aspects of membrane processes related to the separation of biogas, more in specific CO(2) and H(2)S removal from CH(4) and H(2) streams. Considering the limitations of inorganic materials for membranes, the present review will only focus on work done with polymeric materials. An overview on the performance of commercial membranes and lab-made membranes highlighting the problems associated with their applications will be given first. The development studies carried out to enhance the performance of membranes for gas separation will be discussed in the subsequent section. This review has been broadly divided into three sections (i) performance of commercial polymeric membranes (ii) performance of lab-made polymeric membranes and (iii) performance of mixed matrix membranes (MMMs) for gas separations. It will include structural modifications at polymer level, polymer blending, as well as synthesis of mixed matrix membranes, for which addition of silane-coupling agents and selection of suitable fillers will receive special attention. Apart from an overview of the different membrane materials, the study will also highlight the effects of different operating conditions that eventually decide the performance and longevity of membrane applications in gas separations. The discussion will be largely restricted to the studies carried out on polyimide (PI), cellulose acetate (CA), polysulfone (PSf) and polydimethyl siloxane (PDMS) membranes, as these membrane materials have been most widely used for commercial applications. Finally, the most important strategies that would ensure new commercial applications will be discussed (156 references).

  10. Radiochemical solar neutrino experiments

    International Nuclear Information System (INIS)

    Rich, R.; Spiro, M.

    1993-01-01

    This review covers the three presently running radiochemical solar neutrino experiments, namely the Chlorine, SAGE, and GALLEX experiments. The focus of the review is on a discussion of statistical consistency checks of the available data. The chlorine radiochemical experiment is conceptually simple and shows no strong indication of any statistical anomalies. It still forms the basis of the solar neutrino problem. Each of the two gallium experiments show internal statistical consistency. SAGE's recent preliminary results are consistent with the published GALLEX results. If this convergence is confirmed by a more definitive analysis, this would suggest that the combined result of the two gallium experiments, SAGE and GALLEX, be used for comparisons with theoretical expectations. 5 refs., 15 figs

  11. Radiochemical Study on the Separation of Chromium-51 from the Irradiated Target by Using Commercial and/or Synthesized Ion Exchanger

    International Nuclear Information System (INIS)

    Aydia, M.I.M.M.

    2012-01-01

    This work involves the following steps:1- Preparation of Triton X-100 Cerium(IV) Phosphate (TX-100CeP) as a surface active ion exchanger or organometallic molecules. 2- Characterization of the TX-100CeP by different methods (i.e. IR, TGA/DTA X-ray diffraction, X-ray fluorescence and elemental analysis). 3- Development a method for separation and quantification of Cr(III) and Cr(VI) by using high pressure liquid chromatography (HPLC). 4- Separation of 51 Cr(III) from Cr(VI) in the target of K 2 CrO 4 on TX-100CeP and Permutit as a commercial ion exchanger. 5- Quality control on the separated 51 Cr(III).

  12. Evolution and applications of radiochemical procedures. From Marie Curie to Darleane Hoffman

    International Nuclear Information System (INIS)

    Contis, E. T.; Rengan, K.

    1996-01-01

    Marie Curie carried out the first radiochemical separations which eventually lead to the discovery of polonium and radium, two new elements. Nearly a century later Darleane Hoffman and her collaborators are devising new radiochemical separation procedures for studying the chemical properties of newly discovered transactinide elements. Safety requirements as well as changes necessitated by fast decaying radionuclides have transformed the nature of radiochemical separations. Further, applications in a wide variety of areas such as analysis of trace elements in food to radioimmunoassay have broadened the use of radiochemical separations. Examples of some early, historically important, radiochemical separations are described in this article. In addition, recent trends in the use of radiochemical separations in neutron activation analysis, in dating applications, in fission product studies and in the study of transactinide elements are briefly described with specific examples. (author). 52 refs

  13. Radiochemical Means of Investigating Delayed Neutron Precursors

    International Nuclear Information System (INIS)

    Marmol, P. del

    1968-01-01

    Fast radiochemical methods used now for the determination of delayed neutron precursors are classified and reviewed: precipitations, solvent extractions, range experiments, milking, gas sweeping, isotopic and ion exchange, hot atom reactions and diffusion loss. Advantages and limitations of irradiation systems with respect to fast separations are discussed: external beams which allow faster separations only have low neutron fluxes, internal beams which are mostly fit for gaseous reactions; and rabbits for solution irradiations. Future prospects of radiochemical procedures are presented; among these, studies should be mostly oriented towards gaseous reactions which offer possibilities of isolating very short-lived delayed neutron precursors. Chemical procedures for delayed neutron precursor detection are compared with mass spectrometric and isotope separator techniques; it is concluded that the methods are complementary. (author)

  14. Radiochemical Means of Investigating Delayed Neutron Precursors

    International Nuclear Information System (INIS)

    Marmol, P. del

    1968-01-01

    Fast radiochemical methods used now for the determination of delayed neutron precursors are classified and reviewed: precipitations, solvent extractions, range experiments, milking, gas sweeping, isotopic and ion exchange, hot-atom reactions and diffusion loss. Advantages and limitations of irradiation systems with respect to fast separations are discussed: external beams which allow faster separations only have low neutron fluxes, internal beams which are mostly fit for gaseous reactions; and rabbits for solution irradiations. Future prospects of radiochemical procedures are presented; among these, studies should be mostly oriented towards gaseous reactions which offer possibilities of isolating very short-lived delayed neutron precursors. Chemical procedures for delayed neutron precursor detection are compared with mass spectrometric and isotope-separator techniques; it is concluded that the methods are complementary. (author)

  15. Determination of plutonium isotopes (238Pu, 239Pu, 240Pu, 241Pu) in environmental samples using radiochemical separation combined with radiometric and mass spectrometric measurements.

    Science.gov (United States)

    Xu, Yihong; Qiao, Jixin; Hou, Xiaolin; Pan, Shaoming; Roos, Per

    2014-02-01

    This paper reports an analytical method for the determination of plutonium isotopes ((238)Pu, (239)Pu, (240)Pu, (241)Pu) in environmental samples using anion exchange chromatography in combination with extraction chromatography for chemical separation of Pu. Both radiometric methods (liquid scintillation counting and alpha spectrometry) and inductively coupled plasma mass spectrometry (ICP-MS) were applied for the measurement of plutonium isotopes. The decontamination factors for uranium were significantly improved up to 7.5 × 10(5) for 20 g soil compared to the level reported in the literature, this is critical for the measurement of plutonium isotopes using mass spectrometric technique. Although the chemical yield of Pu in the entire procedure is about 55%, the analytical results of IAEA soil 6 and IAEA-367 in this work are in a good agreement with the values reported in the literature or reference values, revealing that the developed method for plutonium determination in environmental samples is reliable. The measurement results of (239+240)Pu by alpha spectrometry agreed very well with the sum of (239)Pu and (240)Pu measured by ICP-MS. ICP-MS can not only measure (239)Pu and (240)Pu separately but also (241)Pu. However, it is impossible to measure (238)Pu using ICP-MS in environmental samples even a decontamination factor as high as 10(6) for uranium was obtained by chemical separation. © 2013 Elsevier B.V. All rights reserved.

  16. Isotopic exchange between 232Th and 234Th using ion exchange resins and its application for the radiochemical separation of thorium and europium

    International Nuclear Information System (INIS)

    Sepulveda Munita, C.J.A.; Atalla, L.T.

    1980-01-01

    The determination of thorium via the measurement of 233 Th activity (obtained by irradiating natural thorium with neutrons) may suffer the interference of various radioisotopes which may be also formed during irradiation, if their parent isotopes are present in the sample. Taking into account this possibility, another technique was chosen for the determination of thorium, based on isotopic exchange associated with ionic exchange. Conditions for the isotopic exchange between 234 Th in solution and 232 Th in the resin were optimized. It was verified that the behaviour of 233 Th and 234 Th is the same regarding isotopic exchange with 232 Th. 234 Th was chosen for the experiments since it has a longer half-life (24.1 days) than 233 Th (22.3 min), thus facilitating the performance of the work. As the major objective of this work is to separate thorium and europium isotopes, the behaviour of 152-154 Eu was studied in the same system used for thorium, envisaging a minimum retention of these radioisotopes in the resin. In order to establish the best conditions for separating 234-Th and 152/154-Eu, the following parameters were considered: the thorium concentration in the solution; the hydrochloric acid concentration in solution; the concentration of other elements in solution; the degree of cross-linking of the resin; the flow rate of the solution through the column. The other elements added to the elutant solution were: uranium, molybdenum, lanthanum, europium, ytterbium, bromine, cobalt, barium, manganese, indium, cesium and selenium. Europium was added so to dilute the 152/154-Eu tracer and avoid the retention of the latter in the resin. The other elements were added because they give rise to radioisotopes which interfere in the activation analysis of thorium when 233-Th activity is used and, the separation of these elements from thorium will also be subsequently studied by the method used in the present work. (C.L.B.) [pt

  17. Radiochemical analysis of military nuclear facilities

    International Nuclear Information System (INIS)

    Bayramov, A.A.; Bayramova, S.M.

    2012-01-01

    Full text : Radiochemical Analysis is a branch of analytical chemistry comprising an aggregate of methods for qualitatively determining the composition and content of radioisotopes in the products of transformations. Safety and minimization of radiation impact on human and environment are important demand of operation of Military Nuclear Facilities (MNF). In accordance of recommendations of International Commission on Radiological Protection there are next objects of radiochemical analysis: 1) potential sources of radiochemical pollution; 2) environment (objects of environment, human environment including buildings, agricultural production, water, air et al.); 3) human himself (determination of dose from external and internal radiation, chemical poisoning). The chemical analysis can be carried out using, for example, the Gas Chromatography instrument whish separates chemical mixtures and identifies the components at a molecular level. It is one of the most accurate tools for analyzing environmental samples. The Gas Chromatography works on the principle that a mixture will separate into individual substances when heated. The heated gases are carried through a column with an inert gas (such as helium). As the separated substances emerge from the column opening, they flow into the Mass Spectrometry. Mass spectrometry identifies compounds by the mass of the analyte molecule. Newly developed portable Gas Chromatography and Mass Spectrometry are techniques that can be used to separate volatile organic compounds and pesticides. Other uses of Gas Chromatography, combined with other separation and analytical techniques, have been developed for radionuclides, explosive compounds such as royal demolition explosive and trinitrotoluene, and metals. So, based on the many years experience of operation of dangerous MNF, in concordance with norms of radiation and chemical safety it was considered that the tasks of the radiochemical analysis of Military Nuclear Facilities include

  18. Radiochemical schemes of obtaining 89Sr and 90Y radionuclides

    International Nuclear Information System (INIS)

    Usarov, Z. O.

    2010-03-01

    Key words: strontium-89, yttrium-90, extraction and extraction-chromatographic purification of radionuclides, radiopharmaceuticals. Subjects of research: strontium-89 and yttrium-90 radionuclides and their chloride forms. Purpose of work is developing of radiochemical technologies on obtaining of 89 Sr and 90 Y on the WWR-SM reactor with high radionuclide purity. Methods of research: extraction and extraction-chromatographic methods of radionuclides separation, beta- and gamma-spectrometric methods of activity measuring. The results obtained and their novelty: Were determined the conformity to laws of Y and Sr distribution in two-phase systems TBP-HNO 3 , TBP-NH 4 NO 3 , TBP-HCI, HDEHP-NO 3 , HDEHP-NH 4 NO 3 and HDEHP-HCI. Were determined the conformity to laws of Y and Sr distribution in systems with craun ethers DB-18K-6 and DTBDB-18K-6 from water solutions of HNO 3 . Radiochemical technologies on obtaining of 89 Sr and 90 Y radionuclides including radiochemical process of yttrium target with using the systems TBP-HNO 3 and HDEHP/Teflone were developed. Practical value: the radiochemical technology of obtaining 89 Sr with high radionuclide purity was developed. The method of preparation a chloride compound of 89 SrCl 2 which is used as a drug form for preparation of 89 Sr- 'Metastron' was developed. The relatively simple method of on the way obtaining 90 Y in the reactor with high radionuclidic purity that is useful for follow using in medical practice was offered. Degree of embed and economic effectivity: the developed technologies have approbation in manufacturing conditions in Radiopreparat Enterprise of INP AS RU and were offered for receiving of domestic preparations against of import foreign analogues. The statement about using the invention by obtained patent is attached to dissertation. Field of application: the received results will be introduced in manufacture at Radiopreparat Enterprise of INP AS RU for receiving of domestic preparations

  19. Radiochemicals in biomedical research

    International Nuclear Information System (INIS)

    Evans, E.A.; Oldham, K.G.

    1988-01-01

    This volume describes the role of radiochemicals in biomedical research, as tracers in the development of new drugs, their interaction and function with receptor proteins, with the kinetics of binding of hormone - receptor interactions, and their use in cancer research and clinical oncology. The book also aims to identify future trends in this research, the main objective of which is to provide information leading to improvements in the quality of life, and to give readers a basic understanding of the development of new drugs, how they function in relation to receptor proteins and lead to a better understanding of the diagnosis and treatment of cancers. (author)

  20. Ceramic membrane technologies for gas separation

    International Nuclear Information System (INIS)

    Badwal, S.P.S.; Ciacchi, F.T.

    2000-01-01

    Solid state electrochemical cells based on oxygen-ion or proton conduction (pure ionic or mixed ionic/electronic conductors) allow selective transport of oxygen (oxygen-ion conducting materials) or hydrogen (for proton conducting materials) in the form of ionic flux at high temperatures. Thus these systems can act as filters for molecular oxygen or hydrogen and can be used for both generation or removal of these gases selectively. The usage of such devices are numerous including control of atmosphere in industrial environments to production of power and chemicals, in petroleum and medical industries, and in combustion processes. In this paper, a brief overview of the technology has been given and various doped materials for construction of such devices, such as zirconia, ceria, bismuth oxides or lanthanum gallates have been briefly reviewed. Copyright (2000) The Australian Ceramic Society

  1. Environmental Consequences of Future Biogas Technologies based on Separated Slurry

    DEFF Research Database (Denmark)

    Hamelin, Lorie; Wesnæs, Marianne; Wenzel, Henrik

    2011-01-01

    different slurry separation technologies have been assessed and compared to a business-as-usual reference slurry management scenario. The results show that the environmental benefits of such biogas production are highly dependent upon the efficiency of the separation technology used to concentrate......This consequential life cycle assessment study highlights the key environmental aspects of producing biogas from separated pig and cow slurry, a relatively new but probable scenario for future biogas production, as it avoids the reliance on constrained carbon cosubstrates. Three scenarios involving...... the volatile solids in the solid fraction. The biogas scenario involving the most efficient separation technology resulted in a dry matter separation efficiency of 87% and allowed a net reduction of the global warming potential of 40%, compared to the reference slurry management. This figure comprises...

  2. Collected radiochemical and geochemical procedures

    Energy Technology Data Exchange (ETDEWEB)

    Kleinberg, J [comp.

    1990-05-01

    This revision of LA-1721, 4th Ed., Collected Radiochemical Procedures, reflects the activities of two groups in the Isotope and Nuclear Chemistry Division of the Los Alamos National Laboratory: INC-11, Nuclear and radiochemistry; and INC-7, Isotope Geochemistry. The procedures fall into five categories: I. Separation of Radionuclides from Uranium, Fission-Product Solutions, and Nuclear Debris; II. Separation of Products from Irradiated Targets; III. Preparation of Samples for Mass Spectrometric Analysis; IV. Dissolution Procedures; and V. Geochemical Procedures. With one exception, the first category of procedures is ordered by the positions of the elements in the Periodic Table, with separate parts on the Representative Elements (the A groups); the d-Transition Elements (the B groups and the Transition Triads); and the Lanthanides (Rare Earths) and Actinides (the 4f- and 5f-Transition Elements). The members of Group IIIB-- scandium, yttrium, and lanthanum--are included with the lanthanides, elements they resemble closely in chemistry and with which they occur in nature. The procedures dealing with the isolation of products from irradiated targets are arranged by target element.

  3. Radiochemical studies of some preparation methods for phosphorus

    International Nuclear Information System (INIS)

    Loos-Neskovic, C.; Fedoroff, M.

    1983-01-01

    Various methods of radiochemical separation were tested for the determination of phosphorus in metals and alloys by neutron activation analysis. Classical methods of separation revealed some defects when they were applied to this problem. Methods using liquid extraction gave low yields and were not reproducible. Methods based on precipitation gave better results, but were not selective enough in most cases. Retention on alumina was not possible without preliminary separations. Authors studied a new radiochemical separation based on the extraction of elemental phosphorus in the gaseous phase after reduction at high temperature with carbon. Measurements with radioactive phosphorus showed that the extraction yield is better than 99%. (author)

  4. Radiochemical analysis of chlorine-36

    International Nuclear Information System (INIS)

    Rodriguez, M.; Pina, G.; Lara, E.

    2006-01-01

    The radioactive chlorine isotope, 36 Cl, decays with a half-life of 3x10 5 years by emitting a beta particle (98 %) and by electron capture. The aim of this paper is to propose a radiochemical separation method of 36 Cl from the other beta-gamma emitters present in low and medium radioactive wastes such as spent ion exchange resins and evaporator concentrates, that arise from Nuclear Power Plants and particularly in the wastes that come from decommissioning activities of graphite reactors, in order to provide data for 36 Cl inventory calculations. The separation method proposed is based on an oxidation technique where chlorine is trapped by NaOH. 36 Cl beta emissions are measured by liquid scintillation counting by the dual label technique in order to avoid the contamination produced by 14 C which is also trapped by NaOH and which is the main contaminant present in graphite samples. The sensitivity of this method is sufficient to achieve the needed thresholds for the radiological characterization of the radioactive materials to which this method can be applied. (author)

  5. Radiochemical synthesis of etomoxir

    Energy Technology Data Exchange (ETDEWEB)

    Abbas, Hafiz G. [Institute of Nuclear Medicine and Oncology (INMOL), New Campus Road, Lahore (Pakistan); Yunus, M. [University of the Punjab, New Campus Road, Lahore (Pakistan); Feinendegen, Ludwig E., E-mail: feinendegen@gmx.ne [Department of Nuclear Medicine, Heinrich-Heine University Duesseldorf, Wannental 45, 88131 Lindau (Germany)

    2011-02-15

    Sodium 2-{l_brace}6-(4-chlorophenoxy)hexyl{r_brace}oxirane-2-carboxylate (Etomoxir) inhibits transport of fatty acids via the carnitine shuttle into mitochondria of muscle cells and prevents long chain fatty acids from providing energy through {beta}-oxidation especially for muscle contraction. The objective of this synthesis is to develop a method for radioiodination of Etomoxir in order to explore its potential in diagnostic metabolic studies and molecular imaging. Thus, a method is described for the radiochemical synthesis and purification of ethyl 2-{l_brace}6-(4-[{sup 131}I]iodophenoxy)hexyl{r_brace}oxirane-2-carboxylate (3) and 2-{l_brace}6-(4-[{sup 131}I]iodo-phenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (4). For the synthesis of these new agents, ethyl 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylate (1) and 2-{l_brace}6-(4-bromophenoxy)hexyl{r_brace}oxirane-2-carboxylic acid (2) were refluxed with [{sup 131}I]NaI in the presence of anhydrous acetone at a temperature of 80 {sup o}C and 90 {sup o}C for a period of 3-4 hours, respectively. The method of radiolabeling, based on the nucleophilic exchange reaction, resulted in a radiochemical yield of 43% and 67% for compounds 3 and 4, respectively. This paper reports on the labeling of etomoxir with radioiodine as {sup 124}I labeled etomoxir may be of great importance in molecular imaging.

  6. Evaluation of Mars CO2 Capture and Gas Separation Technologies

    Science.gov (United States)

    Muscatello, Anthony C.; Santiago-Maldonado, Edgardo; Gibson, Tracy; Devor, Robert; Captain, James

    2011-01-01

    Recent national policy statements have established that the ultimate destination of NASA's human exploration program is Mars. In Situ Resource Utilization (ISRU) is a key technology required to ,enable such missions and it is appropriate to review progress in this area and continue to advance the systems required to produce rocket propellant, oxygen, and other consumables on Mars using the carbon dioxide atmosphere and other potential resources. The Mars Atmospheric Capture and Gas separation project is selecting, developing, and demonstrating techniques to capture and purify Martian atmospheric gases for their utilization for the production of hydrocarbons, oxygen, and water in ISRU systems. Trace gases will be required to be separated from Martian atmospheric gases to provide pure CO2 to processing elements. In addition, other Martian gases, such as nitrogen and argon, occur in concentrations high enough to be useful as buffer gas and should be captured as well. To achieve these goals, highly efficient gas separation processes will be required. These gas separation techniques are also required across various areas within the ISRU project to support various consumable production processes. The development of innovative gas separation techniques will evaluate the current state-of-the-art for the gas separation required, with the objective to demonstrate and develop light-weight, low-power methods for gas separation. Gas separation requirements include, but are not limited to the selective separation of: (1) methane and water from unreacted carbon oxides (C02-CO) and hydrogen typical of a Sabatier-type process, (2) carbon oxides and water from unreacted hydrogen from a Reverse Water-Gas Shift process, (3)/carbon oxides from oxygen from a trash/waste processing reaction, and (4) helium from hydrogen or oxygen from a propellant scavenging process. Potential technologies for the separations include' freezers, selective membranes, selective solvents, polymeric sorbents

  7. X-RAYS SEPARATOR: FORWARD STEP IN TECHNOLOGY OF OPTICAL SEPARATION

    Directory of Open Access Journals (Sweden)

    N. N. Potrakhov

    2017-01-01

    Full Text Available Presently the X-ray separation is used not only for research program, but it is also elaborated and applied for different sectors of economy. The seeds as biological objects that possess the complicated microstructure are very difficult to be exanimated by x-ray technology. The application of x-rays and further elaboration of optical  separators, principle  of action, basic specifications, way of their use and their efficiency was shown in the article. The x-ray separator may distinguish all hidden seed defects as it was described by a programmer, where owing to the use of the optical separating block in visual range it is possible to add some more details as a shape, brightness and a color of object surface being exanimated. The elaboration of such separation equipment is scientifically hard work requiring time and expenses. Last year researchers of ‘LETI’ developed the working model of industrial x-ray separator for examination of grains and nuts in different crops. This model was made on the basis of photoseparator F-5 manufactured at OAO ‘Voronezhselmash’. The instrument state and its mechanism operation are highlighted on monitor. In the regime of processing (separation and examination of each controlled batch, the passport is produced with  following  information on identification  code,  time of material receiving, time of test passed, number of grains or seeds tested. The code of receiver of material is given to each of established characteristics when working the regime of separation, determination of number of objects with characteristics tested and number of unidentified objects. The application of x-ray separators constructed on the basis of photoseparator F-5 enables to carry out the complex estimation on seed quality and separation in only instrument with the development of electronic protocol with many characteristics.

  8. Environmental consequences of future biogas technologies based on separated slurry.

    Science.gov (United States)

    Hamelin, Lorie; Wesnæs, Marianne; Wenzel, Henrik; Petersen, Bjørn M

    2011-07-01

    This consequential life cycle assessment study highlights the key environmental aspects of producing biogas from separated pig and cow slurry, a relatively new but probable scenario for future biogas production, as it avoids the reliance on constrained carbon cosubstrates. Three scenarios involving different slurry separation technologies have been assessed and compared to a business-as-usual reference slurry management scenario. The results show that the environmental benefits of such biogas production are highly dependent upon the efficiency of the separation technology used to concentrate the volatile solids in the solid fraction. The biogas scenario involving the most efficient separation technology resulted in a dry matter separation efficiency of 87% and allowed a net reduction of the global warming potential of 40%, compared to the reference slurry management. This figure comprises the whole slurry life cycle, including the flows bypassing the biogas plant. This study includes soil carbon balances and a method for quantifying the changes in yield resulting from increased nitrogen availability as well as for quantifying mineral fertilizers displacement. Soil carbon balances showed that between 13 and 50% less carbon ends up in the soil pool with the different biogas alternatives, as opposed to the reference slurry management.

  9. Evaluation of radiochemical data usability

    International Nuclear Information System (INIS)

    Paar, J.G.; Porterfield, D.R.

    1997-04-01

    This procedure provides a framework for implementation of radiochemical data verification and validation for environmental remediation activities. It has been developed through participation of many individuals currently involved in analytical radiochemistry, radiochemical validation, and validation program development throughout the DOE complex. It should be regarded as a guidance to use in developing an implementable radiochemical validation strategy. This procedure provides specifications for developing and implementing a radiochemical validation methodology flexible enough to allow evaluation of data useability for project-specific Data Quality Objectives (DQO). Data produced by analytical methods for which this procedure provides limited guidance are classified as open-quotes non-routineclose quotes radionuclides and methods, and analyses by these methods may necessitate adoption of modified criteria from this procedure

  10. Rapid Radiochemical Methods for Asphalt Paving Material ...

    Science.gov (United States)

    Technical Brief Validated rapid radiochemical methods for alpha and beta emitters in solid matrices that are commonly encountered in urban environments were previously unavailable for public use by responding laboratories. A lack of tested rapid methods would delay the quick determination of contamination levels and the assessment of acceptable site-specific exposure levels. Of special concern are matrices with rough and porous surfaces, which allow the movement of radioactive material deep into the building material making it difficult to detect. This research focuses on methods that address preparation, radiochemical separation, and analysis of asphalt paving materials and asphalt roofing shingles. These matrices, common to outdoor environments, challenge the capability and capacity of very experienced radiochemistry laboratories. Generally, routine sample preparation and dissolution techniques produce liquid samples (representative of the original sample material) that can be processed using available radiochemical methods. The asphalt materials are especially difficult because they do not readily lend themselves to these routine sample preparation and dissolution techniques. The HSRP and ORIA coordinate radiological reference laboratory priorities and activities in conjunction with HSRP’s Partner Process. As part of the collaboration, the HSRP worked with ORIA to publish rapid radioanalytical methods for selected radionuclides in building material matrice

  11. RECENT PROGRESS OF OXYGEN/NITROGEN SEPARATION USING MEMBRANE TECHNOLOGY

    Directory of Open Access Journals (Sweden)

    K. C. CHONG

    2016-07-01

    Full Text Available The oxygen-enriched air is highly demanded for various industrial applications such as medical, chemical and enhanced combustion processes. The conventional oxygen/nitrogen production is either cryogenic distillation or pressure swing adsorption (PSA. Both of these techniques possess the production capability of 20 to 300 tonnes of oxygen per day and oxygen purity of more than 95%. However, these techniques are energy intensive. Alternatively, membrane technology is an emerging technology in gas separation as it requires low energy consumption and relatively moderate production volume, if compared to the conventional gas production techniques. These advantages have spurred much interest from industries and academics to speed up the commercial viability of the O2/N2 separation via membrane technology. In this review, the conventional and membrane technologies in O2/N2 separation, as well as recent development of membrane fabrication techniques and materials are reviewed. The latest membrane performance in O2/N2 separation is also tabulated and discussed.

  12. Separations technology development to support accelerator-driven transmutation concepts

    International Nuclear Information System (INIS)

    Venneri, F.; Arthur, E.; Bowman, C.

    1996-01-01

    This is the final report of a one-year Laboratory-Directed Research and Development (LDRD) Project at the Los Alamos National Laboratory (LANL). This project investigated separations technology development needed for accelerator-driven transmutation technology (ADTT) concepts, particularly those associated with plutonium disposition (accelerator-based conversion, ABC) and high-level radioactive waste transmutation (accelerator transmutation of waste, ATW). Specific focus areas included separations needed for preparation of feeds to ABC and ATW systems, for example from spent reactor fuel sources, those required within an ABC/ATW system for material recycle and recovery of key long-lived radionuclides for further transmutation, and those required for reuse and cleanup of molten fluoride salts. The project also featured beginning experimental development in areas associated with a small molten-salt test loop and exploratory centrifugal separations systems

  13. Tightening water quality regulations produces an innovative separation technology

    International Nuclear Information System (INIS)

    Welther, P.B.; Broussard, P.C.

    1994-01-01

    The impact of the recent proposed changes in the water quality standards for offshore producing platforms is having a far reaching effect on the oil and gas industry. At a time when oil companies are cutting back their work forces and reducing capital outlays in order to stay competitive in the market, water treatment equipment manufacturing companies are aggressively seeking innovative and cost effective solutions to meet the environmental requirements. Necessity drives advancements in technology, so Monosep Corporation has accepted the challenge to improve induced gas flotation technology and to develop enhanced gravity separation. This system of improved gas flotation and enhanced gravity separation can be used to consistently meet the proposed new guideline of an ''oil and grease'' maximum monthly average of 29 mg/l (milligrams per liter) in the discharged water from offshore platforms. The results demonstrated in the field suggest that adding enhanced gravity separation upstream of existing gas flotation units can improve performance sufficient to meet the Proposed stricter discharge limits. For platforms that do not have efficient gas flotation units, the old units can be replaced or modified to include the new features improved gas flotation technology like the Veirsep. For those few platforms are having difficulty meeting the current discharge requirements, both a new improved gas flotation unit, as well as a more sophisticated upstream gravity separator like the Cyclosep, may need to be installed. Chemical additives are sometimes a required necessity, but must be used sparingly due to the potential for creating soluble oil problems

  14. Radiochemical methods to enhance efficiency of α-spectral measurements

    International Nuclear Information System (INIS)

    Silkina, G.P.; Artem'ev, O.I.

    2001-01-01

    The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency.The paper describes possible ways to improve a plutonium radiochemical separation technique developed in the Khlopin Radium Institute and modify it to account for the site-specific features of samples from the former Semipalatinsk test site (STS) and enhance the alpha spectrometry efficiency. (author)

  15. Efficient Separations and Processing Crosscutting Program. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

    The Efficient Separations and Processing (ESP) Crosscutting Program was created in 1991 to identify, develop, and perfect separations technologies and processes to treat wastes and address environmental problems throughout the DOE Complex. The ESP funds several multi-year tasks that address high-priority waste remediation problems involving high-level, low-level, transuranic, hazardous, and mixed (radioactive and hazardous) wastes. The ESP supports applied research and development (R and D) leading to demonstration or use of these separations technologies by other organizations within DOE-EM. Treating essentially all DOE defense wastes requires separation methods that concentrate the contaminants and/or purify waste streams for release to the environment or for downgrading to a waste form less difficult and expensive to dispose of. Initially, ESP R and D efforts focused on treatment of high-level waste (HLW) from underground storage tanks (USTs) because of the potential for large reductions in disposal costs and hazards. As further separations needs emerge and as waste management and environmental restoration priorities change, the program has evolved to encompass the breadth of waste management and environmental remediation problems

  16. Development of O-18 stable isotope separation technology using membrane

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jae Woo; Kim, Taek Soo; Choi, Hwa Rim; Park, Sung Hee; Lee, Ki Tae; Chang, Dae Shik

    2006-06-15

    The ultimate goal of this investigation is to develop the separation technology for O-18 oxygen stable isotope used in a cyclotron as a target for production of radioisotope F-18. F-18 is a base material for synthesis of [F-18]FDG radio-pharmaceutical, which is one of the most important tumor diagnostic agent used in PET (Positron Emission Tomography). More specifically, this investigation is focused on three categories as follow, 1) development of the membrane distillation isotope separation process to re-enrich O-18 stable isotope whose isotopic concentration is reduced after used in a cyclotron, 2) development of organic impurity purification technology to remove acetone, methanol, ethanol, and acetonitrile contained in a used cyclotron O-18 enriched target water, and 3) development of a laser absorption spectroscopic system for analyzing oxygen isotopic concentration in water.

  17. Chemical technology of the systems, partitioning and separation, disposal

    International Nuclear Information System (INIS)

    Volk, V.I.

    1997-01-01

    A reactor-accelerator reprocessing complex is described. The complex comprises an electronuclear transmutation installation and chemical and technological support units for maintenance of the steady-state of the blanket, separation of short-lived transmutation products to be disposed of from other components of the blanket, chemical conversion to relevant stable species of products to be disposed of for interim storage and disposal

  18. ESTABLISHMENT OF THE CENTER FOR ADVANCED SEPARATION TECHNOLOGIES

    Energy Technology Data Exchange (ETDEWEB)

    Hugh W. Rimmer

    2003-07-01

    Technical Progress Report describes progress made on the eight sub-projects awarded in the first year of Cooperative Agreement DE-FC26-01NT41091: Establishment of the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices. Due to the time taken up by the solicitation/selection process, these cover the initial 6-month period of activity only.

  19. Establishment of the Center for Advanced Separation Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Christopher E. Hull

    2006-09-30

    This Final Technical Report covers the eight sub-projects awarded in the first year and the five projects awarded in the second year of Cooperative Agreement DE-FC26-01NT41091: Establishment of the Center for Advanced Separation Technologies. This work is summarized in the body of the main report: the individual sub-project Technical Progress Reports are attached as Appendices.

  20. The analytical of radiochemical purity of tumor receptor imaging agent 99Tcm-octreotide

    International Nuclear Information System (INIS)

    Wang Xufu; Zuo Shuyao; Shao Wenbo; Wang Guoming; Sun Jianwen; Zhang Qin

    2003-01-01

    The radiochemical purity of tumor receptor imaging agent 99 Tc m -octreotide is measured by High Pressure Liquid Chromatography (HPLC) and two systems of chromatography combining method of silver stain. The results show that the radiochemical purity of 98 Tc m -octreotide measured by both methods are effective and correct. It can separate 99 Tc m -octreotide from other radioactive compositions correctly and effectively

  1. Fifty years of radiochemical tracers

    International Nuclear Information System (INIS)

    Evans, E.A.

    1992-01-01

    During the past 50 years radiochemical tracers, usually in the form of isotopically labelled organic compounds, have been essential tools to further advance our knowledge at the frontiers of a great variety of scientific developments in the life sciences. This plenary lecture reviews necessarily selected highlights in the synthesis and applications of such radiochemical tracers. Included are examples where important advances, made possible by using radiochemicals, have contributed to improving the quality of life on this planet. The principal radioisotopes involved, 14 C, 3 H, 35 S, 32 P, 125 I, are all relatively safe to handle and are commercially available at maximum theoretical specific activity (carrier free). The compounds labeled with these radioisotopes are used in many fields of research which include biosynthesis and biotechnology studies, cell biology, drug metabolism, clinical research and environmental applications, and are briefly reviewed. (author). 55 refs

  2. Determination of thorium in native gold by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Liu, Y.; Kraehenbuehl, U.

    1995-01-01

    Thorium concentrations in 11 native gold samples from different sources, e.g. placer gold, vein and lode gold were determined. Thorium was determined by radiochemical separation and measurement of protactinium from irradiated native gold samples. The chemical yield of the separation procedures is 90%. Other elements were measured by gamma-ray spectroscopy. The radiochemical separation procedures described in this work make accurate determination of Th concentrations in native gold at picogram concentrations possible. (orig.)

  3. Investigating consumer attitudes towards the new technology of urine separation.

    Science.gov (United States)

    Pahl-Wostl, C; Schönborn, A; Willi, N; Muncke, J; Larsen, T A

    2003-01-01

    The technology of urine separation and the recycling of anthropogenic nutrients as fertilizer in agriculture are considered as major innovations to improve the sustainability of today's urban wastewater management. The acceptance of consumers will be key for the introduction of the new technology. Citizens will have to make important decisions in their role as tenants and owners of houses and as consumers buying products fertilized with urine. Consumer attitudes towards the new technology were explored in a number of citizen focus groups in Switzerland. Focus groups are deliberate, moderated group discussions with informed citizens on a certain topic. The information was provided by a computer based information system specifically designed for this purpose. The acceptance of individual citizens for the new technology proved to be quite high. The majority of the citizens expressed their willingness to move into an apartment with NoMix toilets and to buy food fertilized with urine. However, they were not willing to accept additional financial costs or efforts. Arguments related to long-term sustainability (closing nutrient cycles) were of less importance than arguments that relate directly to the effects of micropollutants on human and ecosystem health. For the introduction of the new technology on a wide scale it will thus be crucial to explore the fate and effects of micropollutants.

  4. Determination of radiochemical purity using gas chromatography

    International Nuclear Information System (INIS)

    1975-01-01

    The concepts of chromatography, gas chromatography, activity, radiochemical impurity are defined; the procedure of the application of gas chromatography for detecting radiochemical purity of substances is standardized. (E.F.)

  5. New Fragment Separation Technology for Superheavy Element Research

    International Nuclear Information System (INIS)

    Shaughnessy, D A; Moody, K J; Henderson, R A; Kenneally, J M; Landrum, J H; Lougheed, R W; Patin, J B; Stoyer, M A; Stoyer, N J; Wild, J F; Wilk, P A

    2008-01-01

    This project consisted of three major research areas: (1) development of a solid Pu ceramic target for the MASHA separator, (2) chemical separation of nuclear decay products, and (3) production of new isotopes and elements through nuclear reactions. There have been 16 publications as a result of this project, and this collection of papers summarizes our accomplishments in each of the three areas of research listed above. The MASHA (Mass Analyzer for Super-Heavy Atoms) separator is being constructed at the U400 Cyclotron at the Flerov Laboratory of Nuclear Reactions in Dubna, Russia. The purpose of the separator is to physically separate the products from nuclear reactions based on their isotopic masses rather than their decay characteristics. The separator was designed to have a separation between isotopic masses of ±0.25 amu, which would enable the mass of element 114 isotopes to be measured with outstanding resolution, thereby confirming their discovery. In order to increase the production rate of element 114 nuclides produced via the 244 Pu+ 48 Ca reaction, a new target technology was required. Instead of a traditional thin actinide target, the MASHA separator required a thick, ceramic-based Pu target that was thick enough to increase element 114 production while still being porous enough to allow reaction products to migrate out of the target and travel through the separator to the detector array located at the back end. In collaboration with UNLV, we began work on development of the Pu target for MASHA. Using waste-form synthesis technology, we began by creating zirconia-based matrices that would form a ceramic with plutonium oxide. We used samarium oxide as a surrogate for Pu and created ceramics that had varying amounts of the starting materials in order to establish trends in material density and porosity. The results from this work are described in more detail in Refs. [1,4,10]. Unfortunately, work on MASHA was delayed in Russia because it was found that

  6. The development of zirconia membrane oxygen separation technology

    International Nuclear Information System (INIS)

    Chiacchi, F.T.; Badwal, S.P.S.; Velizko, V.

    2000-01-01

    The oxygen separation technology based on ceramic membranes constructed from stabilised zirconia is currently under development for applications ranging from oxygen generation or air enrichment for medical use to control of oxygen concentration or oxygen removal from gas streams and enclosures for semiconductor, food packaging and process control instrumentation industries. The technology is based on a rugged tubular design with extensive thermal cycling capability. Several single and three tube devices have been operated for periods up to 5000h. An eight tube module, as a building block for larger scale oxygen production or removal devices, has been constructed and is being evaluated. In this paper, the construction of the device, oxygen generating capacity, life time tests and performance of the ceramic membrane device under development at CSIRO will be discussed. Copyright (2000) The Australian Ceramic Society

  7. Alternative applications of atomic vapor laser isotope separation technology

    International Nuclear Information System (INIS)

    1991-01-01

    This report was commissioned by the Secretary of Energy. It summarizes the main features of atomic vapor laser isotope separation (AVLIS) technology and subsystems; evaluates applications, beyond those of uranium enrichment, suggested by Lawrence Livermore National Laboratory (LLNL) and a wide range of US industries and individuals; recommends further work on several applications; recommends the provision of facilities for evaluating potential new applications; and recommends the full involvement of end users from the very beginning in the development of any application. Specifically excluded from this report is an evaluation of the main AVLIS missions, uranium enrichment and purification of plutonium for weapons. In evaluating many of the alternative applications, it became clear that industry should play a greater and earlier role in the definition and development of technologies with the Department of Energy (DOE) if the nation is to derive significant commercial benefit. Applications of AVLIS to the separation of alternate (nonuranium) isotopes were considered. The use of 157 Gd as burnable poison in the nuclear fuel cycle, the use 12 C for isotopically pure diamond, and the use of plutonium isotopes for several nonweapons applications are examples of commercially useful products that might be produced at a cost less than the product value. Separations of other isotopes such as the elemental constituents of semiconductors were suggested; it is recommended that proposed applications be tested by using existing supplies to establish their value before more efficient enrichment processes are developed. Some applications are clear, but their production costs are too high, the window of opportunity in the market has passed, or societal constraints (e.g., on reprocessing of reactor fuel) discourage implementation

  8. Present status of radiochemical double β decay study (238U)

    International Nuclear Information System (INIS)

    Chevallier, A.; Chevallier, J.; Escoubes, B.; Schulz, N.; Sens, J.C.; Madic, C.; Maillard, C.

    1989-01-01

    The reasons for which the 238 U is a suitable candidate for the β β decay processes are explained. The strategy adopted for the radiochemical separation of the 234 U is given. A chemical system based on extraction chromatography is applied. The Pu IV breakthrough curves obtained at 40C during 238 Pu/ 238 U separation cycles are presented. A short description of the chromatographic facility is given. The solution adopted for the low background α spectrometer is explained

  9. Separations technologies supporting the development of a deployable ATW system

    International Nuclear Information System (INIS)

    Laidler, J. J.

    2000-01-01

    A program has been initiated for the purpose of developing the chemical separations technologies necessary to support a large Accelerator Transmutation of Waste (ATW) system capable of dealing with the projected inventory of spent fuel from the commercial nuclear power stations in the United States. The first several years of the program will be directed toward an elucidation of related technical issues and to the establishment, by means of comprehensive trade studies, of an optimum configuration of the elements of the chemical processing infrastructure required for support of the total ATW system. By adopting this sort of disciplined systems engineering approach, it is expected that development and demonstration costs can be minimized and that it will be possible to deploy an ATW system that is an environmentally sound and economically viable venture

  10. Radiochemical stability of radiopharmaceutical preparations

    International Nuclear Information System (INIS)

    Martins, Patricia de A.; Silva, Jose L. da; Ramos, Marcelo P.S.; Oliveira, Ideli M. de; Felgueiras, Carlos F.; Herrerias, Rosana; Zapparoli Junior, Carlos L.; Mengatti, Jair; Fukumori, Neuza T.O.; Matsuda, Margareth M.N.

    2011-01-01

    The 'in vitro' stability studies of the radiopharmaceutical preparations are an essential requirement for routine practice in nuclear medicine and are an important parameter for evaluating the quality, safety and efficacy required for the sanitary registration of pharmaceutical products. Several countries have published guidelines for the evaluation of pharmaceutical stability. In Brazil, the stability studies should be conducted according to the Guide for Conducting Stability Studies published in the Resolution-RE n. 1, of 29th July 2005. There are also for radiopharmaceutical products, two specific resolutions: RDC-63 regulates the Good Manufacturing Practices for Radiopharmaceuticals and RDC-64 provides the Registration of Radiopharmaceuticals, both published on the 18th December 2009. The radiopharmaceutical stability is defined as the time during which the radioisotope can be safely used for the intended purpose. The radiochemical stability can be affected by a variety of factors, including storage temperature, amount of radioactivity, radioactive concentration, presence or absence of antioxidants or other stabilizing agents. The radiochemical stability studies must be established under controlled conditions determined by the effective use of the product. The aim of this work was to evaluate the radiochemical stability of labeled molecules with 131 I, 123 I, 153 Sm, 18 F, 51 Cr, 177 Lu and 111 In as well as 67 Ga and 201 Tl radiopharmaceuticals. Radiochemical purity was evaluated after production and in the validity period, with the maximum activity and in the recommended storage conditions. The analyses were carried out by thin-layer silica gel plate, paper chromatography and gel chromatography. The experimental results showed to be in accordance with the specified limits for all the analysed products. (author)

  11. Radiochemical Analysis Methodology for uranium Depletion Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Scatena-Wachel DE

    2007-01-09

    This report provides sufficient material for a test sponsor with little or no radiochemistry background to understand and follow physics irradiation test program execution. Most irradiation test programs employ similar techniques and the general details provided here can be applied to the analysis of other irradiated sample types. Aspects of program management directly affecting analysis quality are also provided. This report is not an in-depth treatise on the vast field of radiochemical analysis techniques and related topics such as quality control. Instrumental technology is a very fast growing field and dramatic improvements are made each year, thus the instrumentation described in this report is no longer cutting edge technology. Much of the background material is still applicable and useful for the analysis of older experiments and also for subcontractors who still retain the older instrumentation.

  12. Feasibility evaluation of downhole oil/water separator (DOWS) technology.

    Energy Technology Data Exchange (ETDEWEB)

    Veil, J. A.; Langhus, B. G.; Belieu, S.

    1999-01-31

    The largest volume waste stream associated with oil and gas production is produced water. A survey conducted by the American Petroleum Institute estimated that 20.9 billion barrels of produced water were disposed of in 1985 (Wakim 1987). Of this total, 91% was disposed of through disposal wells or was injected for enhanced oil recovery projects. Treatment and disposal of produced water represents a significant cost for operators. A relatively new technology, downhole oil/water separators (DOWS), has been developed to reduce the cost of handling produced water. DOWS separate oil and gas from produced water at the bottom of the well and reinject some of the produced water into another formation or another horizon within the same formation, while the oil and gas are pumped to the surface. Since much of the produced water is not pumped to the surface, treated, and pumped from the surface back into a deep formation, the cost of handling produced water is greatly reduced. When DOWS are used, additional oil may be recovered as well. In cases where surface processing or disposal capacity is a limiting factor for further production within a field, the use of DOWS to dispose of some of the produced water can allow additional production within that field. Simultaneous injection using DOWS minimizes the opportunity for contamination of underground sources of drinking water (USDWs) through leaks in tubing and casing during the injection process. This report uses the acronym 'DOWS' although the technology may also be referred to as DHOWS or as dual injection and lifting systems (DIALS). Simultaneous injection using DOWS has the potential to profoundly influence the domestic oil industry. The technology has been shown to work in limited oil field applications in the United States and Canada. Several technical papers describing DOWS have been presented at oil and gas industry conferences, but for the most part, the information on the DOWS technology has not been widely

  13. Cleanout and decontamination of radiochemical hot cells

    International Nuclear Information System (INIS)

    Surma, J.E.; Holton, L.K. Jr.; Katayama, Y.B.; Gose, J.E.; Haun, F.E.; Dierks, R.D.

    1990-01-01

    The Pacific Northwest Laboratory is developing and employing advanced remote and contact technologies in cleaning out and decontaminating six radiochemical hot cells at Hanford under the Department of Energy's Surplus Facilities Management Program. The program is using a series of remote and contact decontamination techniques to reduce costs and to significantly lower radiation doses to workers. Refurbishment of the cover blocks above the air lock trench reduced radiation exposure in the air lock and cleanout and decontamination of an analytical cell achieved a reduction in radioactive contamination. Nuclear Regulatory Commission-approved Type B burial boxes are also being used to reduce waste disposal costs and radiation doses. PNL is currently decommissioning its pilot-scale radioactive liquid-fed ceramic melter. Special tools have been developed and are being used to accomplish the world's first such effort. 4 refs., 5 figs

  14. Innovative sludge pretreatment technology for impurity separation using micromesh.

    Science.gov (United States)

    Mei, Xiaojie; Han, Xiaomeng; Zang, Lili; Wu, Zhichao

    2018-05-23

    In order to reduce the impacts on sludge treatment facilities caused by impurities such as fibers, hairs, plastic debris, and coarse sand, an innovative primary sludge pretreatment technology, sludge impurity separator (SIS), was proposed in this study. Non-woven micromesh with pore size of 0.40 mm was used to remove the impurities from primary sludge. Results of lab-scale tests showed that impurity concentration, aeration intensity, and channel gap were the key operation parameters, of which the optimized values were below 25 g/L, 0.8 m 3 /(m 2  min), and 2.5 cm, respectively. In the full-scale SIS with treatment capacity of 300 m 3 /day, over 88% of impurities could be removed from influent and the cleaning cycle of micromesh was more than 16 days. Economic analysis revealed that the average energy consumption was 1.06 kWh/m 3 treated sludge and operation cost was 0.6 yuan/m 3 treated sludge.

  15. Electrochemistry as a basis for radiochemical generator systems

    International Nuclear Information System (INIS)

    Bentley, G.E.; Steinkruger, F.J.; Wanek, P.M.

    1984-01-01

    Ion exchange and solvent extraction techniques have been used extensively as the basis for radiochemical generators exploiting the differences in absorption behavior between the parent nuclide and its useful daughter nuclide. Many parent/daughter pairs of nuclides have sufficiently different polarographic half wave potentials so that their electrochemical behavior may be exploited for rapid separation of the daughter from the parent with minimal contamination of the product with the parent isotope

  16. Process for separating nitrogen from methane using microchannel process technology

    Science.gov (United States)

    Tonkovich, Anna Lee [Marysville, OH; Qiu, Dongming [Dublin, OH; Dritz, Terence Andrew [Worthington, OH; Neagle, Paul [Westerville, OH; Litt, Robert Dwayne [Westerville, OH; Arora, Ravi [Dublin, OH; Lamont, Michael Jay [Hilliard, OH; Pagnotto, Kristina M [Cincinnati, OH

    2007-07-31

    The disclosed invention relates to a process for separating methane or nitrogen from a fluid mixture comprising methane and nitrogen, the process comprising: (A) flowing the fluid mixture into a microchannel separator, the microchannel separator comprising a plurality of process microchannels containing a sorption medium, the fluid mixture being maintained in the microchannel separator until at least part of the methane or nitrogen is sorbed by the sorption medium, and removing non-sorbed parts of the fluid mixture from the microchannel separator; and (B) desorbing the methane or nitrogen from the sorption medium and removing the desorbed methane or nitrogen from the microchannel separator. The process is suitable for upgrading methane from coal mines, landfills, and other sub-quality sources.

  17. Membrane Materials and Technology for Xylene Isomers Separation and Isomerization via Pervaporation

    KAUST Repository

    Bilaus, Rakan

    2014-01-01

    technology’s high energy intensity has become a growing concern. Membrane separation technology is a potential low-energy alternative. Polymeric membranes were investigated in a pervaporation experiment to separate xylene isomers. Polymers of intrinsic

  18. Carbon Dioxide Separation Technology: R&D Needs for the Chemical and Petrochemical Industries

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2007-11-01

    This report, the second in a series, is designed to summarize and present recommendations for improved CO2 separation technology for industrial processes. This report provides an overview of 1) the principal CO2 producing processes, 2) the current commercial separation technologies and 3) emerging adsorption and membrane technologies for CO2 separation, and makes recommendations for future research.

  19. Scientific and technical conference. Problems and horizons of development of chemical and radiochemical control in nuclear energetics. Collection of summaries of reports

    International Nuclear Information System (INIS)

    2001-01-01

    During scientific and technical conference on problems of development of chemical and radiochemical control in nuclear energetics following themes were considered: the problems of methodological and instrumental assurance of chemical and radiochemical control at working nuclear power plants and nuclear energetic units; modern conceptions of automation systems construction of chemical and radiochemical control on the basis of intellectual measuring channels; the ways of decision of generally system problems of organization and management of chemical and radiochemical control using computed technologies; the problems of certification of chemical and radiochemical methods of measuring in nuclear energetics [ru

  20. An overview of the status of radiochemical analysis in Hungary

    International Nuclear Information System (INIS)

    Solymosi, J.; Toth, G.

    1994-01-01

    This overview covers the following activities at radioanalytical laboratories in Hungary: tracer techniques and their applications; some important new results; radioimmunoassay; x-ray emission analysis and x-ray fluorescence analysis, Moessbauer-spectroscopy and their applications in various fields of science and technology; neutron activation analysis; radiochemical analysis for nuclear power plant applications activities in various laboratories; nuclear environmental analysis (radioanalytical methods for the investigation of contamination by nuclear facilities). (N.T.) 1 fig.; 7 tabs

  1. Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants

    International Nuclear Information System (INIS)

    1999-01-01

    The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques [ru

  2. A novel technology coupling extraction and foam fractionation for separating the total saponins from Achyranthes bidentata.

    Science.gov (United States)

    Ding, Linlin; Wang, Yanji; Wu, Zhaoliang; Liu, Wei; Li, Rui; Wang, Yanyan

    2016-10-02

    A novel technology coupling extraction and foam fractionation was developed for separating the total saponins from Achyranthes bidentata. In the developed technology, the powder of A. bidentata was loaded in a nylon filter cloth pocket with bore diameter of 180 µm. The pocket was fixed in the bulk liquid phase for continuously releasing saponins. Under the optimal conditions, the concentration and the extraction rate of the total saponins in the foamate by the developed technology were 73.5% and 416.2% higher than those by the traditional technology, respectively. The foamates obtained by the traditional technology and the developed technology were analyzed by ultraperformance liquid chromatography-mass spectrometry to determine their ingredients, and the results appeared that the developed technology exhibited a better performance for separating saponins than the traditional technology. The study is expected to develop a novel technology for cost effectively separating plant-derived materials with surface activity.

  3. Analysis on two technologic errors of color separation grating used for ICF

    International Nuclear Information System (INIS)

    Chen Dewei; Li Yongping

    2003-01-01

    In this paper, the depth of color separation grating applied in ICF system is optimized firstly for good separating effect. After this, duty cycle error and the trapezoid structure are analyzed. A probable scope of technologic error that make the color separation grating have good effect is given in the end

  4. Trends in coarse and fine grinding and separation technology ...

    African Journals Online (AJOL)

    Journal of Food Technology in Africa. Journal Home · ABOUT · Advanced Search · Current Issue · Archives · Journal Home > Vol 4, No 2 (1999) >. Log in or Register to get access to full text downloads.

  5. RECENT PROGRESS OF OXYGEN/NITROGEN SEPARATION USING MEMBRANE TECHNOLOGY

    OpenAIRE

    K. C. CHONG; S. O. LAI; H. S. THIAM; H. C. TEOH; S. L. HENG

    2016-01-01

    The oxygen-enriched air is highly demanded for various industrial applications such as medical, chemical and enhanced combustion processes. The conventional oxygen/nitrogen production is either cryogenic distillation or pressure swing adsorption (PSA). Both of these techniques possess the production capability of 20 to 300 tonnes of oxygen per day and oxygen purity of more than 95%. However, these techniques are energy intensive. Alternatively, membrane technology is an emerging technology...

  6. [Study on essential oil separation from Forsythia suspensa oil-bearing water body based on vapor permeation membrane separation technology].

    Science.gov (United States)

    Zhang, Qian; Zhu, Hua-Xu; Tang, Zhi-Shu; Pan, Yong-Lan; Li, Bo; Fu, Ting-Ming; Yao, Wei-Wei; Liu, Hong-Bo; Pan, Lin-Mei

    2018-04-01

    To investigate the feasibility of vapor permeation membrane technology in separating essential oil from oil-water extract by taking the Forsythia suspensa as an example. The polydimethylsiloxane/polyvinylidene fluoride (PDMS/PVDF) composite flat membrane and a polyvinylidene fluoride (PVDF) flat membrane was collected as the membrane material respectively. Two kinds of membrane osmotic liquids were collected by self-made vapor permeation device. The yield of essential oil separated and enriched from two kinds of membrane materials was calculated, and the microscopic changes of membrane materials were analyzed and compared. Meanwhile, gas chromatography-mass spectrometry (GC-MS) was used to compare and analyze the differences in chemical compositions of essential oil between traditional steam distillation, PVDF membrane enriched method and PDMS/PVDF membrane enriched method. The results showed that the yield of essential oil enriched by PVDF membrane was significantly higher than that of PDMS/PVDF membrane, and the GC-MS spectrum showed that the content of main compositions was higher than that of PDMS/PVDF membrane; The GC-MS spectra showed that the components of essential oil enriched by PVDF membrane were basically the same as those obtained by traditional steam distillation. The above results showed that vapor permeation membrane separation technology shall be feasible for the separation of Forsythia essential oil-bearing water body, and PVDF membrane was more suitable for separation and enrichment of Forsythia essential oil than PDMS/PVDF membrane. Copyright© by the Chinese Pharmaceutical Association.

  7. Magneto-plasma separating technologies and their possible application for conversion spent fuel and radioactive waste

    International Nuclear Information System (INIS)

    Kovtun, Yu.V.; Skyibenko, Je.Yi.; Yuferov, V.B.

    2007-01-01

    A problem of spent fuel (SF) and radioactive waste (RAW) processing is considered in the views of using magneto-plasma technologies. Basing on this analysis, the block-diagram of RAW processing by the technology using a magneto-plasma separator is offered. The paper describes the device for material element separation, where the main physical mechanism of plasma formation and heating are collective processes involved by the plasma-beam interaction. The dimensions of a pilot-separating device are determined

  8. Thorium base fuels reprocessing at the L.P.R. (Radiochemical Processes Laboratory) experimental plant

    International Nuclear Information System (INIS)

    Almagro, J.C.; Dupetit, G.A.; Deandreis, R.A.

    1987-01-01

    The availability of the LPR (Radiochemical Processes Laboratory) plant offers the possibility to demonstrate and create the necessary technological basis for thorium fuels reprocessing. To this purpose, the solvents extraction technique is used, employing TBP (at 30%) as solvent. The process is named THOREX, a one-cycle acid, which permits an adequate separation of Th 232 and U 233 components and fission products. For thorium oxide elements dissolution, the 'chopp-leach' process (installed at LPR) is used, employing a NO 3 H 13N, 0.05M FH and 0.1M Al (NO 3 ) 3 , as solvent. To adapt the pilot plant to the flow-sheet requirements proposed, minor modifications must be carried out in the interconnection of the existing decanting mixers. The input of the plant has been calculated by Origin Code modified for irradiations in reactors of the HWR type. (Author)

  9. Radiochemical purity determination by paper chromatography 2

    International Nuclear Information System (INIS)

    1975-01-01

    The standard relates to the determination of radiochemical impurities in labelled compounds using paper chromatography. The basic terms are given as is the description of procedure and evaluation of chromatograms. (E.S.)

  10. Radiochemical neutron activation analysis of zirconium and zirconium-niobium alloys

    International Nuclear Information System (INIS)

    Tashimova, F.A.; Sadikov, I.I.; Salimov, M.

    2004-01-01

    Full text: Zirconium and zirconium-niobium alloys are used on nuclear technology, as fuel cladding of nuclear reactors. Their nuclear-physical, mechanical and thermophysical properties are influenced them matrix and impurity composition, therefore determination of matrix and impurity content of these materials is a very important task. Neutron activation analysis is one from multielemental and high sensible techniques that are widely applied in analysis of high purity materials. Investigation of nuclear-physical characteristics of zirconium has shown that instrumental variant NAA is unusable for analysis due to high radioactivity of a matrix. Therefore it is necessary carrying out radiochemical separation of impurity radionuclides from matrix. Study of the literature datum have shown, that zirconium and niobium are very well extracted from muriatic solution with 5% tributyl phosphineoxide (TBPO) solution in toluene and 0,75 M solution of di-2-ethyl hexyl phosphoric acid (HDEHP) in cyclohexanone. Investigation of these elements extraction in these systems has shown that more effective and selective separation of matrix radionuclides is achieved in HDEHP-3M HCI system. This system is also extracted and hafnium, witch is an accompanying element of zirconium and its high content prevented determination of other impurity elements in sample. Therefore we used extraction system HDEHP-3M HCl for analysis of zirconium and zirconium-niobium alloys in chromatographic variant. By measurement of distribution profile of a matrix and of elution curve of determined elements is established, that for effective separation of impurity and matrix radionuclides there is enough chromatographic column with diameter 1 cm and height of a sorbent layer 7 cm, thus volume of elute, necessary for complete elution of determinate elements is 35-40 ml. On the basis of the carried out researches the technique of radiochemical NAA of high purity zirconium and zirconium-niobium alloy, which allows to

  11. Membrane-based separation technologies for cesium, strontium, and technetium

    International Nuclear Information System (INIS)

    Kafka, T.

    1996-01-01

    This work is one of two parallel projects that are part of an ESP task to develop high-capacity, selective, solid extractants for cesium, strontium, and technetium from nuclear wastes. In this subtask, Pacific Northwest National Laboratory (PNNL) is collaborating with 3M, St. Paul, Minnesota, working in cooperation with IBC Advanced Technologies, American Fork, Utah

  12. Efficient Separations and Processing Integrated Program (ESP-IP): Technology summary

    International Nuclear Information System (INIS)

    1994-02-01

    The Efficient Separations and Processing Integrated Program (ESPIP) was created in 1991 to identify, develop and perfect separations technologies and processes to treat wastes and address environmental problems throughout the DOE Complex. These wastes and environmental problems, located at more than 100 contaminated installations in 36 states and territories, are the result of half a century of nuclear processing activities by DOE and its predecessor organizations. The cost of cleaning up this legacy has been estimated to be of the order of hundreds of billions of dollars, and ESPIP's origin came with the realization that if new separations and processes can produce even a marginal reduction in cost then billions of dollars will be saved. The ultimate mission for ESPIP, as outlined in the ESPIP Strategic Plan, is: to provide Separations Technologies and Processes (STPS) to process and immobilize a wide spectrum of radioactive and hazardous defense wastes; to coordinate STP research and development efforts within DOE; to explore the potential uses of separated radionuclides; to transfer demonstrated separations and processing technologies developed by DOE to the US industrial sector, and to facilitate competitiveness of US technology and industry in the world market. Technology research and development currently under investigation by ESPIP can be divided into four broad areas: cesium and strontium removal; TRU and other HLW separations; sludge technology, and other technologies

  13. 75 FR 37860 - Aris Industries, Inc., Bene Io, Inc., Commodore Separation Technologies, Inc., Food Integrated...

    Science.gov (United States)

    2010-06-30

    ...., Commodore Separation Technologies, Inc., Food Integrated Technologies, Inc., Gap Instrument Corp., Skysat Communications Network Corp., and Vicon Fiber Optics Corp.; Order of Suspension of Trading June 28, 2010. It... information concerning the securities of Food Integrated Technologies, Inc. because it has not filed any...

  14. Critical evaluation of the determination of zirconium and hafnium by instrumental and radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Burger, Mario; Kraehenbuehl, Urs

    1991-01-01

    Neutron activation analysis (instrument or radiochemical) is suitable for the determination of zirconium and hafnium in samples of geochemical origin only when sufficient attention is paid to inter-fering nuclides. The size of the necessary correction for INAA depends on the composition of the sample; this problem is discussed. The radio-chemical technique which is recommended involves separation of the samples, precipitations and anion-exchange separation. Results are given for various standard reference materials and for meteorites. (author). 12 refs.; 1 fig.; 9 tabs

  15. Determination of plutonium isotopes (238Pu, 239Pu, 240Pu, 241Pu) in environmental samples using radiochemical separation combined with radiometric and mass spectrometric measurements

    DEFF Research Database (Denmark)

    Xu, Yihong; Qiao, Jixin; Hou, Xiaolin

    2014-01-01

    counting and alpha spectrometry) and inductively coupled plasma mass spectrometry (ICP-MS) were applied for the measurement of plutonium isotopes. The decontamination factors for uranium were significantly improved up to 7.5×105 for 20 g soil compared to the level reported in the literature......, this is critical for the measurement of plutonium isotopes using mass spectrometric technique. Although the chemical yield of Pu in the entire procedure is about 55%, the analytical results of IAEA soil 6 and IAEA-367 in this work are in a good agreement with the values reported in the literature or reference......Pu. However, it is impossible to measure 238Pu using ICP-MS in environmental samples even a decontamination factor as high as 106 for uranium was obtained by chemical separation....

  16. Low temperature radio-chemical energy conversion processes

    International Nuclear Information System (INIS)

    Gomberg, H.J.

    1986-01-01

    This patent describes a radio-chemical method of converting radiated energy into chemical energy form comprising the steps of: (a) establishing a starting chemical compound in the liquid phase that chemically reacts endothermically to radiation and heat energy to produce a gaseous and a solid constituent of the compound, (b) irradiating the compound in its liquid phase free of solvents to chemically release therefrom in response to the radiation the gaseous and solid constituents, (c) physically separating the solid and gaseous phase constituents from the liquid, and (d) chemically processing the constituents to recover therefrom energy stored therein by the irradiation step (b)

  17. Electrochemically Modulated Gas/Liquid Separation Technology for In Situ Resource Utilization Process Streams, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — In this phase I program MicroCell Technologies, LLC (MCT) proposes to demonstrate the feasibility of an electrochemically modulated phase separator for in situ...

  18. The value function as a criterion of analysis in separation technologies

    International Nuclear Information System (INIS)

    Peculea, Marius

    2005-01-01

    Production costs of heavy water are described by two functions: φ(ε), the energy function which represents the variable costs and φ(τ), the technologic function which represents the stable costs. The Dirac value function related to the circulation in the separation cascade allows calculating φ(ε) and consequently the technologic function may be represented in relation to the specific separation process. This representation allows the qualitative analysis of different separation processes or, for a given process, provides the analysis of different technological solutions which were worked out. An example is given referring to the analysis of heavy water technologies of separation through the dual temperature process of H 2 O-H 2 S isotopic exchange

  19. Radionuclide separation and processing for recycle or disposal

    International Nuclear Information System (INIS)

    Allen, W.O.; Morrey, J.R.; Fryberger, T.B.; Wolf, S.M.; Lien, S.C.T.

    1992-01-01

    The U.S. Department of Energy (DOE) Office of Technology Development (OTD) is sponsoring research and development on advanced radiochemical separations, at a modest level, with the long-term goals of reducing the volume of deep geologic repository-disposed waste and the toxicity of low-level waste disposed as cement grout in a near-surface vault. This will help reduce overall environmental risks and the cost of waste management. (author)

  20. Methods for training radiochemical technicians at ORNL

    International Nuclear Information System (INIS)

    Parrott, J.R.; Nicol, R.G.

    The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since programs are constantly shifting. It is essential that provisions be made for the routine retraining of these personnel if they are to make effective contributions on a continuing basis. Training methods are described that have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. Emphasis is placed on training programs for technicians for the 233 U Processing Facility since essentially all aspects of radiochemical operations are encountered in this facility. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. (U.S.)

  1. Life Cycle Assessment of pretreatment technologies for anaerobic digestion of source-separated organic household waste

    DEFF Research Database (Denmark)

    Naroznova, Irina; Møller, Jacob; Scheutz, Charlotte

    2013-01-01

    The environmental performance of two pretreatment technologies for source-separated organic waste was compared using life cycle assessment (LCA). An innovative pulping process where source-separated organic waste is pulped with cold water forming a volatile solid rich biopulp was compared to a more...... including a number of non-toxic and toxic impact categories were assessed. No big difference in the overall performance of the two technologies was observed. The difference for the separate life cycle steps was, however, more pronounced. More efficient material transfer in the scenario with waste pulping...

  2. R&D Opportunities for Membranes and Separation Technologies in Building Applications

    Energy Technology Data Exchange (ETDEWEB)

    Goetzler, William [Navigant Consulting Inc., Burlington, MA (United States); Guernsey, Matt [Navigant Consulting Inc., Burlington, MA (United States); Bargach, Youssef [Navigant Consulting Inc., Burlington, MA (United States)

    2017-10-01

    This report recommends innovative membrane and separation technologies that can assist the Building Technologies Office in achieving its 2030 goal. This report identifies research and development (R&D) initiatives across several building applications where further investigations could result in impactful savings.

  3. Relevance of separation science and technology to nuclear fuel complex operations

    International Nuclear Information System (INIS)

    Rao, S.M.; Ojha, P.B.; Rajashri, M.; Mirji, K.V.; Kalidas, R.

    2004-01-01

    During the last three decades at Nuclear Fuel Complex (NFC), Hyderabad, the Science and Technology of separation to produce various reactor grade materials in tonnage quantity is being practiced in the fields of Zr/Hf, U and Nb/Ta. Apart from this, the separation science is also being used in the production of various high purity materials and in the analytical field. The separation science and technology that is used in the production and characterisation of reactor grade materials has many striking differences from that of the common metals. The relevance and significance of separation science in the field of nuclear materials arises mainly due to the harmful effects w.r.t corrosion property and absorption of neutron caused by the presence of impurities, that are to be brought down to ppm or sub ppm level. In many cases low separation factors, that too from a multi component system call for effective process control at every stage of the bulk production so as to get quality product consistently. This article brings out the importance of separation science and technology and various process standardisations/developments that have been carried out at NFC, starting from laboratory scale to pilot scale and up to industrial scale production in the case of (i) Uranium refining (ii) Zr-Hf separation (iii) Ta-Nb separation and (iv) High purity materials production. (author)

  4. Radiochemical analysis of concrete samples for decommission of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Zapata-Garcia, Daniel; Wershofen, Herbert [Physikalisch-Technische Bundesanstalt (PTB), Bundesallee 100 38116, Braunschweig (Germany); Larijani, Cyrus; Sobrino-Petrirena, Maitane; Garcia-Miranda, Maria; Jerome, Simon M. [National Physical Laboratory (NPL), Hampton Road, Teddington, Middlesex, TW11 0LW (United Kingdom)

    2014-07-01

    Decommissioning of the oldest nuclear power reactors are some of the most challenging technological legacy issues many countries will face in forthcoming years, as many power reactors reach the end of their design lives. Decommissioning of nuclear reactors generates large amounts of waste that need to be classified according to their radioactive content. Approximately 10 % of the contaminated material ends up in different repositories (depending on their level of contamination) while the rest is decontaminated, measured and released into the environment or sent for recycling. Such classification needs to be done accurately in order to ensure that both the personnel involved in decommissioning and the population at large are not needlessly exposed to radiation or radioactive material and to minimise the environmental impact of such work. However, too conservative classification strategies should not be applied, in order to make proper use of radioactive waste repositories since space is limited and the full process must be cost-effective. Implicit in decommissioning and classification of waste is the need to analyse large amounts of material which usually combine a complex matrix with a non-homogeneous distribution of the radionuclides. Because the costs involved are large, it is possible to make great savings by the adoption of best available practices, such as the use of validated methods for on-site measurements and simultaneous determination of more than one radionuclide whenever possible. The work we present deals with the development and the validation of a procedure for the simultaneous determination of {sup 241}Am, plutonium isotopes, uranium isotopes and {sup 90}Sr in concrete samples. Samples are firstly ground and fused with LiBO{sub 2} and Li{sub 2}B{sub 4}O{sub 7}. After dissolution of the fused sample, silicate and alkaline elements are removed followed by radiochemical separation of the target radionuclides using extraction chromatography. Measurement

  5. Animal manure separation technologies diminish the environmental burden of steroid hormones

    DEFF Research Database (Denmark)

    Hansen, Martin; Björklund, Erland; Popovic, Olga

    2015-01-01

    environmental risks associated with the release of steroid hormones to adjacent waterways. To assess the potential benefit of these technologies in reducing the level of release of steroid hormones to adjacent waterways, distribution profiles of nine steroid hormones (pregnenolone, progesterone......Newly developed treatment technologies are capable of separating livestock manure into a liquid fraction and a solid fraction using sedimentation, mechanical, and/or chemical methods. These technologies offer a potential means of distributing nutrients to agricultural lands without the unwanted...

  6. Radiochemical assay for determination of dihydropyrimidinase activity using reversed-phase high-performance liquid chromatography

    NARCIS (Netherlands)

    van Kuilenburg, A. B.; van Lenthe, H.; van Gennip, A. H.

    1999-01-01

    A radiochemical assay was developed to measure the activity of dihydropyrimidinase (DHP) in human liver homogenates. The method is based on the separation of radiolabeled dihydrouracil from N-carbamyl-beta-alanine by HPLC with on-line detection of radioactivity combined with detection of 14CO2 by

  7. The radiochemical purity of radiotracers as the criterion of their usefulness in investigations of hydrocarbons distillation

    International Nuclear Information System (INIS)

    Kolaczkowski, M.

    1976-01-01

    Among numerous analytic techniques of separation and analysis of radioactive products gas radiochromatography has proved to be particularly suitable. Organic bromides labelled with 82 Br-radionuclide are investigated. The analytic gas chromatographs equipped with appropriately constructed radiochromatographic attachments are used. The results of radiochemical purity determination of radiotracers are compared for various techniques. (author)

  8. Radiochemical procedures for determination of selected members of the uranium and thorium series

    International Nuclear Information System (INIS)

    Smithson, G.L.

    1979-01-01

    The radiochemical procedures contained in this manual are adaptations of those developed and published by many radiochemists. In many cases the identity of the originator is not clear and usually modifications in the original procedure have been made by subsequent workers. Nearly all of the basic radiochemical techniques and separations in use today were developed during the Manhattan Project and can be found in U.S.A.E.C. reports published from 1945 to 1953. This manual contains methods for the determination of Pb-210, Po-210; Ra-226, Ra-228, Th-228, Th-230 and Th-232. (auth)

  9. On the methodology of radiochemical neutron activation analysis of noble metals

    International Nuclear Information System (INIS)

    Chai, C.F.; Ma, S.L.; Mao, X.Y.; Liao, K.N.; Liu, W.C.

    1986-01-01

    Two different radiochemical procedures were developed: chelate ion resin exchange and amine solvent extraction. Two kinds of new Chinese chelate resins (NANKAI-3926 and BEI-5) and a new long-chain primary amine N 1923 were compared with Srafion NMRR and the tertiary amine N 235 in absorption performance of noble metals, respectively. Influences of various experimental conditions, e.g. sample digestion, acidity, equilibrium time, as well as elution of noble metals, on analytical sensitivity and chemical yield were discussed. Combining with neutron activation, the radiochemical separation procedures developed were used to determine the noble metal contents in the geological samples from Permina/Triassic boundary in South China. (author)

  10. The role of high performance liquid chromatography in radiochemical/radiopharmaceutical synthesis and quality assurance

    International Nuclear Information System (INIS)

    Boothe, T.E.; Emran, A.M.

    1990-01-01

    The usefulness of HPLC in all areas of radiopharmaceutics has been demonstrated in numerous laboratories, particularly in the development of in-house radiopharmaceuticals for SPECT and PET. HPLC continues to be a powerful tool in preparation and quality assurance (QA) as illustrated in such areas as chemical and radiochemical identification; product separation and isolation; preparative scale purification; and specific activity determination. A review of established HPLC techniques in radiopharmaceutics will be presented. Examples from the literature as well as newer applications will be used in an attempt to assess and define the present-day role of HPLC in the preparation of radiochemicals and radiopharmaceuticals with emphasis on QA

  11. Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

    International Nuclear Information System (INIS)

    Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

    2017-01-01

    The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

  12. Radiochemical studies on Bikini ashes

    Energy Technology Data Exchange (ETDEWEB)

    Shiokawa, T

    1954-01-01

    Decay characteristics of the ashes which were brought back by the crew of the Fukuryu Maru No. 5 were: untreated ash I = ct/sup -1/ /sup 81/, water soluble part t/sup -2/ /sup 71/, insoluble part t/sup -1/ /sup 68/. Radioactive species separated by chemical method with carrier or collector were: nuclide, activity of nuclide (counts/min)/activity of original sample (counts/min), and the date of separation, /sup 89/Sr 6000/80 X 10/sup 4/, April 24; /sup 95/Zr, 280/80 x 10/sup 4/, -; /sup 111/Ag, 200/200 x 10/sup 4/, April 14; /sup 103/Ru, 2.300/25 x 10/sup 4/, etc.

  13. Radiochemical method for 63Ni

    International Nuclear Information System (INIS)

    Holm, E.; Nilsson, U.; Hallstadius, L.

    1985-01-01

    A radianalytical method for the determination of 63 Ni content in environmental samples of activated corrosion products is described. After chemical separation and electrodepositing of 63 Ni on silver briquets, the chemical yield is determined by X-ray fluorescence analysis. For the detection of low-energy beta activity, an open gas flow GM-counter with an anticoincidence guard counter is put to use

  14. Radiochemical Solar Neutrino Experiments - Successful and Otherwise

    International Nuclear Information System (INIS)

    Hahn, R.L.

    2008-01-01

    Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled

  15. Radiochemical solar neutrino experiments, 'successful and otherwise'

    International Nuclear Information System (INIS)

    Hahn, Richard L

    2008-01-01

    Over the years, several different radiochemical systems have been proposed as solar neutrino detectors. Of these, two achieved operating status and obtained important results that helped to define the current field of neutrino physics: the first solar-neutrino experiment, the Chlorine Detector ( 37 Cl) that was developed by chemist Raymond Davis and colleagues at the Homestake Mine, and the subsequent Gallium ( 71 Ga) Detectors that were operated by (a) the SAGE collaboration at the Baksan Laboratory and (b) the GALLEX/GNO collaborations at the Gran Sasso National Laboratory. These experiments have been extensively discussed in the literature and in many previous International Neutrino Conferences. In this paper, I present important updates to the results from SAGE and GALLEX/GNO. I also review the principles of the radiochemical detectors and briefly describe several different detectors that have been proposed. In light of the well-known successes that have been subsequently obtained by real-time neutrino detectors such as Kamiokande, Super-Kamiokande, SNO, and KamLAND, I do not anticipate that any new radiochemical neutrino detectors will be built. At present, only SAGE is still operating; the Chlorine and GNO radiochemical detectors have been decommissioned and dismantled.

  16. Radiochemical studies on nuclear fission at Trombay

    Indian Academy of Sciences (India)

    227Ac to 245Cm were determined by radiochemical methods which involved ... foil, followed by direct γ counting using high resolution Ge(Li) detector was also ... the stiffness to mass asymmetric distortion decreases on either side of lead.Also ...

  17. Trace analysis measurements in high-purity aluminium by means of radiochemical neutron and proton activation analysis

    International Nuclear Information System (INIS)

    Egger, K.P.

    1987-01-01

    The aim of the study consisted in the development of efficient radiochemical composite processes and activation methods for the multi-element determination of traces within the lower ng range in high-purity aluminium. More than 50 elements were determined with the help of activation with reactor neutrons; the selective separation of matrix activity (adsorption with hydrated antimony pentoxide) led to a noticeable improvement of detectability, as compared with instrumental neutron activation analysis. Further improvements were achieved with the help of radiochemical group separations in ion exchangers or with the help of the selective separation of the pure beta-emitting elements. Over 20 elements up to high atomic numbers were determined by means of activating 13 MeV protons and 23 Me protons. In this connection, improvements of the detection limit by as a factor of 10 were achieved with radiochemical separation techniques, as compared with pure instrumental proton activation analysis. (RB) [de

  18. A broad look at separator material technology for valve-regulated lead/acid batteries

    Energy Technology Data Exchange (ETDEWEB)

    Zguris, G.C. [Hollingsworth and Vose, West Groton, MA (United States)

    1998-05-18

    Recent research has proved the importance of a constant force of 40 kPa or greater on the paste solidus-grid interface. This has lead to increased interest in re-examining the microglass separator and the system that the plate-separator interaction forms. This renewed interest has resulted in new separator ideas and the revisiting of concepts tried in the early days of valve-regulated lead/acid (VRLA) technology. The paper is divided into two parts. The first part examines some past separator developments that have been tried but are presently not accepted by the general VRLA community. This is due to the excellent performance of the microglass separator used so successfully during the last 20 years. Many fundamental questions that need to be asked regarding the selection of a new separator system have long ago been forgotten. The second part of the paper reviews some fundamental aspects of separator selection, and some important attributes that the separator must provide based on current knowledge of the separator system. Attributes such as toughness, corrosion resistance, compression, wicking, stratification, porosity and conformability are discussed. (orig.)

  19. Emerging trends in separation science and technology as practised by Indian Rare Earths Ltd

    International Nuclear Information System (INIS)

    Mukherjee, T.K.

    2004-01-01

    Although the core business of Indian Rare Earths Ltd. (IREL) is mining of Indian Beach Sand deposits and separation of associated six heavy minerals, the Company is also engaged in a strategic activity like recovery of the mineral monazite from the sand and its chemical processing to recover two important nuclear materials and the rare earths. Separation science and technology plays an important role in this particular activity of IREL to produce, in commercial scale, the mineral monazite in desired purity and its chemical processing to recover products like thorium oxalate concentrate, nuclear grade ammonium diuranate, tri sodium phosphate and host of rare earths salts both mixed and separated. This paper to start with, will deal with bulk separation of monazite itself, which has an important bearing on down stream chemical separation process to be discussed in the later half

  20. Research on preventive technologies for bed-separation water hazard in China coal mines

    Science.gov (United States)

    Gui, Herong; Tong, Shijie; Qiu, Weizhong; Lin, Manli

    2018-03-01

    Bed-separation water is one of the major water hazards in coal mines. Targeted researches on the preventive technologies are of paramount importance to safe mining. This article studied the restrictive effect of geological and mining factors, such as lithological properties of roof strata, coal seam inclination, water source to bed separations, roof management method, dimensions of mining working face, and mining progress, on the formation of bed-separation water hazard. The key techniques to prevent bed-separation water-related accidents include interception, diversion, destructing the buffer layer, grouting and backfilling, etc. The operation and efficiency of each technique are corroborated in field engineering cases. The results of this study will offer reference to countries with similar mining conditions in the researches on bed-separation water burst and hazard control in coal mines.

  1. Radiochemical neutron activation analysis based multi-elemental analysis of high purity gallium

    International Nuclear Information System (INIS)

    Tashimova, F.A.; Sadikov, I.I; Salimov, M.I.; Zinov'ev, V.G.

    2006-01-01

    Full text: Gallium is one of the widely used materials in semiconductor and optoelectronics industry. Gallium is used to produce infrared detectors, piezoelectric sensors, high- and low-temperature transistors for space and defense technology. One of the most important requirements for semiconductor materials of gallium compounds is an excessive high purity for layers and films. Information on impurities (type of an impurity, concentration, character of distribution) is important as for better understanding of the physical and chemical processes taking place in formed semiconductor structures and for the 'know-how' of devices on their basis. The object of this work is to develop radiochemical neutron activation technique for analysis of high purity gallium. Irradiation of 0.1 g of gallium sample in neutron flux of 5·10 13 cm -2 s -1 for 5 hours will result in induced activity of more than 10 8 Bq, due to 72 Ga radionuclide, half-life of which is 14.1 hours. Therefore to perform instrumental NAA of gallium long period (10 day) cooling is required, and high sensitive determination of elements producing short- and long-lived radionuclides (T 1/2 72 Ga. We have studied the behavior of gallium in extraction-chromatographic system 'TBP-HCl'. The experiments have shown that higher factor of distribution (D) and capacity on gallium can be achieved when 'TBP-4M HCl' system is used. However more than 10 trace elements have high D and thus they cannot be separated from 72 Ga. To resolve the problem and increase the number of separated trace elements we have used preliminary satisfaction of chromatographic column with tellurium, which has D higher than the most of elements in 'TBP-4M HCl' system and thus suppresses extraction of elements. Distribution profile of gallium along the column and elution curve of 25 trace elements have been measured. Chemical yields of separated elements measured by using radiotracers are more than 93%. On the basis of the carried out researches

  2. A radiochemical technique for the determination of mercury in drinking water

    International Nuclear Information System (INIS)

    Ahmad, S.; Chaudhri, M.S.; Qureshi, I.H.

    1982-01-01

    A radiochemical method for the separation and determination of mercury in drinking water has been developed. The radionuclides of mercury formed after neutron irradiation of the sample were separated by liquid/liquid extraction using PAN and TBA mixture in chloroform from aqueous nitric acid medium. Quantitative extraction of mercury was achieved in a single step and the equilibrium was attained within five minutes. (orig.)

  3. Legality, separation of powers, stability of electoral law: The impact of new voting technologies

    OpenAIRE

    Driza Maurer, Ardita

    2016-01-01

    Legality, separation of powers and stability of electoral law are some of the principles of the European constitutional heritage. They should be respected and implemented throughout the electoral process, including when new voting technologies are used. This paper discusses e-voting specific implementations of the principles or challenges to it. Ongoing and proposed improvements in legislation or practice are pinpointed.

  4. Co-crystallization as a separation technology: controlling product concentrations by co-crystals

    NARCIS (Netherlands)

    Urbanus, J.; Roelands, C.P.M.; Verdoes, D.; Jansens, P.J.; Horst, J.H. ter

    2010-01-01

    Co-crystallization is known as a product formulation technology, but it can also be used as a tool to solve crystallization problems. Product removal by co-crystallization in fermentations is used as a showcase to demonstrate the potential of co-crystallization as a separation technique. In

  5. Technologies for the treatment of source-separated urine in the ...

    African Journals Online (AJOL)

    Technologies for the treatment of source-separated urine in the eThekwini ... This practice can lead to environmental pollution, since urine contains high amounts of ... produces only distilled water and a small amount of sludge as by-products.

  6. The review of separation technology for fission nuclides 90Sr and 137Cs

    International Nuclear Information System (INIS)

    Zhang Huaming; Li Xingliang; Luo Shunzhong; Peng Shuming; Lei Jiarong

    2010-01-01

    The progress of separation technologies for fission nuclides 90 Sr and 137 Cs, including precipitation method, liquid-liquid extraction process and ion exchanging operation, are mainly reviewed. Crown ether (DtBuCH18C6) and calixarene-crown ether (BOBCalixC6) can be highly selective for 90 Sr and 137 Cs respectively in acidic waste; Ionic liquids extraction and supercritical fluid extraction can be applied for separation 90 Sr and 137 Cs from high level waste. Crystalline silicotitiate (CST) and metal sulfide (KMS-1) have highly selectivity for 90 Sr and 137 Cs separately in basic condition. The prospects of disposal technology for high level waste are also discussed in this review. (authors)

  7. Methods for training radiochemical technicians at ORNL

    International Nuclear Information System (INIS)

    Parrott, J.R.; Nicol, R.G.

    1975-01-01

    The training of personnel to carry out radiochemical operations at ORNL is a formidable and recurrent task since repetitive, production-type operations are not involved, and programs are constantly shifting. It is essential that provisions be made for the routine retraining of personnel if they are to make effective contributions on a continuing basis. The present training methods have emerged as a result of thirty years experience in a variety of radiochemical pilot-plant programs. These programs have included operations performed in glove boxes, hot-cell manipulator work handling high-neutron-emitting isotopes, and the entire spectrum of remote solvent extraction operations. Present methods of training and the results obtained are summarized

  8. Automated radiochemical processing for clinical PET

    International Nuclear Information System (INIS)

    Padgett, H.C.; Schmidt, D.G.; Bida, G.T.; Wieland, B.W.; Pekrul, E.; Kingsbury, W.G.

    1991-01-01

    With the recent emergence of positron emission tomography (PET) as a viable clinical tool, there is a need for a convenient, cost-effective source of the positron emitter-labeled radiotracers labeled with carbon-11, nitrogen-13, oxygen-15, and fluorine-18. These short-lived radioisotopes are accelerator produced and thus, require a cyclotron and radiochemistry processing instrumentation that can be operated 3 in a clinical environment by competant technicians. The basic goal is to ensure safety and reliability while setting new standards for economy and ease of operation. The Siemens Radioisotope Delivery System (RDS 112) is a fully automated system dedicated to the production and delivery of positron-emitter labeled precursors and radiochemicals required to support a clinical PET imaging program. Thus, the entire RDS can be thought of as an automated radiochemical processing apparatus

  9. Radiochemical analysis of the Bikini ashes

    Energy Technology Data Exchange (ETDEWEB)

    Ishibashi, M; Shigematsu, T; Ishida, T

    1954-01-01

    The following nuclides were detected in the Bikini ashes by radiochemical procedures: /sup 45/Ca, /sup 89/Sr, /sup 91/Y, /sup 95/Zr, /sup 103/Ru, /sup 144/Pr, and /sup 237/U. The ion-exchange method was used for analysis of contaminated rain water which fell on the Kyoto area on May 16, 1954 from which the presence of /sup 89/Sr, /sup 95/Zr, and /sup 140/Ba, was detected. Rare earths seemed also to be present.

  10. Imaging Scanner Usage in Radiochemical Purity Test

    International Nuclear Information System (INIS)

    Norhafizah Othman; Yahaya Talib; Wan Hamirul Bahrin Wan Kamal

    2011-01-01

    Imaging Scanner model BIOSCAN AR-2000 has been used in the radiochemical purity test for the product of Mo-99/ Tc-99m generator. Result from this test was produced directly where the percentage of pertechnetate was calculated based on width peak area by thin layer chromatography. This paperwork will explain the function, procedure, calibration of the instrument and discussed the advantages compared to the previous method. (author)

  11. Handling of Ammonium Nitrate Mother-Liquid Radiochemical Production - 13089

    International Nuclear Information System (INIS)

    Zherebtsov, Alexander; Dvoeglazov, Konstantine; Volk, Vladimir; Zagumenov, Vladimir; Zverev, Dmitriy; Tinin, Vasiliy; Kozyrev, Anatoly; Shamin, Dladimir; Tvilenev, Konstantin

    2013-01-01

    The aim of the work is to develop a basic technology of decomposition of ammonium nitrate stock solutions produced in radiochemical enterprises engaged in the reprocessing of irradiated nuclear fuel and fabrication of fresh fuel. It was necessary to work out how to conduct a one-step thermal decomposition of ammonium nitrate, select and test the catalysts for this process and to prepare proposals for recycling condensation. Necessary accessories were added to a laboratory equipment installation decomposition of ammonium nitrate. It is tested several types of reducing agents and two types of catalyst to neutralize the nitrogen oxides. It is conducted testing of modes of the process to produce condensation, suitable for use in the conversion of a new technological scheme of production. It is studied the structure of the catalysts before and after their use in a laboratory setting. It is tested the selected catalyst in the optimal range for 48 hours of continuous operation. (authors)

  12. Radiolabeling, quality control and radiochemical purity assessment of 99mTc-HYNIC-TOC

    International Nuclear Information System (INIS)

    Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair

    2009-01-01

    Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 μg of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 μg of SnCl 2 .2H 2 O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 μm, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

  13. Radiolabeling, quality control and radiochemical purity assessment of {sup 99m}Tc-HYNIC-TOC

    Energy Technology Data Exchange (ETDEWEB)

    Melero, Laura T.U.H.; Araujo, Elaine B.; Mengatti, Jair [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2009-07-01

    Somatostatine receptors are widely expressed by several tumors, especially of the neuroendocrine origin. In vivo images of these tumors using radiolabeled somatostatine analogues became a useful clinical tool in oncology. The aim of this work was the radiolabeling of the somatostatine analogue HYNIC-TOC with 99mTc as well as the evaluation of the radiochemical stability and quality control of labeled complex. 99mTc-HYNIC-TOC was produced by labeling conditions using 20 {mu}g of peptide, 20 mg of tricine and 10 mg of EDDA as coligands, 1110 MBq of 99mTc (99Mo-99mTc IPEN-TEC generator) and 15 {mu}g of SnCl{sub 2}.2H{sub 2}O. The reaction proceeds for 10 minutes at boiling water bath. Radiochemical purity of labeled preparation was evaluated by different chromatographic systems: ITLC-SG in methanol:ammonium acetate (1:1); TLC-SG in sodium citrate buffer 0.1 N pH 5.0 and methylethylketone, and HPLC employing column C-18, 5 {mu}m, 4.6 mm x 250 mm, UV (220 nm), radioactivity detectors, 1 mL/minute flow of acetonitrile and trifluoroacetic acid solution 0.1 %. Labeled compound has been found radiochemically stable for 5 hours and radiochemical purity was higher than 90 %. The thin layer chromatographic systems enabled the separation of radiochemical species presented in the labeled mixture as well as HPLC system. The labeling procedure studied resulted in high radiochemical yield and easy preparation. Future works include the preparation of a lyophilized reagent to make feasible the preparation of 99mTc-HYNIC-TOC at nuclear medicine services in order to study the clinical potential of the radiopharmaceutical in diagnostic and staging of neuroendocrine tumors. (author)

  14. Separation Science and Technology. Semiannual progress report, April 1993--September 1993

    International Nuclear Information System (INIS)

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

    1996-01-01

    This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April-September 1993. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Other projects are underway with the objective of developing (1) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process, (2) treatment schemes for liquid wastes stored or being generated at Argonne, (3) a process based on sorbing modified TRUEX solvent on magnetic beads to be used for separation of contaminants from radioactive and hazardous waste streams, and (4) a process that uses low-enriched uranium targets for production of 99 Mo for nuclear medicine uses

  15. Preliminary survey of separations technology applicable to the pretreatment of Hanford tank waste (1992--1993)

    International Nuclear Information System (INIS)

    Lawrence, W.E.; Kurath, D.E.

    1994-04-01

    The US Department of Energy has established the Tank Waste Remediation System (TWRS) to manage and dispose of radioactive wastes stored at the Hanford Site. Within this program are evaluations of pretreatment system alternatives through literature reviews. The information in this report was collected as part of this project at Pacific Northwest Laboratory. A preliminary survey of literature on separations recently entered into the Hanford electronic databases (1992--1993) that have the potential for pretreatment of Hanford tank waste was conducted. Separation processes that can assist in the removal of actinides (uranium, plutonium, americium), lanthanides, barium, 137 Cs, 90 Sr, 129 I, 63 Ni, and 99 Tc were evaluated. Separation processes of interest were identified through literature searches, journal reviews, and participation in separation technology conferences. This report contains brief descriptions of the potential separation processes, the extent and/or selectivity of the separation, the experimental conditions, and observations. Information was collected on both national and international separation studies to provide a global perspective on recent research efforts

  16. Trace determination of uranium and thorium in biological samples by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Benedik, Ljudmila; Repinc, Urska; Byrne, Anthony R.; Stegnar, Peter

    2002-01-01

    Radiochemical neutron activation analysis (RNAA) is an excellent method for determining uranium and thorium; it offers unique possibilities for their ultratrace analysis using selective radiochemical separations. Regarding the favourably sensitive nuclear characteristics of uranium and of thorium with respect to RNAA, but the different half-lives of their induced nuclides, two different approaches were used. In the first approach uranium and thorium were determined separately via 239 U, 239 Np and 233 Pa. In the second approach these elements were 239 239 233 determined simultaneously in a single sample using U and/or Np and Pa. Isolation of induced nuclides was based on separation by extraction and/or anion exchange chromatography. Chemical yields were measured in each sample aliquot using added 235 U, 238 Np and 231 Pa radioisotopic tracers. (author)

  17. 15th radiochemical conference: Booklet of abstracts and conference programme

    International Nuclear Information System (INIS)

    John, J.; Benes, P.; Kucera, J.; Havela, L.; Bartonicek, B.; Vobecky, M.; Krizova, V.; Kopicka, K.; Prasil, Z.

    2006-04-01

    The conference was structured as follows: Opening plenary lectures (6 lectures); Topic 1 - radionuclides in the environment, radioecology (22 verbal presentations (VPs), 23 poster presentations (PPs)); Topic 2 - nuclear analytical methods (22 VPs, 32 PPs); Topic 3 - chemistry of actinide and transactinide elements (8 VPs, 10 PPs); Topic 4 - radiation chemistry (9 VPs, 5 PPs); Topic 5 - production and application of radionuclides (17 VPs, 6 PPs); Topic 6 - separation methods, speciation (21 VPs, 23 PPs); Topic 7 - chemistry of nuclear fuel cycle, radiochemical problems in nuclear waste management (20 VPs, 16 PPs); Topic 8 - nuclear methods in medicine, radiopharmaceuticals, and radiodiagnostics, labelled compounds (8 VPs, 7 PPs); and Panels (2 introductions). (P.A.)

  18. Radiochemical neutron activation analysis of gold in geochemical samples

    International Nuclear Information System (INIS)

    Zilliacus, R.

    1983-01-01

    A fast method for the radiochemical neutron activation analysis of gold in geochemical samples is described. The method is intended for samples having background concentrations of gold. The method is based on the dissolution of samples with hydrofluoric acid and aqua regia followed by the dissolution of the fluorides with boric acid and hydrochloric acid. Gold is then adsorbed on activated carbon by filtrating the solution through a thin carbon layer. The activity measurements are carried out using a Ge(Li)-detector and a multichannel analyzer. The chemical yields of the separation determined by reirradiation vary between 60 and 90%. The detection limit of the method is 0.2 ng/g gold in rock samples. USGS standard rocks and exploration reference materials are analyzed and the results are presented and compared with literature data. (author)

  19. Energy Saving Separations Technologies for the Petroleum Industry: An Industry-University-National Laboratory Research Partnership

    Energy Technology Data Exchange (ETDEWEB)

    Dorgan, John R.; Stewart, Frederick F.; Way, J. Douglas

    2003-03-28

    This project works to develop technologies capable of replacing traditional energy-intensive distillations so that a 20% improvement in energy efficiency can be realized. Consistent with the DOE sponsored report, Technology Roadmap for the Petroleum Industry, the approach undertaken is to develop and implement entirely new technology to replace existing energy intensive practices. The project directly addresses the top priority issue of developing membranes for hydrocarbon separations. The project is organized to rapidly and effectively advance the state-of-the-art in membranes for hydrocarbon separations. The project team includes ChevronTexaco and BP, major industrial petroleum refiners, who will lead the effort by providing matching resources and real world management perspective. Academic expertise in separation sciences and polymer materials found in the Chemical Engineering and Petroleum Refining Department of the Colorado School of Mines is used to invent, develop, and test new membrane materials. Additional expertise and special facilities available at the Idaho National Engineering and Environmental Laboratory (INEEL) are also exploited in order to effectively meet the goals of the project. The proposed project is truly unique in terms of the strength of the team it brings to bear on the development and commercialization of the proposed technologies.

  20. Freeze-drying technology: A separation technique for liquid nuclear materials

    International Nuclear Information System (INIS)

    Musgrave, J.A.; Efurd, D.W.; Banar, J.C.

    1997-01-01

    Freeze-drying technology (FDT) has been around for several decades as a separation technology. Most commonly, FDT is associated with the processing of food, but the largest industrial-scale use of FDT is in the pharmaceutical industry. Through a Cooperative Research and Development Agreement (CRADA) with BOC Edwards Calumatic, we are demonstrating the feasibility of FDT as a waste minimization and pollution prevention technology. This is a novel and innovative application of FDT. In addition, we plan to demonstrate that the freeze-dried residue is an ideal feed material for ceramic stabilization of radioactive waste and excess fissile material. The objective of this work is to demonstrate the feasibility of FDT for the separation of complex radioactive and nonradioactive materials, including liquids, slurries, and sludges containing a wide variety of constituents in which the separation factors are >10 8 . This is the first application of FDT in which the condensate is of primary importance. Our focus is applying this technology to the elimination of radioactive liquid discharges from facilities at Los Alamos National Laboratory (LANL) and within the U.S. Department of Energy complex; however, successful demonstration will lead to nuclear industry-wide applications

  1. Review and assessment of technologies for the separation of cesium from acidic media

    Energy Technology Data Exchange (ETDEWEB)

    Orth, R.J.; Brooks, K.P.; Kurath, D.E.

    1994-09-01

    A preliminary literature survey has been conducted to identify and evaluate methods for the separation of cesium from acidic waste. The most promising solvent extraction, precipitation, and ion exchange methods, along with some of the attributes for each method, are listed. The main criteria used in evaluating the separation methods were as follows: (1) good potential for cesium separation must be demonstrated (i.e., cesium decontamination factors on the order of 50 to 100). (2) Good selectivity for cesium over bulk components must be demonstrated. (3) The method must show promise for evolving into a practical and fairly simple process. (4) The process should be safe to operate. (5) The method must be robust (i.e., capable of separating cesium from various acidic waste types). (6) Secondary waste generation must be minimized. (7) The method must show resistance to radiation damage. The most promising separation methods did not necessarily satisfy all of the above criteria, thus key areas requiring further development are suggested for each method. The report discusses in detail these and other areas requiring further development, as well as alternative solvent extraction, precipitation, ion exchange, and {open_quote}other{close_quote} technologies that, based on current information, show less promise for the separation of cesium from acidic wastes because of significant process limitations. When appropriate, the report recommends areas of future development.

  2. Radiochemical studies on environmental radioactivity in Sudan

    Energy Technology Data Exchange (ETDEWEB)

    Sam, Adam Khatir [Sudan Atomic Energy Commission, Khartoum (Sudan)

    1998-09-01

    Measurements of uranium and thorium isotopes, {sup 226} Ra, {sup 210} Po, {sup 228} Ra, {sup 40} K and fallout radionuclide {sup 137} Cs in soil samples collected from different districts in Sudan, rock phosphate samples collected from the uro and kurun rock phosphate deposits in the eastern part of the Nuba mountains in Western Sudan, and surface marine sediments and marine organisms collected from the sudanese coastal waters of the Red Sea have been made using a high resolution gamma-spectrometry, radiochemical separation and {alpha} spectrometry. The external exposure due to {gamma} radiation from the ground has been calculated. The average exposure was found to be 45.4 {+-} 21.3 nGy/h, corresponding to the annual dose equivalent of 278 {mu}Sv/y. With the exception of some areas, the calculated exposure falls within the global wide range of outdoor radiation exposure given in the UNSCEAR publications. The nation-wide average concentrations of {sup 226} Ra, {sup 238} U, {sup 232} Th, {sup 40} K and {sup 137} Cs determined were 31.6 {+-} 27, 20.1 {+-} 16.4, 19.1 {+-} 8.1, 280.3 {+-} 137.6 and 4.1 {+-} 4.3 Bq/Kg, respectively. This shows that there is little contamination due to fallout radioactivity at survey sites. The exchangeable radium fraction constitutes 19-24% of the total radium content. The data show that {sup 238} U and its decay products are the principal contributors of radioactivity in both phosphate deposits at Uro and Kurun. The equivalent mass concentrations of uranium in the Uro rock phosphate fall within the range that could be economically recovered as the by-product of fertilizer industry. The mean activity concentrations weighted by average agricultural consumption of 300 kg/ha of untreated ground rock fertilizer resulted in an annual distribution of 120.63 Bq Ra/m{sup 2} with Uro rock and 12.97, 0.21 and 4.24 Bq/m{sup 2} respectively, with Kurun rock fertilizer. The external radiation exposure over agricultural areas was estimated 23.41 x 10

  3. Radiochemical studies on environmental radioactivity in Sudan

    International Nuclear Information System (INIS)

    Sam, Adam Khatir

    1998-01-01

    Measurements of uranium and thorium isotopes, 226 Ra, 210 Po, 228 Ra, 40 K and fallout radionuclide 137 Cs in soil samples collected from different districts in Sudan, rock phosphate samples collected from the uro and kurun rock phosphate deposits in the eastern part of the Nuba mountains in Western Sudan, and surface marine sediments and marine organisms collected from the sudanese coastal waters of the Red Sea have been made using a high resolution gamma-spectrometry, radiochemical separation and α spectrometry. The external exposure due to γ radiation from the ground has been calculated. The average exposure was found to be 45.4 ± 21.3 nGy/h, corresponding to the annual dose equivalent of 278 μSv/y. With the exception of some areas, the calculated exposure falls within the global wide range of outdoor radiation exposure given in the UNSCEAR publications. The nation-wide average concentrations of 226 Ra, 238 U, 232 Th, 40 K and 137 Cs determined were 31.6 ± 27, 20.1 ± 16.4, 19.1 ± 8.1, 280.3 ± 137.6 and 4.1 ± 4.3 Bq/Kg, respectively. This shows that there is little contamination due to fallout radioactivity at survey sites. The exchangeable radium fraction constitutes 19-24% of the total radium content. The data show that 238 U and its decay products are the principal contributors of radioactivity in both phosphate deposits at Uro and Kurun. The equivalent mass concentrations of uranium in the Uro rock phosphate fall within the range that could be economically recovered as the by-product of fertilizer industry. The mean activity concentrations weighted by average agricultural consumption of 300 kg/ha of untreated ground rock fertilizer resulted in an annual distribution of 120.63 Bq Ra/m 2 with Uro rock and 12.97, 0.21 and 4.24 Bq/m 2 respectively, with Kurun rock fertilizer. The external radiation exposure over agricultural areas was estimated 23.41 x 10 -9 Gy/h and 2.59 x 10 -9 Gy/h at 1 m above ground level for Uro and Kurun rock phosphate fertilizers

  4. Interactions of microorganisms with rare earth ions and their utilization for separation and environmental technology.

    Science.gov (United States)

    Moriwaki, Hiroshi; Yamamoto, Hiroki

    2013-01-01

    In recent years, rare earth elements (REEs) have been widely used in various modern technological devices and the global demand for REE has been increasing. The increased demand for REEs has led to environmental exposure or water pollution from rare earth metal mines and various commercial products. Therefore, the development of a safe technology for the separation and adsorption of REEs is very important from the perspective of green chemistry and environmental pollution. In this review, the application and mechanisms of microorganisms for the removal and extraction of REEs from aqueous solutions are described. In addition, the advantages in using microorganisms for REE adsorption and future studies on this topic are discussed.

  5. Tail gas treatment of SEWGS technology. Literature review on CO2 and H2S separation

    Energy Technology Data Exchange (ETDEWEB)

    Fabbri, E.N.; Van Dijk, H.A.J. [ECN Biomass and Energy Efficiency, Petten (Netherlands)

    2011-12-15

    This literature review is the result of an investigation of the most important way to remove sulphur for the last decades. We will discuss Claus and Claus tail gas process options to solve the problem. Next to solutions which come from membranes, direct oxidation catalysis, from acid gas removal technology, sorbent technology, and liquid oxidation. Each field will be described and explained to understand in which way it could be suitable to separate CO2 and H2S and reach our goals with regard to CO2 transport and storage conditions. Finally, the target of this work will be to propose some interesting and promising solutions in view of future experiments.

  6. Pyrochemical separations technologies envisioned for the U.S. accelerator transmutation of waste system

    International Nuclear Information System (INIS)

    Laidler, J. J.

    2000-01-01

    A program has been initiated for the purpose of developing the chemical separations technologies necessary to support a large Accelerator Transmutation of Waste (ATW) system capable of dealing with the projected inventory of spent fuel from the commercial nuclear power stations in the United States. The baseline process selected combines aqueous and pyrochemical processes to enable the efficient separation of uranium, technetium, iodine, and the transuranic elements from LWR spent fuel. The diversity of processing methods was chosen for both technical and economic factors. A six-year technology evaluation and development program is foreseen, by the end of which an informed decision can be made on proceeding with demonstration of the ATW system

  7. Airborne Separation Assurance and Traffic Management: Research of Concepts and Technology

    Science.gov (United States)

    Ballin, Mark G.; Wing, David J.; Hughes, Monica F.; Conway, Sheila R.

    1999-01-01

    To support the need for increased flexibility and capacity in the future National Airspace System, NASA is pursuing an approach that distributes air traffic separation and management tasks to both airborne and ground-based systems. Details of the distributed operations and the benefits and technical challenges of such a system are discussed. Technology requirements and research issues are outlined, and NASA s approach for establishing concept feasibility, which includes development of the airborne automation necessary to support the concept, is described.

  8. Radiochemical determination of zirconium by inductively coupled plasma mass spectrometry (ICPMS)

    International Nuclear Information System (INIS)

    Oliveira, Thiago C.; Oliveira, Arno Heeren de

    2013-01-01

    The zirconium isotope 93 Zr is a long-lived pure β-particle-emitting radionuclide thus occurring as one of the radionuclides found in nuclear reactors. It's produced from 235 U fission and from 92 Zr neutron activation. Due to its long half-life, 93 Zr is one of the interest radionuclides for assessment studies performance of waste storage or disposal. Measurement of 93 Zr is difficult owing to its trace level concentration and its low activity in nuclear wastes and further because its certified standards are not frequently available. The aim of this work was to apply a selective radiochemical separation methodology for 93 Zr determination in nuclear waste and analyze it by Inductively Coupled Plasma Mass Spectrometry (ICPMS). To set up the zirconium radiochemical separation procedure, a zirconium tracer solution was used in order to follow the zirconium behavior during the radiochemical separation. A tracer solution containing the main interferences, Ba, Co, Eu, Fe, Mn, Nb, Ni, Sr, and Y was used in order to verify the decontamination factor during separation process. The limit of detection of 0,039 ppb was obtained for zirconium standard solutions by ICPMS. Then, the protocol will be applied to low level waste (LLW) and intermediate level waste (ILW) from nuclear power plants. (author)

  9. Development of robotic plasma radiochemical assays for positron emission tomography

    International Nuclear Information System (INIS)

    Alexoff, D.L.; Shea, C.; Fowler, J.S.; Gatley, S.J.; Schlyer, D.J.

    1995-01-01

    A commercial laboratory robot system (Zymate PyTechnology II Laboratory Automation System; Zymark Corporation, Hopkinton, MA) was interfaced to standard and custom laboratory equipment and programmed to perform rapid radiochemical analyses for quantitative PET studies. A Zymark XP robot arm was used to carry out the determination of unchanged (parent) radiotracer in plasma using only solid phase extraction methods. Robotic throughput for the assay of parent radiotracer in plasma is 4--6 samples/hour depending on the radiotracer. Robotic assays of parent compound in plasma were validated for the radiotracers [ 11 C]Benztropine, [ 11 C]cocaine, [ 11 C]clorgyline, [ 11 C]deprenyl, [ 11 C]methadone, [ 11 C]methylphenidate, [ 11 C]raclorpride, and [ 11 C]SR46349B. A simple robot-assisted methods development strategy has been implemented to facilitate the automation of plasma assays of new radiotracers

  10. Safety decommissioning regulations of radiochemical objects - the problem, requires urgent decision

    International Nuclear Information System (INIS)

    Rovnyj, S.I.; Arsent'eva, N.V.; Emel'yanov, N.M.; Kolesnikov, V.N.

    2001-01-01

    The necessity of planning and pursuance of the measures on decommissioning of radiochemical industry is discussed. Technological processes were stopped more than in 30 buildings and constructions of the PO Mayak. The characteristics of the technological buildings to be decommissioned were treated in the context of building peculiarities, function, character and level of contamination. An acceptable variant for reactor decommissioning invites development of the standard-legal aspects [ru

  11. Diaphragms obtained by radiochemical grafting in PTFE

    International Nuclear Information System (INIS)

    Nenner, T.; Fahrasmane, A.

    1984-01-01

    Diaphragms for alkaline water electrolysis are prepared by radiochemical grafting of PTFE fabric with styrene, which is later on sulfonated, or with acrylic acid. The diaphragms obtained are mechanically resistant to potash at temperatures up to 200 0 C, but show some degrafting, which limits the lifetime. The sulfonated styrene group has been found to be more stable in electrolysis than the acrylic acid. In both cases, the incorporation of a cross-linking agent like divinyl benzene improves the lifetime of the diaphragms. Electrolysis during 500 hours at 120 0 C and 10 kAm 2 could be performed. (author)

  12. Separation of the metallic and non-metallic fraction from printed circuit boards employing green technology

    Energy Technology Data Exchange (ETDEWEB)

    Estrada-Ruiz, R.H., E-mail: rhestrada@itsaltillo.edu.mx; Flores-Campos, R., E-mail: rcampos@itsaltillo.edu.mx; Gámez-Altamirano, H.A., E-mail: hgamez@itsaltillo.edu.mx; Velarde-Sánchez, E.J., E-mail: ejvelarde@itsaltillo.edu.mx

    2016-07-05

    Highlights: • Small sizes of particles are required in order to separate the different fractions. • Inverse flotation process is an efficient green technology to separate fractions. • Superficial air velocity is the main variable in the inverse flotation process. • Inverse flotation is a green process because the pulṕs pH is 7.0 during the test. - Abstract: The generation of electrical and electronic waste is increasing day by day; recycling is attractive because of the metallic fraction containing these. Nevertheless, conventional techniques are highly polluting. The comminution of the printed circuit boards followed by an inverse flotation process is a clean technique that allows one to separate the metallic fraction from the non-metallic fraction. It was found that particle size and superficial air velocity are the main variables in the separation of the different fractions. In this way an efficient separation is achieved by avoiding the environmental contamination coupled with the possible utilization of the different fractions obtained.

  13. The Investigation of Separability of Particles Smaller Than 5 mm by Eddy Current Separation Technology. Part I : Rotating Type Eddy Current Separators

    NARCIS (Netherlands)

    Zhang, S.; Rem, P.C.; Forssberg, E.

    1999-01-01

    Owing to the growing emergence of the end-of-life electrical and electronic products with complex material structures and an ever-diminishing particle size of the valuable metals involved, development of eddy current separators (ECS) has been targeting selective separation of small non-ferrous metal

  14. Separations Science and Technology, Semiannual progress report, October 1991--March 1992

    International Nuclear Information System (INIS)

    Vandegrift, G.F.; Betts, S.; Chamberlain, D.B.

    1994-01-01

    This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period October 1991--March 1992. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Two other projects are underway with the objective of developing (1) a membrane-assisted solvent extraction method for treating natural and process waters contaminated by volatile organic compounds and (2) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process

  15. Carbon dioxide separation from flue gases: a technological review emphasizing reduction in greenhouse gas emissions.

    Science.gov (United States)

    Songolzadeh, Mohammad; Soleimani, Mansooreh; Takht Ravanchi, Maryam; Songolzadeh, Reza

    2014-01-01

    Increasing concentrations of greenhouse gases (GHGs) such as CO2 in the atmosphere is a global warming. Human activities are a major cause of increased CO2 concentration in atmosphere, as in recent decade, two-third of greenhouse effect was caused by human activities. Carbon capture and storage (CCS) is a major strategy that can be used to reduce GHGs emission. There are three methods for CCS: pre-combustion capture, oxy-fuel process, and post-combustion capture. Among them, post-combustion capture is the most important one because it offers flexibility and it can be easily added to the operational units. Various technologies are used for CO2 capture, some of them include: absorption, adsorption, cryogenic distillation, and membrane separation. In this paper, various technologies for post-combustion are compared and the best condition for using each technology is identified.

  16. Carbon Dioxide Separation from Flue Gases: A Technological Review Emphasizing Reduction in Greenhouse Gas Emissions

    Directory of Open Access Journals (Sweden)

    Mohammad Songolzadeh

    2014-01-01

    Full Text Available Increasing concentrations of greenhouse gases (GHGs such as CO2 in the atmosphere is a global warming. Human activities are a major cause of increased CO2 concentration in atmosphere, as in recent decade, two-third of greenhouse effect was caused by human activities. Carbon capture and storage (CCS is a major strategy that can be used to reduce GHGs emission. There are three methods for CCS: pre-combustion capture, oxy-fuel process, and post-combustion capture. Among them, post-combustion capture is the most important one because it offers flexibility and it can be easily added to the operational units. Various technologies are used for CO2 capture, some of them include: absorption, adsorption, cryogenic distillation, and membrane separation. In this paper, various technologies for post-combustion are compared and the best condition for using each technology is identified.

  17. Separation science and technology. Semiannual progress report, April 1992--September 1992

    International Nuclear Information System (INIS)

    Vandegrift, G.F.; Betts, S.; Bowers, D.L.

    1994-09-01

    This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April-September 1992. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Two other projects are underway with the objective of developing (1) a membrane-assisted solvent extraction method for treating natural and process waters contaminated by volatile organic compounds and (2) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process

  18. Analysis of the radiochemical purity of 18F-FDG by HPLC

    International Nuclear Information System (INIS)

    Chen Liguang; Tang Anwu; He Shanzhen; Chen Yulong

    2001-01-01

    The radiochemical purity (RCP) of 18 F-FDG is analyzed by HPLC. Eighty-five percent acetonitrile is used as the eluting solution. Carbon hydrate column is used as separation column. The t R of 18 F - is 6.50 min and 18 F-FDG is 9.00 min. HPLC take less time and has higher sensitivity than TLC for the same sample at the same time. So HPLC excels TLC in analyzing RCP of 18 F-FDG

  19. Determination of heavy metal pollutants such as Hg, Zn, Se, Cd, and Cu in aquatic environment of Thana Creek by radiochemical thermal neutron activation analysis

    International Nuclear Information System (INIS)

    khan, S.Z.; Shah, P.K.; Ramani Rao, V.; Turel, Z.r.; Haldar, B.C.

    1984-01-01

    A rapid method has been developed for the radiochemical separation of Cu, As, Se, Hg, and Zn from thermal neutron irradiated environmental samples. The concentration of the elements in the environmental samples has been ascertained by radiochemical neutron activation analysis. The accuracy, precision and sensitivity of the method has been determined. The results of the analysis indicates the location of maximum pollution of the aquatic environment and the extent of pollution in the 5 locations of Thana Creek. 1 reference, 3 tables

  20. Separation Science and Technology. Semiannual progress report, April 1993--September 1993

    Energy Technology Data Exchange (ETDEWEB)

    Vandegrift, G.F.; Chamberlain, D.B.; Conner, C. [and others

    1996-01-01

    This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April-September 1993. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Other projects are underway with the objective of developing (1) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process, (2) treatment schemes for liquid wastes stored or being generated at Argonne, (3) a process based on sorbing modified TRUEX solvent on magnetic beads to be used for separation of contaminants from radioactive and hazardous waste streams, and (4) a process that uses low-enriched uranium targets for production of {sup 99}Mo for nuclear medicine uses.

  1. Separation science and technology. Semiannual progress report, October 1993 - March 1994

    International Nuclear Information System (INIS)

    Vandegrift, G.F.; Aase, S.B.; Buchholz, B.

    1997-12-01

    This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory (ANL), in the period October 1993-March 1994. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Other projects are underway with the objective of developing (1) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process, (2) treatment schemes for liquid wastes stored are being generated at ANL, (3) a process based on sorbing modified TRUEX solvent on magnetic beads to be used for separation of contaminants from radioactive and hazardous waste streams, and (4) a process that uses low-enriched uranium targets for production of 99 Mo for nuclear medicine uses

  2. Spectrophotometric determination of uranium by previous extraction chromatography separation in polimetalic mineral, phosphorites and technological licours

    International Nuclear Information System (INIS)

    Moreno Bermudez, J.; Cabrera Quevedo, C.; Alfonso Mendez, L.; Rodriguez Aguilera, M.

    1994-01-01

    The development of an analytical procedure for spectrophotometric determination of uranium in polimetalic mineral, phosphorites and technological licours is described. The method is based on the previous separation of interfering elements by extraction chromatography and on spectrophotometric determination of uranium (IV) with arsenazo III in concentrated hydrochloric acid. Tributyl phosphate impregnate on politetrafluoroethylene is used as stationary phase and 5.5 M nitric acid is used as movie phase. The influence of matrix-component elements was studies. The development procedure was applied to real samples, being the results compared with those obtained by other well established analytical methods like gamma-spectrometry, laser fluorimetric, spectrophotometry previous uranium separation by liquid liquid extraction and anion exchange. The reproducibility is evaluated and the detection limited has been established for each studied matrix. A procedure for correcting the thorium interference has been developed for samples with a Th/ 3U8O higher than 0.2

  3. Development of a radiochemical neutron activation analysis procedure for determination of rhenium in biological and environmental samples at ultratrace level

    Czech Academy of Sciences Publication Activity Database

    Kučera, Jan; Byrne, A. R.; Mizera, Jiří; Lučaníková, M.; Řanda, Zdeněk

    2006-01-01

    Roč. 269, č. 2 (2006), s. 251-257 ISSN 0236-5731 R&D Projects: GA ČR(CZ) GA203/04/0943 Institutional research plan: CEZ:AV0Z10480505 Keywords : radiochemical neutron activation analysis * rhenium * biological and environmental samples Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 0.509, year: 2006

  4. LLNL medical and industrial laser isotope separation: large volume, low cost production through advanced laser technologies

    International Nuclear Information System (INIS)

    Comaskey, B.; Scheibner, K. F.; Shaw, M.; Wilder, J.

    1998-01-01

    The goal of this LDRD project was to demonstrate the technical and economical feasibility of applying laser isotope separation technology to the commercial enrichment (>lkg/y) of stable isotopes. A successful demonstration would well position the laboratory to make a credible case for the creation of an ongoing medical and industrial isotope production and development program at LLNL. Such a program would establish LLNL as a center for advanced medical isotope production, successfully leveraging previous LLNL Research and Development hardware, facilities, and knowledge

  5. Improvements on heavy water separation technology by isotopic water-hydrogen sulfide exchange

    International Nuclear Information System (INIS)

    Peculea, M.

    1987-01-01

    A series of possible variance is presented for the heavy water separation technology by isotopic H 2 O-H 2 S exchange at dual temperatures. The critical study of these variants, which are considered as characteristic quantities for the isotopes transport (production) and the extraction level is related to a dual temperature plant fed by liquid and cold column, which is the up-to-date technology employed in all heavy water production plants as variants of following plants are studied: dual temperature plant with double feeding; dual-temperature plant with equilibrium column (booster); dual-temperature-dual-pressure plant. Attention is paid to the variant with equilibration column (booster), executed and tested at the State Committee for Nuclear Energy and to the dual-temperature-dual pressure plant which presents the highest efficiency. (author)

  6. Mixing and sampling tests for Radiochemical Plant

    International Nuclear Information System (INIS)

    Ehinger, M.N.; Marfin, H.R.; Hunt, B.

    1999-01-01

    The paper describes results and test procedures used to evaluate uncertainly and basis effects introduced by the sampler systems of a radiochemical plant, and similar parameters associated with mixing. This report will concentrate on experiences at the Barnwell Nuclear Fuels Plant. Mixing and sampling tests can be conducted to establish the statistical parameters for those activities related to overall measurement uncertainties. Density measurements by state-of-the art, commercially availability equipment is the key to conducting those tests. Experience in the U.S. suggests the statistical contribution of mixing and sampling can be controlled to less than 0.01 % and with new equipment and new tests in operating facilities might be controlled to better accuracy [ru

  7. Standardization of equations for radiochemical calculations

    International Nuclear Information System (INIS)

    Danahy, R.J.; Dugan, T.A.; Tomlinson, F.K.; Jones, H.W.

    1994-01-01

    In mid 1993, the Fernald Environmental Restoration Management Corporation (FERMCO), with USEPA approval implemented a project quality assurance plan containing performance-based specifications for radiochemical sample analyses conducted in support of the Fernald site remediation activities. FERMCO's initial approach to acquiring performance-based radioanalytical services was to provide limited guidance regarding equations for computation of the quantities required in each analysis report. It became evident that there was a significant divergence of opinion on how to compute some very basic radiochemical quantities. The use of a standardized set of equations was needed in order to ensure comparability of data from different laboratories. In a remediation project of this magnitude, use of multiple laboratories is a virtual necessity. Consequently comparability of data becomes an extremely important issue. A critical issue in the Remedial Investigation/Feasibility Study (RI/FS) phase of the dean up project is to avoid the occurrence of excessive false positive sample results. Such results could lead to unnecessary clean up and significant additional cost. This paper describes the specific formulas FERMCO is currently using to define such quantities as net sample count rate, sample radionuclide concentration, radiometric tracer and gravimetric carrier recovery. Equations have also been produced to define the uncertainty in each of the above quantities. Equations for the Total Propagated Uncertainty (TPU) and for a sample-specific Minimum Detectable Concentration (MDC) have also been specified. Generalized equations have been reformulated to address the specific conditions which apply to the analysis of FERMCO samples. In particular, FERMCO requires results which have been corrected for the radioactivity in the blank while in other instances, sample results without blank correction are required

  8. Advanced Acid Gas Separation Technology for the Utilization of Low Rank Coals

    Energy Technology Data Exchange (ETDEWEB)

    Kloosterman, Jeff

    2012-12-31

    Air Products has developed a potentially ground-breaking technology – Sour Pressure Swing Adsorption (PSA) – to replace the solvent-based acid gas removal (AGR) systems currently employed to separate sulfur containing species, along with CO{sub 2} and other impurities, from gasifier syngas streams. The Sour PSA technology is based on adsorption processes that utilize pressure swing or temperature swing regeneration methods. Sour PSA technology has already been shown with higher rank coals to provide a significant reduction in the cost of CO{sub 2} capture for power generation, which should translate to a reduction in cost of electricity (COE), compared to baseline CO{sub 2} capture plant design. The objective of this project is to test the performance and capability of the adsorbents in handling tar and other impurities using a gaseous mixture generated from the gasification of lower rank, lignite coal. The results of this testing are used to generate a high-level pilot process design, and to prepare a techno-economic assessment evaluating the applicability of the technology to plants utilizing these coals.

  9. Membrane Materials and Technology for Xylene Isomers Separation and Isomerization via Pervaporation

    KAUST Repository

    Bilaus, Rakan

    2014-11-01

    P-xylene is one of the highly influential commodities in the petrochemical industry. It is used to make 90% of the world’s third largest plastic production, polyethylene terephthalate (PET). With a continuously increasing demand, the current technology’s high energy intensity has become a growing concern. Membrane separation technology is a potential low-energy alternative. Polymeric membranes were investigated in a pervaporation experiment to separate xylene isomers. Polymers of intrinsic microporosity (PIMs) as well as polyimides (PIM-PI), including thermally cross-linked PIM-1, PIM-6FDA-OH and thermally-rearranged PIM-6FDA-OH were investigated as potential candidates. Although they exhibited extremely high permeability to xylenes, selectivity towards p-xylene was poor. This was attributed to the polymers low chemical resistance which was apparent in their strong tendency to swell in xylenes. Consequently, a perfluoro-polymer, Teflon AF 2400, with a high chemical resistance was tested, which resulted in a slightly improved selectivity. A super acid sulfonated perfluoro-polymer (Nafion-H) was used as reactive membrane for xylenes isomerization. The membrane exhibited high catalytic activity, resulting in 19.5% p-xylene yield at 75ᵒC compared to 20% p-xylene yield at 450ᵒC in commercial fixed bed reactors. Nafion-H membrane outperforms the commercial technology with significant energy savings.

  10. Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B., E-mail: rpgm@cdtn.br, E-mail: reisas@cdtn.br, E-mail: gfk@cdtn.br, E-mail: esct@cdtn.br, E-mail: tco@cdtn.br, E-mail: ama@cdtn.br, E-mail: francom@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, {sup 3}H, {sup 14}C, {sup 55}Fe, {sup 59}Ni, {sup 63}Ni, {sup 90}Sr, {sup 93}Zr, {sup 94}Nb, {sup 99}Tc, {sup 129}I, {sup 235}U, {sup 238}U, {sup 238}Pu, {sup 239}+{sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 242}Cm e {sup 243}+{sup 244}Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

  11. Procedural and developmental aspects of a multielement automatic radiochemical machine, applied to neutron irradiated biomedical samples

    International Nuclear Information System (INIS)

    Iyengar, G.V.

    1976-06-01

    This report is intended to serve as a practical guide, elaborately describing the working details and some developmental work connected with an automatic multielement radiochemical machine based on thermal neutron activation analysis using ion exchange and partition chromatography. Some of the practical aspects and personal observations after much experience with this versatile multielement method, applied to investigate the elemental composition of different biomedical matrices, are summarized. Standard reference materials are analyzed, and the data are presented with a set of gamma-spectra obtained before and after chemical separation into convenient groups suitable for gamma spectroscopy. The samples analyzed included various human and animal tissues, body fluids, IAEA biological standard reference materials, and samples from the WHO/IAEA project on 'Trace elements in relation to cardiovascular diseases'. Simplified modifications of the radiochemical processing, suitable for fast and routine analysis of clinical samples have also been discussed. (orig.) [de

  12. Radiochemical neutron activation analysis for trace elements of basic ingredients of pan

    International Nuclear Information System (INIS)

    Zaidi, J.H.; Arif, M.; Fatima, I; Qureshi, I.H.

    2002-01-01

    Extensive use of pan, by one-tenth of world's population, entails the evaluation of trace element contents in its ingredients. Radiochemical neutron activation analysis (RNAA) was developed and successfully employed to determine the concentration of 36 trace elements (essential, toxic and nonessential) in its four basic ingredients, leaf of betel pepper, betel nut, catechu and lime. The radiochemical separation methodology has significantly improved the detection limits of most of these elements due to suppression of Compton background. Base-line values of certain toxic and essential elements in these ingredients is provided. The daily intake of essential and toxic elements through pan was estimated and compared with the recommended values. The cumulative intake of Mn is four times higher than the recommended value and that of toxic elements is well below the tolerance limits. (author)

  13. RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

    Energy Technology Data Exchange (ETDEWEB)

    Sidhu, R. [Inst. for Energy Technology (Norway)

    2006-04-15

    An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

  14. RADCHEM - Radiochemical procedures for the determination of Sr, U, Pu, Am and Cm

    International Nuclear Information System (INIS)

    Sidhu, R.

    2006-04-01

    An accurate determination of radionuclides from various sources in the environment is essential for assessment of the potential hazards and suitable countermeasures both in case of accidents, authorised release and routine surveillance. Reliable radiochemical separation and detection techniques are needed for accurate determination of alpha and beta emitters. Rapid analytical methods are needed in case of an accident for early decision-making. The objective of this project has been to compare and evaluate radiochemical procedures used at Nordic laboratories for the determination of strontium, uranium, plutonium, americium and curium. To gather detailed information on the procedures in use, a questionnaire regarding various aspects of radionuclide determination was developed and distributed to all (sixteen) relevant laboratories in the Nordic countries. The response and the procedures used by each laboratory were then discussed between those who answered the questionnaire. This report summaries the findings and gives recommendation on suitable practice. (au)

  15. Reprocessing of spent nuclear fuel, Annex 2: Chemical-technology study of the modified 'Purex' process Chemical and radiochemical control analyses; Prerada isluzenog nuklearnog goriva, Prilog 2: Hemijsko tehnolosko ispitivanje modifikovanog 'purex' procesa

    Energy Technology Data Exchange (ETDEWEB)

    Gal, I [Institute of Nuclear Sciences Boris Kidric, Laboratorija za hemiju visoke aktivnosti, Vinca, Beograd (Serbia and Montenegro)

    1964-12-15

    The objective of this task was testing of the modified purex process in the constructed separation cell, and verification of the reliability and efficiency of the process. Extractors used were 1BX, 1BS and 1C. testing was done with syntetic solutions.

  16. Lamination technology for separation of solid wastes; La tecnologia de la Laminacion para separacion de residuos solidos compuestos

    Energy Technology Data Exchange (ETDEWEB)

    Rocas, J.

    1998-07-01

    The lamination technology has been developed, and introduces a form of separation of solid wastes totally new in its concept and development. No longer will be a problem the economic and ecological efficient separation of wastes like tetra-brick, compound of metals and plastics, aluminum scum, electric or electronic wastes and many other. (Author)

  17. Proceedings of the Tripartite Seminar on Nuclear Material Accounting and Control at Radiochemical Plants; Trudy trekhstoronnego seminara Uchet i kontrol' yadernykh materialov na radiokhimicheskikh ustanovkakh

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    The problems of creation and operation of nuclear materials (NM) control and accounting systems and their components at radiochemical plants were discussed in seminar during November 2-6 of 1998. There were 63 Russian and 25 foreign participants in seminar. The seminar programme includes following sessions and articles: the aspects of State NM control and accountancy; NM control and accounting in radiochemical plants and at separate stages of reprocessing of spent nuclear fuel and irradiated fuel elements of commercial reactors; NM control and accountancy in storage facilities of radiochemical plants; NM control and accounting computerization, material balance assessment, preparation of reports; qualitative and quantitative measurements in NM control and accounting at radiochemical plants destructive analysis techniques.

  18. The integration of innovative technologies into a physical-separation-based soil washing system

    International Nuclear Information System (INIS)

    Krstich, M.A.

    1995-01-01

    An innovative system's approach to the treatment of soils at the Fernald Environmental Management Project (FEMP) has been proposed to effectively and cost competitively treat a significant mass of soil. The use of an integrated soil treatment system to decontaminate FEMP soils is a unique application of the soil washing technology. Due to the unfavorable soil particle size distribution and the ubiquitous distribution of uranium among these particle size fractions, conventional soil washing processes commonly used on predominantly sandy soils alone may not achieve the desirable waste minimization level without the inclusion of innovative technologies. This objective of this paper is to briefly describe the physical separation and chemical extraction process commonly used in soil washing operation and to present the baseline soil washing approach used on FEMP soils. Noting the successful and not-so-successful processes within the soil washing operation at the FEMP, a proposed innovative system's approach to treating FEMP soils will be described. This system's approach will integrate a conventional soil washing operation with proposed innovative technologies

  19. Development of Ultrafiltration Membrane-Separation Technology for Energy-Efficient Water Treatment and Desalination Process

    Energy Technology Data Exchange (ETDEWEB)

    Yim, Woosoon [Univ. of Nevada, Las Vegas, NV (United States); Bae, Chulsung [Rensselaer Polytechnic Inst., Troy, NY (United States)

    2016-10-28

    The growing scarcity of fresh water is a major political and economic challenge in the 21st century. Compared to thermal-based distillation technique of water production, pressure driven membrane-based water purification process, such as ultrafiltration (UF), nanofiltration (NF) and reverse osmosis (RO), can offer more energy-efficient and environmentally friendly solution to clean water production. Potential applications also include removal of hazardous chemicals (i.e., arsenic, pesticides, organics) from water. Although those membrane-separation technologies have been used to produce drinking water from seawater (desalination) and non-traditional water (i.e., municipal wastewater and brackish groundwater) over the last decades, they still have problems in order to be applied in large-scale operations. Currently, a major huddle of membrane-based water purification technology for large-scale commercialization is membrane fouling and its resulting increases in pressure and energy cost of filtration process. Membrane cleaning methods, which can restore the membrane properties to some degree, usually cause irreversible damage to the membranes. Considering that electricity for creating of pressure constitutes a majority of cost (~50%) in membrane-based water purification process, the development of new nano-porous membranes that are more resistant to degradation and less subject to fouling is highly desired. Styrene-ethylene/butylene-styrene (SEBS) block copolymer is one of the best known block copolymers that induces well defined morphologies. Due to the polarity difference of aromatic styrene unit and saturated ethylene/butylene unit, these two polymer chains self-assemble each other and form different phase-separated morphologies depending on the ratios of two polymer chain lengths. Because the surface of SEBS is hydrophobic which easily causes fouling of membrane, incorporation of ionic group (e,g, sulfonate) to the polymer is necessary to reduces fouling

  20. Radiochemical search for neutron-rich isotopes of element 107

    International Nuclear Information System (INIS)

    Schaedel, M.

    1987-01-01

    Recent mass calculations have indicated that there is a region of deformed nuclei around neutron number N=162 that is especially stable against spontaneous fission. Barrier heights of about 5 MeV for Z = 107 nuclides can be extrapolated. To search for new, neutron-rich isotopes of element 107 in radiochemical experiments with 254 Es as a target an on-line chemical separation of element 107 (EKA-Rhenium), especially from the actinide elements is needed. An on-line gas-phase chemistry was developed with the homolog Re based on the volatility of the oxide which is transported in an O 2 containing atmosphere along a temperature gradient in a quartz tube and is condensed onto a thin Ta coated Ni-foil. The authors applied this technique in two series of experiments with their rotating wheel on-line gas-phase chemistry apparatus at the 88-inch cyclotron where they irradiated 254 Es as a target with 93 MeV and 96 MeV 16 O ions to search for 266 107. The assignment of the observed alpha events between 8 and 9 MeV to possibly (1) non actinide contaminants like 212 Po, (2) known isotopes of heavy elements like 261 105, or (3) a new isotope will be discussed

  1. A uranium enrichment facility safeguards technology based on the separation nozzle process

    International Nuclear Information System (INIS)

    Bahm, W.; Weppner, J.; Didier, H.J.

    1979-01-01

    Under the Trilateral Agreement between Brazil, the Federal Republic of Germany and the IAEA an enrichment plant operating on the basis of the separation nozzle process, will be safeguarded under INFCIRC/66/Rev.2. For nuclear materials balancing purposes the plant has been subdivided into 17 key measuring points to assess the nuclear material flow and the nuclear material inventory. Preliminary studies have indicated that the balancing accuracy required for safeguards purposes cannot be achieved by only using the foreseen in-plant measuring systems, since considerable quantities of enriched uranium cannot be covered in this way. This fraction will merely be estimated by the operator and thus cannot be verified by the inspection authorities. The plant components, whose inventories could not be verified in the first estimate of the balancing accuracy referred to above by means of the in-plant measuring systems, also include the low-temperature separators of the cascade shoulder and the product. Assessing and verifying the inventories of these key measuring points is particularly important because of the enrichment (some 3% 235 U for the product) and the relatively large inventory and, hence, the considerable contribution to the balancing inaccuracy. An estimate of the balancing inaccuracy on the basis of the measuring uncertainties to be expected in the light of the present status of technology indicated values between 0.2 and 0.3% relative to the feed flow with semi-annual inventory-taking. However, this is based on the condition that the experiments planned to determine the inventories of cryogenic separators confirm the measuring uncertainties underlying the calculation

  2. Separation technologies for the treatment of Idaho National Engineering Laboratory wastes

    Energy Technology Data Exchange (ETDEWEB)

    Todd, T.A. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1997-10-01

    Currently about 6.8 million L of acidic, radioactive liquid waste that is not amenable to calcination, and about 3800 m{sup 3} of calcine exist at the ICPP. Legal drivers (court orders) and agreements between the state of Idaho, the U.S. Navy, and DOE exist that obligate INEL to develop, demonstrate, and implement technologies for treatment and interim storage of the radioactive liquid and calcine wastes. Per these agreements, all tank waste must be removed from the underground liquid storage tanks by the year 2012, and high-level radioactive waste must be treated and removed from INEL by 2035. Separation of the radionuclides from the wastes, followed by immobilization of the high-activity and low-activity fractions in glass and grout, respectively, is the approach preferred by INEL. Technologies to remove actinides (U, Np, Pu, and Am), Cs, Sr, and possibly Tc from highly acidic solutions are required to process INEL wastes. Decontamination of the wastes to NRC Class A low-level waste (LLW) is planned. Separation and isolation of Resource Conservation and Recovery Act (RCRA) metals (Hg, Pb, Cd, and Cr) from the highly radioactive waste streams may also be required. Remediation efforts will begin in FY 1997 to remove volatile organic compounds (VOCs) and radionuclides (Cs and Sr) from groundwater located at the Test Area North facility at INEL. A plume of VOCs and radionuclides has spread from the former TSF-05 injection well, and a Comprehensive Environmental Response, Conservation, and Liability Act (CERCLA) remediation action is under way. A Record of Decision was signed in August 1995 that commits INEL to remediate the plume from TSF-05. Removal of Sr and Cs from the groundwater using commercially available ion-exchange resins has been unsuccessful at meeting maximum contaminant levels, which are 119 pCi/L and 8 pCi/L for Cs and Sr, respectively. Cesium and Sr are the major contaminants that must be removed from the groundwater.

  3. Rapid Radiochemical Analyses in Support of Fukushima Nuclear Accident - 13196

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, Sherrod L.; Culligan, Brian K.; Hutchison, Jay B. [Savannah River National Laboratory, Building 735-B, Aiken, SC 29808 (United States)

    2013-07-01

    precipitations, followed by Sr-Resin separation and gas flow proportional counting. To achieve a lower detection limit for analysis of some of the Japanese soil samples, a 10 gram aliquot of soil was taken, acid-leached and processed with similar preconcentration chemistry. The MDA using this approach was ∼0.03 pCi/g (1.1 mBq/g)/, which is less than the 0.05-0.10 pCi/g {sup 90}Sr levels found in soil as a result of global fallout. The chemical yields observed for the Japanese soil samples was typically 75-80% and the laboratory control sample (LCS) and matrix spike (MS) results looked very good for this work Individual QC results were well within the ± 25% acceptable range and the average of these results does not show significant bias. Additional data for a radiostrontium in soil method for 50 gram samples will also be presented, which appears to be a significant step forward based on looking at the current literature, with higher chemical yields for even larger sample aliquots and lower MDA [5, 6, 7] Hou et al surveyed a wide range of separation methods for Pu in waters and environmental solid samples [8]. While there are many actinide methods in the scientific literature, few would be considered rapid due to the tedious and time-consuming steps involved. For actinide analyses in soil, a new rapid method for the determination of actinide isotopes in soil samples using both alpha spectrometry and inductively-coupled plasma mass spectrometry was employed. The new rapid soil method utilizes an acid leaching method, iron/titanium hydroxide precipitation, a lanthanum fluoride soil matrix removal step, and a rapid column separation process with TEVA Resin. The large soil matrix is removed easily and rapidly using these two simple precipitations with high chemical recoveries and effective removal of interferences. [9, 10] Vacuum box technology and rapid flow rates were used to reduce analytical time. Challenges associated with the mineral content in the volcanic soil will be

  4. Use of new composite materials for the determination of Cu, Cd, Mo, As, and Sb in biological samples by radiochemical neutron activation analysis

    Czech Academy of Sciences Publication Activity Database

    Lučaníková, M.; Kučera, Jan; Šebesta, F.; John, J.

    2006-01-01

    Roč. 269, č. 2 (2006), s. 463-468 ISSN 0236-5731 R&D Projects: GA ČR(CZ) GA203/04/0943 Institutional research plan: CEZ:AV0Z10480505 Keywords : radiochemical neutron activation analysis * separation using composite materials Subject RIV: CB - Analytical Chemistry, Separation Impact factor: 0.509, year: 2006

  5. Radiochemical surveillance of KNK primary sodium

    International Nuclear Information System (INIS)

    Stamm, H.-H.; Stade, K.Ch.

    1987-05-01

    Radiochemical surveillance of the KNK primary sodium has been performed now for 15 years with 953 effective full-power days. The overflow method used for sodium sampling proved to be reliable. Different crucible materials have been used for different analytical tasks. The amount of radionuclides in the primary system has not given restrictions to plant operation at any time. On-line gamma spectroscopy on pipings and components of the primary circuits was accomplished in reactor downtimes. Activity depositions on the walls were dominated by Ta-182 after KNK I operation. Main deposited activities at KNK II were Mn-54 (fresh core) and after operation with failed fuel Cs-137, in cover gas areas together with Zn-65. Efficient experimental radionuclide traps for the removal of Mn-54, Zn-65 and Cs-137 from the primary coolant were tested successfully. The dose rates on primary pipes and components of KNK I and KNK II were lower by an order of magnitude compared to water-cooled reactors. This is in good agreement with experiences from LMFBR's in other countries. The resulting average yearly accumulated personal dose rate was 0.21 man-Sv at KNK, compared to 3.9 man-Sv at German light-water-cooled power reactors

  6. Radiochemical studies on amorphous zirconium phosphate

    Energy Technology Data Exchange (ETDEWEB)

    Dyer, A; Moores, G E [Salford Univ. (UK). Dept. of Chemistry and Applied Chemistry

    1981-01-01

    Amorphous zirconium phosphate (ZrP) is used in some hemodialysis machines for the regeneration of dialysate. Its function is to adsorb ammonium ions formed by the pretreatment of urea by urease. It also adsorbs Ca, Mg and K ions but leaches phosphate ions which are then removed (along with F/sup -/ ions) by a bed of hydrous zirconium oxide. The sodium form of ZrP is used although other forms have been suggested for use. The work reported here describes some preliminary radiochemical studies on the mechanism of release of phosphate ions and its possible relationship to sodium ion-exchange. /sup 32/P labelled material (HHZrP) was used for elution experiments with deionized water and buffer solutions having the pH's 4.2, 7.0 and 9.2. Buffer solutions used were as supplied by BDH. Elution was at four different temperatures in the range 293 to 363/sup 0/C. In the second series of experiments HHZrP was suspended in a NaCl solution labelled with /sup 22/Na. From this, /sup 22/Na labelled ZrP (NaHZrP) was prepared and eluted in the same way as the HHZrP. Results are given and discussed.

  7. Radiochemical measurement of mass transport in sodium

    International Nuclear Information System (INIS)

    Cooper, M.H.; Chiang, S.H.

    1976-01-01

    Mass transport processes in the sodium coolant of Liquid Metal Fast Breeder Reactors (LMFBRs) are significant in determining rates of corrosion and deposition of radioactive nuclides from the fuel cladding, deposition and cold trapping of fission products from defect or failed fuel, carbon and nitrogen redistribution in the containment materials, and removal of impurities by cold trapping or hot trapping. Mass transport between rotating, concentric cylinders in molten sodium has been investigated using a unique radiochemical method. Long-lived (33 year) cesium-137, dissolved in the sodium, decays radioactively emitting a beta to barium-137m, which decays with a short half-life (2.6 minutes) emitting a gamma. Cesium is weakly adsorbed and remains in solution, while the barium is strongly adsorbed on the stainless steel surfaces. Hence, by measuring the barium-137m activity on movable stainless steel surfaces, one can calculate the mass transport to that surface. Mass transfer coefficients in sodium measured by this method are in agreement with published heat transfer correlations when the effect of the volumetric mass source is taken into account. Hence, heat transfer correlations can be confidently utilized by analogy in estimating mass transfer in liquid-metal systems

  8. The use of robots for automation in the radiochemical laboratory

    International Nuclear Information System (INIS)

    Huddleston, J.

    1988-01-01

    The use of robotic systems for automated processes such as overnight operations, procedures involving radiation hazards in radiochemical laboratories is discussed. Particular reference is made to their use in analytical problems. Their flexibility is emphasised. (U.K.)

  9. A radiochemical assay for biotin in biological materials

    International Nuclear Information System (INIS)

    Hood, R.L.

    1975-01-01

    A radiochemical assay for biotin is described. The assay was sensitive to one nanogram and simple enough for routine biotin analyses. The assay yielded results which were comparable to those obtained from a microbiological assay using Lactobacillus plantarum. (author)

  10. The publication lapse of papers in Radiochemical and Radioanalytical Letters

    International Nuclear Information System (INIS)

    Braun, T.; Nagydiosi-Kocsis, Gy.

    1982-01-01

    The time needed for passing through journal editorial and publication processing has been examined for the papers published in Radiochemical and Radioanalytical Letters for the years 1969-1981. (author)

  11. Safety and Waste Management for SAM Radiochemical Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the radiochemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  12. Radiochemical problems of radiation chemical synthesis in n, γ-field of nuclear reactor

    International Nuclear Information System (INIS)

    Mironov, V.P.; Frejdus, N.V.; Bugaenko, L.T.; Kalyazin, E.P.; Petryaev, E.P.

    1981-01-01

    A wide applicability of products of radiation chemical synthesis (RCS), using n, γ-irradiation, is limited by possible contamination of the latter with long-lived radioactive isotopes of chemical elements included in the composition of the reagent and compounds syntesized (chemically non-separable radionuclides - CNR). A technique of the determination of the limit accumulation CNR on the basis of radiation chemical parameters of the synthesis (radiation-chemical yield, the dose rate absorbed, singleness of purpose of RCS etc.) and radiochemical parameters of formation and accumulation of CNR (radiochemical yields of CNR in the products of radiolysis, neutron fluence, the reagent purity etc.) is suggested. The radiochemical evaluation of CNR accumulation (tritium and carbon-14), formed at the expense of activation with neutrons of chemical elements of water and organic substances, consisting of hydrogen, carbon and oxygen has shown that at relatively low yields of final products (> or approximately 3 molecules/100 eV) no accumulation of radionuclides in concentrations reaching the average admissible concentration takes place [ru

  13. Radiochemical and instrumental neutron activation analysis - recent trends

    International Nuclear Information System (INIS)

    Dams, R.

    1990-01-01

    Recent trends of radiochemical and instrumental neutron activation analysis are discussed. Novel developments include the application of cyclic and pulsed activation, better energy resolution with hyperpure germanium detectors, and use of pulse processing systems allowing extremely high count rates of very short-lived isotopes. Further development is anticipated in the field of speciation in biological and environmental studies. Radiochemical methods have led to accurate determinations at the ng/g level. A promising future is expected for neutron activation techniques. (orig.)

  14. OPERATIONAL EXPERIENCE: UPGRADED MPC AND A SYSTEMS FOR THE RADIOCHEMICAL PLANT OF THE SIBERIAN CHEMICAL COMBINE

    International Nuclear Information System (INIS)

    RODRIGUEZ, C.; GOLOSKOKOV, I.; FISHBONE, L.; GOODEY, K.; LOOMIS, M.; CRAIN, B. JR.; LARSEN, R.

    2003-01-01

    The success of reducing the risk of nuclear proliferation through physical protection and material control/accounting systems depends upon the development of an effective design that includes consideration of the objectives of the systems and the resources available to implement the design. Included among the objectives of the design are facility characterization, definition of threat, and identification of targets. When considering resources, the designer must consider funds available, rapid low-cost elements, technology elements, human resources, and the availability of resources to sustain operation of the end system. The Siberian Chemical Combine (SCC) is a multi-function nuclear facility located in the Tomsk region of Siberia, Russia. Beginning in 1996, SCC joined with the United States Department of Energy (US/DOE) Material Protection, Control, and Accounting (MPC and A) Program to develop and implement MPC and A upgrades for the Radiochemical, Chemical Metallurgical, Conversion, Uranium Enrichment, and Reactor Plants of the SCC. At the Radiochemical Plant the MPC and A design and implementation process has been largely completed for the Plutonium Storage Facility and related areas of the Radiochemical Plant. Design and implementation of upgrades for the Radiochemical Plant include rapid physical protection upgrades such as bricking up of doors and windows, and installation of security-hardened doors. Rapid material control and accounting upgrades include installation of modern balances and bar code equipment. Comprehensive MPC and A upgrades include the installation of access controls to sensitive areas of the Plant, alarm communication and display (AC and D) systems to detect and annunciate alarm conditions, closed circuit (CCTV) systems to assess alarm conditions, central and secondary alarm station upgrades that enable security forces to assess and respond to alarm conditions, material control and accounting upgrades that include upgraded physical

  15. Application of the radiochemical - and the direct gamma ray spectrometry method to the burnup determination of irradiated uranium oxide

    International Nuclear Information System (INIS)

    Cunha, I.I.L.

    1979-01-01

    The burn up of natural U 3 O 8 that occurs by the action of thermal neutrons was determined, using the radioisotopes 144 Ce, 137 Cs, 103 Ru, 106 Ru and 95 Zr as monitors. The determination of the burn up was made using both destructive and non-destructive methods. In the non-destructive method, the technique of direct gamma-ray spectrometry was used and the radioisotopes mentioned were simultaneously counted in a Ge-Li detector. In the radiochemical method the same radioisotopes were isolated one from the other and from all other fission products before counting. The solvent extraction technique was used for the radiochemical separation of uranium, cerium, cesium and ruthenium. To separate zirconium and niobium, adsorption in silica-gel was used. The extraction agent employed to isolate cesium was dipycrilamine and for the separation of the other radioisotopes Di-(2-Ethyl Hexyl) Phosphoric acid (HDEHP) was used. (Author) [pt

  16. Assessment of Carbon- and Metal-Based Nanoparticle DNA Damage with Microfluidic Electrophoretic Separation Technology.

    Science.gov (United States)

    Schrand, Amanda M; Powell, Thomas; Robertson, Tiffany; Hussain, Saber M

    2015-02-01

    In this study, we examined the feasibility of extracting DNA from whole cell lysates exposed to nanoparticles using two different methodologies for evaluation of fragmentation with microfluidic electrophoretic separation. Human lung macrophages were exposed to five different carbon- and metal-based nanoparticles at two different time points (2 h, 24 h) and two different doses (5 µg/ml, 100 µg/ml). The primary difference in the banding patterns after 2 h of nanoparticle exposure is more DNA fragmentation at the higher NP concentration when examining cells exposed to nanoparticles of the same composition. However, higher doses of carbon and silver nanoparticles at both short and long dosing periods can contribute to erroneous or incomplete data with this technique. Also comparing DNA isolation methodologies, we recommend the centrifugation extraction technique, which provides more consistent banding patterns in the control samples compared to the spooling technique. Here we demonstrate that multi-walled carbon nanotubes, 15 nm silver nanoparticles and the positive control cadmium oxide cause similar DNA fragmentation at the short time point of 2 h with the centrifugation extraction technique. Therefore, the results of these studies contribute to elucidating the relationship between nanoparticle physicochemical properties and DNA fragmentation results while providing the pros and cons of altering the DNA isolation methodology. Overall, this technique provides a high throughput way to analyze subcellular alterations in DNA profiles of cells exposed to nanomaterials to aid in understanding the consequences of exposure and mechanistic effects. Future studies in microfluidic electrophoretic separation technologies should be investigated to determine the utility of protein or other assays applicable to cellular systems exposed to nanoparticles.

  17. Development of Decontamination Technology for Separating Radioactive Constituents from Contaminated Concrete Waste

    International Nuclear Information System (INIS)

    Min, B. Y.; Kim, G. N.; Lee, G. W.; Choi, W. K.; Jung, U. S.

    2010-01-01

    The large amount of contaminated concrete produced during decommissioning procedures and available decontamination. In Korea, more than more than 60 tons of concrete wastes contaminated with uranium compounds have been generated from UCP (Uranium Conversion Plant) by dismantling. A recycling or a volume reduction of the concrete wastes through the application of appropriate treatment technologies have merits from the view point of an increase in a resource recycling as well as a decrease in the amount of wastes to be disposed of resulting in a reduction of a disposal cost and an enhancement of the disposal safety. For unconditional release of building and reduction of radioactive concrete waste, mechanical methods and thermal stress methods have been selected. In the advanced countries, such as France, Japan, Germany, Sweden, and Belgium, techniques for reduction and reuse of the decommissioning concrete wastes have applied to minimize the total radioactive concrete waste volume by thermal and mechanical processes. It was found that volume reduction of contaminated concrete can be achieved by separation of the fine cement stone and coarse gravel. Typically, the contaminated layer is only 1∼10mm thick because cementitious materials are porous media, the penetration of radionuclides may occur up to several centimenters from the surface of a material. Most of the dismantled concrete wastes are slightly contaminated rather than activated. This decontamination can be accomplished during the course of a separation of the concrete wastes contaminated with radioactive materials through a thermal treatment step of the radionuclide (e.g. cesium and strontium), transportation of the radionuclide to fine aggregates through a mechanical treatment step. Concrete is a structural material which generally consists of a binder (cement), water, and aggregate. The interaction between highly charged calcium silicate hydrate (C-S-H) particles in the presence of divalent calcium

  18. Continuous radiochemical analysis of fission products in a nuclear reactor water coolant

    International Nuclear Information System (INIS)

    Moskvin, L.N.; Zakharov, L.K.; Leont'ev, G.G.; Mel'nikov, V.A.; Orlenkov, I.S.; Slutskij, G.K.

    1975-01-01

    Method for continuous radiochemical analysis of I, Cs, Ba, Sr and Ce isotopes in a reactor water heat-transfer agent was developed. A continuous two-dimensional chromatographic process of complex mixtures separation of substances proved to be feasible on several parallel sorbent layers, which moved at constant velocities and separated by stationary intermediate collectors. Tests on model solutions containing I, Ce, Cs and Ba isotopes and on heat-carrier samples showed quantitative separation of elements. The results were indicative of a basic possibility of using multisorbent chromatographs for continuous control of multicomponent mixtures, particularly for control of radioactive fission product compositions in water heat-transfer agents in nuclear power plants. A diagram is shown for a two-dimensional chromatographic separation of a multicomponent mixture. Also shown is a flow chart of an installation for continuous control of iodine and cesium isotope activities

  19. Radiochemical procedure for the determination of plutonium isotopes in powdered milk

    International Nuclear Information System (INIS)

    Taddei, M.H.T.; Silva, N.C.

    2006-01-01

    A radiochemical procedure for the determination of alpha-emitting isotopes of plutonium in powdered milk is proposed. The procedure involves sample dissolution (by HNO 3 and HClO 4 ), separation by ionic-exchange resin, electrodeposition and alpha-spectroscopy. In order to determine the chemical recovery, 242 Pu was employed as a tracer. A reference material (Marine Sediment IAEA 135) was analyzed to validate such procedure, and to show its reliability. Afterwards, some powdered milk, produced for international trade, was analyzed and chemical recovery was found to be around 95%. (author)

  20. Radiochemical analysis of radio-nuclides in sea water collected near Bikini Atoll

    Energy Technology Data Exchange (ETDEWEB)

    Miyake, Y; Sugiura, Y

    1955-01-01

    A radiochemical analysis of sea water containing fission materials collected near Bikini Atoll in June, 1954, was performed. The sea water was boiled with hydrochloric acid, iron and lanthanum salts each 5 mg as Fe and La were added to it. They were precipitated as hydroxide, which was dissolved in hydrochloric acid and ferric chloride was extracted with ethyl ether. The remaining solution was evaporated to dryness and the residue was dissolved in hydrochloric acid. Using the latter solution the group separation was done with cation exchanger resins.

  1. Separation, fractionation, concentration and drying of food products: Technology progress report, October 1, 1984-March 3, 1987

    Energy Technology Data Exchange (ETDEWEB)

    Rose, W. W.; Pederson, L. D.; Merlo, C. A.; Brewbaker, P. L.

    1987-11-01

    This report describes the first and second phases of a three phase project, the object of which is to develop energy efficient separation, concentration, and drying processes for food products, especially juice products, in order to reduce energy requirements and their associated costs for processing, preservation, and transportation. Presently in juice processing, much water is eliminated through evaporation. However, there are significant limits to the current evaporation technology. If, however, the juice could be separated, prior to evaporation, into liquid and solid fractions, and the liquid concentrated further, the containerization and transportation costs could be significantly reduced. Separation methods investigated in this project are: vacuum filtration, centrifugation, and crossflow microfiltration.

  2. Improvement of auditing technology of safety analysis through thermal-hydraulic separate effect tests

    Energy Technology Data Exchange (ETDEWEB)

    No, Hee Cheon; Moon, Young Min; Lee, Dong Won; Lee, Sang Ik; Kim, Eung Soo; Yeom, Keum Soo [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2002-03-15

    The objective of the present research is to perform the separate effect tests and to assess the RELAP5/MOD3.2 code for the analysis of thermal-hydraulic behavior in the reactor coolant system and the improvement of the auditing technology of safety analysis. Three Separate Effect Tests (SETs) are the reflux condensation in the U-tube, the direct contact condensation in the hot-leg and the mixture level buildup in the pressurizer. The experimental data and the empirical correlations are obtained through SETs. On the ases of the three SET works, models in RELAP5 are modified and improved, which are compared with the data. The Korea Standard Nuclear Power Plant (KSNP) are assessed using the modified RELAP5. In the reflux condensation test, the data of heat transfer coefficients and flooding are obtained and the condensation models are modified using the non-iterative model, as results, modified code better predicts the data. In the direct contact condensation test, the data of heat transfer coefficients are obtained for the cocurrent and countercurrent flow between the mixture gas and the water in condition of horizontal stratified flow. Several condensation and friction models are modified, which well predict the present data. In the mixture level test, the data for the mixture level and the onset of water draining into the surge line are obtained. The standard RELAP5 over-predicts the mixture level and the void fraction in the pressurizer. Simple modification of model related to the pool void fraction is suggested. The KSNP is assessed using the standard and the modified RELAP5 resulting from the experimental and code works for the SETs. In case of the pressurizer manway opening with available secondary side of the steam generators, the modified code predicts that the collapsed level in the pressurizer is little accumulated. The presence and location of the opening and the secondary condition of the steam generators have an effect on the coolant inventory. The

  3. Radiochemical verification and validation in the environmental data collection process

    International Nuclear Information System (INIS)

    Rosano-Reece, D.; Bottrell, D.; Bath, R.J.

    1994-01-01

    A credible and cost effective environmental data collection process should produce analytical data which meets regulatory and program specific requirements. Analytical data, which support the sampling and analysis activities at hazardous waste sites, undergo verification and independent validation before the data are submitted to regulators. Understanding the difference between verification and validation and their respective roles in the sampling and analysis process is critical to the effectiveness of a program. Verification is deciding whether the measurement data obtained are what was requested. The verification process determines whether all the requirements were met. Validation is more complicated than verification. It attempts to assess the impacts on data use, especially when requirements are not met. Validation becomes part of the decision-making process. Radiochemical data consists of a sample result with an associated error. Therefore, radiochemical validation is different and more quantitative than is currently possible for the validation of hazardous chemical data. Radiochemical data include both results and uncertainty that can be statistically compared to identify significance of differences in a more technically defensible manner. Radiochemical validation makes decisions about analyte identification, detection, and uncertainty for a batch of data. The process focuses on the variability of the data in the context of the decision to be made. The objectives of this paper are to present radiochemical verification and validation for environmental data and to distinguish the differences between the two operations

  4. Application of the spectrometric and radiochemical techniques in analyzing environmental samples from the Bulgarian Black Sea region

    International Nuclear Information System (INIS)

    Veleva, B.S.; Mungov, G.; Galabov, N.; Kolarova, M.; Guenchev, T.

    1999-01-01

    Development of the appropriate methods and techniques for marine and atmospheric radioactivity measurements in the NIMH-BAS during the last 5 years is presented. Approaches for pre-concentration of the radionuclides from the atmosphere and sea water samples followed with reliable radiochemical methods for radionuclides separation and low level counting are discussed. Dissolved radiocesium concentrations measured in a period of time starting in 1993 show some decrease with years and spatial variations probably due to the hydrophysical features of the sampling sides - the lower measured concentrations during 1995 and 1998 correspond to the lower salinity. Application of the radiochemical separation of Plutonium, Thorium, 90 Sr and Americium on the samples from the Bulgarian Black Sea coastal region is reported. (author)

  5. Collected radiochemical procedures (radiochemistry group CNC-11)

    Energy Technology Data Exchange (ETDEWEB)

    Smith, H.L. (ed.)

    1975-04-01

    Separation techniques are given for: Am, Sb, As, Ba, Be, Bi, C, Cd, Ca, Ce, Cs, Cl, Cr, Co, Cm, Ge, Au, In, Fe, lanthanides, Pb, Mg, Mn, Mo, Np, Ni, Nb, Pd, P, Pu, Pa, Rh, Ru, Sc, Ag, Na, Sr, sulfate, Ta, Te, Tl, Th, Sn, transactinides, tritium, W, U, Y, and Zr. Combined procedures and group separations of the heavy elements are also included. (DLC)

  6. Collected radiochemical procedures (radiochemistry group CNC-11)

    International Nuclear Information System (INIS)

    Smith, H.L.

    1975-04-01

    Separation techniques are given for: Am, Sb, As, Ba, Be, Bi, C, Cd, Ca, Ce, Cs, Cl, Cr, Co, Cm, Ge, Au, In, Fe, lanthanides, Pb, Mg, Mn, Mo, Np, Ni, Nb, Pd, P, Pu, Pa, Rh, Ru, Sc, Ag, Na, Sr, sulfate, Ta, Te, Tl, Th, Sn, transactinides, tritium, W, U, Y, and Zr. Combined procedures and group separations of the heavy elements are also included

  7. Alternative polymer separation technology by centrifugal force in a melted state

    International Nuclear Information System (INIS)

    Dobrovszky, Károly; Ronkay, Ferenc

    2014-01-01

    Highlights: • Waste separation should take place at high purity. • Developed a novel, alternative separation method, where the separation occurred in a melted state by centrifugal forces. • Possibility of separation two different plastics into neat fractions. • High purity fractions were established at granulates and also at prefabricated blend. • Results were verified by DSC, optical microscopy and Raman spectroscopy. - Abstract: In order to upgrade polymer waste during recycling, separation should take place at high purity. The present research was aimed to develop a novel, alternative separation opportunity, where the polymer fractions were separated by centrifugal force in melted state. The efficiency of the constructed separation equipment was verified by two immiscible plastics (polyethylene terephthalate, PET; low density polyethylene, LDPE), which have a high difference of density, and of which large quantities can also be found in the municipal solid waste. The results show that the developed equipment is suitable not only for separating dry blended mixtures of PET/LDPE into pure components again, but also for separating prefabricated polymer blends. By this process it becomes possible to recover pure polymer substances from multi-component products during the recycling process. The adequacy of results was verified by differential scanning calorimetry (DSC) measurement as well as optical microscopy and Raman spectroscopy

  8. Alternative polymer separation technology by centrifugal force in a melted state

    Energy Technology Data Exchange (ETDEWEB)

    Dobrovszky, Károly; Ronkay, Ferenc, E-mail: ronkay@pt.bme.hu

    2014-11-15

    Highlights: • Waste separation should take place at high purity. • Developed a novel, alternative separation method, where the separation occurred in a melted state by centrifugal forces. • Possibility of separation two different plastics into neat fractions. • High purity fractions were established at granulates and also at prefabricated blend. • Results were verified by DSC, optical microscopy and Raman spectroscopy. - Abstract: In order to upgrade polymer waste during recycling, separation should take place at high purity. The present research was aimed to develop a novel, alternative separation opportunity, where the polymer fractions were separated by centrifugal force in melted state. The efficiency of the constructed separation equipment was verified by two immiscible plastics (polyethylene terephthalate, PET; low density polyethylene, LDPE), which have a high difference of density, and of which large quantities can also be found in the municipal solid waste. The results show that the developed equipment is suitable not only for separating dry blended mixtures of PET/LDPE into pure components again, but also for separating prefabricated polymer blends. By this process it becomes possible to recover pure polymer substances from multi-component products during the recycling process. The adequacy of results was verified by differential scanning calorimetry (DSC) measurement as well as optical microscopy and Raman spectroscopy.

  9. Advanced Membrane Separation Technologies for Energy Recovery from Industrial Process Streams

    Energy Technology Data Exchange (ETDEWEB)

    Keiser, J. R.; Wang, D. [Gas Technology Institute; Bischoff, B.; Ciora, [Media and Process Technology; Radhakrishnan, B.; Gorti, S. B.

    2013-01-14

    Recovery of energy from relatively low-temperature waste streams is a goal that has not been achieved on any large scale. Heat exchangers do not operate efficiently with low-temperature streams and thus require such large heat exchanger surface areas that they are not practical. Condensing economizers offer one option for heat recovery from such streams, but they have not been widely implemented by industry. A promising alternative to these heat exchangers and economizers is a prototype ceramic membrane system using transport membrane technology for separation of water vapor and recovery of heat. This system was successfully tested by the Gas Technology Institute (GTI) on a natural gas fired boiler where the flue gas is relatively clean and free of contaminants. However, since the tubes of the prototype system were constructed of aluminum oxide, the brittle nature of the tubes limited the robustness of the system and even limited the length of tubes that could be used. In order to improve the robustness of the membrane tubes and make the system more suitable for industrial applications, this project was initiated with the objective of developing a system with materials that would permit the system to function successfully on a larger scale and in contaminated and potentially corrosive industrial environments. This required identifying likely industrial environments and the hazards associated with those environments. Based on the hazardous components in these environments, candidate metallic materials were identified that are expected to have sufficient strength, thermal conductivity and corrosion resistance to permit production of longer tubes that could function in the industrial environments identified. Tests were conducted to determine the corrosion resistance of these candidate alloys, and the feasibility of forming these materials into porous substrates was assessed. Once the most promising metallic materials were identified, the ability to form an alumina

  10. Radiochemical determination of 210 Pb and 226Ra in petroleum sludges and scales

    International Nuclear Information System (INIS)

    Araujo, Andressa Arruda de

    2005-01-01

    The oil extraction and production, both onshore and offshore, can generate different types of residues, such as sludge, that is deposited in the water/oil separators, valves and storage tanks and scales, which form i the inner surface of ducts and equipment. Analyses already carried out through gamma spectrometry indicated the existence of high radioisotope concentration. However, radionuclides emitting low-energy gamma-rays, such as 210 Pb, are hardly detected by that technique. Consequently, there is a need to test alternative techniques to determine this and other radionuclides from the 238 U series. This work, therefore, focuses on the radiochemical determination of the concentration of 210 Pb, and 226 Ra in samples of sludge and scale from the oil processing stations of the UN-SEAL, a PETROBRAS unit responsible for the exploration and production of petroleum in Sergipe and Alagoas. The sludge and scale samples went through a preliminary process of extraction of oil, in order to separate the solid phase, where the largest fraction of the radioactivity is concentrated. After oil removal, the samples were digested using alkaline fusion as an option for dissolution. Finally, their activity concentration was determined for the samples of sludge and scales, using and alternative radiochemical method, which is based on ionic exchange. The activity concentration found for 210 Pb varied from 1,14 to 507,3 kBq kg -1 . The values for 226 Ra were higher, varying from 4,36 to 3.445 kBq kg -1 . The results for 226 Ra were then compared with the ones found for the same samples of sludge and scales using gamma spectrometry. The results of the comparison confirm the efficiency of the methodology used int hi work, that is, radiochemical determination by means of ionic exchange. (author)

  11. Novel highly integrated biodiesel production technology in a centrifugal contactor separator device

    NARCIS (Netherlands)

    Kraai, G. N.; Schuur, B.; van Zwol, F.; van de Bovenkamp, H. H.; Heeres, H. J.

    2009-01-01

    The base catalyzed production of biodiesel (FAME) from sunflower oil and methanol in a continuous centrifugal contactor separator (CCS) with integrated reaction and phase separation was studied. The effect of catalyst loading (sodium methoxide), temperature, rotational frequency and flow rates of

  12. Radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2010-07-01

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  13. Radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

    2010-07-15

    The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

  14. Radiochemical studies on nuclear fission at Trombay

    Indian Academy of Sciences (India)

    2015-07-30

    Jul 30, 2015 ... Home; Journals; Pramana – Journal of Physics; Volume 85; Issue 2 ... Due to the ability to separate individual elements from a complex reaction mixture with a ... At Trombay, a small group of radiochemists initiated the work on ...

  15. 17. radiochemical conference. Booklet of abstracts

    International Nuclear Information System (INIS)

    Bečková, Věra; Ekberg, Christian; Feldman, Vladimir I.

    2014-05-01

    The conference was divided into the following sessions: Plenary Session; Radionuclides in the environment, radioecology; Nuclear analytical methods; Chemistry of actinide and trans-actinide elements; Radiation chemistry; Production and application of radionuclides; Separation methods, speciation; Chemistry of nuclear fuel cycle; Radiopharmaceutical chemistry, labelled compounds; and Education / coordination. (P.A.)

  16. Effect of rheological characteristics and technology of application of a viscoelastic separator on its displacing ability

    Energy Technology Data Exchange (ETDEWEB)

    Gnibidin, V N

    1980-01-01

    Presented are the results of industrial tests of the displacing ability of a viscoelastic separator, obtained by mixing a clay suspension and an aqueous solution of polyacrylamide. It is established that the displacing ability of the viscoelastic separator is determined mainly by the value of the final normal stresses sigma /SUB f/ . The greatest effect from the use of this separator is achieved with sigma /SUB f/ of at least 600 dyne/cm/sup 2/ and a rate of movement of not more than 0.5 m/sec.

  17. Higher-Order Blind Signal Feature Separation: An Enabling Technology for Battlefield Awareness

    National Research Council Canada - National Science Library

    Su, Wei; Kosinski, John A

    2006-01-01

    Higher-order transform blind signal feature classification is discussed for separating bar-shaped, circular, squared, circular-squared, and offset-diamonded constellation patterns of digital linear signals...

  18. A radiochemical NAA method for the determination of tin, barium, copper and antimony- role of tin as an indicator for gun shot residues

    International Nuclear Information System (INIS)

    Chattopadhyay, N.; Basu, A.K.; Tripathi, A.B.R.; Rao, M.S.; Anil Kumar, S.; Parthasarathy, R.; Mathur, P.K.

    1998-01-01

    Metallic tin being present as impurity and hardening agent of lead bullet/shot, is expected to play an important role in forensic ballistics in matching of bullet lead specimens for establishment of commonness of origin and also as an additional parameter for characterisation of Gun Shot Residue (GSR). 121 Sn is a suitable radioisotope for quantification of the element at ppm level if it is separated in highest radiochemical purity. A sequential Radiochemical Neutron Activation Analysis (RNAA) procedure for its simultaneous determination along with trace levels of Ba, Cu and Sb has been developed and its applications in forensic science are described. (author)

  19. ZZ HATCHES-18, Database for radiochemical modelling

    International Nuclear Information System (INIS)

    Heath, T.G.

    2008-01-01

    1 - Description of program or function: HATCHES is a referenced, quality assured, thermodynamic database, developed by Serco Assurance for Nirex. Although originally compiled for use in radiochemical modelling work, HATCHES also includes data suitable for many other applications e.g. toxic waste disposal, effluent treatment and chemical processing. It is used in conjunction with chemical and geochemical computer programs, to simulate a wide variety of reactions in aqueous environments. The database includes thermodynamic data (the log formation constant and the enthalpy of formation for the chemical species) for the actinides, fission products and decay products. The datasets for Ni, Tc, U, Np, Pu and Am are based on the NEA reviews of the chemical thermodynamics of these elements. The data sets for these elements with oxalate, citrate and EDTA are based on the NEA-selected values. For iso-saccharinic acid, additional data (non-selected values) have been included from the NEA review as well as data derived from other sources. HATCHES also includes data for many toxic metals and for elements commonly found in groundwaters or geological materials. HARPHRQ operates by reference to the PHREEQE master species list. Thus the thermodynamic information supplied is: a) the log equilibrium constant for the formation reaction of the requested species from the PHREEQE master species for the corresponding elements; b) the enthalpy of reaction for the formation reaction of the requested species from the PHREEQE master species for the corresponding elements. This version of HATCHES has been updated since the previous release to provide consistency with the selected data from two recent publications in the OECD Nuclear Energy Agency series on chemical thermodynamics: Chemical Thermodynamics Series Volume 7 (2005): Chemical Thermodynamics of Selenium by Aeke Olin (Chairman), Bengt Nolaeng, Lars-Olof Oehman, Evgeniy Osadchii and Erik Rosen and Chemical Thermodynamics Series Volume 8

  20. Radiochemical determination of thallium by substoichiometric reduction

    International Nuclear Information System (INIS)

    Muralidhar, N.; Rangamannar, B.; Krishnan, V.R.

    1983-01-01

    A method was developed for the determination of thallium by substoichiometric reduction of Tl(III) with thiourea and separation of the two oxidation states by the extraction of the former into iso-amyl acetate. Thiourea reduces Tl(III) at room temperature quantitatively, with a 2:1 stoichiometry. 2-25 μg Tl can be determined by this method with a precision of 4%. (author)

  1. Minicomputer system for radiochemical analysis by coincidence spectrometry

    International Nuclear Information System (INIS)

    Brauer, F.P.; Fager, J.E.

    1979-01-01

    Minicomputer-based coincidence analysis methods have been developed for use in performing radiochemical analysis by high-resolution x- and gamma-ray coincidence spectrometry. This paper describes the data-acquisition and analysis methods develolped for qualitative and quantitative analyses of coincidence spectrometric data. Data-acquisition capabilities include both direct multiparameter pulse-height analysis and buffered list-mode acquisition

  2. Instrumentation for chemical and radiochemical monitoring in nuclear power plants

    International Nuclear Information System (INIS)

    Nordmann, F.; Ballard, G.

    2009-01-01

    This article details the instrumentation implemented in French nuclear power plants for the monitoring of chemical and radiochemical effluents with the aim of limiting their environmental impact. It describes the controls performed with chemical automata for the search for drifts, anomalies or pollution in a given circuit. The operation principles of the different types of chemical automata are explained as well as the manual controls performed on samples manually collected. Content: 1 - general considerations; 2 - objectives of the chemical monitoring: usefulness of continuous monitoring with automata, transmission to control rooms and related actions, redundancy of automata; 3 - instrumentation and explanations for the main circuits: principle of chemical automata monitoring, instrumentation of the main primary circuit, instrumentation of the main secondary circuit, instrumentation of the tertiary circuit, preparation of water makeup (demineralized water), other loops, instrumentation for effluents and environment monitoring, measurement principles of chemical automata, control and maintenance of chemical automata; 4 - manual controls after sampling; 5 - radiochemical monitoring: automatized radiochemical measurements, manual radiochemical measurements; 6 - conclusion

  3. Advanced Acid Gas Separation Technology for Clean Power and Syngas Applications

    Energy Technology Data Exchange (ETDEWEB)

    Amy, Fabrice [Air Products and Chemicals Inc., Allentown, PA (United States); Hufton, Jeffrey [Air Products and Chemicals Inc., Allentown, PA (United States); Bhadra, Shubhra [Air Products and Chemicals Inc., Allentown, PA (United States); Weist, Edward [Air Products and Chemicals Inc., Allentown, PA (United States); Lau, Garret [Air Products and Chemicals Inc., Allentown, PA (United States); Jonas, Gordon [Air Products and Chemicals Inc., Allentown, PA (United States)

    2015-06-30

    Air Products has developed an acid gas removal technology based on adsorption (Sour PSA) that favorably compares with incumbent AGR technologies. During this DOE-sponsored study, Air Products has been able to increase the Sour PSA technology readiness level by successfully operating a two-bed test system on coal-derived sour syngas at the NCCC, validating the lifetime and performance of the adsorbent material. Both proprietary simulation and data obtained during the testing at NCCC were used to further refine the estimate of the performance of the Sour PSA technology when expanded to a commercial scale. In-house experiments on sweet syngas combined with simulation work allowed Air Products to develop new PSA cycles that allowed for further reduction in capital expenditure. Finally our techno economic analysis of the use the Sour PSA technology for both IGCC and coal-to-methanol applications suggests significant improvement of the unit cost of electricity and methanol compared to incumbent AGR technologies.

  4. Evaluation of a new pulping technology for pre-treating source-separated organic household waste prior to anaerobic digestion

    DEFF Research Database (Denmark)

    Naroznova, Irina; Møller, Jacob; Larsen, Bjarne

    2016-01-01

    A new technology for pre-treating source-separated organic household waste prior to anaerobic digestion was assessed, and its performance was compared to existing alternative pre-treatment technologies. This pre-treatment technology is based on waste pulping with water, using a specially developed...... screw mechanism. The pre-treatment technology rejects more than 95% (wet weight) of non-biodegradable impurities in waste collected from households and generates biopulp ready for anaerobic digestion. Overall, 84-99% of biodegradable material (on a dry weight basis) in the waste was recovered...... in the biopulp. The biochemical methane potential for the biopulp was 469±7mL CH4/g ash-free mass. Moreover, all Danish and European Union requirements regarding the content of hazardous substances in biomass intended for land application were fulfilled. Compared to other pre-treatment alternatives, the screw...

  5. Preparation of a technology development roadmap for the Accelerator Transmutation of Waste (ATW) System : report of the ATW separations technologies and waste forms technical working group

    International Nuclear Information System (INIS)

    Collins, E.; Duguid, J.; Henry, R.; Karell, E.J.; Laidler, J.J.; McDeavitt, S.M.; Thompson, M.; Toth, L.M.; Williamson, M.; Willit, J.L.

    1999-01-01

    In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD and D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years

  6. Preparation of a technology development roadmap for the Accelerator Transmutation of Waste (ATW) System : report of the ATW separations technologies and waste forms technical working group.

    Energy Technology Data Exchange (ETDEWEB)

    Collins, E.; Duguid, J.; Henry, R.; Karell, E.; Laidler, J.; McDeavitt, S.; Thompson, M.; Toth, M.; Williamson, M.; Willit, J.

    1999-08-12

    In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD&D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years.

  7. Determination of individual rare earth elements in Vietnamese monazite by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Nguyen Van Suc; Nguyen Mong Sinh

    1993-01-01

    Radiochemical neutron activation analysis (RNAA) has been applied for determination of rare earth elements (REE) in Vietnamese monazite. The chemical separation procedure used is based on the chromatographic elution of rare earth groups, after the separation of 233 Pa(Th) in irradiated monazite samples by coprecipitation with MnO 2 , the rare earth elements were retained by Biorad AG1 x 8 resin column in 10% 15.4M HNO 3 -90% methanol solution. The elution of heavy rare earth (HREE) and middle rare earth (MREE) groups was carried out with 10% 1M HNO 3 - 90% methanol and 10% 0.05M HNO 3 -90% methanol solution, respectively; while the light rare earths (LREE) were eluted from the column by 0.1M HNO 3 solution. The accuracy of the method was checked by the analysis of granodiorite GSP-I and the rare earth values were in good agreement. (author) 7 refs.; 3 tabs

  8. Radiochemical applications of insoluble sulfate columns. Analytical possibilities in the field of the fission product solutions

    International Nuclear Information System (INIS)

    Barrachina, M.; Sauvagnac, R.

    1962-01-01

    In this paper we go on with our study of the heterogeneous ion-isotopic exchange in column. At present, we apply it to determine the radiochemical composition of the raw solutions used in the industrial recuperation of the long-lived fission products. The separation of the radioelements contained in these solutions is carried out mainly by making use of small columns, 1-3 cm height, of BaSO 4 or SrSO 4 , under selected experimental conditions. These columns behave like a special type of inorganic exchangers, working by absorption or by ion-isotopic exchange depending on the cases,a nd they provide the means for the selective separation of several important fission products employing very small volumes of fixing and eluting solutions. (Author) 11 refs

  9. Radio-chemical applications of functionalized membranes

    International Nuclear Information System (INIS)

    Pandey, Ashok K.

    2011-01-01

    Functionalized polymer membranes have many potential applications as they are task specific. We have developed many functionalized membranes like polymer inclusion membranes, pore-filled membranes and nano-membranes. Radiotracers and other methods have been used to understand the diffusional-transport properties of the Nafion-117 membrane as well as home-made membranes. These membranes have been used to develop novel analytical and separation methods for toxic metal ions and radionuclides. In this talk, an overview of our work on functionalized membrane is presented. (author)

  10. Present status and perspective of radiochemical analysis of radionuclides in Nordic countries

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Olsson, Mattias; Togneri, Laura

    2016-01-01

    Radiochemical analysis plays a critical role in the determination of pure beta and alpha emitting radionuclides for environmental monitoring, radioecology, decommissioning, nuclear forensics and geological dating. A remarkable development on radiochemical analysis has been achieved in the past...... of radionuclides, especially in Nordic countries; some requirements from nuclear industries and research organizations, as well as perspectives on the development of radiochemical analysis are discussed....

  11. Review and assessment of technologies for the separation of strontium from alkaline and acidic media

    International Nuclear Information System (INIS)

    Orth, R.J.; Kurath, D.E.

    1994-01-01

    A literature survey has been conducted to identify and evaluate methods for the separation of strontium from acidic and alkaline media as applied to Hanford tank waste. The most promising methods of solvent extraction, precipitation, and ion exchange are described. The following criteria were used for evaluating the separation methods: Appreciable strontium removal must be demonstrated; Strontium selectivity over bulk components must be demonstrated; The method must show promise for evolving into a practical and fairly simple process; The process should be safe to operate; The method must be robust (i.e., capable of separating strontium from various waste types); Secondary waste generation must be minimized; and The method must show resistance to radiation damage. The methods discussed did not necessarily satisfy all of the above criteria; thus, key areas requiring further development are also given for each method. Less promising solvent extraction, precipitation, and ion exchange methods were also identified; areas for potential development are included in this report

  12. Numerical Study of Water Control with Downhole Oil-Water Separation Technology

    Directory of Open Access Journals (Sweden)

    Yin Khor Yin

    2014-07-01

    Full Text Available The maturing oil fields with increasing water production can pose a challenging produced water handling and disposal issues. This paper presents a numerical study of a motorless hydrocyclone to enhance understanding of the downhole oil-water separation. The turbulence of fluid flow is obtained using K-ε Realizable Turbulence model for complex swirl dominated flow, while the interface between hydrocarbon and water is described using the Discrete Phase model. In this approach, factors which contribute to the hydrocyclone separation instability were discussed. Discussion is then extended to the relationship of residence time with pressure difference between overflow and underflow. These pressure differences are able to relate to pressure condition for high water cut well which require downhole separation.

  13. Technological process and optimum design of organic materials vacuum pyrolysis and indium chlorinated separation from waste liquid crystal display panels

    Energy Technology Data Exchange (ETDEWEB)

    Ma, En; Xu, Zhenming, E-mail: zmxu@sjtu.edu.cn

    2013-12-15

    Highlights: • The vacuum pyrolysis–vacuum chlorinated separation system was proposed to recover the waste LCD panel. • The system can recycle the whole waste LCD panels efficiently without negative effects to environment. • The 82.03% of the organic materials was reclaimed. All pyrolysis products can be utilized by a reasonable way. • The separation of indium was optimized by the central composite design (CCD) under response surface methodology (RSM). • The recovery ratio of indium was further increased to 99.97%. -- Abstract: In this study, a technology process including vacuum pyrolysis and vacuum chlorinated separation was proposed to convert waste liquid crystal display (LCD) panels into useful resources using self-design apparatuses. The suitable pyrolysis temperature and pressure are determined as 300 °C and 50 Pa at first. The organic parts of the panels were converted to oil (79.10 wt%) and gas (2.93 wt%). Then the technology of separating indium was optimized by central composite design (CCD) under response surface methodology (RSM). The results indicated the indium recovery ratio was 99.97% when the particle size is less than 0.16 mm, the weight percentage of NH{sub 4}Cl to glass powder is 50 wt% and temperature is 450 °C. The research results show that the organic materials, indium and glass of LCD panel can be recovered during the recovery process efficiently and eco-friendly.

  14. Simulative technology for auxiliary fuel tank separation in a wind tunnel

    Directory of Open Access Journals (Sweden)

    Ma Xin

    2016-06-01

    Full Text Available In this paper, we propose a simulative experimental system in wind tunnel conditions for the separation of auxiliary fuel tanks from an aircraft. The experimental system consists of a simulative release mechanism, a scaled model and a pose measuring system. A new release mechanism was designed to ensure stability of the separation. Scaled models of the auxiliary fuel tank were designed and their moment of inertia was adjusted by installing counterweights inside the model. Pose parameters of the scaled model were measured and calculated by a binocular vision system. Additionally, in order to achieve high brightness and high signal-to-noise ratio of the images in the dark enclosed wind tunnel, a new high-speed image acquisition method based on miniature self-emitting units was presented. Accuracy of the pose measurement system and repeatability of the separation mechanism were verified in the laboratory. Results show that the position precision of the pose measurement system can reach 0.1 mm, the precision of the pitch and yaw angles is less than 0.1° and that of the roll angle can be up to 0.3°. Besides, repeatability errors of models’ velocity and angular velocity controlled by the release mechanism remain small, satisfying the measurement requirements. Finally, experiments for the separation of auxiliary fuel tanks were conducted in the laboratory.

  15. formulation of nano-ceramic filters used in separation of heavy metals and nuclear technology

    International Nuclear Information System (INIS)

    Khalil, T.; Labib, Sh.; Abou El-Nour, F.H.; Abdel-Khalik, M.

    2004-01-01

    the choice of suitable preparation methods and experimental preparation conditions to formulate ceramic filters of stable chemical -and thermal properties and of high mechanical strength and stable structure, which permit their use for separation of heavy metals at high separation conditions and to produce compact matrices suitable for radiation protection are the aim of this study . ceramic filters are characterized by multi- layered body including rigid support and one or more layers with pore size lower than that of the support. the top layer determines.the separation conditions of the whole system. the used ceramic filters include micro-, ultra- and nano-sized materials . alumina and titania substrates were prepared using the wet chemical techniques. optimization of the produced substrates was followed through comparative studies with standard reference commercial substrate. specific surface area measurements and pore size distribution using mercury porosimeter were carried out . the present study led to optimization of the experimental conditions to formulate the suitable substrate used in preparation of filters applied in separation of heavy metals. in addition, their use to produce compact matrices suitable for protection from the hazardous effect of some radioisotopes could applied

  16. Hybrid Separations/Distillation Technology. Research Opportunities for Energy and Emissions Reduction

    Energy Technology Data Exchange (ETDEWEB)

    Eldridge, R. Bruce [Univ. of Texas, Austin, TX (United States); Seibert, A. Frank [Univ. of Texas, Austin, TX (United States); Robinson, Sharon [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Rogers, Jo [American Inst. of Chemical Engineers, New York, NY (United States)

    2005-04-01

    This report focuses on improving the existing separations systems for the two largest energy-consuming sectors: the chemicals and petroleum refining industries. It identifies the technical challenges and research needs for improving the efficiency of distillation systems. Areas of growth are also highlighted.

  17. A demonstration of applying ATS thermal screw technology to the processing of separated construction and other waste materials

    Energy Technology Data Exchange (ETDEWEB)

    Jones, D.; Golan, A.; Bosschieter, H.A.

    1991-06-01

    A demonstration was carried out by Spider Recycling, a waste haulage company, to determine how to sort, process and recycle or reuse waste disposed of by the company, using a new processing system based on the ATS thermal screw press technology. Selected loads of waste totalling one thousand tonnes from construction, sawmill, landscape and tire industries located around greater Toronto were delivered to a pilot separation and processing site and separated into piles of similar material such as wood, drywall and tires. The separated piles were drawn on as feedstock for processing through the ATS thermal screw press system to produce useable forms of product and raw material. The applications included: turning wood waste into firelogs or wood fuel; yard waste into mulch; waste drywall into gypsum powder; tires into crumb rubber; asphalt shingles into a bitumix; and mixed garbage into densified logs or flakes. Wide ranges of throughput were found depending on the material processed, material size, density, moisture content and model of the ATS thermal screw press used. It was shown that it is practical to separate selected wastes from industry and process them with the ATS machine, and that the system could probably offer recycling and reuse solutions to separable waste where product markets are available and in some cases where the operation could collect the estimated $100/tonne tipping fees available in southern Ontario. 37 figs., 20 tabs.

  18. Environmental friendly crush-magnetic separation technology for recycling metal-plated plastics from end-of-life vehicles.

    Science.gov (United States)

    Xue, Mianqiang; Li, Jia; Xu, Zhenming

    2012-03-06

    Metal-plated plastics (MPP), which are important from the standpoint of aesthetics or even performance, are increasingly employed in a wide variety of situations in the automotive industry. Serious environmental problems will be caused if they are not treated appropriately. Therefore, recycling of MPP is an important subject not only for resource recycling but also for environmental protection. This work represents a novel attempt to deal with the MPP. A self-designed hammer crusher was used to liberate coatings from the plastic substrate. The size distribution of particles was analyzed and described by the Rosin-Rammler function model. The optimum retaining time of materials in the crusher is 3 min. By this time, the liberation rate of the materials can reach 87.3%. When the density of the suspension is 31,250 g/m(3), the performance of liberation is the best. Two-step magnetic separation was adopted to avoid excessive crushing and to guarantee the quality of products. Concerning both the separation efficiency and grade of products, the optimum rotational speed of the magnetic separator is 50-70 rpm. On the basis of the above studies about the liberating and separating behavior of the materials, a continuous recycling system (the technology of crush-magnetic separation) is developed. This recycling system provides a feasible method for recycling MPP efficiently, economically, and environmentally.

  19. RAPID AUTOMATED RADIOCHEMICAL ANALYZER FOR DETERMINATION OF TARGETED RADIONUCLIDES IN NUCLEAR PROCESS STREAMS

    International Nuclear Information System (INIS)

    O'Hara, Matthew J.; Durst, Philip C.; Grate, Jay W.; Egorov, Oleg; Devol, Timothy A.

    2008-01-01

    Some industrial process-scale plants require the monitoring of specific radionuclides as an indication of the composition of their feed streams or as indicators of plant performance. In this process environment, radiochemical measurements must be fast, accurate, and reliable. Manual sampling, sample preparation, and analysis of process fluids are highly precise and accurate, but tend to be expensive and slow. Scientists at Pacific Northwest National Laboratory (PNNL) have assembled and characterized a fully automated prototype Process Monitor instrument which was originally designed to rapidly measure Tc-99 in the effluent streams of the Waste Treatment Plant at Hanford, WA. The system is capable of a variety of tasks: extraction of a precise volume of sample, sample digestion/analyte redox adjustment, column-based chemical separations, flow-through radiochemical detection and data analysis/reporting. The system is compact, its components are fluidically inter-linked, and analytical results can be immediately calculated and electronically reported. It is capable of performing a complete analytical cycle in less than 15 minutes. The system is highly modular and can be adapted to a variety of sample types and analytical requirements. It exemplifies how automation could be integrated into reprocessing facilities to support international nuclear safeguards needs

  20. High-efficiency technology for lithium isotope separation using an ionic-liquid impregnated organic membrane

    International Nuclear Information System (INIS)

    Hoshino, Tsuyoshi; Terai, Takayuki

    2011-01-01

    The tritium needed as a fuel for fusion reactors is produced by the neutron capture reaction of lithium-6 ( 6 Li) in tritium breeding materials. New lithium isotope separation technique using ionic-liquid impregnated organic membranes (Ionic-Liquid-i-OMs) have been developed. Lithium ions are able to move by electrodialysis through certain Ionic-Liquid-i-OMs between the cathode and the anode in lithium solutions. In this report, the effects of protection cover and membrane thickness on the durability of membrane and the efficiency of isotope separation were evaluated. In order to improve the durability of the Ionic-Liquid-i-OM, we developed highly-durable Ionic-Liquid-i-OM. Both surfaces of the Ionic-Liquid-i-OM were covered by a nafion 324 overcoat or a cation exchange membrane (SELEMION TM CMD) to prevent the outflow of the ionic liquid. It was observed that the durability of the Ionic-Liquid-i-OM was improved by a nafion 324 overcoat. On the other hand, the organic membrane selected was 1, 2 or 3 mm highly-porous Teflon film, in order to efficiently impregnate the ionic liquid. The 6 Li isotope separation factor by electrodialysis using highly-porous Teflon film of 3 mm thickness was larger than using that of 1 or 2 mm thickness.

  1. Gas phase adsorption technology for nitrogen isotope separation and its feasibility for highly enriched nitrogen gas production

    International Nuclear Information System (INIS)

    Inoue, Masaki; Asaga, Takeo

    2000-04-01

    Highly enriched nitrogen-15 gas is favorable to reduce radioactive carbon-14 production in reactor. The cost of highly enriched nitrogen-15 gas in mass production is one of the most important subject in nitride fuel option in 'Feasibility Study for FBR and Related Fuel Cycle'. In this work gas phase adsorption technology was verified to be applicable for nitrogen isotope separation and feasible to produce highly enriched nitrogen-15 gas in commercial. Nitrogen isotopes were separated while ammonia gas flows through sodium-A type zeolite column using pressure swing adsorption process. The isotopic ratio of eight samples were measured by high resolution mass spectrometry and Fourier transform microwave spectroscopy. Gas phase adsorption technology was verified to be applicable for nitrogen isotope separation, since the isotopic ratio of nitrogen-15 and nitrogen-14 in samples were more than six times as high as in natural. The cost of highly enriched nitrogen-15 gas in mass production were estimated by the factor method. It revealed that highly enriched nitrogen-15 gas could be supplied in a few hundred yen per gram in mass production. (author)

  2. Miniaturized chromatographic radiochemical procedure for 131I - MIBG

    International Nuclear Information System (INIS)

    Barboza, M.F. de; Pereira, N.S. de; Colturato, M.T.; Silva, C.P.G. da.

    1989-12-01

    Different solvents were used in paper chromatographic methods to obtain the best system in routine radiochemical control for 131 I-MIBG produced at IPEN-CNEN/SP. The dates were compared with those obtained with eletrophoresis method in buffer acetate, pH=4.5, 350V, during 40 minutes. The stability of the labeled compound store under 4 0 C was studied during 15 days. Miniaturized chromatographic procedures were established using Whatman 3MM (8x1cm) and n-butanol-:acetic acid: water (S:2:1) as a solvent. the Rf values were: 0.3 (I - ) and 1.0 (MIBG). The radiochemical purity was 99.3 and 99.2% (first day) obtained with eletrophoresis and miniaturized chromatographic procedures, respectively and, 84.7% after 15 days of its preparation. It is a rapid, practical and reproductive method. (author) [pt

  3. A reflection on the relationship between technology and teacher education : synergy or separate entities?

    NARCIS (Netherlands)

    Collis, Betty

    1994-01-01

    The basis of this paper is the observation, supported by various international surveys and discussions, that much of the 'education' teachers receive concerning the applications of computer-related technology has occurred not only apart from a direct relationship to research about information

  4. Technologies for the treatment of source-separated urine in the ...

    African Journals Online (AJOL)

    2Pollution Research Group, School of Chemical Engineering, University of ... Laboratory, School of Architecture, Civil and Environmental Engineering ... disciplinary research project VUNA was initiated in order to explore technologies and management methods for ... ent recovery from urine lowers the cost of sanitation, pro-.

  5. Investigation on an innovative technology for wet separation of plastic wastes.

    Science.gov (United States)

    Lupo, Emanuela; Moroni, Monica; La Marca, Floriana; Fulco, Simone; Pinzi, Valentina

    2016-05-01

    This paper presents an original device for the separation of plastic polymers from mixtures. Due to the combination of a characteristic flow pattern developing within the apparatus and density, shape and size differences among two or more polymers, this device allows their separation into two products, one collected within the instrument and the other one expelled through its outlet ducts. Experimental tests have been conducted to investigate the effectiveness of the apparatus, using two geometric arrangements, nine hydraulic configurations and three selections of polymers at three stages of a material life cycle. Tests with samples composed of a single typology of polymer have been used to understand the interaction between the particles and the carrying fluid within the apparatus in different hydraulic configurations and geometric arrangements. Multi-material tests are essential to simulate the real conditions in an industrial recycling plant. The separation results have been evaluated in terms of grade and recovery of a useful material. Under the proper hydraulic configurations, the experimentation showed that it is possible to produce an almost pure concentrate of Polyethylene Terephthalate (PET) from a mixture of 85% PET and 15% Polycarbonate (PC) (concentrate grade and recovery equal to 99.5% and 95.1%) and a mixture of 85% PET and 15% Polyvinyl Chloride (PVC) (concentrate grade and recovery equal to 97.9% and 100.0%). It is further demonstrated that almost pure concentrates of PVC and PC can be produced from a mixture of 85% PVC and 15% PC (PVC grade and recovery equal to 99.9% and 99.7%) and a mixture of 85% PC and 15% PVC (PC grade and recovery equal to 99.0% and 99.5%). Copyright © 2016 Elsevier Ltd. All rights reserved.

  6. Radiochemical regularities of migration mobility of Chernobyl' discharge radionuclides

    International Nuclear Information System (INIS)

    Skorobogat'ko, E.P.; Rybalko, S.I.

    1992-01-01

    Data on the radionuclude (RN) migration in environment later the Chernobyl' accident are generalized. Introduction of fallout of the radioactive discharge into environment causes necessity to account and to study different factors of geochemical and physicochemical character determining further RN behaviour in the medium. For a well-founded forecast of the behaviour it is necessity to use a complex of radiochemical and physicochemical research, lying in the base of radiation monitoring of environment. 1 refs

  7. Decontamination and decommission of a radiochemical laboratory building complex

    International Nuclear Information System (INIS)

    Zoubek, Norbert

    2008-01-01

    Full text: Handling of unsealed radioactive substances for research and development purposes in chemical or pharmaceutical industries or research centres as well as production of radioactive substances (e.g. for applications in nuclear medicine or industry) requires operation of special radiochemical laboratories. In general, operation of radiochemical laboratories is strongly regulated by the government and national authorities. The operator needs a permit related to radiological protection. In general, technical requirements for such facilities are very high. To ensure high safety standards with respect to the employees and the environment, several radiological protection measures have to be taken. These measures (for example special shielding or ventilation and waste water systems) depend on various factors, e.g. activity in use, kind of nuclides, chemical properties and volatility of substances. In order to close-down such radiochemical laboratories some radiological protection measures have to be maintained to ensure protection of both humans and the environment induced by possible residual contaminations within the facility including technical inventory. However, a later reuse of the facility as a non-radioactive facility requires removal of all radioactive contamination with respect to national regulation. Resulting radioactive wastes have to be disposed of under control of competent authorities. Based on the experience of a decontamination and decommission project for a former radiochemical laboratory complex, the main steps necessary to release such a facility are discussed. Analytical aspects of initial conditions, necessary organisational structures within the project, resources needed estimation and exploration of the radiological situation in the laboratory, elaboration of a measuring strategy and decontamination methods as well as different waste disposal routes in relation to different waste types are reported. (author)

  8. Future directions for separation science in nuclear and radiochemistry

    International Nuclear Information System (INIS)

    Pruett, D.J.

    1986-01-01

    Solvent extraction and ion exchange have been the most widely used separation techniques in nuclear and radiochemistry since their development in the 1940s. Many successful separations processes based on these techniques have been used for decades in research laboratories, analytical laboratories, and industrial plants. Thus, it is easy to conclude that most of the fundamental and applied research that is needed in these areas has been done, and that further work in these ''mature'' fields is unlikely to be fruitful. A more careful review, however, reveals that significant problems remain to be solved, and that there is a demand for the development of new reagents, methods, and systems to solve the increasingly complex separations problems in the nuclear field. Specifically, new separation techniques based on developments in membrane technology and biotechnology that have occurred over the last 20 years should find extensive applications in radiochemical separations. Considerable research is needed in such areas as interfacial chemistry, the design and control of highly selective separation agents, critically evaluated data bases and mathematical models, and the fundamental chemistry of dilute solutions if these problems are to be solved and new techniques developed in a systematic way. Nonaqueous separation methods, such as pyrochemical and fluoride volatility processes, have traditionally played a more limited role in nuclear and radiochemistry, but recent developments in the chemistry and engineering of these processes promises to open up new areas of research and application in the future

  9. Aluminum Oxide Nanoparticles for Highly Efficient Asphaltene Separation from Crude Oil Using Ceramic Membrane Technology

    Directory of Open Access Journals (Sweden)

    Rezakazemi Mashallah

    2017-11-01

    Full Text Available The effects of aluminum oxide nanoparticles on the removal of asphaltenes from an Iranian crude oil (Soroush using a ceramic membrane with pore size of 0.2 µm were investigated. In order to achieve superior asphaltene separation by ultrafiltration, it is essential to make some changes for destabilizing asphaltene in crude oil. The asphaltene destabilization was done using crude oil contact with an acid containing dissolved metal ions. Metal oxide nanoparticles adsorbed asphaltene molecules and increased their molecular size. The nanoparticle of aluminum oxide was applied to alter precipitation and peptization properties of asphaltenes. Dynamic Light Scattering (DLS was used to measurement of the asphaltene molecular size dissolved in toluene. Raman spectroscopy and the Tuinstra equation were used to determine the aromatic sheet diameter (La via the integrated intensities of the G and D1 modes. This revealed that the asphaltene particles react with nano aluminum oxide and the average molecular size of asphaltene was raised from 512.754 to 2949.557 nm and La from 5.482 to 13.787. The obtained results showed that using nano aluminum oxides, asphaltene separation increased from 60–85 wt% to 90–97 wt% based on the asphaltene content of crude oil.

  10. Improvement of auditing technology of safety analysis through thermal-hydraulic separate effect tests

    Energy Technology Data Exchange (ETDEWEB)

    No, Hee Cheon; Park, Hyun Sik; Kim, Hyougn Tae; Moon, Young Min; Choi, Sung Won; Heo, Sun [Korea Advanced Institute Science and Technology, Taejon (Korea, Republic of)

    1999-04-15

    The loss-of-RHR accident during midloop operation has been important as results of the probabilistic safety analysis. The condensation models In RELAP5/MOD3 are not proper to analyze the midloop operation. To audit and improve the model in RELAP5/MOD3.2, several items of separate effect tests have been performed. The 29 sets of reflux condensation data is obtained and the correlation is developed with these heat transfer coefficient's data. In the experiment of the direct contact condensation in hot leg, the apparatus setting is finished and a few experimental data is obtained. Non-iterative model is used to predict the model in RELAP5/MOD3.2 with the results of reflux condensation and evaluates better than the present model. The results of the direct contact condensation in a hot leg represent to be similar with the present model. The study of the CCF and liquid entrainment in a surge line and pressurizer is selected as the third separate experiment and is on performance.

  11. The Hurriclon technology; La technique Hurriclon de separation a force centrifuge

    Energy Technology Data Exchange (ETDEWEB)

    Kaufmann, M. [PMT Zyclontechnik GmbH, Krems (Austria)

    2000-09-01

    Saving specific energy consumption is a main target in modem cement plants. But reducing pressure loss in cyclone systems results normally in a lesser separation efficiency. These two problems can be overcome by the use of a new system of guided vanes, called vortex finder vanes which can be also installed in existing cyclone systems. The obtained pressure loss reduction is higher than 30 %. Another development is the Hurriclon system which combines the above mentioned device with a double dip tube cyclone system. The advantage is a better separation efficiency at lower pressure losses leading to a higher production rate and therefore lower specific energy consumption as well as smaller filter units. The residual dust particles in the clean gas have also a significantly smaller size leading to less wear in the subsequent installations. The field of application encompasses all dedusting systems of cement plants starting after the mills or after the cooler, but also the preheater cyclones. In the case of upgrading of existing systems, the investment payback periods can be within some months. The paper shows the principles of these systems and several reference projects with guaranteed and obtained values regarding operation parameters. (author)

  12. Development of Pyro-separation Technology Based on Molten Salt Electrolysis

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Joon Bo; Kim, E. H.; Yoo, J. H. (and others)

    2007-06-15

    The focus of this study was to develop recovery technologies in the pyroprocessing. The unit processes of the project can be classified into two groups; electro-refining process to recover uranium and long-lived nuclides, and cathode processing to produce a metal ingot both from a salt-contained metal and from Cd-contained metal. This project has been carried out for the third phase period of the long-term nuclear R and D program, and focused on the development of key technologies of the pyroprocessing such as electrorefining, draw down and cathode processing. Mock-up system of 1 kg-U/batch was built for performance tests which were conducted to ensure the adequacy of the research and development of the pyroprocessing technology. The experiments were carried out through bench-scale inactive tests except for uranium. In particular, the sticking problem was inevitable in the US's Mark-V and PEER electrorefiner. As a result of this study, a graphite cathode was developed, which exhibited self-scraping behavior and did not need scraping step. The design of an electrorefiner could be simplified, and the throughput was enhanced due to an increased cathode area. A long-term R and D plan was established to develop pyroprocessing technology. In the near term, the results of the current project will be utilized in the next phase of the R and D plan ('07 - '10), and long-term wise, is expected to contribute to recovering fuel materials for transmutation in a Gen-IV reactor.

  13. Development of Pyro-separation Technology Based on Molten Salt Electrolysis

    International Nuclear Information System (INIS)

    Shim, Joon Bo; Kim, E. H.; Yoo, J. H.

    2007-06-01

    The focus of this study was to develop recovery technologies in the pyroprocessing. The unit processes of the project can be classified into two groups; electro-refining process to recover uranium and long-lived nuclides, and cathode processing to produce a metal ingot both from a salt-contained metal and from Cd-contained metal. This project has been carried out for the third phase period of the long-term nuclear R and D program, and focused on the development of key technologies of the pyroprocessing such as electrorefining, draw down and cathode processing. Mock-up system of 1 kg-U/batch was built for performance tests which were conducted to ensure the adequacy of the research and development of the pyroprocessing technology. The experiments were carried out through bench-scale inactive tests except for uranium. In particular, the sticking problem was inevitable in the US's Mark-V and PEER electrorefiner. As a result of this study, a graphite cathode was developed, which exhibited self-scraping behavior and did not need scraping step. The design of an electrorefiner could be simplified, and the throughput was enhanced due to an increased cathode area. A long-term R and D plan was established to develop pyroprocessing technology. In the near term, the results of the current project will be utilized in the next phase of the R and D plan ('07 - '10), and long-term wise, is expected to contribute to recovering fuel materials for transmutation in a Gen-IV reactor

  14. Hanford Environmental Restoration data validation process for chemical and radiochemical analyses

    International Nuclear Information System (INIS)

    Adams, M.R.; Bechtold, R.A.; Clark, D.E.; Angelos, K.M.; Winter, S.M.

    1993-10-01

    Detailed procedures for validation of chemical and radiochemical data are used to assure consistent application of validation principles and support a uniform database of quality environmental data. During application of these procedures, it was determined that laboratory data packages were frequently missing certain types of documentation causing subsequent delays in meeting critical milestones in the completion of validation activities. A quality improvement team was assembled to address the problems caused by missing documentation and streamline the entire process. The result was the development of a separate data package verification procedure and revisions to the data validation procedures. This has resulted in a system whereby deficient data packages are immediately identified and corrected prior to validation and revised validation procedures which more closely match the common analytical reporting practices of laboratory service vendors

  15. The determination of the radiochemical purity of 99Tcm-DTPA-HSA injection

    International Nuclear Information System (INIS)

    Yin Guangrong; Zhang Yan

    1996-01-01

    A simple, rapid analytical method of radiochemical purity for the 99 Tc m -DTPA-HSA injection is established. 99 Tc m (VII), 99 Tc m (IV) and labelled compound 99 Tc m -DTPA-HSA are separated by two systems of paper chromatography on Whatman No.1. The solvent of the system A is 85% methanol and that of the system B is water-95% alcohol-ammonium hydroxide (volume ratio is 5:2:1). 90 Tc m (IV) and labelled compound are located at the origin, while R f of 99 Tc m (VII) is about 0.4-0.5 in the system A. R f of 99 Tc m (VII) and labelled compound are about 0.7-0.8, while 99 Tc m (IV) is located at the origin in the system B

  16. A radiochemical procedure for the determination of Po-210 in environmental samples

    International Nuclear Information System (INIS)

    Godoy, J.M.; Schuettelkopf, H.

    1980-07-01

    A radiochemical procedure for the determination of Po-210 in environmental samples was developed. Soil, sediments, filter materials, plants, water and food samples can be analyzed for Po-210. Wet ashing is achieved with HNO 3 + H 2 O 2 or HCl + HNO 3 . To separate disturbing substances, a coprecipitation with Te is used for sample materials containing silica. Po-210 deposition from HCl solution on Ag platelets with other sample materials is possible directly. Deposited Po-210 is counted by α-spectrometry. For chemical yield determination Po-208 is added, yields range between 60% and 100%. A lower detection limit of about 0,002 pCi Po-210/sample is achievable. (orig./HP) [de

  17. Remediation of water pollution caused by pharmaceutical residues based on electrochemical separation and degradation technologies: a review.

    Science.gov (United States)

    Sirés, Ignasi; Brillas, Enric

    2012-04-01

    In the last years, the decontamination and disinfection of waters by means of direct or integrated electrochemical processes are being considered as a very appealing alternative due to the significant improvement of the electrode materials and the coupling with low-cost renewable energy sources. Many electrochemical technologies are currently available for the remediation of waters contaminated by refractory organic pollutants such as pharmaceutical micropollutants, whose presence in the environment has become a matter of major concern. Recent reviews have focused on the removal of pharmaceutical residues upon the application of other important methods like ozonation and advanced oxidation processes. Here, we present an overview on the electrochemical methods devised for the treatment of pharmaceutical residues from both, synthetic solutions and real pharmaceutical wastewaters. Electrochemical separation technologies such as membrane technologies, electrocoagulation and internal micro-electrolysis, which only isolate the pollutants from water, are firstly introduced. The fundamentals and experimental set-ups involved in technologies that allow the degradation of pharmaceuticals, like anodic oxidation, electro-oxidation with active chlorine, electro-Fenton, photoelectro-Fenton and photoelectrocatalysis among others, are further discussed. Progress on the promising solar photoelectro-Fenton process devised and further developed in our laboratory is especially highlighted and documented. The abatement of total organic carbon or reduction of chemical oxygen demand from contaminated waters allows the comparison between the different methods and materials. The routes for the degradation of the some pharmaceuticals are also presented. Copyright © 2011 Elsevier Ltd. All rights reserved.

  18. Query-by-Example Music Information Retrieval by Score-Informed Source Separation and Remixing Technologies

    Directory of Open Access Journals (Sweden)

    Goto Masataka

    2010-01-01

    Full Text Available We describe a novel query-by-example (QBE approach in music information retrieval that allows a user to customize query examples by directly modifying the volume of different instrument parts. The underlying hypothesis of this approach is that the musical mood of retrieved results changes in relation to the volume balance of different instruments. On the basis of this hypothesis, we aim to clarify the relationship between the change in the volume balance of a query and the genre of the retrieved pieces, called genre classification shift. Such an understanding would allow us to instruct users in how to generate alternative queries without finding other appropriate pieces. Our QBE system first separates all instrument parts from the audio signal of a piece with the help of its musical score, and then it allows users remix these parts to change the acoustic features that represent the musical mood of the piece. Experimental results showed that the genre classification shift was actually caused by the volume change in the vocal, guitar, and drum parts.

  19. Determination of isotopic ratios of osmium and ruthenium in meteorites by pretreatment and radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Chinfang Chai; Yongzhong Liu; Xueying Mao

    1996-01-01

    The isotopic abundance ratios of 190 Os/ 184 Os and 96 Ru/ 102 Ru for the metal phases of the Jilin and Taonan stone meteorites were determined by pretreatment and radiochemical neutron activation analysis. All experimental factors affecting Os and Ru isotopic ratios were discussed, including sampling, standard, irradiation, separation and counting. The statistical errors of measurements for the 199 Os/ 184 Os ratio can be controlled within 1%. The experimental results indicate that the statistically significant anomalies of the 190 Os/ 184 Os and 96 Ru/ 102 Ru ratios have not been found relative to the terrestrial Os and Ru standards. (author). 6 refs., 1 fig., 5 tabs

  20. Sustainable Solution for Crude Oil and Natural Gas Separation using Concentrated Solar Power Technology

    Science.gov (United States)

    Choudhary, Piyush; Srivastava, Rakesh K.; Nath Mahendra, Som; Motahhir, Saad

    2017-08-01

    In today’s scenario to combat with climate change effects, there are a lot of reasons why we all should use renewable energy sources instead of fossil fuels. Solar energy is one of the best options based on features like good for the environment, independent of electricity prices, underutilized land, grid security, sustainable growth, etc. This concept paper is oriented primarily focused on the use of Solar Energy for the crude oil heating purpose besides other many prospective industrial applications to reduce cost, carbon footprint and moving towards a sustainable and ecologically friendly Oil & Gas Industry. Concentrated Solar Power technology based prototype system is proposed to substitute the presently used system based on natural gas burning method. The hybrid system which utilizes the solar energy in the oil and gas industry would strengthen the overall field working conditions, safety measures and environmental ecology. 40% reduction on natural gas with this hybrid system is estimated. A positive implication for an environment, working conditions and safety precautions is the additive advantage. There could also decrease air venting of CO2, CH4 and N2O by an average of 30-35%.

  1. Advanced separation technology for flue gas cleanup. Final report, February 1998

    Energy Technology Data Exchange (ETDEWEB)

    Bhown, A.S.; Alvarado, D.; Pakala, N.; Tagg, T.; Riggs, T.; Ventura, S.; Sirkar, K.K.; Majumdar, S.; Bhaumick, D.

    1998-06-01

    The objective of this work by SRI International was to develop a novel system for regenerable SO{sub 2} and NO{sub x} scrubbing of flue gas that focuses on (1) a novel method for regenerating spent SO{sub 2} scrubbing liquor and (2) novel chemistry for reversible absorption of NO{sub x}. High efficiency, hollow fiber contactors (HFCs) were proposed as the devices for scrubbing the SO{sub 2} and NO{sub x} from the flue gas. The system would be designed to remove more than 95% of the SO{sub 2} and more than 75% of the NO{sub x} from flue gases typical of pulverized coal-fired power plants at a cost that is at least 20% less than combined wet limestone scrubbing of SO{sub x} and selective catalytic reduction of NO{sub x}. In addition, the process would generate only marketable by-products, if any (no waste streams are anticipated). The major cost item in existing technology is capital investment. Therefore, the approach was to reduce the capital cost by using high-efficiency, hollow fiber devices for absorbing and desorbing the SO{sub 2} and NO{sub x}. The authors also introduced new process chemistry to minimize traditionally well-known problems with SO{sub 2} and NO{sub x} absorption and desorption. The process and progress in its development are described.

  2. Improvement of auditing technology of safety analysis through thermal-hydraulic separate effect tests

    Energy Technology Data Exchange (ETDEWEB)

    No, Hee Cheon; Park, Hyun Sik; Kim, Hyoung Tae; Moon, Young Min; Choi, Sung Won; Hwang, Do Hyun [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    2000-03-15

    The direct-contact condensation hear transfer coefficients are experimentally obtained in the following conditions : pure steam/steam in the presence of noncondensible gas, horizontal/slightly inclined pipe, cocurrent/countercurrent stratified flow with water. The empirical correlation for liquid Nusselt number is developed in conditions of the slightly inclined pipe and the cocurrent stratified flow. The several models - the wall friction coefficient, the interfacial friction coefficient, the correlation of direct-contact condensation with noncondensible gases, and the correlation of wall film condensation - in the RELAP5/MOD3.2 code are modified, As results, RELAP5/MOD3.2 is improved. The present experimental data is used for evaluating the improved code. The standard RELAP5/MOD3.2 code is modified using the non-iterative modeling, which is a mechanistic model and does not require any interfacial information such as the interfacial temperature, The modified RELAP5/MOD3.2 code os used to simulate the horizontally stratified in-tube condensation experiment which represents the direct-contact condensation phenomena in a hot leg of a nuclear reactor. The modeling capabilities of the modified code as well as the standard code are assessed using several hot-leg condensation experiments. The modified code gives better prediction over local experimental data of liquid void fraction and interfacial heat transfer coefficient than the standard code. For the separate effect test of the thermal-hydraulic phenomena in the pressurizer, the scaling analysis is performed to obtain a similarity of the phenomena between the Korea Standard Nuclear Power Plant(KSNPP) and the present experimental facility. The diameters and lengths of the hot-leg, the surge line and the pressurizer are scaled down with the similitude of CCFL and velocity. The ratio of gas flow rate is 1/25. The experimental facility is composed of the air-water supply tank, the horizontal pipe, the surge line and the

  3. Radiochemical neutron activation analysis of high pure palladium and platinum by ion exchange chromatography

    International Nuclear Information System (INIS)

    Sadikov, I.I.; Zinov'ev, V.G.; Sadikova, Z.O.; Salimov, M.I.

    2006-01-01

    Full text: The palladium and platinum are widely used for jewel manufacture because of their beautiful white color. However the most part of these metals are widely adopted in the world as catalysts. Many works on analytical chemistry of platinum group elements published during last years are devoted to determination of platinum and palladium in other materials. There are no articles on analysis technique of the palladium and platinum purity published during last 20 years. Available publications are very old and are published till 70th of the last century, and implement chemical and spectral methods. At the same time, the palladium and platinum are very suitable for NAA. Therefore the purpose of our research was development of high-sensitivity and multielement techniques of radiochemical neutron activation analysis of a high pure palladium and platinum. Research of nuclear characteristics of palladium and platinum has shown that radioactive nuclides with different yields are formed under the reactor neutrons. 109 , 111 , 111m Pd, 109m , 111 Ag, 191 , 197 , 199 Pt, 199 Au are the most important among them. 109Pd separation factor is equal to 1*10 5 at palladium analysis, whereas 197 Pt and 199 Au separation factor is equal to 1*10 4 at the platinum analysis every other day after irradiation. Palladium and platinum can be separated by precipitation, extraction and ion exchange methods. For separation of radioactive nuclide of the matrix elements from the impurity elements we used ion exchange chromatography system Dowex-1x8 - 1 M HNO 3 for palladium and Dowex-1x8 - 0.1 M HNO 3 for platinum. At the HNO 3 acid concentrations variation from 0,1 M to 1 M more then 25 elements have distribution factors less than 1 and 10 elements have distribution factors 5 while matrix elements have distribution factors higher than 100. It allows an effective separation of these elements from palladium and platinum. Optimum sizes of the chromatographic column and the column effluent

  4. CO2 CAPTURE PROJECT - AN INTEGRATED, COLLABORATIVE TECHNOLOGY DEVELOPMENT PROJECT FOR NEXT GENERATION CO2 SEPARATION, CAPTURE AND GEOLOGIC SEQUESTRATION

    Energy Technology Data Exchange (ETDEWEB)

    Dr. Helen Kerr

    2003-08-01

    The CO{sub 2} Capture Project (CCP) is a joint industry project, funded by eight energy companies (BP, ChevronTexaco, EnCana, Eni, Norsk Hydro, Shell, Statoil, and Suncor) and three government agencies (1) European Union (DG Res & DG Tren), (2) Norway (Klimatek) and (3) the U.S.A. (Department of Energy). The project objective is to develop new technologies, which could reduce the cost of CO{sub 2} capture and geologic storage by 50% for retrofit to existing plants and 75% for new-build plants. Technologies are to be developed to ''proof of concept'' stage by the end of 2003. The project budget is approximately $24 million over 3 years and the work program is divided into eight major activity areas: (1) Baseline Design and Cost Estimation--defined the uncontrolled emissions from each facility and estimate the cost of abatement in $/tonne CO{sub 2}. (2) Capture Technology, Post Combustion: technologies, which can remove CO{sub 2} from exhaust gases after combustion. (3) Capture Technology, Oxyfuel: where oxygen is separated from the air and then burned with hydrocarbons to produce an exhaust with high CO{sub 2} for storage. (4) Capture Technology, Pre -Combustion: in which, natural gas and petroleum coke are converted to hydrogen and CO{sub 2} in a reformer/gasifier. (5) Common Economic Model/Technology Screening: analysis and evaluation of each technology applied to the scenarios to provide meaningful and consistent comparison. (6) New Technology Cost Estimation: on a consistent basis with the baseline above, to demonstrate cost reductions. (7) Geologic Storage, Monitoring and Verification (SMV): providing assurance that CO{sub 2} can be safely stored in geologic formations over the long term. (8) Non-Technical: project management, communication of results and a review of current policies and incentives governing CO{sub 2} capture and storage. Technology development work dominated the past six months of the project. Numerous studies are making

  5. Advanced separation technology for flue gas cleanup. Quarterly technical report No. 11, October 1994--December 1994

    Energy Technology Data Exchange (ETDEWEB)

    Bhown, A.S.; Alvarado, D.; Pakala, N. [and others

    1994-12-01

    The objective of this work is to develop a novel system for regenerable SO{sub 2} and NO{sub x} scrubbing of flue gas that focuses on (a) a novel method for regeneration of spent SO{sub 2} scrubbing liquor and (b) novel chemistry for reversible absorption of NO{sub x}. In addition, high efficiency hollow fiber contactors (HFC) are proposed as the devices for scrubbing the SO{sub 2} and NO{sub x} from the flue gas. The system will be designed to remove more than 95% of the SO{sub x} and more than 75% of the NO{sub x} from flue gases typical of pulverized coal-fired power plants at a cost that is at least 20% less than combined wet limestone scrubbing of SO{sub x} and selective catalytic reduction of NO{sub x}. In addition, the process will make only marketable byproducts, if any (no waste streams). The major cost item in existing technology is capital investment. Therefore, our approach is to reduce the capital cost by using high efficiency hollow fiber devices for absorbing and desorbing the SO{sub 2} and NO{sub x}. We will also introduce new process chemistry to minimize traditionally well-known problems with SO{sub 2} and NO{sub x} absorption and desorption. For example, we will extract the SO{sub 2} from the aqueous scrubbing liquor into an oligomer of dimethylaniline to avoid the problem of organic liquid losses in the regeneration of the organic liquid.

  6. Cryo magnetic separation adaptation to environment technologies: application to industrial effluents; Adaptation de la separation cryomagnetique aux technologies de l`environnement: application a l`epuration d`effluents liquides industriels

    Energy Technology Data Exchange (ETDEWEB)

    Bureau, V

    1993-12-20

    Cryomagnetic separation adaptation to environment technologies application to industrial liquid effluents. The performance, obtained by superconducting high filed - high gradient magnetic separation, permitted to foresee the magnetic treatment of heavy metals in rinse waters, derived from the surface finishing industry. The paramagnetic ions, precipitated in basic media as hydroxides, present a very hydrated amorphous structure, which masks their subjacent magnetic properties. Coprecipitation of a `magnetic carrier`, jointly with the heavy metals, has been studied: ferric chloride forms in basic media, an hydrated iron oxide. Its structure is of the goethite type, and it stabilizes as hematite. The magnetic susceptibility of the obtained product is still weak and its crystalline structure is not enough affirmative to utilize magnetic filtration with efficiency. Mixture of ferrous sulphate and ferric chloride forms, in a basic media, an hydrated magnetite. Initial ideal ratio between divalent iron and trivalent iron, varies between 0,5 and 1,2. This mixture, coprecipitated with the heavy metals, permits to optimize the magnetic cleaning of the fluids in a high field - high gradient filter. (author)

  7. Burn-up determination of irradiated uranium oxide by means of direct gama spectrometry and by radiochemical method

    International Nuclear Information System (INIS)

    Cunha, I.I.L.; Nastasi, M.J.C.; Lima, F.W.

    1981-09-01

    The burn-up of thermal neutrons irradiated U 3 O 8 (natural uranium) samples has been determined by using both direct gamma spectrometry and radiochemical methods and the results obtained were compared. The fission products 144 Ce, 103 Ru, 106 Ru, 137 Cs and 95 Zr were chosen as burn-up monitors. In order to isolate the radioisotopes chosen as monitors, a radiochemical separation procedure has been established, in which the solvent extraction technique was used to separate cerium, cesium and ruthenium one from the other and all of them from uranium. The separation between zirconium and niobium and of both elements from the other radioisotopes and uranium was accomplished by means of adsorption on a silica-gel column, followed by selective elution of zirconium and of niobium. When use was made of the direct gamma-ray spectrometry method, the radioactivity of each nuclide of interest was measured in presence of all others. For this purpose use was made of gamma-ray spectrometry and of a Ge-Li detector. Comparison of burn-up values obtained by both methods was made by means of Student's 't' test, and this showed that results obtained in each case are statistically equal. (Author) [pt

  8. Self-decomposition of radiochemicals. Principles, control, observations and effects

    International Nuclear Information System (INIS)

    Evans, E.A.

    1976-01-01

    The aim of the booklet is to remind the established user of radiochemicals of the problems of self-decomposition and to inform those investigators who are new to the applications of radiotracers. The section headings are: introduction; radionuclides; mechanisms of decomposition; effects of temperature; control of decomposition; observations of self-decomposition (sections for compounds labelled with (a) carbon-14, (b) tritium, (c) phosphorus-32, (d) sulphur-35, (e) gamma- or X-ray emitting radionuclides, decomposition of labelled macromolecules); effects of impurities in radiotracer investigations; stability of labelled compounds during radiotracer studies. (U.K.)

  9. International intercalibration as a method for control of radiochemical analyses

    International Nuclear Information System (INIS)

    Angelova, A.; Totseva, R.; Karaivanova, R.; Dandulova, Z.; Botsova, L.

    1994-01-01

    The participation of the Radioecology Section at the National Centre for Radiology and Radiation Protection (NCRRP) in the International Interlaboratory Comparison of radiochemical analyses organized by WHO is reported. The method of evaluating accuracy of the results from inter calibrations concerning radionuclide determination of environmental samples is outlined. The data from analysis of cesium 137, strontium 90 and radium 226 in milk, sediments, soil and seaweed made by 21 laboratories are presented. They show a good accuracy values of the results from NCRRP. 1 tab. 2 figs., 6 refs

  10. Rapid, radiochemical-ligand binding assay for methotrexate

    International Nuclear Information System (INIS)

    Caston, J.D.

    1976-01-01

    A radiochemical ligand binding assay for methotrexate is provided. A binder factor comprising a partially purified dihydrofolic acid reductase preparation is employed. The binder factor is conveniently prepared by homogenizing a factor containing animal organ such as liver, and extracting with isotonic saline and ammonium sulfate. A binder cofactor, NADPH 2 , is also employed in the binding reaction. The procedure contemplates both direct and sequential assay techniques, and it is not interfered with by vast excesses of many natural folate derivatives. 12 claims, 6 drawing figures

  11. Guiding Principles for Sustainable Existing Buildings: Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Pope, Jason E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-11-11

    In 2006, the United States (U.S.) Department of Energy (DOE) signed the Federal Leadership in High Performance and Sustainable Buildings Memorandum of Understanding (MOU), along with 21 other agencies. Pacific Northwest National Laboratory (PNNL) is exceeding this requirement and, currently, about 25 percent of its buildings are High Performance and Sustainable Buildings. The pages that follow document the Guiding Principles conformance effort for the Radiochemical Processing Laboratory (RPL) at PNNL. The RPL effort is part of continued progress toward a building inventory that is 100 percent compliant with the Guiding Principles.

  12. Preparation of proton rich radionuclides in support of radiochemical analysis

    International Nuclear Information System (INIS)

    Jerome, Simon; Larijani, Cyrus; Parker, David

    2012-01-01

    The production of proton rich radionuclides supports a wide range of radiochemical analyses via radioactive yield tracers ( 95m Tc and 236 Pu). In recent years, NPL and the University of Birmingham cyclotron have collaborated to produce these, and other, radionuclides. - Highlights: ► In this paper we options for the production of Tc and Pu tracers. ► The irradiation and measurement of targets producing Tc-95 m and Pu-236 are described. ► Options for production are discussed. ► The results of this study and future work needed are described.

  13. Studies on some Indian paints for radiochemical plants

    International Nuclear Information System (INIS)

    Mahesh Kumar, V.V.; Srinivasan, R.; Natarajan, R.

    1996-01-01

    The choice of paints in areas subjected to contamination and radiation in nuclear installation need special attention. The types of generic coatings are examined with reference to these requirements. Among those examined, certain types of epoxy paints are found to be attractive for these applications. Samples of epoxy paints obtained from some Indian manufacturers are tested for their suitability. Decontaminability and radiation resistance properties are also evaluated with special reference to radiochemical plants. Important specifications for such applications are listed. This report summarizes the results of these studies. (author)

  14. Evaluation report on the R and D of the membrane separation process introduction technology; Makubunri process donyu gijutsu no kenkyu kaihatsu hyoka hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The paper reported the R and D of the membrane separation process introduction technology during a period of 1994 through 1998. The membrane separation technology is not associated with the phase change which requires large energy and expected to be an energy saving process. For the production of membranes required of high functions, the vapor deposition polymerization method was considered, and high order structure control of the membrane, control of adhesion and attachment, and control of orientation, and development of the high polymerization technology were required. For the high grade control of vapor polymerization, the substrate surface structure/quality were important. The molecular level analysis of the vapor deposition surface was also needed. Therefore, the paper took notice of STM (scanning tunneling microscopy), AFM (atomic force microscopy) and HREELS (high resolution electron energy loss spectroscopy) as surface atomic/molecular configuration analysis technology, and designed/fabricated and studied the high resolving power and high sensitivity analysis equipment using the analysis equipment which combined HREELS and STM and the analysis equipment using SFG (sum frequency generation) which can detect signals in the low frequency region. Making full use of the highest technology, technology was able to be developed for substrate surface analysis and surface reaction analysis technologies which become the basis of the high performance separation membrane fabrication technology by the vapor deposition polymerization method indispensable for introduction of the membrane separation process. The technology can be the base applicable to a lot of fields where surfaces and interfaces are concerned

  15. Assessment of radiochemical purity of [{sup 18}F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

    Energy Technology Data Exchange (ETDEWEB)

    Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z., E-mail: radiofarmacoscdtn@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil). Unidade de Pesquisa e Producao de Radiofarmacos

    2011-07-01

    The quality control of [{sup 18}F]fludeoxyglucose ({sup 18}FDG) has received attention due to its increasing clinical use. Although the quality requirements of {sup 18}FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of {sup 18}FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. {sup 18}FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of {sup 18}FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of {sup 18}FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of {sup 18}FDG, considering operational conditions of our laboratory. (author)

  16. Assessment of radiochemical purity of [18F]fludeoxyglucose by high pressure liquid chromatography (HPLC)

    International Nuclear Information System (INIS)

    Lacerda, Aline E.; Silva, Juliana B.; Silveira, Marina B.; Ferreira, Soraya Z.

    2011-01-01

    The quality control of [ 18 F]fludeoxyglucose ( 18 FDG) has received attention due to its increasing clinical use. Although the quality requirements of 18 FDG are established in various pharmacopoeia, the suitability of all testing methods used should be verified under actual conditions of use and documented. The aim of this study was to develop a high pressure liquid chromatography (HPLC) method for radiochemical purity evaluation of 18 FDG, based on pharmacopoeia references, and to verify its suitability for routine quality control in our centre. HPLC analysis was performed with an Agilent HPLC. 18 FDG and impurities were separated on an anion-exchange column by isocratic elution with 0.1 M NaOH as the mobile phase. Detection was accomplished with refractive index and NaI (Tl) scintillation detectors. The flow rate of the mobile phase was set at 0.8 mL/min and the column temperature was kept at 35 deg C. Specificity, linearity, precision and robustness were assessed to verify if the method was adequate for its intended purpose. Retention time of 18 FDG was not affected by the presence of other components of the formulation and a good peak resolution was achieved. The analytical curve of 18 FDG was linear, with a correlation coefficient value of 0.9995. Intraday repeatable precision, reported as the relative standard deviation, was 0.11%. Analytical procedure remained unaffected by small variations in mobile phase flow rate. Results evidenced that HPLC is suitable for radiochemical purity evaluation of 18 FDG, considering operational conditions of our laboratory. (author)

  17. Improving the radiochemical purity determination of 123I-labeled metaiodobenzylguanidine

    International Nuclear Information System (INIS)

    Luciana Carvalheira; Paulo Bechara Dutra; Paula Fernandes de Aguiar

    2014-01-01

    The HPLC method originally applied at the Nuclear Engineering Institute (IEN) for the radiochemical purity determination of 123iodine labeled m-iodobenzylguanidine ( 123 I-mIBG) takes 18.5 min. The final product release also depends on this result, and to facilitate this stage, we aimed to decrease this analysis time. We also intended to use fewer toxic compounds, if feasible. The optimization approach used herein was a combination of factorial and mixture designs to study simultaneously the selected variables. Analysis time, resolution and chromatograms aspect were the measured responses. The qualitative analysis of these responses provided the best chromatographic separation conditions that were 52 mM KH 2 PO 4 in a solution of ethanol and water (1:1), applying a flow rate of 0.50 mL min -1 and C18 column (4.6 × 250 mm, 5 μm). These optimum conditions not only decreased the analysis time in 61 %, but also allowed the reduction of mobile phase toxicity. To assure reliable data, method validation was performed for these conditions. The method has proved its specificity, the detection limit found was 3.70 × 10 -4 MBq mL -1 and the quantification limit has corresponded to 1.11 × 10 -3 MBq mL -1 . Repeatability and intermediate precision has not exceeded 3 and 5 %, respectively, and the accuracy has matched the interval of 95-105 %. This new method has been routinely applied in the radiochemical purity determination of 123 I-mIBG at IEN. (author)

  18. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    International Nuclear Information System (INIS)

    Shields, K.D.; Ballinger, M.Y.

    1999-03-01

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

  19. A radiochemical analyses of metastudtite and leachates from spent fuel

    International Nuclear Information System (INIS)

    McNamara, Bruce K.; Hanson, Brady D.; Buck, Edgar C.; Soderquist, Chuck Z.

    2004-01-01

    Immersion of commercial spent nuclear fuel (CSNF) in deionized water produced two novel corrosion products after a two-year contact period. Another unexpected result was that suspensions of aggregates were observed to form at the air-water interface for each of five samples. These solids were characterized, by SEM and XRD to be nearly pure metastudtite (UO4-2H2O); while the corrosion present on the surface of the fuel itself was determined to be studtite (UO4-2H2O). The occurrence of the floating phase prompted a radiochemical analysis of these solids. This chemical analysis was a unique opportunity to study the relatively pure corrosion phase for incorporation of radionuclides. The analysis indicated that high concentration of 90Sr, 137Cs, 99Tc, and that lower concentrations 237Np, 238, 239Pu and 243, 244Cm had partitioned with the air-water interface aggregates. The concentrations of 241Am were two orders of magnitude lower than the expected inventory in the suspended solids. The radiochemical analyses of the several leachate samples provide preliminary solubility data for the hydrogen peroxide leaching of CSNF and these data are compared to leaching of the same fuel in J-13 and deionized waters. The extent of fuel dissolution in these media are discussed

  20. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  1. RADIOCHEMICAL YIELDS OF GRAFT POLYMERIZATION REACTIONS OF CELLULOSE

    Energy Technology Data Exchange (ETDEWEB)

    Arthur, Jr, J C; Blouin, F A

    1963-12-15

    The preparation of radioinduced graft polymers of cotton cellulose, while retaining the fibrous nature and high molecular weight of the cellulose, depended primarily on the radiochemical yields of cellulose reactions and of graft polymerization reactions. Yields of the initial major molecular changes in cellulosic polymer indicated that, in the case of scission of the molecule and carboxyl group formation, chain reactions were not initiated by radiation; however, in the case of carbonyl group formation chain reactions were initiated but quickly terminated. Generally, experimental procedures, used in graft polymerization reactions, were: simultaneous irradiation reactions, that is, application of monomers or solutions of monomers to cellulose or chemically modified celluloses, then irradiation; and post-irradiation reactions, that is, irradiation of cellulose or chemically modified celluloses, then after removal from the field of radiation, contacting the irradiated cellulose with monomer. Some of the most important factors influencing the radiochemical yields of graft polymerization reactions, of styrene and acrylonitrile onto cellulose were: concentration of monomer in treating solution; solvent; ratio of monomer solution to cellulose; prior chemical modification of cellulose; and absence of oxygen, particularly in post-irradiation reactions. Experimental data are presented, and the direct and indirect effects of Co/sup 60/ gamma radiation on these reactions are discussed. (auth)

  2. Determination of selenium in roasted beans coffee samples consumed in Algeria by radiochemical neutron activation analysis method

    International Nuclear Information System (INIS)

    Messaoudi, Mohammed; Begaa, Samir; Hamidatou, Lylia; Salhi, M'hamed

    2018-01-01

    The essential trace element selenium is a focus of attention due to its effects on human health, there being consequences of both its deficiency and excess. Due to the ultra-trace content of selenium, the neutron activation analysis method (NAA) is difficult to apply. We therefore made use of the radiochemical neutron activation analysis (RNAA) to determine Se at low level concentrations in several consumed food items in Algeria. A radiochemical procedure based on liquid-liquid separation was established in our laboratory. In this research we focused on the determination of selenium in two species of coffee: Arabica and Robusta. The accuracy of the method was assessed by analyzing the certified reference material NIST-SRM 1573a (tomato leaves). The results obtained show a selenium variation from 0.025 to 0.052 μg/g in coffee beans and an average yield of the separation of about 85%. The results of this study were compared with those obtained with samples from Brazilian, Caribbean, Indian and Kenyan coffee beans.

  3. Investigation of the 168Hf electron capture decay using fast radiochemical separation

    International Nuclear Information System (INIS)

    Trubert, D.; Hussonnois, M.; Brillard, L.; Barci, V.; Ardisson, G.; Szeglowski, Z.; Constantinescu, O.

    1995-01-01

    The (EC + β + ) decay of 168 Hf, produced by the 156 Gd ( 16 O,4n) reaction, has been studied, with high efficiency HPGe coaxial detectors, using on-line measurements carried out with the RACHEL setup, built to investigate the chemical properties of transactinide elements. Off-line measurements were also carried out using catcher collection technique. Energies and intensities of 119 γ-lines are reported among which only two were known in the earlier study of Chu and Reednick. The 168 Lu level scheme built on the basis of single and γ-γ coincidence measurements, allows the interpretation of more than 79 γ-transitions, between 38 excited states reported for the first time. (orig.)

  4. Testing the radiochemical purity of radiopharmaceuticals: application to 99mTc-HMPAO

    International Nuclear Information System (INIS)

    Ait Ben Ali, S.; Darsin, D.; Rizzo, N.; Lours, S.; De Beco, V.; Dumont, A.; Goudou-Sinha, C.; Izembart, M.; Jourdain, J.R.; Lemercier, V.; Linsker, S.; Moati, F.; Piketty, M.L.; Schlageter, M.H.; Moretti, J.L.

    1997-01-01

    The low stability of 99m Tc-HMPAO imposes to carry out the quality testing within the 15 minutes following the preparation. This study has the aim of comparing different methods of radiochemical purity determination (RP) of this radiopharmaceutical in order to validate a fast, reproducible, feasible technique, capable of separating the primary lipophilic 99m Tc-HMPAO (I) of impurities: hydrophilic secondary complex (II), TcO 4 - , reduced and halyards Tc. The reference technique associating two thin-layer chromatographies (TLC), 'C1' and 'C2', has been compared with a TLC 'W' technique and with liquid-liquid extraction 'E' technique: C1 - stationary phase, ITLC Silica gel/mobile phase, Butanone-2; C2 - stationary phase, ITLC Silica gel/mobile phase, 0.9% NaCl; W - stationary phase, Papier Whatman n o 1/mobile phase, Ether; E - extraction with ethyls acetate /0.9% NaCl (1/1 v/v). The 'C1' chromatography allows isolating the reduced Tc and the complex II, the 'C2' chromatography does the same with TcO 4 - but it requires too long techniques (20 min.). The 'W' and 'E' techniques are rapid, reproducible and allow to separate the complex I from the other impurities without discrimination. However, as their results depend upon the deposited quantity of sampling, an optimization and standardization of the techniques are necessary. A forth technique by chromatography on Sep-Pak column is to be evaluated

  5. Paleomagnetism and radiochemical age estimates for Late Brunhes polarity episodes

    International Nuclear Information System (INIS)

    Denham, C.R.; Anderson, R.F.; Bacon, M.P.

    1977-01-01

    Several reversed polarity magnetozones occur within deep-sea sediment core CH57-8 from the Greater Antilles Outer Ridge, within sediment of latest Pleistocene/Late Brunhes age. The uppermost reversed interval spanning 31 data points coincides with the X faunal zone of the Last Interglacial Period. Radiochemical dating of cores CH57-8 and KN25-4 has shown that all the reversed polarity magnetozones are significantly younger than the Brunhes/Matuyama boundary at 0.7 m.y.B.P. A variation of the excess 230 Th method was used, in which 210 Po and 238 U were the actual radionuclides measured. In a third core from the Mid-Atlantic Ridge, the 210 Po results were similar to those which others obtained earlier by direct 230 Th measurements. (Auth.)

  6. Radiochemical analysis in the nuclear research establishment (KFA) Juelich, FRG

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    KFA Juelich is one of the two great nuclear research centres of the Federal Republic of Germany. About 3700 employees including about 700 scientists are engaged in a great number of programs and projects belonging to six main fields of research and development: high temperature reactor and energy techniques; nuclear fusion; properties of materials; materials research; life and environment; methods. In the article the radiochemical analysis work of the former Central Institute of Analytical Chemistry and its two successors is described: activation analysis, application of tracer techniques, fission product analysis. Further on the irradiation facilities are described, a short survey is given on the instrumentation, and the future work is outlined. (T.G.)

  7. Computer aided design of piping for a radiochemical plant

    Energy Technology Data Exchange (ETDEWEB)

    Selvaraj, P G; Chandrasekhar, A; Chandrasekar, A V [Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam (India); Raju, R P; Mahudeeswaran, K V; Kumar, S V [Reprocessing Group, Bhabha Atomic Research Centre, Mumbai (India)

    1994-06-01

    In a radiochemical plant such as reprocessing plants, process equipment, storage tanks, liquid transfer systems and the associated pipe lines etc. are housed in series of concrete cells. Availability of limited cell space/volume, provision of various modes of liquid transfers with associated redundancies and instrumentation lines with standby alternatives increase the overall piping density. Designing such high density piping layout without interference is quite complex and needs lot of human efforts. This paper briefly describes development of computer codes for the entire scheme of design, drafting and fabrication of piping for nuclear fuel reprocessing plant. The general organisation of various programs, their functions, the complete sequence of the scheme and the flow of data are presented. High degree of reliability of each routine, considerable error checking facilities, marking legends on the drawings, provision for scaling in drafting and accuracy to the extent of one mm in layout design are some of the important features of this scheme. (author). 1 fig.

  8. The design of a new radiochemical laboratory complex

    International Nuclear Information System (INIS)

    Lewis, A.G.

    1984-01-01

    A brief account is given of the history and scope of Amersham International plc in the manufacture of radiopharmaceuticals and other labelled organic compounds, and radioactive sources. Extra facilities were needed and a new site was found, and contracts placed for new radiochemical laboratories. The two new laboratories, which are described in some detail, are intended as follows: (a) a Medical Products building for the production of a range of diagnostic kits for use in the treatment of thyroid and other disorders, the main isotope used being iodine-125; and (b) the Chemical Products building, for the development and manufacture of a wide range of organic compounds, which are labelled with either tritium or carbon-14. Particular emphasis is given to the description of the air conditioning and ventilation systems, the open work benches, and the special ventilated enclosures, and the drainage system. Planning for maximum flexibility is also stressed. (U.K.)

  9. Fast analysis procedure of radiochemical coordinat uptake for methotrexate

    International Nuclear Information System (INIS)

    Caston, J.D.; Kamen, B.A.

    1976-01-01

    Under this invention, a radio-chemical analysis is submitted to determine the concentration of methotrexate or its equivalents in analysis in a biological medium. The amounts taken up of the labelled compound and the known concentrations of the unlabelled compound to be determined are radio-isotopically related to a first system containing a pre-determined amount of the labelled compound and a pre-determined amount of the unlabelled compound. In a second system, identical to the first, save that the sample of the biological medium to be analyzed takes the place of the unlabelled compound, the amount of labelled compound taken up is determined radio-isotopically. The concentration of the compound in the sample is then determined by correlation of the labelled compound uptake determined in the second system with the relation determined in the first system. The radio-isotopic relations and determinations may be made by direct and sequential analytical techniques [fr

  10. Radiochemical methods for studying lipase-catalyzed interesterification of lipids

    International Nuclear Information System (INIS)

    Schuch, R.; Mukherjee, K.D.

    1987-01-01

    Reactions involving lipase-catalyzed interesterification of lipids, which are of commendable interest in biotechnology, have been monitored and assayed by radiochemical methods using 14 C-labeled substrates. Medium chain (C 12 plus C 14 ) triacylglycerols were reacted in the presence of an immobilized lipase from Mucor miehei and hexane at 45 0 C with methyl [1- 14 C]oleate, [1- 14 C]oleic acid, [carboxyl- 14 C]trioleoylglycerol, [1- 14 C]octadecenyl alcohol, and [U- 14 C]glycerol, each of known specific activity. The reactions were monitored and the rate of interesterification determined by radio thin layer chromatography from the incorporation of radioactivity into acyl moieties of triacylglycerols (from methyl oleate, oleic acid, and trioleoylglycerol), alkyl moieties of wax esters (from octadecenyl alcohol), and into glycerol backbone of monoacylglycerols and diacylglycerols (from glycerol). (orig.)

  11. Research reactor FR2 - 20 years chemical and radiochemical measurements

    International Nuclear Information System (INIS)

    Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

    1986-09-01

    The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

  12. Radiochemical plasma salicylamide assay using ring-labeled tritiated salicylamide

    Energy Technology Data Exchange (ETDEWEB)

    Stella, V J; Varia, S A; Riedy, M

    1979-05-01

    A rat plasma salicylamide assay was developed using ring-labeled tritiated salicylamide, synthesized by reacting salicylamide with tritium oxide in the presence of heptafluorobutyric acid. The reaction yielded /sup 3/H-salicylamide of specific activity up to 8.41 mCi/mmole, 60% yield. Plasma containing /sup 3/H-salicylamide and its metabolites was extracted with a toluene-based scintillation fluid, which was subsequently counted. Specificity for free salicylamide was demonstrated by radiochemical and standard fluorescence plasma salicylamide level-time curves. Specificity resulted from nonextraction of the salicylamide sulfate and glucuronide metabolites. Sulfatase and beta-glucuronidase treatment allowed the analysis of plasma sulfate and glucuronide conjugates as free salicylamide. This procedure should be effective for the analysis of salicylamide and its metabolites in the presence of similar phenolic compounds.

  13. Radiochemical investigations on the solubility of molybdatophosphate in phosphate determination

    International Nuclear Information System (INIS)

    Noack, S.

    1975-01-01

    The solubility of various molybdatophosphates was determined under the conditions of a gravimetric phosphate determination by radiochemical means by labelling PO 4 3- with P-32. Starting with various conditions for phosphate determination via the molybdatophosphate of quinoline, 8-hydroxyquinoline, dimorpholino ethane, N,N,N',N'-tetrakis-β-hydroxypropyl ethylene diamine and N,N,N',N'-tetrakis-β-hydroxybutyl ethylene diamine, a general working rule was developed to determine the solubility. Taking the example of quinoline molybdatophosphates, a series of influencing factors - work, concentration and measuring parameters - were investigated in order to be able to limit the reliability region of the gravimetric phosphate determination. Depending on the conditions, the measured solubilities were between 10 -10 and 10 -6 Mol/l, the corresponding degrees of precipitation between 99.0 and 99.9999%. Apparent solubility products were calculated for the different molybdatophosphates using computer programmes especially developed for this purpose. (orig./RB) [de

  14. A rapid, simple method for obtaining radiochemically pure hepatic heme

    International Nuclear Information System (INIS)

    Bonkowski, H.L.; Bement, W.J.; Erny, R.

    1978-01-01

    Radioactively-labelled heme has usually been isolated from liver to which unlabelled carrier has been added by long, laborious techniques involving organic solvent extraction followed by crystallization. A simpler, rapid method is devised for obtaining radiochemically-pure heme synthesized in vivo in rat liver from delta-amino[4- 14 C]levulinate. This method, in which the heme is extracted into ethyl acetate/glacial acetic acid and in which porphyrins are removed from the heme-containing organic phase with HCl washes, does not require addition of carrier heme. The new method gives better heme recoveries than and heme specific activities identical to, those obtained using the crystallization method. In this new method heme must be synthesized from delta-amino[4- 14 C]levulinate; it is not satisfactory to use [2- 14 C]glycine substrate because non-heme counts are isolated in the heme fraction. (Auth.)

  15. Radiochemical analyses of several spent fuel Approved Testing Materials

    International Nuclear Information System (INIS)

    Guenther, R.J.; Blahnik, D.E.; Wildung, N.J.

    1994-09-01

    Radiochemical characterization data are described for UO 2 and UO 2 plus 3 wt% Gd 2 O 3 commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, 14 C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program

  16. Radiochemical study on preparation and quality control of 1-125/1-131 labelled some organic compounds for medical uses

    International Nuclear Information System (INIS)

    El-azoney, K.M.S.E.

    1997-01-01

    The main objective of this thesis is to investigate the optimum condition for the radioiodination of some organic compounds which find wide applications in nuclear medicine. Iodine-131 (T 1 /2= 8.04 d) which is of great importance in the field, are used for this purpose. long chain fatty acids such as 16-Bromo-hexadecanoic (16-brHDA) and -phenyl -fatty acids such as 15-p-iodophenyl pentadecanoic acid (p-IPPA) will be used as model substrates. 1- Labelling of 16-Br-HDA with Na 131 I. Labelling of 16-BrHDA will be investigated via the non-isotopic exchange between 16-Br HDA and Na 131 I to give 16- 131 IHDA. In order to obtain a high radiochemical yield with high radiochemical purity for the product 16- 131 IHDA, simple and fast methods will be followed. The influence of reagents concentrations, time, temperature, solvents and four quaternary ammonium salts as phase transfer catalysts with only one crown ether will be studied. The determination of reaction velocities and activation energies of catalysed systems was effected and compared with results on the dry state system. 2- Labelling of p-Ipa with Na 131 I. Radioiodination of 15-p-iodophenyl pentadecanoic acid is investigated by the nucleophilic substitution reaction via the isotopic exchange between p-Ipa and Na 131 I. As with 16-BrHDA, factors affecting the labelling yield such as reagent concentrations, solvents, reaction time, temperature and catalyst, is examine. The effect of different temperatures on the radiochemical yield of P- 131 Ipa is studied to determine the activation energy of the exchange reaction. Because of the necessity to separate the iodinated products from the starting materials, high performance liquid chromatographic techniques were applied for this purpose. 3.15 figs., 3.2 tabs., 179 refs

  17. Feasibility studies to assess the use of 236Pu as a radiochemical yield monitor in bioassay samples

    International Nuclear Information System (INIS)

    Sawant, P.D.; Kalsi, P.C.

    2007-01-01

    Various plutonium compounds are handled in nuclear facilities of BARC. Hence, there is a possibility of occupational workers getting exposed to Pu. In vitro bioassay monitoring in which Pu is separated by chemical procedures from excreta samples and estimated by alpha-spectrometry, is the method of choice for the evaluation of internal dose to the occupational workers handling Pu. However, this method requires a suitable Pu tracer for reducing the uncertainties due to chemical yield in the separation, electro-deposition and counting efficiency. 242 Pu is commonly used as a tracer but due to its non-availability, efforts were made earlier to indigenously synthesis 236 Pu by proton irradiation of 237 Np in BARC-TIFR pelletron facility. The present study, reports the feasibility of using 236 Pu as a radiochemical yield monitor (tracer) in bioassay samples. (author)

  18. Cell surface engineering of Saccharomyces cerevisiae combined with membrane separation technology for xylitol production from rice straw hydrolysate.

    Science.gov (United States)

    Guirimand, Gregory; Sasaki, Kengo; Inokuma, Kentaro; Bamba, Takahiro; Hasunuma, Tomohisa; Kondo, Akihiko

    2016-04-01

    Xylitol, a value-added polyol deriving from D-xylose, is widely used in both the food and pharmaceutical industries. Despite extensive studies aiming to streamline the production of xylitol, the manufacturing cost of this product remains high while demand is constantly growing worldwide. Biotechnological production of xylitol from lignocellulosic waste may constitute an advantageous and sustainable option to address this issue. However, to date, there have been few reports of biomass conversion to xylitol. In the present study, xylitol was directly produced from rice straw hydrolysate using a recombinant Saccharomyces cerevisiae YPH499 strain expressing cytosolic xylose reductase (XR), along with β-glucosidase (BGL), xylosidase (XYL), and xylanase (XYN) enzymes (co-)displayed on the cell surface; xylitol production by this strain did not require addition of any commercial enzymes. All of these enzymes contributed to the consolidated bioprocessing (CBP) of the lignocellulosic hydrolysate to xylitol to produce 5.8 g/L xylitol with 79.5 % of theoretical yield from xylose contained in the biomass. Furthermore, nanofiltration of the rice straw hydrolysate provided removal of fermentation inhibitors while simultaneously increasing sugar concentrations, facilitating high concentration xylitol production (37.9 g/L) in the CBP. This study is the first report (to our knowledge) of the combination of cell surface engineering approach and membrane separation technology for xylitol production, which could be extended to further industrial applications.

  19. The development of radioactive waste treatment technology(IV)

    International Nuclear Information System (INIS)

    Kim, Joon Hyung; Yim, Sung Paal; Lee, Kune Woo; Yoo, Jeong Woo; Kim, Young Min; Park, Seong Chul

    1992-03-01

    Following studies were performed in the project of development of radioactive waste treatment technology. 1) Treatment of radioactive borated liquid wastes by reverse osmosis : Separation characteristics of boric acid were estimated using cellulose acetate membrane and aromatic polyamide membrane. The performance of reverse osmosis process was evaluated in terms of boric acid recovery, radiochemical rejection, and membrane flux by operating variables such as applied pressure and feed concentration. 2) Oily waste treatment : The mathematical model to estimate oil removal efficiency is to be proposed at coalescence column. 3) Treatment of radioactive laundry waste 4) Comparison of evaporation and ion-exchange 5) State of the art of high integrity container. (Author)

  20. Fast radiochemical procedure to measure neptunium, plutonium, americium and curium in environmental samples for application in environmental monitoring and in radioecology research

    International Nuclear Information System (INIS)

    Pimpel, M.; Schuettelkopf, H.

    1984-01-01

    A radiochemical method is described by which Np, Pu, Am and Cm in environmental samples can be determined. The transuranium elements are dissolved with acids out of the ashed material. Np/Pu is separated from Am/Cm by sequential extraction using TOPO/cyclohexane. The two fractions are radiochemically purified. Np-237, Pu-239+240, Pu-238 and Pu-236 as well as Am-243, Am-241, Cm-244 and Cm-242 are measured by alpha spectrometery. Pu-236, Am-243 and Np-239 are used to determine the respective yields. A fast method of Np-239 preparation is described. The chemical yields range from 60 to 90%. The detection limit attained per nuclide is 10 fCi/sample. 20 reference, 1 table

  1. Remote-controlled module-assisted synthesis of O-(2-[18F]fluoroethyl)-L-tyrosine as tumor PET tracer using two different radiochemical routes

    International Nuclear Information System (INIS)

    Wang Mingwei; Yin Duanzhi; Zhang Lan; Zhou Wei; Wang Yongxian

    2006-01-01

    The positron-emitter fluorine-18 labeled amino acid O-(2-[ 18 F]fluoroethyl)-L-tyrosine ([ 18 F]FET) has shown very promising perspectives for brain tumor diagnosis with positron emission tomography (PET). There have been two existing preparation routes of [ 18 F]FET named direct nucleophilic radiofiuorination of protected L-tyrosine and radiofiuoroallcylation of unprotected L-tyrosine, respectively. A general module was designed specifically for the routine synthesis of [ 18 F]FET, which could be suitable for the present two chemical methods with simple modifications. The fluorinated intermediates and the final product were separated and purified using solid phase extraction (SPE) on the Sep-Pak silica plus cartridge instead of the time-consuming high performance liquid chromatography (HPLC) procedures. The total synthesis time was about 50-60 rain with good radiochemical yield (about 20-40%, no-decay-corrected) and good radiochemical purity (more than 97%) for both the synthetic methods. (authors)

  2. Costs of slurry separation technologies and alternative use of the solid fraction for biogas production or burning

    DEFF Research Database (Denmark)

    Jacobsen, Brian H.

    2011-01-01

    Separation is an option when livestock are produced in livestock intensive areas producing a surplus of nutrients. Separation of the slurry into a liquid nitrogen rich fraction and a more solid phosphorus rich fraction, which is exported away from the farm, may alleviate this problem. Separation...

  3. Weak cation magnetic separation technology and MALDI-TOF-MS in screening serum protein markers in primary type I osteoporosis.

    Science.gov (United States)

    Shi, X L; Li, C W; Liang, B C; He, K H; Li, X Y

    2015-11-30

    We investigated weak cation magnetic separation technology and matrix-assisted laser desorption ionization-time of flight-mass spectrometry (MALDI-TOF-MS) in screening serum protein markers of primary type I osteoporosis. We selected 16 postmenopausal women with osteoporosis and nine postmenopausal women as controls to find a new method for screening biomarkers and establishing a diagnostic model for primary type I osteoporosis. Serum samples were obtained from controls and patients. Serum protein was extracted with the WCX protein chip system; protein fingerprints were examined using MALDI-TOF-MS. The preprocessed and model construction data were handled by the ProteinChip system. The diagnostic models were established using a genetic arithmetic model combined with a support vector machine (SVM). The SVM model with the highest Youden index was selected. Combinations with the highest accuracy in distinguishing different groups of data were selected as potential biomarkers. From the two groups of serum proteins, 123 cumulative MS protein peaks were selected. Significant intensity differences in the protein peaks of 16 postmenopausal women with osteoporosis were screened. The difference in Youden index between the four groups of protein peaks showed that the highest peaks had mass-to-charge ratios of 8909.047, 8690.658, 13745.48, and 15114.52. A diagnosis model was established with these four markers as the candidates, and the model specificity and sensitivity were found to be 100%. Two groups of specimens in the SVM results on the scatterplot were distinguishable. We established a diagnosis model, and provided a new serological method for screening and diagnosis of osteoporosis with high sensitivity and specificity.

  4. Testing the radiochemical purity of a radiopharmaceutical: study of 99mTc-Tetrofosmin (Myoview)

    International Nuclear Information System (INIS)

    Moati, F.; Quartarone, C.; Jourdain, J.R.; Rizzo, N.; Dumont, A.; De Beco, V.; Ait Ben Ali, S.; Lours, S.; Piketty, M.L.; Izembart, M.; Goudou, C.; Lemercier, V.; Schlageter, M.H.; Moretti, J.L.; Progent, A.

    1997-01-01

    The goal of this study is to optimize the testing method of radiochemical purity (RCP) of 99m Tc-Tetrofosmin proposed by the Amersham Company: thin-layer chromatography (TLC); ITLC-SG support, migration on 15 Cm; acetone-dichloromethane mobile phase, (35/65, v/v), This technique allows separating the reduced-Tc (Rf = 0), the TcO 4 - (Rf = 1), and in intermediary position (0.2 99m Tc-Tetrofosmin. The results of RCP depend on working conditions, particularly, on the volume of deposit (10 to 20 μl, expected). If the deposited is too small, the 99m Tc-Tetrofosmin does not migrate. With a volume of 20 μl, the separation is weak and the peak width is un-resolvable. The results obtained correspond to the following operational conditions: migration on 8 cm; deposit of 8 to 10 μl; no drying. In these conditions the peak of 99m Tc-Tetrofosmin is well singled out: migration Rf of 0.375 to 0.625. These results have been obtained by the analysis of radio-chromatographic peak. Every strip has been cut cm by cm and the activity was measured by a gamma counter. Repeatability of the method on a series of 8 tests is good: average RCP 93.22%, mean value = 93.24%. The reproducibility was realized by measuring directly by the activity-meter the activity corresponding to 3 identifiable peaks: Reduced Tc (Rf 4 - (Rf 99m Tc-Tetrofosmin (0.25 < Rf < 0.75). On the 21 effectuated tests the inter-test RCP reproducibility was good: average value = 95.24%, CV = 2.07%, mean value 95.3%). In conclusion, the miniaturization improves the separation by Myoview (0.25 < Rf < 0.75), diminishes the migration time by a factor 4 and lowers the reactive cost of testing by 50%

  5. Radioactive preparations. Determination of radiochemical purity by thin-layer chromatography

    International Nuclear Information System (INIS)

    1986-01-01

    The standard sets the data which must be attached to every sample, and the equipment, chemicals and auxiliary substances used in the determination of radiochemical purity of substances by chromatography. Described are preparation of the sample, the procedure of sample deposition, the development, drying and detection of the radioactive preparation. The qualitative and quantitative assessment of the radiochromatogram is described as are the calculation of radiochemical purity and the determination of the reproducibility of measurement of radiochemical purity of radioactive preparations. (E.S.)

  6. Costs of slurry separation technologies and alternative use of the solid fraction for biogas production or burning

    DEFF Research Database (Denmark)

    Jacobsen, Brian H.

    2011-01-01

    separation, in order to establish the overall costs. Key parameters are livestock density, transport distance, price of additional land and cost of separation. The conclusion is that unless land prices or prices on slurry agreements are very high, traditional handling of animal manure has the lowest costs......The purpose of this paper is to analyse different separation concepts in order to evaluate the overall costs based on a systems approach from stable to field. When livestock are produced in livestock intensive areas the distribution of manure without creating a surplus of nutrients is often....... Decanter separation can be the cheapest if area is limited and cooperation with neighbours is possible as large volumes reduce separation costs per tonne. Flocculation is the best if much P has to be removed from the farm in the solid fraction. Separation will in the future in many cases be combined...

  7. Dramatically improve the Safety Performance of Li ion Battery Separators and Reduce the Manufacturing Cost Using Ultraviolet Curing and High Precision Coating Technologies

    Energy Technology Data Exchange (ETDEWEB)

    Voelker, Gary [Miltec UV International, LLC, Stevensville, MD (United States); Arnold, John [Miltec UV International, LLC, Stevensville, MD (United States)

    2017-06-30

    The objective of this project was to improve the safety of operation of Lithium ion batteries (LIB)and at the same time significantly reduce the manufacturing cost of LIB separators. The project was very successful in demonstrating the improved performance and reduced cost attributed to using UV curable binder and high speed printing technology to place a very thin and precisely controlled ceramic layer on the surface of base separators made of polyolefins such as Polyethylene, Polypropylene and combinations of the two as well as cellulosic base separators. The underlying need for this new technology is the recently identified potential of fire in large format Lithium ion batteries used in hybrid, plug-in hybrid and electric vehicles. The primary potential cause of battery fire is thermal runaway caused by several different electrical or mechanical mechanisms; such as, overcharge, puncture, overheating, compaction, and internal short circuit. During thermal runaway, the ideal separator prevents ion flow and continues to physically separate the anode from the cathode. If the temperature of the battery gets higher, the separator may melt and partially clog the pores and help prevent ion flows but it also can shrink which can result in physical contact of the electrodes and accelerate thermal run-away even further. Ceramic coated separators eliminate many of the problems related to the usage of traditional separators. The ceramic coating provides an electrically insulating layer that retains its physical integrity at high temperature, allows for more efficient thermal heat transfer, helps reduce thermal shrinkage, and inhibits dendrite growth that could create a potential short circuit. The use of Ultraviolet (UV) chemistry to bind fine ceramic particles on separators is a unique and innovative approach primarily because of the instant curing of the UV curable binder upon exposure to UV light. This significant reduction in drying/curing time significantly reduces the

  8. Evaluation of radiochemical neutron activation analysis methods for determination of arsenic in biological materials.

    Science.gov (United States)

    Paul, Rick L

    2011-01-01

    Radiochemical neutron activation analysis (RNAA) with retention on hydrated manganese dioxide (HMD) has played a key role in the certification of As in biological materials at NIST. Although this method provides very high and reproducible yields and detection limits at low microgram/kilogram levels, counting geometry uncertainties may arise from unequal distribution of As in the HMD, and arsenic detection limits may not be optimal due to significant retention of other elements. An alternate RNAA procedure with separation of arsenic by solvent extraction has been investigated. After digestion of samples in nitric and perchloric acids, As(III) is extracted from 2 M sulfuric acid solution into a solution of zinc diethyldithiocarbamate in chloroform. Counting of (76)As allows quantitation of arsenic. Addition of an (77)As tracer solution prior to dissolution allows correction for chemical yield and counting geometries, further improving reproducibility. The HMD and solvent extraction procedures for arsenic were compared through analysis of SRMs 1577c (bovine liver), 1547 (peach leaves), and 1575a (pine needles). Both methods gave As results in agreement with certified values with comparable reproducibility. However, the solvent extraction method yields a factor of 3 improvement in detection limits and is less time-consuming than the HMD method. The new method shows great promise for use in As certification in reference materials.

  9. Method Development of Cadmium Investigation in Rice by Radiochemical Neutron Activation Analysis

    International Nuclear Information System (INIS)

    Promsawad, Arunee; Pareepart, Ratirot; Laoharojanaphand, Sirinart; Arunee, Kongsakpaisal

    2007-08-01

    Full text: A radiochemical neutron activation analysis for the determination of cadmium was investigated. A chemical separation of cadmium utilized ion exchange chromatography of a strong basic anion-exchange resin BIO-RAD 1X 8 (Chloride form). The adsorbing medium of 2M HCl was found to be the most suitable among the concentration attempted (2, 4, 6, 8 and 10M HCl) and the eluent for desorption of the cadmium from column was 8M NH 3 solution. A chemical yield of 95% was found. The method has been evaluated by analyzing certified reference materials with 0.5.g/g (SRM 1577b, Bovine Liver) and 2.48.g/g (SRM 1566b, Oyster Tissue) cadmium. The agreement of the result with certified values is within 92% for Bovine Liver and 96% for Oyster Tissue. The method developed was applied to determine the cadmium concentrations in contaminated Thai rice. It was found that the cadmium concentrations ranged from 7.4 to 578.9 ppb

  10. Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

    International Nuclear Information System (INIS)

    Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

    1986-01-01

    Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving safe standby condition by the end of FY 1989. The ventilation system must maintain containment thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding, Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation

  11. Standard method of test for atom percent fission in uranium fuel - radiochemical method

    International Nuclear Information System (INIS)

    Anon.

    The determination of the U at. % fission that has occurred in U fuel from an analysis of the 137 Cs ratio to U ratio after irradiation is described. The method is applicable to high-density, clad U fuels (metal, alloys, or ceramic compounds) in which no separation of U and Cs has occurred. The fuels are best aged for several months after irradiation in order to reduce the 13-day 136 Cs activity. The fuel is dissolved and diluted to produce a solution containing a final concentration of U of 100 to 1000 mg U/l. The 137 Cs concentration is determined by ASTM method E 320, for Radiochemical Determination of Cesium-137 in Nuclear Fuel Solutions, and the U concentration is determined by ASTM method E 267, for Determination of Uranium and Plutonium Concentrations and Isotopic Abundances, ASTM method E 318, for Colorimetric Determination of Uranium by Controlled-Potential Coulometry. Calculations are given for correcting the 137 Cs concentration for decay during and after irradiation. The accuracy of this method is limited, not only by the experimental errors with which the fission yield and the half-life of 137 Cs are known

  12. Determination of radiochemical purity of 125I-TOC and 125I-F-PGA

    International Nuclear Information System (INIS)

    Yang Keya; Fan Wo; Zhang Youjiu; Xu Yujie; Zhu Ran; Hu Mingjiang

    2006-01-01

    To explore whether there is accordance among three determination methods of the radiochemical purity of [Tyr 3 ] octreotide (TOC) and folate-penicillin G amidase conjugate (F-PGA), which are both labeled with 125 I by Iodogen method, the RCP of the labelings are determined by high performance liquid chromatography (HPLC), paper chromatography and trichloroacetic acid (TCA) precipitation, in which four different concentrations of proteins are used to investigate the effect of them on the determination of RCP. It is shown that both HPLC and paper chromatography can separate the labelings from free iodine efficiently, though HPLC is the most precise and reliable method to determinate RCP of such labelings. In TCA precipitation, the RCP measured with 0.2%BSA is the lowest, but those with three other concentrations of the BSA are similar (P>0.05). When RCP 0.05), whereas higher than that with HPLC (P 10%, the RCP of 125 I-TOC obtained by TCA precipitation is a bit lower than those by two other methods (P 0.05), and there are no significant differences to determinate the RCP of 125 I-F-PGA (P>0.05). The three methods are correlated each other (r=0.0996-0.999, P<0.001). (authors)

  13. Placement of the radiochemical processing plant at Oak Ridge National Laboratory into a safe standby condition

    International Nuclear Information System (INIS)

    Holladay, D.W.; Bopp, C.D.; Farmer, A.J.; Johnson, J.K.; Miller, C.H.; Powers, B.A.; Collins, E.D.

    1986-01-01

    Extensive upgrade, cleanup, and decontamination efforts are being conducted for appropriate areas in the Radiochemical Processing Plant (RPP) with the goal of achieving ''safe standby'' condition by the end of FY 1989. The ventilation system must maintain containment; thus, it is being upgraded via demolition and replacement of marginally adequate ductwork, fans, and control systems. Areas that are being decontaminated and stripped of various services (e.g., piping, ductwork, and process tanks) include hot cells, makeup rooms, and pipe tunnels. Operating equipment that is being decontaminated includes glove boxes and hoods. Replacement of the ventilation system and removal of equipment from pipe tunnels, cells, and makeup rooms are accomplished by contact labor by workers using proper attire, safety rules, and shielding. Removal of contaminated ductwork and piping is conducted with containment enclosures that are strategically located at breakpoints, and methods of separation are chosen to conform with health physics requirements. The methods of cutting contaminated piping and ductwork include portable reciprocating saws, pipe cutters, burning, and plasma torch. Specially designed containment enclosures will be used to prevent the spread of radioactive contamination while maintaining adequate ventilation. 6 figs

  14. The suspended magnetic separator with large blocks from NdFeB magnets and its long term technological tests

    Czech Academy of Sciences Publication Activity Database

    Žežulka, Václav; Straka, Pavel

    2011-01-01

    Roč. 8, č. 1 (2011), s. 89-97 ISSN 1214-9705 Institutional research plan: CEZ:AV0Z30460519 Keywords : magnetic separation * magnetic separators * magnetic circuits Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 0.530, year: 2011 http://www.irsm.cas.cz/abstracts/AGG/01_11/8_Zezulka.pdf

  15. Development of a radiochemical sensor. Part I: Feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    Tarancon, A. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain); Garcia, J.F. [Departament de Pintura, Facultat de Belles Arts, Universitat de Barcelona, C/ Pau Gargallo 4, 08028 Barcelona (Spain)]. E-mail: jfgarcia@apolo.qui.ub.es; Rauret, G. [Departament de Quimica Analitica, Facultat de Quimica, Universitat de Barcelona, C/ Marti Franques 1, 08028 Barcelona (Spain)

    2005-05-04

    The evolution of nuclear activities and criteria for radiation protection have led to a continuous increase in measures to monitor and control the environment and therefore in the number of determinations required for such purposes. Classical analytical procedures are time-consuming, labor-intense and generate a large amount of waste. The alternative use of sensors for such determinations has seen very limited development. The present study focuses on the evaluation of the behavior of a prototype radiochemical sensor for liquid effluents. The sensor is based on a receptor made of a plastic scintillator and is capable of continuous, on-time and accurate remote quantification of the activity of alpha, beta and beta-gamma emitters. Low-level active solutions of {sup 90}Sr/{sup 90}Y, {sup 238}Pu, {sup 134}Cs and {sup 60}Co in matrices of groundwater, seawater and drinking water were quantified with prediction errors lower than 10% in most cases. The study also yields information about light generation and transmission and transductor configuration that will be useful in the design of future versions of this sensor.

  16. Planning for maintenance in radiochemical facilities [Paper No.: VB-2

    International Nuclear Information System (INIS)

    Balasubramanian, G.R.

    1981-01-01

    Reprocessing facilities in the earlier stages of development were planned mainly based on the concept of direct maintenance in view of the inherent advantage of man-machine interface and initial savings in the investment costs. With the mechanical processes finding a firm place in head-end operation and increase in down time necessary for elaborate decontamination efforts even for a minor modification has led to the review of the concept. For the same reason, the recent plants are based on the concept of harmonious blend of both direct and remote maintenance. The paper describes the planning needed from consideration of various aspects related to such concepts of maintenance during different phases of such type of facilities, highlighting some of the tools and special equipments to be developed for this purpose. A brief description of recent development in the field of remote maintenance is also given. Though the basic hot facility of reference is the one of reprocessing fast reactor fuels, the concepts and systems discussed are equally applicable to other radiochemical and radiometallurgical facilities also. (author)

  17. Waste treatment at the Radiochemical Engineering Development Center

    International Nuclear Information System (INIS)

    Brunson, R.R.; Bond, W.D.; Chattin, F.R.; Collins, R.T.; Sullivan, G.R.; Wiles, R.H.

    1997-01-01

    At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste streams for removal of excess radioactive contaminants at the REDC. Radionuclides that are removed will be stored as solids and thus the future discharge of radionuclides to liquid low level waste tank storage will be greatly reduced. The treatment system is of modular design and is installed in a hot cell (Cubicle 7) in Building 7920 at the REDC where preliminary testing is in progress. The module incorporates the following: (1) a resorcinol-formaldehyde resin column for Cs removal, (2) a cross flow filtration unit for removal of rare earths and actinides as hydroxide, and (3) a waste solidification unit. Process flowsheets for operation of the module, key features of the module design, and its computer-assisted control system are presented. Good operability of the cross flow filter system is mandatory to the successful treatment of REDC wastes. Results of tests to date on the operation of the filter in its slurry collection mode and its slurry washing mode are presented. These tests include the effects of entrained organic solvent in the waste stream feed to the filter

  18. Remote sampling of process fluids in radiochemical plants

    International Nuclear Information System (INIS)

    Sengar, P.B.; Bhattacharya, R.; Ozarde, P. D.; Rana, D.S.

    1990-01-01

    Sampling of process fluids, continuous or periodic, is an essential requirement in any chemical process plant, so as to keep a control on process variables. In a radiochemical plant the task of taking and conveying the samples is a very tricky affair. This is due to the fact that neither the vessels/equipment containing radioactive effluents can be approached for manual sampling nor sampled fluids can be handled directly. The problems become more accute with higher levels of radioactivity. As such, inovative systems have to be devised to obtain and handle the raioactive samples employing remote operations. The remote sampling system developed in this Division has some of the unique features such as taking only requisite amount of samples in microlitre range, practically maintenance free design, avoidence of excess radioactive fluids coming out of process systems, etc. The paper describes in detail the design of remote sampling system and compares the same with existing systems. The design efforts are towards simplicity in operation, obtaining homogenised representative samples and highly economical on man-rem expenditure. The performance of a prototype system has also been evaluated. (author). 3 refs

  19. Automated radiochemical synthesis and biodistribution of [11C]l-α-acetylmethadol ([11C]LAAM)

    International Nuclear Information System (INIS)

    Sai, Kiran Kumar Solingapuram; Fan, Jinda; Tu, Zhude; Zerkel, Patrick; Mach, Robert H.; Kharasch, Evan D.

    2014-01-01

    Long-acting opioid agonists methadone and l-α-acetylmethadol (LAAM) prevent withdrawal in opioid-dependent persons. Attempts to synthesize [ 11 C]-methadone for PET evaluation of brain disposition were unsuccessful. Owing, however, to structural and pharmacologic similarities, we aimed to develop [ 11 C]LAAM as a PET ligand to probe the brain exposure of long-lasting opioids in humans. This manuscript describes [ 11 C]LAAM synthesis and its biodistribution in mice. The radiochemical synthetic strategy afforded high radiochemical yield, purity and specific activity, thereby making the synthesis adaptable to automated modules. - Highlights: • Radiochemical synthesis of opioid [ 11 C]l-α-acetylmethadol (LAAM) described for the first time. • High radiochemical yield, purity and specific activity. • Easily reproducible and adaptable synthesis to any C-11 automated modules. • [ 11 C]LAAM utility as a PET radiopharmaceutical for assessing brain penetration

  20. Investigations of radiochemical methods for the platinum group metals for NAA

    International Nuclear Information System (INIS)

    Tredoux, M.

    A radiochemical procedure for the determination of the platinum group metals and gold is outlined in this report. The sample is irradiated, treated with acids and passed through anion-exchange columns before being determined by gamma spectrometry

  1. Radiochemical and biological control of metaiodobenzyl-guanidine (MIBG) labeled with 131I

    International Nuclear Information System (INIS)

    Barboza, M.R.F.F. de; Muramoto, E.; Colturato, M.T.; Silva Valente Goncalves, R. da; Pereira, N.P.S. de; Almeida, M.A.T.M. de; Silva, C.P.G. da.

    1988-07-01

    This study shows the standardization of the radiochemical control of MIBG - 131 I in eletrophoretic system and also the biological control in Wistar rat for a period of time, not longer than 60 minutes after tracer administration. (author) [pt

  2. The use of radiochemical analysis for detecting biotracers of food radioactive contamination in Cherkasy Region

    International Nuclear Information System (INIS)

    Matvyijenko, D.G.

    2003-01-01

    Stable biotracers of radioactive contamination according to the findings of analytical control of the foodstuffs was determined. The use of radiochemical analysis for determining the activity of the foodstuffs and water (Sr-90, Cs-137) was evaluated

  3. The application of transition metal ion chromatography to the determination of elemental and radiochemical species in PWR primary coolant

    International Nuclear Information System (INIS)

    Bridle, D.A.; Brown, G.R.; Johnson, P.A.V.

    1992-01-01

    The accurate determination of both elemental and radiochemical transition metal corrosion products, particularly cobalt and nickel, in PWR coolants is necessary if the transport mechanisms and their role in the development of out-of-core radiation fields are to be fully understood. AEA Technology, Winfrith, has collaborated for several years with a number of PWR utilities in Europe, developing advanced sampling and analytical techniques for the determination of both soluble and insoluble corrosion products in primary coolant. The design and installation of continuously flowing isokinetic capillary modifications to the existing sampling systems has been shown to be an effective method of providing a low, but representative, sample flow from high pressure systems for on-line determination of corrosion product species. Transition metal ion chromatography coupled with gamma-spectrometry has been used to determine both insoluble and soluble elemental and radiochemical species in reactor coolant, with particular attention being given to the determination of soluble elemental cobalt at levels as low as 1 ng per kg. Soluble species were determined directly following their concentration from up to 1 litre of coolant. Insoluble species collected on 0.45 micron filter membranes, following filtration of up to 1500 litres of coolant, were solubilised by fusion with potassium hydrogen sulphate before the application of ion chromatography. In each case the eluant from the chromatographic column was collected and the radionuclides determined by gamma-spectrometry

  4. Report on the separation and refining technology sub-committee meetings in fiscal 1987; 1987 nendo bunri seisei gijutsu bukai hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-03-01

    The separation and refining technology sub-committee has held two meetings in this fiscal year. The first sub-committee meeting (October 9, 1987) was held for the major agenda of the research and development of the basic studies; as the summary of the achievements in fiscal 1986, the up-grading by fractions and of the total fraction collectively, up-grading of kerosene and light oil fractions, up-grading of medium to heavy fractions; and as the study plans for fiscal 1987, the up-grading of coal liquefied oil, a technology to separate hetero compounds, development of their applications, and the reports and deliberations thereon. The major agenda of the second sub-committee meeting (February 10, 1988) were the interim report on the achievements in research of up-grading the coal liquefied oil in fiscal 1987, the interim reports on research achievements in the technology to separate hetero compounds and development of its applications, and the reports and deliberations thereon. The conventional up-grading sub-committee was dissolved in fiscal 1987 to form a new organization, whereas the 'separation and refining sub-committee' was founded newly. With respect to the up-grading matters, reports were given on the achievements thereon as a result of using a micro reaction device and a bench reaction device as in the past, and on the achievements in the application development. In addition, on the hetero related matters, directionality of the survey and the result therefrom were reported. (NEDO)

  5. Current studies of biological materials using instrumental and radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Fardy, J.J.; McOrist, G.D.; Farrar, Y.J.

    1985-01-01

    Instrumental neutron activation analysis still remains the preferred option when analysing the trace element distribution in a wide rage of materials by neutron activation analysis. However, when lower limits of detection are required or major interferences reduce the effectiveness of this technique, radiochemical neutron activation analysis is applied. This paper examines the current use of both methods and the development of rapid radiochemical techniques for analysis of the biological materials, hair, cow's milk, human's milk, milk powder, blood and blood serum

  6. A comparison of the radiochemical stability of different iodine-131 labelled metaiodobenzylguanidine formulations for therapeutic use

    International Nuclear Information System (INIS)

    Wafelman, A.R.; Beijnen, J.H.; Hoefnagel, C.A.; Maes, R.A.A.

    1994-01-01

    The results of a stability study of three commercially available formulations of [ 131 I]MIBG for therapeutic use and an unstabilized formulation, stored under various conditions, are presented. The stability was followed for 20 days. In all formulations tested, free [ 131 I]iodide, formed by radiolysis, was the most important radiochemical impurity. The pharmaceutical formulation with the largest amount of stabilizer was radiochemically - but not chemically -most stable. (author)

  7. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

  8. Application of radiochemical methods for development of new biological preparation designed for soil bioremediation

    International Nuclear Information System (INIS)

    Kim, A.A.; Djuraeva, G.T.; Djumaniyazova, G.I.; Yadgarov, Kh.T.

    2006-01-01

    Full text: Internationally the bioremediation of agricultural lands contaminated by persistent chloroorganic compounds by means of the microbial methods are used as the most low-cost and the most effective. One of the factors reducing efficacy of microbial degradation, is often the low quantity of microorganisms - destructors in the soil. Therefore, we have designed bioremediation technology of soils, contaminated by organochlorine compounds, with use of the alive microorganisms as active agent. We developed the biological preparation containing 5 aboriginal active strains of bacteria - destructors of persistent chloroorganic compounds and investigated the ability of biological preparation to increase the bioremediation potential of contaminated soils. To carry out the investigation we developed the complex of radiochemical methods with use of tritium labeled PCBs, including the following methods: 1.The method to define the accumulation and degradation of PCBs in soil bacteria in culture allows determination of quantitative characteristics of bacterial strains. 2. The method to define the PCBs degradation by soil bacteria strains in model conditions in the soil allows to estimate the PCB-destructive activity of strains after introducing in soil. 3. A method to define the PCB-destructive activity of own microbiota of contaminated soil. 4. A method to define the effect of stimulation of the PCB-destructive activity of biological preparation and own microbiota of soil with the help of biofertilizers. By using the developed radiochemical methods we have carried out investigation on creation of new biological preparation on the basis of strains of soil bacteria - destructors of PCBs. We also determined the quality and quantity characteristics of HCCH and PCBs-destructive activity of new biological preparation. It is shown that the new biological preparation is capable of accumulation and destruction of the PCBs in culture and in soil at model conditions. Thus, the

  9. The role of high performance liquid chromatography in radiochemical/radiopharmaceutical synthesis and quality assurance

    International Nuclear Information System (INIS)

    Boothe, T.E.; Emran, A.M.

    1991-01-01

    This article discusses some specifications for HPLC methodology and reviews some recent applications of HPLC with emphasis on quality assurance (QA). Developments in the HPLC field will continue to find their way into practical everyday use in the radiopharmaceutical industry. This is illustrated in the area of column technology by the use of chiral columns for the determination of enantiomeric purity of receptor-based radiopharmaceuticals and by the use of internal surface reversed-phase (ISRP) columns for determination of radiolabelled metabolites in whole blood. An increased use of optimization and chemometric methods should provide better resolution in preparative and analytical procedures. Computer techniques applied to data manipulation could aid in the elimination of human bias in determining radiochemical purities and specific activities. If HPLC is to be adopted as a routine tool for the QC of radiopharmaceuticals, particularly those prepared in-house, more effort should be made to guarantee that proper standards are in place to assure compliance, especially as responsibilities are passed from the more highly trained senior level personnel to the technologist/technician level

  10. Phenolsulphotransferase in human tissue: radiochemical enzymatic assay and biochemical properties

    International Nuclear Information System (INIS)

    Anderson, R.J.; Weinshilboum, R.M.

    1980-01-01

    Phenolsulphotransferase (EC 2.8.2.1) (PST) is an important catecholamine and drug metabolizing enzyme. Optimal conditions have been determined for the accurate measurement of PST activity in the human platelet, human renal cortex, and human jejunum with a radiochemical microassay. 3-Methoxy-4-hydroxyphenylglycol (MHPG) and 35 S-3'-phosphoadenosine-5'-phosphosulfate ( 35 S-PAPS) were the substrates for the reaction. The apparent Michaelis-Menten (Ksub(m)) values for MHPG with platelet, renal cortex, and jejunum were 1.09, 0.46 and 1.16 mmol/l, respectively. Apparent Ksub(m) values for PAPS in the same tissues were 0.14, 0.13 and 0.21 μmol/l. The pH optimum of the reacton in all three tissues was approximately 6.2-6.8 with three different buffer systems. The coefficients of variation for the assay of platelet, renal cortex, and jejunal activities were 6.2%, 3.4% and 4.4%, respectively. Mean platelet PST activity in blood samples from 75 randomly selected adult subjects was 5.0 +- 1.72 mmol of MHPG sulfate formed per hour per mg of platelet protein (8.3 X 10 -5 +- 2.9 X 10 -5 μmol min -1 mg -1 , mean +- S.D.). There was a 5-fold intersubject variation in platelet PST activity within two standard deviations of the mean value. Experiments in which partially purified human erythrocyte PST was added to platelet, kidney and gut homogenates under these assay conditions provided evidence that endogenous PST inhibitors did not affect the observed enzyme activity. (Auth.)

  11. Certification of total arsenic in blood and urine standard reference materials by radiochemical neutron activation analysis and inductively coupled plasma-mass spectrometry

    International Nuclear Information System (INIS)

    Paul, R.L.; Clay Davis, W.; Lee Yu; Murphy, K.E.; Bryan, C.E.; Vetter, T.W.; Guthrie, W.F.; Leber, D.D.; Gulchekhra Shakirova; Graylin Mitchell

    2014-01-01

    Radiochemical neutron activation analysis (RNAA) was used to measure arsenic at four levels in standard reference material (SRM) 955c Toxic Elements in Caprine Blood and at two levels in SRM 2668 Toxic Elements in Frozen Human Urine for the purpose of providing mass concentration values for certification. Samples were freeze-dried prior to analysis followed by neutron irradiation for 3 h at a fluence rate of 1 × 10 14 cm -2 s -1 . After sample dissolution in perchloric and nitric acids, arsenic was separated from the matrix either by retention on hydrated manganese dioxide (urine) or by extraction into zinc diethyldithiocarbamate in chloroform (blood). 76 As was quantified by gamma-ray spectroscopy. Differences in chemical yield and counting geometry between samples and standards were monitored by measuring the count rate of a 77 As tracer added before sample dissolution. RNAA results were combined with inductively coupled plasma-mass spectrometry values from National Institute of Standards and Technology and collaborating laboratories to provide certified values of 10.81 ± 0.54 and 213.1 ± 0.73 μg/L for SRM 2668 Levels I and II, and certified values of 21.66 ± 0.73, 52.7 ± 1.1, and 78.8 ± 4.9 μg/L for SRM 955c Levels II-IV, respectively. Because of discrepancies between values obtained by different methods for SRM 955c Level I, an information value of <5 μg/L was assigned for this material. (author)

  12. Performance and techno-economic assessment of several solid-liquid separation technologies for processing dilute-acid pretreated corn stover.

    Science.gov (United States)

    Sievers, David A; Tao, Ling; Schell, Daniel J

    2014-09-01

    Solid-liquid separation of pretreated lignocellulosic biomass slurries is a critical unit operation employed in several different processes for production of fuels and chemicals. An effective separation process achieves good recovery of solute (sugars) and efficient dewatering of the biomass slurry. Dilute acid pretreated corn stover slurries were subjected to pressure and vacuum filtration and basket centrifugation to evaluate the technical and economic merits of these technologies. Experimental performance results were used to perform detailed process simulations and economic analysis using a 2000 tonne/day biorefinery model to determine differences between the various filtration methods and their process settings. The filtration processes were able to successfully separate pretreated slurries into liquor and solid fractions with estimated sugar recoveries of at least 95% using a cake washing process. A continuous vacuum belt filter produced the most favorable process economics. Copyright © 2014 Elsevier Ltd. All rights reserved.

  13. Investigational study of the CO2 balance in high temperature CO2 separation technology; Nisanka tanso koon bunri gijutsu ni okeru CO2 balance ni kansuru chosa kenkyu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    An investigational study was conducted to clarify the adaptable environment and effectivity of technologies of high temperature separation/recovery/reutilization of CO2. In the study, data collection, arrangement and comparison were made of various separation technologies such as the membrane method, absorption method, adsorption method, and cryogenic separation method. With the LNG-fired power generation as an example, the adaptable environment and effectivity were made clear by making models by a process simulator, ASPEN PLUS. Moreover, using this simulator, effects of replacing the conventional steam reforming of hydrocarbon with the CO2 reforming were made clear with the methanol synthesis as an example. As to the rock fixation treatment of high temperature CO2, collection/arrangement were made of the data on the fixation treatment of the CO2 separated at high temperature into basic rocks such as peridotite and serpentinite in order to clarify the adaptable environment and effectivity of the treatment. Besides, a potentiality of the fixation to concrete waste was made clear. 57 refs., 57 figs., 93 tabs.

  14. Development of long-lived radionuclide partitioning technology - Preparation of ion exchanges for selective separation of radioactive elements

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Si Joong; Jeong, Hae In; Shim, Min Sook [Korea University, Seoul (Korea, Republic of); Kim, Jeong [Seonam University, Namwon (Korea, Republic of)

    1995-07-01

    Ion exchanger contained nitrogen-oxygen donor macrocyclic units was synthesized, and immobilization process was carried out by adsorption of the exchanger to silica gel. The binding constants were measured with acid concentration. From the binding constants, selectivity for Pt(II) ion and acid concentration of eluents were determined. The most optimum conditions for the separation were also determined from investigating the effects of amount of immobile phase and column length. And liarit aza-crown ethers were synthesized and selectively separated Cs/Sr ion from mixed metal solution. 37= refs., 24 tabs., 40 figs. (author)

  15. Mortality coefficients among personnel of radiochemical plants of open-quotes Mayakclose quotes-Combine for 40-year period of observation

    International Nuclear Information System (INIS)

    Koshurnikova, N.A.; Komleva, N.S.; Baisogolov, G.D.

    1993-01-01

    The results of the epidemiological research, conducted among the personnel of the radiochemical plants of open-quotes Mayakclose quotes. Combine are as follows: during the 40-year-period of observation the mortality rate from all and separate causes, except age, is lower, than the expected one, which is calculated on the basis of the National Statistics. Oncological mortality rate is reliably higher, than the expected one, which is conditioned by the high frequency of lung cancer and leucaemia. Internal α-irradiation plays the leading role in the induction of lung cancer, and the increase of mortality rate from leukemia is closely connected with external γ-irradiation

  16. Anaerobic treatment as a core technology for energy, nutrients and water from source-separated domestic waste(water)

    NARCIS (Netherlands)

    Zeeman, G.; Kujawa, K.; Mes, de T.Z.D.; Graaff, de M.S.; Abu-Ghunmi, L.N.A.H.; Mels, A.R.; Meulman, B.; Temmink, B.G.; Buisman, C.J.N.; Lier, van J.B.; Lettinga, G.

    2008-01-01

    Based on results of pilot scale research with source-separated black water (BW) and grey water (GW), a new sanitation concept is proposed. BW and GW are both treated in a UASB (-septic tank) for recovery of CH4 gas. Kitchen waste is added to the anaerobic BW treatment for doubling the biogas

  17. Web technology in the separation of strontium and cesium from INEL-ICPP radioactive acid waste (WM-185)

    International Nuclear Information System (INIS)

    Bray, L.A.; Brown, G.N.

    1995-01-01

    Strontium and cesium were successfully removed from radioactive acidic waste (WM-185) at the Idaho National Engineering Laboratory, Idaho Chemical Processing Plant (ICPP), with web technology from 3M and IBC Advanced Technologies, Inc. (IBC). A technical team from Pacific Northwest Laboratory, ICPP, 3M and IBC conducted a very successful series of experiments from August 15 through 18, 1994. The ICPP, Remote Analytical Laboratory, Idaho Falls, Idaho, provided the hot cell facilities and staff to complete these milestone experiments. The actual waste experiments duplicated the initial 'cold' simulated waste results and confirmed the selective removal provided by ligand-particle web technology

  18. From SRAFAP to SISAK - rapid chemical separations in nuclear research

    International Nuclear Information System (INIS)

    Herrmann, G.

    1988-10-01

    The author gives an overview of rapid radiochemical separations, starting from the early experiments done by Rutherford up to the very sophisticated recoil fragment separations by fast on-line methods as an attempt to produce superheavy elements. Main emphasis is given to developments during the last decades and the extensive work performed by collaborators of the Nuclear Chemistry Institute at the University of Mainz. (RB)

  19. Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

    International Nuclear Information System (INIS)

    1993-01-01

    During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE's current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered

  20. Literature search, review, and compilation of data for chemical and radiochemical sensors: Task 1 report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-01-01

    During the next several decades, the US Department of Energy is expected to spend tens of billions of dollars in the characterization, cleanup, and monitoring of DOE`s current and former installations that have various degrees of soil and groundwater contamination made up of both hazardous and mixed wastes. Each of these phases will require site surveys to determine type and quantity of hazardous and mixed wastes. It is generally recognized that these required survey and monitoring efforts cannot be performed using traditional chemistry methods based on laboratory evaluation of samples from the field. For that reason, a tremendous push during the past decade or so has been made on research and development of sensors. This report contains the results of an extensive literature search on sensors that are used or have applicability in environmental and waste management. While restricting the search to a relatively small part of the total chemistry spectrum, a sizable body of reference material is included. Results are presented in tabular form for general references obtained from data base searches, as narrative reviews of relevant chapters from proceedings, as book reviews, and as reviews of journal articles with particular relevance to the review. Four broad sensor types are covered: electrochemical processes, piezoelectric devices, fiber optics, and radiochemical processes. The topics of surface chemistry processes and biosensors are not treated separately because they often are an adjunct to one of the four sensors listed. About 1,000 tabular entries are listed, including selected journal articles, reviews of conference/meeting proceedings, and books. Literature to about mid-1992 is covered.

  1. Comparison of different thin layer detection techniques to determine the radiochemical purity of radiopharmaceuticals

    International Nuclear Information System (INIS)

    Hammermaier, A.; Reich, E.; Boegl, W.

    1985-01-01

    Ten radiopharmaceuticals frequently used in clinical treatment were examined as to their radiochemical purity by paper and thin layer chromatography or electrophoresis, respectively. It is known that radiochemical impurities may result in an unnecessary exposure of the patients to be examined. Other than determining the radiochemical purity of several radiopharmaceuticals, a comparison of the different measuring methods of distributing activity on radiochromatograms or electropherograms is intended by this study. For this, the activity distribution in the developed radiochromatograms was assessed by four different measuring methods (TLC-linear analyzer, TLC-scanner with NaI(Tl) detector, TLC-scanner with gas flow counter and NaI(Tl) well-typ counter). As shown by the above analysis, only the TLC-linear analyzer and the NaI(Tl) well-typ counter (measurement of chromatograms or electropherograms cut into strips) are generally suitable methods for determining the radiochemical purity of radiochemicals, the TLC-scanner with gas flow counter is usable in most cases, while TLC-scanner with NaI(Tl) detector is yielding unsatisfactory results. (orig.) [de

  2. Application of thin film composite membranes with forward osmosis technology for the separation of emulsified oil-water

    KAUST Repository

    Duong, Hoang Hanh Phuoc; Chung, Neal Tai-Shung

    2014-01-01

    Large amounts of oily wastewater have been produced from various industries. The main challenge of oily wastewater treatments is to separate the stable emulsified oil particles from water. Therefore, the aim of this study is to investigate the effectiveness of forward osmosis (FO) processes to treat the stable oil-water emulsions. The FO technique has been demonstrated successfully for the treatment of a wide range of oil-water emulsions from a low to a very high concentration up to 200,000. ppm. The dependence of separation performance on oily feed concentration and flow rate has been investigated. Water can be separated from oily feeds containing 500. ppm or 200,000. ppm emulsified oil at a relatively high flux of 16.5±1.2. LMH or 11.8±1.6. LMH respectively by using a thin film composite membrane PAN-TFC and 1. M NaCl as the draw solution. Moreover, this membrane can achieve an oil rejection of 99.88% to produce water with a negligible oil level. Due to the presence of emulsified oil particles in the oily feed solutions, the membrane fouling has been addressed in this study. Better anti-fouling TFC FO membranes are needed. © 2013 Elsevier B.V.

  3. Application of thin film composite membranes with forward osmosis technology for the separation of emulsified oil-water

    KAUST Repository

    Duong, Hoang Hanh Phuoc

    2014-02-01

    Large amounts of oily wastewater have been produced from various industries. The main challenge of oily wastewater treatments is to separate the stable emulsified oil particles from water. Therefore, the aim of this study is to investigate the effectiveness of forward osmosis (FO) processes to treat the stable oil-water emulsions. The FO technique has been demonstrated successfully for the treatment of a wide range of oil-water emulsions from a low to a very high concentration up to 200,000. ppm. The dependence of separation performance on oily feed concentration and flow rate has been investigated. Water can be separated from oily feeds containing 500. ppm or 200,000. ppm emulsified oil at a relatively high flux of 16.5±1.2. LMH or 11.8±1.6. LMH respectively by using a thin film composite membrane PAN-TFC and 1. M NaCl as the draw solution. Moreover, this membrane can achieve an oil rejection of 99.88% to produce water with a negligible oil level. Due to the presence of emulsified oil particles in the oily feed solutions, the membrane fouling has been addressed in this study. Better anti-fouling TFC FO membranes are needed. © 2013 Elsevier B.V.

  4. Radiochemical procedure and quantitative determination of the activation product, 63Ni, in environmental soft water samples with high Ca and Mg phosphate concentration

    International Nuclear Information System (INIS)

    Jordan, N.; Michel, H.; Barci-Funel, G.; Barci, V.

    2008-01-01

    Nickel-63 is a low energy beta-emitter needing a radiochemical separation before β-counting. Several papers described the separation and the detection of 63 Ni in environmental samples. The method used in our work was first developed by SKWARZEC and HOLM. The main steps of this separation are the selective precipitation of nickel with dimethylglyoxime (DMG) and the use of the non-sorption of nickel on anion resin in hydrochloric acid solutions. In this paper, a new step is added to eliminate high quantities of calcium and magnesium phosphate disturbing the iron hydroxide precipitation step. The procedure has been applied to soft water samples: sediments, plants and fishes. The chemical yields are 60, 70 and 20%, respectively. The detection limit of 63 Ni by liquid scintillation spectrometer is 10 mBq. (author)

  5. Method of determination of radiochemical purity of gallium-67 citrate injection

    International Nuclear Information System (INIS)

    Wang Quanji

    1985-01-01

    A simple method is used to compare the effect of five developing agents on the radiochemical purity of neutral products of 67 GaCit and on Rsub(f) values. Two preferable developing agents are recommended as suitable for the identification of 67 GaCit injection in its production. The effect of six pH values of different developing agents on radiochemical purity, Rsub(f) and chromatogram are compared for the neutral products. The results of the experiments show that the ascending paper chromatography with 1:2:4 pyridine/ethanol/water and 85:15 methanol/water is preferable for the determination of the radiochemical purity of 67 GaCit. The other developing agents also can be used if there are not any impurities except gallium radioisotopes

  6. Northern Marshall Islands Radiological Survey: a quality-control program for a radiochemical analyses

    International Nuclear Information System (INIS)

    Jennings, C.D.; Mount, M.E.

    1983-08-01

    More than 16,000 radiochemical analyses were performed on about 5400 samples of soils, vegetation, animals, fish, invertebrates, and water to establish amounts of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in the Northern Marshall Islands. Three laboratories were contracted by Lawrence Livermore National Laboratory to perform the radiochemical analyses: Environmental Analysis Laboratory (EAL), Richmond, California; Eberline Instrument Corporation (EIC), Albuquerque, New Mexico; and Laboratory of Radiation Ecology (LRE), University of Washington, Seattle, Washington. The analytical precision and accuracy were monitored by regularly including duplicate samples and natural matrix standards in each group of about 100 samples analyzed. Based on the duplicates and standards, over 83% of the radiochemical analyses in this survey were acceptable - 97% of the analyses by EAL, 45% of the analyses by EIC, and 98% of the analyses by LRE

  7. The laboratory technology of discrete molecular separation: the historical development of gel electrophoresis and the material epistemology of biomolecular science, 1945-1970.

    Science.gov (United States)

    Chiang, Howard Hsueh-hao

    2009-01-01

    Preparative and analytical methods developed by separation scientists have played an important role in the history of molecular biology. One such early method is gel electrophoresis, a technique that uses various types of gel as its supporting medium to separate charged molecules based on size and other properties. Historians of science, however, have only recently begun to pay closer attention to this material epistemological dimension of biomolecular science. This paper substantiates the historiographical thread that explores the relationship between modern laboratory practice and the production of scientific knowledge. It traces the historical development of gel electrophoresis from the mid-1940s to the mid-1960s, with careful attention to the interplay between technical developments and disciplinary shifts, especially the rise of molecular biology in this time-frame. Claiming that the early 1950s marked a decisive shift in the evolution of electrophoretic methods from moving boundary to zone electrophoresis, I reconstruct various trajectories in which scientists such as Oliver Smithies sought out the most desirable solid supporting medium for electrophoretic instrumentation. Biomolecular knowledge, I argue, emerged in part from this process of seeking the most appropriate supporting medium that allowed for discrete molecular separation and visualization. The early 1950s, therefore, marked not only an important turning point in the history of separation science, but also a transformative moment in the history of the life sciences as the growth of molecular biology depended in part on the epistemological access to the molecular realm available through these evolving technologies.

  8. Advanced Aqueous Separation Systems for Actinide Partitioning

    Energy Technology Data Exchange (ETDEWEB)

    Nash, Kenneth L.; Clark, Sue; Meier, G Patrick; Alexandratos, Spiro; Paine, Robert; Hancock, Robert; Ensor, Dale

    2012-03-21

    One of the most challenging aspects of advanced processing of spent nuclear fuel is the need to isolate transuranium elements from fission product lanthanides. This project expanded the scope of earlier investigations of americium (Am) partitioning from the lanthanides with the synthesis of new separations materials and a centralized focus on radiochemical characterization of the separation systems that could be developed based on these new materials. The primary objective of this program was to explore alternative materials for actinide separations and to link the design of new reagents for actinide separations to characterizations based on actinide chemistry. In the predominant trivalent oxidation state, the chemistry of lanthanides overlaps substantially with that of the trivalent actinides and their mutual separation is quite challenging.

  9. Abyssal sediment erosion from the Central Indian Basin: Evidence from radiochemical and radiolarian studies

    Digital Repository Service at National Institute of Oceanography (India)

    Banakar, V.K.; Gupta, S.M.; Padmavati, V.K.

    ) 167-173 167 Elsevier Science Publishers B.V., Amsterdam Letter Section Abyssal sediment erosion in the Central Indian Basin: Evidence from radiochemical and radiolarian studies V.K. Banakar, S.M. Gupta and V.K. Padmavathi National Institute... of Oceanography, Dona-Paula, Goa-403 004, India (Revision accepted September 17, 1990) ABSTRACT Banakar, V.K., Gupta, S.M. and Padmavathi, V.K., 1991. Abyssal sediment erosion from the Central Indian Basin: Evi- dence from radiochemical and radiolarian studies...

  10. Kit preparation of 153Sm-EDTMP and factors affecting radiochemical purity and stability

    International Nuclear Information System (INIS)

    Ferro-Flores, G.; Tendilla, J.I.; Lopez-Gomez, M.A.; Aguilar-Hernandez, F.; Gonzalez-Zavala, M.A.; Parades-Gutierrez, L.; Avila-Ramirez, E.

    1996-01-01

    A fast kit method was developed for the production of 153 Sm-EDTMP in two steps avoiding the use of nitric acid, evaporation and sterilization of the final solution by autoclave. Methods of analysis for the determination of chemical and radiochemical purity in the radiopharmaceutical solution were established. Factors affecting radiochemical purity and stability of the complex as the molar ratio of EDTMP/Sm, concentration of phosphate buffer and neutralization of EDTMP prior kit preparation were also analyzed. The use of this radiopharmaceutical in rabbits and patients showed selective skeletal uptake. (author). 5 refs., 4 figs., 3 tabs

  11. Radiochemical determination of 210Pb using crown ether

    International Nuclear Information System (INIS)

    Vajda, N.; Bodizs, D.; Vodicska, M.

    1994-01-01

    Gamma spectrometric determination of 210 Pb following chemical separation has been performed very precisely and with high sensitivity, due to the low and constant self-absorption of the chemically pure sample. A simple and quick method for the chemical separation of lead using crown ether has been developed. Its four steps are described in detail. The new method was verified using phosphate ore and gypsum samples that were measured in an interlaboratory comparison and with a standard reference material. This method can also be used for self-absorption correction in direct gamma spectrometry of 210 Pb. (N.T.) 4 refs.; 2 figs.; 2 tabs

  12. Equipment Design and Cost Estimation for Small Modular Biomass Systems, Synthesis Gas Cleanup, and Oxygen Separation Equipment; Task 9: Mixed Alcohols From Syngas -- State of Technology

    Energy Technology Data Exchange (ETDEWEB)

    Nexant Inc.

    2006-05-01

    This deliverable is for Task 9, Mixed Alcohols from Syngas: State of Technology, as part of National Renewable Energy Laboratory (NREL) Award ACO-5-44027, ''Equipment Design and Cost Estimation for Small Modular Biomass Systems, Synthesis Gas Cleanup and Oxygen Separation Equipment''. Task 9 supplements the work previously done by NREL in the mixed alcohols section of the 2003 technical report Preliminary Screening--Technical and Economic Assessment of Synthesis Gas to Fuels and Chemicals with Emphasis on the Potential for Biomass-Derived Syngas.

  13. Devising of the method for the determination of small and very small amounts of cadmium in biological materials by radiochemical version of neutron activation analysis

    International Nuclear Information System (INIS)

    Dybczynski, R.; Samczynski, Z.

    1996-01-01

    The newly modified version of the method for the determination of cadmium in biological materials by radiochemical NAA based on selective post irradiation separation of Cd using ion exchange rasin Retardion 11A8 is presented. The conditions necessary for the selective retaining of Cd on the column exploiting both anionic and cationic ion exchange function of the resin have been discussed. Depending on the composition of the external solution, cadmium existing in the form of either anionic chloride complexes or cationic amine species is taken up by quaternary ammonium or carboxylate functional groups, respectively while accompanying elements are eluted. The elaborated method was further verified by determine Cd content in several certified biological reference materials using neutron activation analysis. The ion exchange separation procedure assures very high radiochemical purity of the cadmium fraction. Decontamination factors obtained for Mo, Sb, Na, Zn, Co, Sc amounted to 10 3 - 10 6 . Detection limit for Cd was 0.5 μg kg -1 . Analytical results show good agreement with the certified values. (author). 10 refs, 7 figs, 1 tab

  14. Research and development of basic technologies for next-generation industry. Ultimate evaluation report on research and development of highly efficient polymeric separation membrane material; Jisedai sangyo kiban gijutsu kenkyu kaihatsu. Kokoritsu kobunshi bunrimaku zairyo saishu kenkyu kaihatsu hyoka

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-05-01

    For the enhancement of separation process efficiency and energy efficiency in the chemical industry, etc., basic technologies are developed involving high-performance separation membrane materials which are excellent in durability and usable in the field where separation by membranes has been impractical. The liquid mixtures subjected to separation are a neutral organic compound/water system, an acidic organic compound/water system, and a polar organic compound/water system; the gas mixtures subjected to separation are an oxygen/nitrogen system and a carbon monoxide/nitrogen system. After a 10-year/3-phase development endeavors, the initially intended goals are sufficiently achieved. Among those that have to be mentioned is the development of a nonaqueous separation membrane, a supported liquid membrane with amino acid optically active high performance separation capability, a high-precision evaluation unit for gas separation membrane characteristics, a selective permeation membrane with high-level oxygen and carbon monoxide carriers and reactivation technology, a high-performance ethanol separation membrane, a water/polar organic compound separation membrane, and a water/acetic acid separation membrane and stability providing technology. In particular, the water selective permeation membrane for a mixture of water and alcohol has already arrived at the stage of bench plant demonstration. (NEDO)

  15. Anaerobic treatment as a core technology for energy, nutrients and water recovery from source-separated domestic waste(water).

    Science.gov (United States)

    Zeeman, Grietje; Kujawa, Katarzyna; de Mes, Titia; Hernandez, Lucia; de Graaff, Marthe; Abu-Ghunmi, Lina; Mels, Adriaan; Meulman, Brendo; Temmink, Hardy; Buisman, Cees; van Lier, Jules; Lettinga, Gatze

    2008-01-01

    Based on results of pilot scale research with source-separated black water (BW) and grey water (GW), a new sanitation concept is proposed. BW and GW are both treated in a UASB (-septic tank) for recovery of CH4 gas. Kitchen waste is added to the anaerobic BW treatment for doubling the biogas production. Post-treatment of the effluent is providing recovery of phosphorus and removal of remaining COD and nitrogen. The total energy saving of the new sanitation concept amounts to 200 MJ/year in comparison with conventional sanitation, moreover 0.14 kg P/p/year and 90 litres of potential reusable water are produced. (c) IWA Publishing 2008.

  16. Characterization of sodium stibogluconate by online liquid separation cell technology monitored by ICPMS and ESMS and computational chemistry

    DEFF Research Database (Denmark)

    Hansen, Helle Rusz; Hansen, Claus; Kepp, Kasper Planeta

    2008-01-01

    High-performance liquid chromatography (HPLC), mass spectrometry (MS), and computational chemistry has been applied to resolve the composition and structure of the Sb species present in dilutions of Pentostam, a first-line treatment drug against Leishmania parasites. Using HPLC-inductively coupled......(V)-glyconate complexes of various stoichiometry (1:1, 1:2, 1:3, 2:2, 2:3, 2:4, 3:3, 3:4). The 1:1 complex became the most abundant low molecular mass Sb(V) complex with dilution time. A novel mixed-mode chromatographic system was applied in order to separate complexes of various stoichiometry and isomers. Density...

  17. Fiscal 1993 report on the separation/refining technology section meeting; 1993 nendo bunri seisei gijutsu bukai hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-01

    Group activities in fiscal 1993 are reported. In the study of hydrogenation refining of the naphtha fraction under the project for 'the upgrading of coal oil and the development of oil blending technology,' a hydrogenation experiment is conducted for deheterocyclicity for in the naphtha fraction (90-180 degrees C). The neutralization process is found to greatly accelerate denitrification, multiplying the rate constant 2-5 times at 300 degrees C. In the research and development of application technologies, the ASTM-D4625-86 method is applied to the storage test of crude oils such as naphtha from liquefied Yallourn coal, kerosene, and light oil, and the results are compared with those from natural storage. It is then found that this acceleration test is applicable even to oils from coal liquefaction. In the research and development of novel catalysts, it is found, relative to the 1st-stage hydrogenation catalyst, that an increase in the amount of supported tungsten enhances the activity and life of the catalyst and, relative to the 2nd-stage hydrocracking catalyst, that YD zeolite is effective in prolonging the life of the catalyst. (NEDO)

  18. Development of radiochemical methods for the determination of radionuclides in water samples

    International Nuclear Information System (INIS)

    Vajda, N.; Molnar, Zs.; Bodizs, D.

    2004-01-01

    Depending on the composition of minerals, ores, soils and the properties of water various amounts of radionuclides of natural origin are released into different types of water i.e. surface and ground water, mineral and well water. Furthermore, man-made radionuclides can contaminate the surface waters in the form of fallout from nuclear incidents followed by migration of the deposited isotopes into water. Measurement of radionuclides in water helps prevent the consumption of radioactive water causing high radiation doses and also enables the early discovery of contamination sources. For the latter reason monitoring radioactivity in ground water in the vicinity of nuclear installations is of great importance. High sensitivity radiochemical methods have been developed/adopted for the simultaneous determination of 90 Sr-Pu nuclides, 137 Cs- 90 Sr-Pu nuclides in 50-100 L of water. Typically, procedures contain a pre-concentration step most likely by means of co-precipitation followed by a selective separation procedure preferably by means of extraction chromatography. In most cases Sr and Pu are extracted with a crown ether and an organic phosphonate compound, respectively, while Cs is concentrated using AMP. In the presence of extremely high salt content e.g. in case of 100 L of sea water the standard extraction chromatographic procedure has to be replaced by the conventional technique of Sr-Ca separation based on the different solubilities of the nitrate precipitates. Selection criteria as well as description of the procedures will be given in detail. A high sensitivity procedure has been developed for the analysis of 129 I in 100 L of ground water based on pre-concentration with AgCI and separation by extraction with CCl 4 . The following nuclear measuring techniques were applied: LSC, alpha spectrorhetry, gamma spectrometry, neutron activation (including gamma spectrometry) for 90 Sr, 239,240 Pu, 137 Cs, and 129 I, respectively. Sensitivities of the given methods

  19. The Main Technological Characteristics of Apparatus for Industrial Radiochemical Processes, in Particular Ethylene Polymerization; Caracteristique techniques fondamentals des appareils pour l'application industrielle de reactions chimiques sous rayonnement (notamment la polymerisation de l'ethylene ); Osnovnye tekhnologicheskie kharakteristiki apparatov dlya provedeniya radiatsionno-khimi-cheskikh protsessov (v chastnosti, dlya polimerizatsii ehtilena) v promyshlennom masshtabe; Principales caracteristicas tecnologicas de los aparatos para la aplicacion industrial de reacciones radioquimicas

    Energy Technology Data Exchange (ETDEWEB)

    Syrkus, N P; Breger, A K; Weinstein, B I [Karpov Physicochemical Institute, Moscow, USSR (Russian Federation)

    1960-07-15

    The paper gives a general review of some of the main technological features of apparatus, for instance spherical apparatus, for industrial radiochemical processes. A method is proposed for estimating the effectiveness of apparatus of any given construction by comparing it with the output of an infinitely large apparatus having the same radiation source. An account is given of the technological features of an apparatus for radio-polymerizing ethylene at 200 atmospheres and 25{sup o}C{sup 1} with a rodshaped gamma-radiation source (Co{sup 60}) of variable activity. This apparatus can be designed to suit the mean dose rate which the power efficiency of the apparatus allows. It is shown that the yield, Q, of the apparatus is, other things being equal, a constant ration of the power, W{sub 0}, of the gamma-radiation of the apparatus. In the apparatus reviewed, Q {approx} W{sub 0}{sup 0,5}. (author) [French] Le memoire contient un expose general des caracteristiques techniques essentielles des appareils, par exemple d'un appareil du type spherique, pour l'application industrielle de reactions chimiques sous rayonnement. Le memoire propose une methode pour evaluer l'efficacite d'appareils de tous types en comparant la productivite de chaque modele avec celle d'un appareil infiniment grand, alimente par une source de rayonnement identique. Le memoire indique le calcul des caracteristiques techniques de l'appareil destine a la polymerisation sous rayonnement de l'ethylene (pression : 200 atmospheres, temperature: 25{sup o}C{sup 2} avec une source allongee de rayonnement gamma Co{sup 60} pour diverses activites. Un appareil de ce type peut etre calcule selon les valeurs moyennes de l'intensite des doses, determinees selon la valeur du coefficient d'efficacite totale energetique de l'appareil. On constate que la productivite (Q) de l'appareil, toutes choses egales d'ailleurs, est puissance de l'intensite (W{sub 0}) du rayonnement gamma de l'appareil. Pour l'appareil considere

  20. On the radiochemical purity of elementary 35S with high specific activity

    International Nuclear Information System (INIS)

    Todorovsky, D.S.; Kostadinov, K.N.; Efremova, Yu.N.

    1979-01-01

    Radiochemical composition and chemical changes with increasing storage time of benzene solutions and of solid species of elementary 35 S with high specific activity are studied. The dependence of the stability on the specific activity and the radioactive concentration is shown and some tentative limits are given for permissible storage periods. (author)

  1. Determination of the radiochemical purity of phosphorus-32 and tritium-labeled diisopropylphosphorofluoridate (DFP)

    International Nuclear Information System (INIS)

    Christopher, R.E.; Sheppard, G.

    1975-01-01

    A method is described for the determination of the radiochemical purity of labeled diisopropylphosphorofluoridate (DFP), based on the irreversible inhibition reaction with the enzyme α-chymotrypsin. The nature of the impurities in commercially available 32 P- and 3 H-labeled DFP is discussed

  2. Rapid and sensitive enzymatic-radiochemical assay for the determination of triglycerides

    International Nuclear Information System (INIS)

    Khoo, J.C.; Miller, E.; Goldberg, D.I.

    1987-01-01

    An enzymatic-radiochemical method suitable for the determination of triglyceride levels of cells in culture is described. The method is based on the enzymatic hydrolysis of triglycerides to free fatty acids which then complex with 63 Ni. The method is rapid, accurate, and inexpensive. The procedure extends the sensitivity of triglyceride measurement to as low as 0.25 nanomoles

  3. Triphenyl phosphine oxide as a substoichiometric radiochemical reagent: Determination of thallium

    International Nuclear Information System (INIS)

    Reddy, P.C.; Polaiah, B.; Rangamannar, B.

    1991-01-01

    A rapid radiochemical method has been developed for the determination of microgram amounts of thallium based on the substoichiometric extraction of its ocmplex with triphenylphosphine oxide into benzene from 6 M sulphuric acid. 10-90 μg of thallium was determined with an average error of 2.06%. The effect of diverse metal ions on the extraction was studied. (orig.)

  4. Computer aided piping layout design in radiochemical plants- an improved software package

    International Nuclear Information System (INIS)

    Raju, R.P.; Siddiqui, H.R.

    1995-01-01

    A software package was developed and it was successfully implemented for the piping layout design of the four process cells of the Kalpakkam Reprocessing Project. This paper discusses in detail all the improvements and modifications that are being carried out in the package so that it becomes more meaningful and useful for implementation for the forthcoming radiochemical plants

  5. Evaluation of radiochemical purities of some radiopharmaceuticals in Shiraz Namazi teaching hospital

    Directory of Open Access Journals (Sweden)

    Hossein Sadeghpour

    2015-03-01

    Full Text Available Many radiopharmaceuticals, as a special group of drugs, are eventually prepared at the nuclear medicine departments of the hospitals. Therefore, their quality control procedures such as sterility tests, radionuclide, radiochemical and chemical purity should be carried out in the hospitals. In this study, radiochemical purity for more than 300 preparations of three different radiopharmaceutical formulations from commercial kits were tested using instant thin layer chromatography. The formulations 99mTc-DTPA, 99mTc-MDP and 99mTc-MIBI were obtained from Pars Isotope Co. Several paper chromatographic systems including standard and factory recommended thin layer chromatography systems were used in this study. In addition different equipments for detection of radioactivity in paper chromatography like gamma camera and dose calibrator were used. The results showed that the most observed impurities were hydrolyzed reduced technetium (HR-Tc. There were no significant differences between calculated 99mTc-MIBI radiochemical purities when the radioactive detection device was gamma camera instead of dose calibrator. In case of 99mTc-DTPA and 99mTc-MDP, there were significant differences in detection of HR-Tc. On the contrary, no significant differences in free pertechnetate were observed when package insert procedures for quality control were used instead of those recommended in the references. Finally, we observed that the package insert procedures for quality control can offer higher radiochemical purities.

  6. Application of radiochemical determination methods in cleanability research of building materials

    International Nuclear Information System (INIS)

    Maeaettae, Jenni; Kymaelaeinen, Hanna-Riitta; Sjoeberg, Anna-Maija

    2011-01-01

    During recent years increasing effort has been made to modify surface properties with easy-to-clean or self-cleaning characteristics, and concomitantly there is a need to be able to quantify cleanability. Methodology is a complex issue, including aspects of selection and characterization of the surface materials, the soiling materials (contaminants), soiling and cleaning methods, and the detection methods. Different biological, chemical, physical and visual methods have been included in studies of surface cleanability. One challenge has been to obtain quantitative information about soiling. The radiochemical methods, gamma spectrometry (NaI(Tl)-crystal) and liquid scintillation counting, have been shown to be suitable for evaluating cleanability of different surface materials and different soiling material types, providing quantitative information about the amount of soiling material both on and beneath the surface. Due to the different labelled soiling components, the interaction of the surface with different soiling material types can be evaluated. Radiochemical methods have unique benefits particularly for examining porous materials and surfaces. However, they are suitable only for highly controlled studies because of the hazards. Different features and details of radiochemical methods are discussed with the view to aid planning of future cleanability studies. - Highlights: → Radiochemical methods can be used for cleanability studies. → These methods give quantitative information about the amount of soiling material. → These methods are suitable particularly for examining porous materials. → These methods are suitable for highly controlled studies because of the hazards.

  7. Analytical and radiochemical methods in the stability study of the MIBI-Sm

    International Nuclear Information System (INIS)

    Isaac, M.; Leyva, R.; Gamboa, R.; Turino, D.

    1997-01-01

    99mT c-MIBI is a radiopharmaceutical imaging agent useful for assessing myocardial perfusion. This paper presents the stability results obtained in the radiochemical purity and others parameters in the quality control of 5 batch during more than 2 years

  8. Protein binding studies with radiolabeled compounds containing radiochemical impurities. Equilibrium dialysis versus dialysis rate determination

    DEFF Research Database (Denmark)

    Honoré, B

    1987-01-01

    The influence of radiochemical impurities in dialysis experiments with high-affinity ligands is investigated. Albumin binding of labeled decanoate (97% pure) is studied by two dialysis techniques. It is shown that equilibrium dialysis is very sensitive to the presence of impurities resulting...

  9. FY1998 research report on the R and D on high- temperature CO{sub 2} separation, recovery and recycling technologies; 1998 nendo nisanka tanso koon bunri kaishu sairiyo gijutsu kekyu kaihatsu seika hokokusho

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    This project aims to develop high-temperature (over 300 degrees C) CO{sub 2} separation, recovery and recycling technologies. For separation membranes, control technology of micro-pore structure using templates, and that of a permeation gas affinity by metal ion exchange and metallic element addition to separation membrane textures were developed. The result gave the guide to control, design and evaluation of permeation and separation properties. The prototype module was prepared, and improvement of joining technology and evaluation of material fatigue property were also carried out. As for optimization of the developed system and research on its marketability, study was mainly made on the ripple effect of inorganic membranes. The current state and trend of technologies were studied also for power plants. In the concept design of the module, further study was made on high-temperature sealing technology and inorganic membrane technology for H{sub 2} gas separation. Use of CO{sub 2} gas separation technology for steelmaking process was newly studied. The ripple effect was studied for future important fields. (NEDO)

  10. The Northern Marshall Islands radiological survey: A quality control program for radiochemical and gamma spectroscopy analysis

    International Nuclear Information System (INIS)

    Kehl, S.R.; Mount, M.E.; Robison, W.L.

    1995-09-01

    From 1979 to 1989, approximately 25,000 Post Northern Marshall Islands Radiological Survey (PNMIRS) samples were collected, and over 71,400 radiochemical and gamma spectroscopy analyses were performed to establish the concentration of 90 Sr, 137 Cs, 241 Am, and plutonium isotopes in soil, vegetation, fish, and animals in the Northern Marshall Islands. While the Low Level Gamma Counting Facility (B379) in the Health and Ecological Assessment (HEA) division accounted for over 80% of all gamma spectroscopy analyses, approximately 4889 radiochemical and 5437 gamma spectroscopy analyses were performed on 4784 samples of soil, vegetation, terrestrial animal, and marine organisms by outside laboratories. Four laboratories were used by Lawrence Livermore National Laboratory (LLNL) to perform the radiochemical analyses: Thermo Analytical Norcal, Richmond, California (TMA); Nuclear Energy Services, North Carolina State University (NCSU); Laboratory of Radiation Ecology, University of Washington (LRE); and Health and Ecological Assessment (HEA) division, LLNL, Livermore, California. Additionally, LRE and NCSU were used to perform gamma spectroscopy analyses. The analytical precision and accuracy were monitored by including blind duplicates and natural matrix standards in each group of samples analyzed. On the basis of reported analytical values for duplicates and standards, 88% of the gamma and 87% of the radiochemical analyses in this survey were accepted. By laboratory, 93% of the radiochemical analyses by TMA; 88% of the gamma-ray spectrometry and 100% of the radiochemistry analyses by NCSU; 89% of the gamma spectroscopy and 87% of the radiochemistry analyses by LRE; and 90% of the radiochemistry analyses performed by HEA's radiochemistry department were accepted

  11. CO2 Capture Project-An Integrated, Collaborative Technology Development Project for Next Generation CO2 Separation, Capture and Geologic Sequestration

    Energy Technology Data Exchange (ETDEWEB)

    Helen Kerr; Linda M. Curran

    2005-04-15

    The CO{sub 2} Capture Project (CCP) was a joint industry project, funded by eight energy companies (BP, ChevronTexaco, EnCana, ENI, Norsk Hydro, Shell, Statoil, and Suncor) and three government agencies (European Union [DG RES & DG TREN], the Norwegian Research Council [Klimatek Program] and the U.S. Department of Energy [NETL]). The project objective was to develop new technologies that could reduce the cost of CO{sub 2} capture and geologic storage by 50% for retrofit to existing plants and 75% for new-build plants. Technologies were to be developed to ''proof of concept'' stage by the end of 2003. Certain promising technology areas were increased in scope and the studies extended through 2004. The project budget was approximately $26.4 million over 4 years and the work program is divided into eight major activity areas: Baseline Design and Cost Estimation--defined the uncontrolled emissions from each facility and estimate the cost of abatement in $/tonne CO{sub 2}. Capture Technology, Post Combustion: technologies, which can remove CO{sub 2} from exhaust gases after combustion. Capture Technology, Oxyfuel: where oxygen is separated from the air and then burned with hydrocarbons to produce an exhaust with high CO{sub 2} for storage. Capture Technology, Pre-Combustion: in which, natural gas and petroleum cokes are converted to hydrogen and CO{sub 2} in a reformer/gasifier. Common Economic Model/Technology Screening: analysis and evaluation of each technology applied to the scenarios to provide meaningful and consistent comparison. New Technology Cost Estimation: on a consistent basis with the baseline above, to demonstrate cost reductions. Geologic Storage, Monitoring and Verification (SMV): providing assurance that CO{sub 2} can be safely stored in geologic formations over the long term. Non-Technical: project management, communication of results and a review of current policies and incentives governing CO{sub 2} capture and storage. Pre

  12. Status Of The Development Of In-Tank/At-Tank Separations Technologies For High-Level Waste Processing For The U.S. Department Of Energy

    International Nuclear Information System (INIS)

    Aaron, G.; Wilmarth, B.

    2011-01-01

    Within the U.S. Department of Energy's (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in 'tank farms'). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are 'first-of-a-kind' and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant re-engineering to adapt to DOE's specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanford's Waste Treatment and Immobilization Plant (WTP) or Savannah River's Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration. This paper will review the status of several of the R and D projects being developed by the U.S. DOE including insertion of the ion exchange (IX) technologies, such as Small Column Ion Exchange (SCIX) at Savannah River. This has the potential to align the

  13. Progress on radiochemical analysis for nuclear waste management in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Hou, X. (Technical Univ. of Denmark. Center for Nuclear Technologies (NuTech), Roskilde (Denmark))

    2012-01-15

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  14. Progress on radiochemical analysis for nuclear waste management in decommissioning

    International Nuclear Information System (INIS)

    Hou, X.

    2012-01-01

    This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

  15. Progress on Radiochemical Analysis for Nuclear Waste Management in Decommissioning

    DEFF Research Database (Denmark)

    Hou, Xiaolin; Qiao, Jixin; Shi, Keliang

    With the increaed numbers of nuclear facilities have been closed and are being or are going to be decommissioned, it is required to characterise the produced nuclear waste for its treatment by identification of the radionuclides and qualitatively determine them. Of the radionuclides related...... separation of radionuclides. In order to improve and maintain the Nodic competence in analysis of radionculides in waste samples, a NKS B project on this topic was launched in 2009. During the first phase of the NKS-B RadWaste project (2009-2010), a good achivement has been reached on establishment...... of collaboration, identifing the requirements from the Nordic nuclear industries and optimizing and development of some analytical methods (Hou et al. NKS-222, 2010). In the year 2011, this project (NKS-B RadWaste2011) continued. The major achievements of this project in 2011 include: (1) development of a method...

  16. Radiologic contamination of fish. III. Radiochemical studies of contaminated fish

    Energy Technology Data Exchange (ETDEWEB)

    Kawabata, T

    1955-01-01

    The decay rate of the radioactivity of the organs of fish caught by the crew of the Shunkotsu Maru was measured. After 3 months, the spleens, kidneys, and gonads retained considerable radioactivity, suggesting the presence of long-lived radioactive elements. At the end of this time, the liver and other organs retained only about 10% of the initial radioactivity and the bile had lost most of its activity. The retention by the pyloric coeca and the intestinal contents varied considerably and was probably dependent on the food consumed. Absorption of the ash of the organs on Dowex 50 and elution located most of the activity in the fractions eluted with 0.5% oxalic acid and 5% citrate buffers of pH 4.1 and 4.6. Qualitative separation with carriers identified the main radioactive element of the citrate buffer, pH 4.1, eluate as /sup 65/Zn.

  17. Nuclear material control and accountancy in a radiochemical plant

    International Nuclear Information System (INIS)

    Crawford, J. M.

    1999-01-01

    The measurement systems in use at Savannah River Site, SRS, to determine material balance around dissolution of fuel, separation and purification of actinides to a nitrate product are described. To ensure that volume accuracy's are as expected, SRS has implemented a volumetric measurement control program to control errors and to detect anomalies. The program consists of periodic instrument calibrations, comparison of in-tank density measurements. An analytical quality control program is in place at SRS to provide assurance that analysis are reliable and to estimate and monitor method performance. Checks include the analysis of standard prior to the use of each method each shift the method is used. At SRS cumulative inventory difference is compared to the combined errors for the balance. The results from current evaluations for uranium and plutonium balances are presented [ru

  18. Improved monitoring procedure for Iodine -131 in radiochemical process laboratory

    International Nuclear Information System (INIS)

    Singh, Pratap; Yadav, R.K.B.; Anilkumar, S.; Gopalakrishnan, R.K.; Chakraborty, S.

    2016-01-01

    Radiation Hazard Control Unit at Isotope wing provides radiological safety support and advises for safe processing and production of radiopharmaceuticals. Tellurium Oxide (TeO 2 ), irradiated in a nuclear reactor, is processed in a process laboratory for separating 131 I using dry distillation technique. The workplace environment is being assessed for airborne radioactivity using installed Static Air Samplers (SASs). SASs contains two filter media (glass fibre and charcoal impregnated paper) to collect airborne 131 I radioactivity and laboratory air sampled at 50 litres per minutes (lpm). Personal Air Sampler (PAS) consists of three types of filters viz. a glass fibre, charcoal impregnated paper and cartridges containing activated charcoal granules. Three combinations were studied at a sampling rate of 5 lpm

  19. Radiochemical determination of 210 Po in tobacco and farm food

    International Nuclear Information System (INIS)

    Chung, K. H.; Lee, H. P.; Cho, Y. H.; Choi, G. S.; Kim, C. K.; Lee, C. W.

    2002-01-01

    A method for measuring 210 Po in tobacco (cigarette and leaf) and farm food has been studied by alpha- spectrometry. Polonium was separated from HCl solution in the presence of other radionuclides and ascorbic acid (reduction of Fe 3+ ) by spontaneous deposition onto a silver disc. To determine the optimum conditions for plating polonium on a disc, the effects of reducing agent, plating time etc. were investigated. In the method, the samples are spiked with 208 Po (or 209 Po) as a chemical yield tracer. Because the main sources of 210 Po in the human body are food and cigarette smoke, this procedure to determine 210 Po has been applied to tobacco and farm food samples. Analyses of 210 Po in tobacco leaves and farm food samples using this method are in progress. The concentrations of 210 Po in cigarettes were ranged from 17 to 21 mBq/g and compared with published data on this natural radionuclide

  20. Determination of radiochemical purity of chlormerodrin-203 by electrophoretic method

    Energy Technology Data Exchange (ETDEWEB)

    Jovanovic, V; Zmbova, B; Bzenic, J [Institut za Nuklearne Nauke Boris Kidric, Belgrade (Yugoslavia)

    1977-01-01

    Experiments were performed with NaCl (Merck) as an electrolyte in the concentration range from 1.10/sup -5/ to 5.10/sup -2/N at pH 6.8 using low-voltage electrophoresis in a wet chamber (JEVIPLS-Ljujbljana) with a rectifier MA8901. 0.005 cm/sup 3/ of labelled neohydrin-203, at the concentration of 2-4 mg/cm/sup 3/ and with an activity of mCi/cm/sup 3/ was spotted on Whatman No 3, MM (30x2) chromatographic paper stripes. Correction for electroosmosis was performed with 5% H/sub 2/O/sub 2/, and 5% KI was used for the identification of peroxide mobility. Maximum separation of /sup 203/Hg adn and hydroxychlormerodrin was achieved at 0.05 M NaCl at the potential gradient of 8 V/cm for 2 hrs.

  1. Application of mercury cathode electrolysis to fission-product separation

    International Nuclear Information System (INIS)

    Besson, A.; Prigent, Y.; Van-Kote, F.

    1969-01-01

    A method involving controlled potential mercury cathode electrolysis has been developed to separate fission products. It allows the radiochemical determination of Ag, Cd, Pd, Rh, Ru, Sn, Te, Sb and Mo from solutions of fission products highly concentrated in mineral salts. The general procedure consists in three main steps: electrolytic amalgam generation, destruction of amalgams and ultimate purification of elements by other means. Electrolytic operations last about five hours. Chemical yields lie between 10 per cent and 70 per cent. (authors) [fr

  2. Low-level simultaneous determination of As and Sb in standard reference materials using radiochemical neutron activation analysis with isotopic 77As and 125Sb tracers

    International Nuclear Information System (INIS)

    Byrne, A.R.

    1987-01-01

    The aim of the present work was to develop an older method used in our laboratory based on selective solvent extraction of As and Sb as their iodides with toluene, and by the use of the radioisotopic tracers 77 As and 125 Sb, to improve the accuracy by better control of the radiochemical yields. 77 As was produced for each sample run by concurrent irradiation of a few mg of GeO 2 followed by a rapid separation of 77 As from 77 Ge. The radiochemically purified sample fraction containing 76+77 As and 122+125 Sb was counted on a Ge detector in good geometry. The γ-lines of the four nuclides do not mutually interfere so that a combined measurement of As and Sb may be made. The method was applied to IAEA Milk Powder A-11, Animal Muscle H-4, Bowen's Kale and some other SRMs. The results obtained are discussed in the light of literature measurements. From present and previous results, together with data by Heydorn, the presently accepted value for As in Bowen's Kale of 140 ngxg -1 may be 20% too high. (orig.)

  3. Application of radiochemical method under radioecological situation study in locations of radioactive wastes damping in shallow gulfs of the Novaya Zemlya Archipelago

    International Nuclear Information System (INIS)

    Stepanets, O.V.; Borisov, A.P.; Komarevskij, V.M.; Ligachev, A.N.; Solov'eva

    2005-01-01

    Results of works carried out on the 'Boris Petrov Academician' research ship on burial locations examination of submarine potential hazardous objects in the Kara Sea and in the Stepovoj, Abrosimov and Stivol'ka gulfs are cited. Comprehensive radioecological studies in the damping locations of solid radioactive wastes in the Novaya Zemlya Archipelago conducted in 2002-2004 with application of radio-chemical methods for certain radionuclides determination in the samples of bottom sediments and water in the immediate vicinity from the submerged objects are allowing to revealing the objective picture of man-caused contamination of water environment near submerged objects and by the gulfs water area. The studies uniting instrumental tools of acoustic search and visual objects inspection, opportunity of sampling of bottom sediments and near bottom water in the object vicinity and away from it with subsequent analysis of selected samples by the method of direct gamma-spectroscopy and radio-chemical concentration of certain radionuclides are permitting to obtain the statistically assisted data set on special concentrations of cesium, strontium, cobalt, plutonium radionuclides in a water layer and bottom sediments. Obtained results with taking into account of hydrological conditions allow to explain the peculiarities of radioactivity distribution in separate water areas

  4. A new technology for separation and recovery of materials from waste printed circuit boards by dissolving bromine epoxy resins using ionic liquid

    International Nuclear Information System (INIS)

    Zhu, P.; Chen, Y.; Wang, L.Y.; Qian, G.Y.; Zhou, M.; Zhou, J.

    2012-01-01

    Highlights: ► WPCBs were heated in [EMIM + ][BF 4 − ] for recovering solider at 240 °C. ► The bromine epoxy resins in WPCBs were all dissolved in [EMIM + ][BF 4 − ] at 260 °C. ► Used [EMIM + ][BF 4 − ] is treated by water to obtain regeneration. - Abstract: Recovery of valuable materials from waste printed circuit boards (WPCBs) is quite difficult because WPCBs is a heterogeneous mixture of polymer materials, glass fibers, and metals. In this study, WPCBs was treated using ionic liquid (1-ethyl-3-methylimizadolium tetrafluoroborate [EMIM + ][BF 4 − ]). Experimental results showed that the separation of the solders went to completion, and electronic components (ECs) were removed in WPCBs when [EMIM + ][BF 4 − ] solution containing WPCBs was heated to 240 °C. Meanwhile, metallographic observations verified that the WPCBs had an initial delamination. When the temperature increased to 260 °C, the separation of the WPCBs went to completion, and coppers and glass fibers were obtained. The used [EMIM + ][BF 4 − ] was treated by water to generate a solid–liquid suspension, which was separated completely to obtain solid residues by filtration. Thermal analyses combined with infrared ray spectra (IR) observed that the solid residues were bromine epoxy resins. NMR (nuclear magnetic resonance) showed that hydrogen bond played an important role for [EMIM + ][BF 4 − ] dissolving bromine epoxy resins. This clean and non-polluting technology offers a new way to recycle valuable materials from WPCBs and prevent environmental pollution from WPCBs effectively.

  5. Study of the feasibility of distributed cathodic arc as a plasma source for development of the technology for plasma separation of SNF and radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Amirov, R. Kh.; Vorona, N. A.; Gavrikov, A. V.; Liziakin, G. D.; Polistchook, V. P.; Samoylov, I. S.; Smirnov, V. P.; Usmanov, R. A., E-mail: ravus46@yandex.ru; Yartsev, I. M. [Russian Academy of Sciences, Joint Institute for High Temperatures (Russian Federation)

    2015-12-15

    One of the key problems in the development of plasma separation technology is designing a plasma source which uses condensed spent nuclear fuel (SNF) or nuclear wastes as a raw material. This paper covers the experimental study of the evaporation and ionization of model materials (gadolinium, niobium oxide, and titanium oxide). For these purposes, a vacuum arc with a heated cathode on the studied material was initiated and its parameters in different regimes were studied. During the experiment, the cathode temperature, arc current, arc voltage, and plasma radiation spectra were measured, and also probe measurements were carried out. It was found that the increase in the cathode heating power leads to the decrease in the arc voltage (to 3 V). This fact makes it possible to reduce the electron energy and achieve singly ionized plasma with a high degree of ionization to fulfill one of the requirements for plasma separation of SNF. This finding is supported by the analysis of the plasma radiation spectrum and the results of the probe diagnostics.

  6. Radiochemical studies on some industrial pollutants released to the environment

    International Nuclear Information System (INIS)

    Metwally, E.M.Abel-Ghany

    1997-01-01

    This work aims at characterizing the industrial pollutants that may be released from: Abu-Zaabal fertilizer company, arab ceramic industry, Egyptian alum company near the compass of Atomic Energy Authority (AEA) in Inshas and petroleum pipelines company at the start of lsmailia canal. The work concentrates on soil or/and sediment pollution, the lsmailia canal water stream pollution and plant pollution. Type of the element and its content are major parameters that are traced in the traced in the experimental work. The work stresses on the analysis of the raw materials used in the chosen Factories, their products of current use as well as their wastes and drainage. Instrumental neutron activation analysis (INAA) technique and radiometric determination of elements are adopted through this work. The selection of the technique is based on less time consumption, high accuracy, reliability, selectivity as well as chemical processing and separation need not to applied. Together with INAA determination of natural radioactivity are also adopted for accessing certain specific elements of importance to the fertilizer industry. Beside the mentioned techniques several classical analytical techniques as atomic absorption, spectrophotometric determination and volumetric methods are handled. 25 tabs., 80 figs., 117 refs

  7. Radiochemical Procedures Used at Iaea-Ilmr Monaco for Measuring Artificial Radionuclides Resulting from the Chernobyl Accident

    Science.gov (United States)

    Ballestra, S.; Gastaud, J.; Lopez, J. J.

    The Chernobyl accident which occurred on 26 April 1986 resulted in relatively high levels of radioactive fallout over the major part of Europe. Air filter and precipitation samples enabled us to follow the contamination from the accident. In addition contamination was also monitored in selected environmental samples such as seaweeds, sea water, sediment, soil, suspended matter and biological material from the Mediterranean. All samples were counted on Ge(Li) or Ge(HP) detectors to determine the type and quantity of gamma emitting radionuclides and plutonium, americium and curium isotopes were separated and measured using radiochemical techniques and alpha counting. Increased atmospheric radioactivity from the Chernobyl accident was first detected by observing increased activity levels on air filters taken on April 30, 1986, with maximum activities occurring during 1-3 May. Most of the radionuclides initially measured were short-lived fission products. Cs-137 was one of the predominant isotope in the fallout debris and its deposition at Monaco due to Chernobyl was estimated to be around 1400 Bq m-2, which represents 25-40% of the integrated fallout at this latitude. The deposition of Pu-239+240 was much smaller and was estimated to be around 10 mBq m-2 or only 0.1% of the total deposition from nuclear weapon testing.

  8. The analysis of thallium in geological materials by radiochemical neutron activation and x-ray fluorescence spectrometry: a comparison

    Energy Technology Data Exchange (ETDEWEB)

    McGoldrick, P J; Robinson, P [Tasmania Univ., Sandy Bay, TAS (Australia)

    1994-12-31

    Carrier-based radiochemical neutron activation (RNAA) is a precise and accurate technique for the analysis of Tl in geological materials. For about a decade, until the mid-80s, a procedure modified from Keays et al. (1974) was used at the University of Melbourne to analyse for Tl in a wide variety of geological materials. Samples of powdered rock weighing several hundred milligrams each were irradiated in HIFAR for between 12 hours and 1 week, and subsequently fused with a sodium hydroxide - sodium peroxide mixture and several milligrams of inactive Tl carrier. Following acid digestion of the fusion mixture anion exchange resin was used to separate Tl from the major radioactive rock constituents. The Tl was then stripped from the resin and purified as thallium iodide and a yield measured gravimetrically. Activity from {sup 204}Tl (a {beta}-emitter with a 3 8 year half-life) was measured and Tl determined by reference to pure chemical standards irradiated and processed along with the unkowns. Detection limits for the longer irradiations were about one part per billion. Precision was monitored by repeat analyses of `internal standard` rocks and was estimated to be about five to ten percent (one standard deviation). On the other hand, X-ray fluorescence spectrometry (XRF) was seen as an excellent cost-effective alternative for thallium analysis in geological samples, down to 1 ppm. 6 refs. 1 tab., 1 fig.

  9. The analysis of thallium in geological materials by radiochemical neutron activation and x-ray fluorescence spectrometry: a comparison

    Energy Technology Data Exchange (ETDEWEB)

    McGoldrick, P.J.; Robinson, P. [Tasmania Univ., Sandy Bay, TAS (Australia)

    1993-12-31

    Carrier-based radiochemical neutron activation (RNAA) is a precise and accurate technique for the analysis of Tl in geological materials. For about a decade, until the mid-80s, a procedure modified from Keays et al. (1974) was used at the University of Melbourne to analyse for Tl in a wide variety of geological materials. Samples of powdered rock weighing several hundred milligrams each were irradiated in HIFAR for between 12 hours and 1 week, and subsequently fused with a sodium hydroxide - sodium peroxide mixture and several milligrams of inactive Tl carrier. Following acid digestion of the fusion mixture anion exchange resin was used to separate Tl from the major radioactive rock constituents. The Tl was then stripped from the resin and purified as thallium iodide and a yield measured gravimetrically. Activity from {sup 204}Tl (a {beta}-emitter with a 3 8 year half-life) was measured and Tl determined by reference to pure chemical standards irradiated and processed along with the unkowns. Detection limits for the longer irradiations were about one part per billion. Precision was monitored by repeat analyses of `internal standard` rocks and was estimated to be about five to ten percent (one standard deviation). On the other hand, X-ray fluorescence spectrometry (XRF) was seen as an excellent cost-effective alternative for thallium analysis in geological samples, down to 1 ppm. 6 refs. 1 tab., 1 fig.

  10. Report on the radiochemical and environmental isotope character for monitoring well UE-1-q: Groundwater Characterization Program

    International Nuclear Information System (INIS)

    Davisson, M.L.; Hudson, G.B.; Kenneally, J.; Nimz, G.J.; Rego, J.H.

    1993-06-01

    Well UE-1-q is located in the northeastern portion of area 1 of the Nevada Test Site in southwestern Nevada, 1244.1 meters above sea level. The well was originally an exploratory hole drilled to a depth of 743 meters below the surface (mbs) by LANL in November of 1980. In May 1992, the Groundwater Characterization Program (GCP) extended the total depth to approximately 792.5 mbs. UE-1-q is cased to a total depth of 749.5 mbs, with the remaining uncased depth exposed exclusively to Paleozoicaged carbonate rock, the principle zone of groundwater sampling. Geologic logging indicates approximately 390 meters of tuffaceous and calcareous alluvium overlies 320 meters of Tertiary-aged volcanic ash-flow and bedded tuffs. Paleozoic carbonate lithology extends from 716 mbs to the total well depth and is separated from the overlying Tertiary volcanic deposits by 6 meters of paleocolluvium. This report outlines the results and interpretations of radiochemical and environmental isotopic analyses of groundwater sampled from UE-1-q on July 10, 1992 during the well pump test following well development. In addition, results of the field tritium monitoring performed during the well drilling are reported in Appendix 1. Sampling, analytical techniques, and analytical uncertainties for the groundwater analyses are presented in Appendix 2

  11. Syntheses of therapeutically active labelled molecules for metabolic and pharmacokinetic studies. Synthesis, preservation and radiochemical purity problems

    International Nuclear Information System (INIS)

    Pichat, L.

    1977-01-01

    Molecules labelled with radioactive isotopes are without question an essential tool for metabolic and pharmacokinetic studies. Carbon 14 is often preferred to tritium since it allows better observation of the fate of carbonated structures. The fact that 14 CO 2 alone is used as basic material is the distinguishing feature of syntheses with isotopic carbon. In many cases the synthesis schemes of labelled drugs diverge considerably or entirely from those normally adopted for the unlabelled product. It is usually necessary to work on micro-quantities in order to maintain high specific activities, which implies the use of special synthesis techniques and of chromatographic separation and purification methods. Radiochemical purity tests are carried out by thin layer, column and gas phase chromatography, purity and identity checks by mass spectrometry and by 13 C and proton RMN. Labelled products are radiolysed by interaction of excited species with the molecules of the compound, a phenomenon much faster with tritiated than with 14 C-labelled molecules. The radiolysis rates may be reduced by molecule dilution. For ethical reasons it is not convenient to use 14 C molecules in human experiments, but molecular labelled with stable isotopes ( 13 C, 15 N, D) can serve instead [fr

  12. Radiochemical analysis - a survey of its present state

    International Nuclear Information System (INIS)

    Kosta, L.

    1986-01-01

    Recent decline in the utilization of nuclear activation analysis is in part the consequence of diminished interest in nuclear energy and of a parallel decrease in the availability of irradiation facilities. Associated radiation is another important factor making nuclear techniques less popular. Progress in other analytical approaches currently reduces the share of activation analysis in the total output of analytical data. Thermal neutron activation analysis specifically is indispensable in providing multielement analytical data at low concentration levels for most environmental and geological research projects. High technologies involving less common or high-purity materials also need supporting results by this technique which offers high sensitivity and is not affected by blanks. Recent development of powerful computer programs for optimization of analytical parameters and for deconvolution of complex spectra, together with easy adaptation to automated operation, enhance the instrumental capabilities of nuclear activation techniques. (orig.) [de

  13. Organic separations with membranes

    International Nuclear Information System (INIS)

    Funk, E.W.

    1993-01-01

    This paper presents an overview of present and emerging applications of membrane technology for the separation and purification of organic materials. This technology is highly relevant for programs aimed at minimizing waste in processing and in the treatment of gaseous and liquid effluents. Application of membranes for organic separation is growing rapidly in the petrochemical industry to simplify processing and in the treatment of effluents, and it is expected that this technology will be useful in numerous other industries including the processing of nuclear waste materials

  14. Slifers revisited: a method for determining yields independent of radiochemical measurements

    International Nuclear Information System (INIS)

    Rambo, J.T.

    1976-01-01

    It would be very desirable if an independent method other than radiochemical measurement were available to determine the yields of low-yield events in the alluviums and tuffs of areas 2, 9, and 10 at the Nevada Test Site. The successful application of slifers to the measurement of yields from high-yield events suggests that under some conditions they may also be usable with low-yield events. This view is supported by the evidence discussed here, which is based on direct experience with slifer yield measurements for low-yield events in porous media. Suggested methods for improving slifer yield determinations and a method for determining yields independent of radiochemical measurements are offered

  15. Requirement of radiochemical recovery determination for gross alpha and gross beta estimation in drinking water

    International Nuclear Information System (INIS)

    Raveendran, Nanda; Rao, D.D.; Hegde, A.G.

    2010-01-01

    Presence of radionuclides in drinking water which emits Alpha and Beta particles are the potential sources of internal exposure in drinking water. Gross alpha and gross beta determination in drinking water and packaged drinking water (PDW) as per BIS (Bureau of Indian standards) standards is discussed here. The methods have been tested to account for losses in the radiochemical procedures using radionuclides such as 137 Cs, 90 Sr, 226 Ra, 239 Pu, 243 Am, 232 U. The methods have also been validated in an IAEA proficiency test conducted during 2009. Monitoring of gross alpha and gross beta activity observed in drinking water/packaged drinking water from various states of India were within the limits set by BIS. Average radiochemical recoveries of 84% and 63% were obtained for gross α and gross β respectively. (author)

  16. Radiochemical syntheses further radiopharmaceuticals for positron emission tomography and new strategies for their production

    CERN Document Server

    Kilbourn, Michael R; Kilbourn, Michael R

    2015-01-01

    This book describes methods and procedures for preparing PET radiopharmaceuticals, and highlights new methods for conducting radiochemical reactions with carbon-11 (C11) and fluorine-18 (F18), which are two of the most commonly used radionuclides in positron emission tomography (PET) imaging.     Provides reliable methods for radiochemical syntheses and reactions, including all essential information to duplicate the procedure     Eliminates the time-consuming process of searching journal articles and extracting pertinent details from lengthy experimental sections or supporting information     Focuses on an emerging and important area for pharmaceutical and medical applications     Encompasses technical, regulatory, and application aspects     Includes solid-phase radiochemistry, transition-metal catalyzed radiochemistry, microfluidics, click chemistry, green radiochemistry and new strategies for radiopharmaceutical quality control.

  17. Leakage evaluation in the PCV (Primary Containment Vessel) using chemical and radiochemical data

    International Nuclear Information System (INIS)

    Maeda, Katsuji; Nagasawa, Katsumi

    1998-01-01

    Keeping the reliability of nuclear power plant operation, the primary coolant leakage in the PCV is strictly restricted by the Technical Specifications. It is very important to detect an indication of leakage and estimate the source of leakage to provide countermeasures. Usually the indication of leakage will be detected by increase of drain flow in the PCV sump. There are some possibilities of leakage sources in the PCV, such as reactor water, main steam, condensate, feedwater and closed cooling water. The leakage source contain different chemical and radiochemical species. This means that the leakage source can be presumed and detected by using chemical information from the PCV atmosphere and sump water. To detect the leakage indication and the source quickly and exactly, the PCV Leakage Detection Expert System has been developed. This paper describes how to evaluate the leakage indication and source in the PCV by using chemical and radiochemical data. (author)

  18. Rapid radiochemical methods for preparation of sup(99m)Tc labelled compounds

    International Nuclear Information System (INIS)

    Narasimhan, D.V.S.; Banodkar, S.M.; Kothari, K.; Mani, R.S.

    1981-01-01

    Several inorganic and organic compounds incorporating sup( 99 m)Tc are being extensively used for imaging various body organs. The preparation of these sup( 99 m)Tc compounds with the necessary purity requirements is carried out by controlled reduction of sup( 99 m)Tc-pertechnetate using Sn(II) ions as the reducing agent followed by complexation with various active ingredients. The authors here present procedures developed at Radiopharmaceuticals Section of BARC for preparing sup( 99 m)Tc-diphosphonate, sup( 99 m)Tc-glucoheptonate, sup( 99 m)Tc-albumin microspheres and sup( 99 m)Tc-phytate with high radiochemical purity. The paper also describes procedures for the preparation of freeze-dried kits for single step preparation of these compounds. The paper also describes the authors' experience with various analytical procedures for the determination of radiochemical purity of these preparations. (author)

  19. Study of performance characteristics of a radiochemical method to determine uranium in biological samples

    International Nuclear Information System (INIS)

    Puga, Maria J.; Cerchietti, Maria L.R.; Prudenzo, J.E.; Arguelles, Maria G.

    2005-01-01

    In this paper is described a methodology to calculate detection limit (Ld), quantification level (Lq) and minimum detectable activity (MDA) in a radiochemical method for determination of uranium in urine samples. The concentration is measured by fluorimetry and alpha gross activity using liquid scintillation counting (LSC). The calculation of total propagated uncertainty on a spike sample is presented. Furthermore, the major sources of uncertainty and percentage contribution in both measurements are assessed. (author)

  20. Determination of mercury in biologycal samples by radiochemical neutron activation analysis

    International Nuclear Information System (INIS)

    Suc, N.V.

    1989-01-01

    The radiochemical neutron activation analysis was applied to determine contents of mercury in biological samples. Samples were digested in mixing of H 2 SO 4 and HNO 3 acid. After extraction of mercury by Ni-Ditiodietylphosphoric acid in carbontetrachloride, mercury was back extracted by 5% KI solution. Contents of mercury from five samples of fish was determined by this method. The accuracy of the method was checked by comparing it with NBS standard samples and results are good agreement

  1. Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

    International Nuclear Information System (INIS)

    Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

    1996-10-01

    This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams

  2. A separator

    Energy Technology Data Exchange (ETDEWEB)

    Prokopyuk, S.G.; Dyachenko, A.Ye.; Mukhametov, M.N.; Prokopov, O.I.

    1982-01-01

    A separator is proposed which contains separating slanted plates and baffle plates installed at a distance to them at an acute angle to them. To increase the effectiveness of separating a gas and liquid stream and the throughput through reducing the secondary carry away of the liquid drops and to reduce the hydraulic resistance, as well, openings are made in the plates. The horizontal projections of each opening from the lower and upper surfaces of the plate do not overlap each other.

  3. Synthesis of N-[methyl-11C]hydromorphone by using multivariate strategies for optimization of radiochemical yields

    International Nuclear Information System (INIS)

    Rimland, Annika; Bergson, Goeran; Obenius, Ulf; Sjoeberg, Stefan; Langstroem, Bengt

    1987-01-01

    The synthesis of N-[methyl- 11 C]hydromorphone has been performed by using [ 11 C]methyl iodide and desmethyl hydromorphone in a mixture of dimethylsulphoxide and dimethylformamide as solvent. Optimization of the radiochemical yield by varying the reaction conditions was performed by using multivariate strategies. The labelled hydromorphone was obtained in 72% radiochemical yield in the alkylation reaction with [ 11 C]-methyl iodide, counted from the end of the [ 11 C]methyl iodide synthesis. N-[Methyl- 11 C]hydromorphone was obtained as a ready injectable pharmaceutical solution with a total synthesis time of 40 min and in a 10% total radiochemical yield, with a radiochemical purity > 99.5%, according to HPLC analysis. (author)

  4. Radiochemical aging of an epoxy network; Vieillissement radiochimique d'un reseau epoxyde

    Energy Technology Data Exchange (ETDEWEB)

    Devanne, Th

    2003-05-01

    This thesis is to give a better understanding of the radiochemical aging of a thermoset resin under gamma irradiation. The conditions of aging are gamma irradiation under air with a dose rate of 2 kGy/h at 120 C. The requested lifetime is four years, it means a dose of 70 MGy. The first step of this work was the choice of a resistive epoxy resin. This choice was made thanks to the literature data. The high glass transition temperature and the high amount of aromatic groups were the main criteria of the final choice. After this choice, thermal and mechanical properties were followed under thermal and radiochemical aging: i) under thermal aging, after 600 hours at 220 C, the glass transition temperature remained unchanged. But, from a mechanical point of view, properties at break dramatically decreased. This embrittlement was assigned to a critical oxidized layer. The thickness of this layer was estimated about 30 {mu}m. ii) the same kind of embrittlement was observed under radiochemical aging. Moreover, it appeared a decrease of the glass transition temperature when increasing the dose of irradiation. This indicates that the main degradation mechanism is chain scission under anaerobic atmosphere. We, then, proposed a mechanistic model associated with a kinetic model to predict the evolution of the glass transition temperature depending on the irradiation conditions. Parameters of the kinetic model were determined by solid NMR and ESR experiments. Comparison between experimental and calculated values at 120 C is satisfactory, a global good agreement was found. (author)

  5. Influence of Storage Temperature on Radiochemical Purity of 99mTc-Radiopharmaceuticals.

    Science.gov (United States)

    Uccelli, Licia; Boschi, Alessandra; Martini, Petra; Cittanti, Corrado; Bertelli, Stefania; Bortolotti, Doretta; Govoni, Elena; Lodi, Luca; Romani, Simona; Zaccaria, Samanta; Zappaterra, Elisa; Farina, Donatella; Rizzo, Carlotta; Giganti, Melchiore; Bartolomei, Mirco

    2018-03-15

    The influence of effective room temperature on the radiochemical purity of 99m Tc-radiopharmaceuticals was reported. This study was born from the observation that in the isolators used for the preparation of the 99m Tc-radiopharmaceuticals the temperatures can be higher than those reported in the commercial illustrative leaflets of the kits. This is due, in particular, to the small size of the work area, the presence of instruments for heating, the continuous activation of air filtration, in addition to the fact that the environment of the isolator used for the 99m Tc-radiopharmaceuticals preparation and storage is completely isolated and not conditioned. A total of 244 99m Tc-radiopharmaceutical preparations (seven different types) have been tested and the radiochemical purity was checked at the end of preparation and until the expiry time. Moreover, we found that the mean temperature into the isolator was significantly higher than 25 °C, the temperature, in general, required for the preparation and storage of 99m Tc-radiopharmaceuticals. Results confirmed the radiochemical stability of radiopharmaceutical products. However, as required in the field of quality assurance, the impact that different conditions than those required by the manufacturer on the radiopharmaceuticals quality have to be verified before human administration.

  6. Evaluation of the Ra-226 activity in public-consumption water in the Huarangal Valley using the radiochemical precipitation method as Ba(Ra)SO4

    International Nuclear Information System (INIS)

    Ysla C, M.A.

    1999-01-01

    Five radiochemical methods for Ra-226 determination in public-consumption river waters are developed in this work. Quantification of this radionuclide was conducted through high-resolution gamma spectrometry. These five methods are based on the precipitation of Ra-226 as Ba(Ra)SO 4 . The second of these methods has been considered the best due to its low cost, high radiochemical performance (83,53%) and lowest standard deviation (7,97). Using the second method (standardized method) it was determined that the activity present in a 32 L sample of water is 0,1526 Bq/L. Assuming that each person in Huarangal Valley consumes an average of 2 liters of water a day, we can estimate that this person consumes 111,398 Bq anally, a very low percentage compared to the limit activity reported in other parts of the world. Physicochemical analysis were also conducted in waters of the Chillon river; the results obtained are within the permissible limits established by the World Health Organization, the Institute of Technological, Industrial and Technical Regulation Research (ITINTEC), and the law for Waters of the Ministry of Agriculture. One can conclude, from the physicochemical analysis that have been conducted, that the waters of the Chillon river are fit for public consumption and do not present specific radio-sanitary risks for people living in the Huarangal valley

  7. Implementation of advanced electrochemical oxidation for radiochemical concentrate treatment

    International Nuclear Information System (INIS)

    Velin, Anna; Bengtsson, Bernt; Lundblad, Magnus

    2012-09-01

    Water treatments in Nuclear Power Plants include ion exchange, evaporation and mechanical filtration techniques. These technologies are used to control the chemical release and to treat coolant in light water reactor types from chemicals and most importantly, from radioactive nuclides. Most of the conventional methods are efficient, but at the same time producing aqueous concentrates with high organic load. Before final storage, the level of organic content of those concentrates must be reduced. Advanced electrochemical oxidation with Boron Doped Diamond (BDD) electrodes are being investigated in laboratory- and pilot scale for treatment of dilute and concentrated aqueous waste streams at Vattenfall-Ringhals NPP. BDD anodes and cathodes are having high over potential against water electrolysis, and therefore well suitable for oxidation of organics. Dilute wastewater, such as laundry water, which has an initial COD level of around 500 mg/l, was reduced to a level of < 20 mg/l in the laboratory. Evaporator concentrates, with a TS content of 3% and pH of 7-8, were treated in pilot scale of 800 liters, working in batch operation mode, at temperatures between 25-50 deg. C. Initial COD levels between 2500 and 8000 mg/l in concentrate was reduced to < 100 mg/l at the first tests and later to < 300 mg/l. The advanced electrochemical oxidation is proven to be a promising technique for radioactive concentrate treatment. Long-term operation is still ongoing to evaluate the performance of the electrodes, cell components and overall process efficiency. (authors)

  8. A Synergistic Combination of Advanced Separation and Chemical Scale Inhibitor Technologies for Efficient Use of Imparied Water As Cooling Water in Coal-based Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jasbir Gill

    2010-08-30

    Nalco Company is partnering with Argonne National Laboratory (ANL) in this project to jointly develop advanced scale control technologies that will provide cost-effective solutions for coal-based power plants to operate recirculating cooling water systems at high cycles using impaired waters. The overall approach is to use combinations of novel membrane separations and scale inhibitor technologies that will work synergistically, with membrane separations reducing the scaling potential of the cooling water and scale inhibitors extending the safe operating range of the cooling water system. The project started on March 31, 2006 and ended in August 30, 2010. The project was a multiyear, multi-phase project with laboratory research and development as well as a small pilot-scale field demonstration. In Phase 1 (Technical Targets and Proof of Concept), the objectives were to establish quantitative technical targets and develop calcite and silica scale inhibitor chemistries for high stress conditions. Additional Phase I work included bench-scale testing to determine the feasibility of two membrane separation technologies (electrodialysis ED and electrode-ionization EDI) for scale minimization. In Phase 2 (Technology Development and Integration), the objectives were to develop additional novel scale inhibitor chemistries, develop selected separation processes, and optimize the integration of the technology components at the laboratory scale. Phase 3 (Technology Validation) validated the integrated system's performance with a pilot-scale demonstration. During Phase 1, Initial evaluations of impaired water characteristics focused on produced waters and reclaimed municipal wastewater effluents. Literature and new data were collected and evaluated. Characteristics of produced waters vary significantly from one site to another, whereas reclaimed municipal wastewater effluents have relatively more uniform characteristics. Assessment to date confirmed that calcite and silica

  9. Radiochemical separation of actinides from environmental samples for determination with DF-ICP-MS and alpha spectrometry

    International Nuclear Information System (INIS)

    Ayranov, M.; Kraehenbuehl, U.; Sahli, H.; Roellin, S.; Burger, M.

    2005-01-01

    The purpose of this study was to develop an optimised sample preparation method for the determination of Pu, Am, and Cm in environmental samples, soils, and sediments, and to compare the sensitivities of DF-ICP-MS, alpha spectrometry, and liquid scintillation alpha spectrometry. Borate fusion was used for sample material digestion. Two methods based on TOPO liquid-liquid extraction and combination of TEVA and TRU extraction chromatography showed highest yields of 92.7% for Pu, 86.8% for Am, and 87.6% for Cm. The detection limits were between 0.014-0.034 Bq/kg for 239 Pu, 0.014-0.093 Bq/kg for 240 Pu, and 0.011-1.20 Bq/kg for 241 Am. Analytical results for 238 Pu, 239 Pu, 240 Pu, 241 Pu and 241 Am and their isotope ratios in certified reference materials (IAEA-135 and IAEA-300) indicated very good accuracy of the methods proposed. (orig.)

  10. General aspects of the cyclotrons and radiochemical separation of: 11 C, 15 O, 18 F and 14 N

    International Nuclear Information System (INIS)

    Alanis M, J.

    1997-07-01

    The particle accelerators, as the cyclotrons, are extraordinarily important as tools for the radioisotope production and its application in the area of the medicine. In this time, another method exists for the production of artificial radioisotopes, based on the irradiation of samples with alpha particles or with neutrons coming from a natural radioisotope being obtained a neutron source (Ra + Be, Rn + Be, Po + Be). However, its can be obtained a great quantity of radioisotopes by means of cyclotrons in very short time, compared with other methods. After the second world war, artificial radioisotopes took place by means of reactors and its had many applications, not only medical and in little time the accelerators were manufactured that were more indispensable that the reactors to produce radioisotopes with medical aims. For this reason, the accelerators, in few years became in machines very important for the production of artificial radioisotopes and consequently its were developed techniques of radioactive traces progressively more sophisticated, since it is evident that the production of radioactive nuclei through nuclear reactors its cannot satisfy all the demands. In general terms, only the neutrons can be used as nuclear projectiles in reactors and as a result, the production spectra of radioisotopes is limited and as alternative it is unavoidable that the cyclotrons are a good tool for this end. The use of a cyclotron to produce radioisotopes, it can be justified, only if the following conditions are completed. 1. If the radioisotopes of an element produced in a reactor don't favor with the nuclear properties for the purposes of the traced studies, for example: if the half life is very short or very big, if the decay system not to suit him. 2. If the wanted radioisotope cannot produce in the reactor with enough specific activity. (Author)

  11. Isotope separation

    International Nuclear Information System (INIS)

    Eerkens, J.W.

    1979-01-01

    A method of isotope separation is described which involves the use of a laser photon beam to selectively induce energy level transitions of an isotope molecule containing the isotope to be separated. The use of the technique for 235 U enrichment is demonstrated. (UK)

  12. Simultaneous radiochemical determination of plutonium, strontium, uranium, and iron nuclides and application to atmospheric deposition and aerosol samples

    Energy Technology Data Exchange (ETDEWEB)

    Rosner, G.; Hoetzl, H.; Winkler, R. (Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen, Neuherberg (Germany, F.R.). Inst. fuer Strahlenschutz)

    1990-11-01

    A procedure for the sequential radiochemical determination of plutonium, strontium, uranium and iron nuclides is described. The separation is carried out on a single anion exchange column. Pu(IV), U(VI) and Fe(III) are fixed on Bio Rad AG 1-X4 from 9 mol/l HCl, while the sample effluent is used for the determination of radiostrontium. Fe and U are eluted separately with 7 mol/l HNO{sub 3}, and Pu(III) is eluted with 1.2 mol/l HCl containing hydrogen peroxide. Subsequently, Pu and U are electrolysed and counted by alpha spectrometry. Radiostrontium is purified by the nitrate method and counted in a low level beta proportional counter. Fe is purified by extraction and cation exchange and {sup 55}Fe is counted by X-ray spectrometry with a Si(Li) detector. The sample preparation and the application of the procedure to large samples, namely aerosols from 10{sup 5} m{sup 3} of air, and monthly deposition samples from 0.6 m{sup 2} sampling area (10-100 l) are described. Chemical yields are for Pu 70 {plus minus} 20, for Sr 80 {plus minus} 15, for U 80-90, and for Fe 75 {plus minus} 10%. As an example, the maximum airborne radionuclide concentrations determined with that procedure in fortnightly collected samples at Neuherberg after the Chernobyl accident were: {sup 239+240}Pu, 2.58; {sup 238}Pu, 1.40; {sup 238}U, 0.65; {sup 234}U, 0.67; {sup 90}Sr, 7600; and {sup 55}Fe, 990 {mu}Bqm{sup -3}. With appropriate changes in sample preparation, the procedure is applicable to other kinds of samples. (orig.).

  13. Simultaneous radiochemical determination of plutonium, strontium, uranium, and iron nuclides and application to atmospheric deposition and aerosol samples

    International Nuclear Information System (INIS)

    Rosner, G.; Hoetzl, H.; Winkler, R.

    1990-01-01

    A procedure for the sequential radiochemical determination of plutonium, strontium, uranium and iron nuclides is described. The separation is carried out on a single anion exchange column. Pu(IV), U(VI) and Fe(III) are fixed on Bio Rad AG 1-X4 from 9 mol/l HCl, while the sample effluent is used for the determination of radiostrontium. Fe and U are eluted separately with 7 mol/l HNO 3 , and Pu(III) is eluted with 1.2 mol/l HCl containing hydrogen peroxide. Subsequently, Pu and U are electrolysed and counted by alpha spectrometry. Radiostrontium is purified by the nitrate method and counted in a low level beta proportional counter. Fe is purified by extraction and cation exchange and 55 Fe is counted by X-ray spectrometry with a Si(Li) detector. The sample preparation and the application of the procedure to large samples, namely aerosols from 10 5 m 3 of air, and monthly deposition samples from 0.6 m 2 sampling area (10-100 l) are described. Chemical yields are for Pu 70 ± 20, for Sr 80 ± 15, for U 80-90, and for Fe 75 ± 10%. As an example, the maximum airborne radionuclide concentrations determined with that procedure in fortnightly collected samples at Neuherberg after the Chernobyl accident were: 239+240 Pu, 2.58; 238 Pu, 1.40; 238 U, 0.65; 234 U, 0.67; 90 Sr, 7600; and 55 Fe, 990 μBqm -3 . With appropriate changes in sample preparation, the procedure is applicable to other kinds of samples. (orig.)

  14. Environmental Assessment for the Commercial Demonstration of the Low NOx Burner/Separated Over-Fire Air (LNB/SOFA) Integration System Emission Reduction Technology, Finney County, Kansas

    Energy Technology Data Exchange (ETDEWEB)

    n/a

    2003-03-11

    The U.S. Department of Energy (DOE) proposes to provide partial funding to the Sunflower Electric Power Corporation (Sunflower), to demonstrate the commercial application of Low-NO{sub x} Burner/Separated Over-Fire Air (LNB/SOFA) integration system to achieve NO{sub x} emission reduction to the level of 0.15 to 0.22 pounds per million British thermal units (lb/MM Btu). The proposed project station is Sunflower's 360 MW coal-fired generation station, Holcomb Unit No. 1 (Holcomb Station). The station, fueled by coal from Wyoming's Powder River Basin, is located near Garden City, in Finney County, Kansas. The period of performance is expected to last approximately 2 years. The Holcomb Station, Sunflower LNB/SOFA integrated system would be modified in three distinct phases to demonstrate the synergistic effect of layering NO{sub x} control technologies. Once modified, the station would demonstrate that a unit equipped with an existing low-NO{sub x} burner system can be retrofitted with a new separated over-fire air (SOFA) system, coal flow measurement and control, and enhanced combustion monitoring to achieve about 45 percent reduction in nitrogen oxides (NO{sub x}) emissions. The proposed project would demonstrate a technology alternative to Selective Catalytic Reduction (SCR) systems. While SCR does generally achieve high reductions in NO{sub x} emissions (from about 0.8 lb/MM to 0.12 lb/MM Btu), it does so at higher capital and operating cost, requires the extensive use of critical construction labor, requires longer periods of unit outage for deployment, and generally requires longer periods of time to complete shakedown and full-scale operation. Cost of the proposed project technology would be on the order of 15-25 percent of that for SCR, with consequential benefits derived from reductions in construction manpower requirements and periods of power outages. This proposed technology demonstration would generally be applicable to boilers using opposed

  15. 全膜分离技术及其在电厂化学水处理中的应用%Whole Membrane Separation Technology and Its Application in Chemical Water Treatment of Power Plant

    Institute of Scientific and Technical Information of China (English)

    马福刚

    2011-01-01

    This paper introduces the definition, types and characteristics of membrane separation technology, and application instance of whole membrane separation treatment process (UF-RO-EDI) in power plant boiler feed water treatment.%介绍了膜分离技术的定义、种类、特点以及全膜分离处理工艺(UF-RO-EDI)在电厂锅炉补给水处理中的应用实例.

  16. Separating oil from water

    Energy Technology Data Exchange (ETDEWEB)

    Webb, C

    1991-04-11

    The technology available to deal with oil spills has assumed many new faces in recent years. Methods of dealing with small-scale pollution in the process industries and vast oil slicks such as that in the Gulf have developed in parallel. The progress being made in finding new means of separating oil from water is reported and the relative merits of bioremediation, hydrocylones, horizontal separators and gas flotation are discussed. (author).

  17. CENTRIFUGAL SEPARATORS

    Science.gov (United States)

    Skarstrom, C.

    1959-03-10

    A centrifugal separator is described for separating gaseous mixtures where the temperature gradients both longitudinally and radially of the centrifuge may be controlled effectively to produce a maximum separation of the process gases flowing through. Tbe invention provides for the balancing of increases and decreases in temperature in various zones of the centrifuge chamber as the result of compression and expansions respectively, of process gases and may be employed effectively both to neutralize harmful temperature gradients and to utilize beneficial temperaturc gradients within the centrifuge.

  18. Microparticle Separation by Cyclonic Separation

    Science.gov (United States)

    Karback, Keegan; Leith, Alexander

    2017-11-01

    The ability to separate particles based on their size has wide ranging applications from the industrial to the medical. Currently, cyclonic separators are primarily used in agriculture and manufacturing to syphon out contaminates or products from an air supply. This has led us to believe that cyclonic separation has more applications than the agricultural and industrial. Using the OpenFoam computational package, we were able to determine the flow parameters of a vortex in a cyclonic separator in order to segregate dust particles to a cutoff size of tens of nanometers. To test the model, we constructed an experiment to separate a test dust of various sized particles. We filled a chamber with Arizona test dust and utilized an acoustic suspension technique to segregate particles finer than a coarse cutoff size and introduce them into the cyclonic separation apparatus where they were further separated via a vortex following our computational model. The size of the particles separated from this experiment will be used to further refine our model. Metropolitan State University of Denver, Colorado University of Denver, Dr. Randall Tagg, Dr. Richard Krantz.

  19. Development of a radiochemical procedure for certification of phosphorus implantation dose in silicon

    International Nuclear Information System (INIS)

    Paul, R.L.; Simons, D.S.

    2002-01-01

    The U.S. semiconductor industry relies heavily on secondary ion mass spectrometry (SIMS) for characterization of the depth distribution of dopants such as boron, arsenic, and phosphorus in silicon. To assist the industry in achieving high accuracy measurements, two Standard Reference Materials (SRMs) have been developed by NIST as SIMS calibration standards: SRM 2137 (Boron Implant in Silicon), certified by neutron depth profiling, and SRM 2134 (Arsenic Implant in Silicon), certified by instrumental neutron activation analysis. The industry is still in need of a phosphorus standard. Plans are currently underway to develop a phosphorus implant in silicon SRM, to be certified by radiochemical neutron activation analysis (RNAA). RNAA was chosen because other techniques lack the necessary sensitivity, chemical specificity and matrix independence to measure phosphorus at implantation levels. In order to assess the sensitivity, accuracy, and precision of RNAA for this work, preliminary measurements were carried out on six pieces of a phosphorus-implanted silicon wafer that was previously used in a round-robin study of SIMS measurement repeatability. Standards were prepared by depositing micro litre amounts of a standardized phosphorus solution on aluminum foil. A non-implanted silicon wafer was analysed as a blank. Samples were irradiated at a neutron fluency rate of 1 x 10 14 cm -2 s -1 to convert 31 P to 32 P, then mixed with milligram amounts of phosphorus carrier and dissolved in a mixture of nitric and hydrofluoric acids. Phosphorus was separated from the matrix by precipitation first as ammonium phosphomolybdate then as magnesium ammonium phosphate. The yield (fraction of recovered carrier) was determined gravimetrically as Mg(NH 4 )PO 4 .6H 2 O. 32 P was measured using a beta proportional counter. The measurements yielded a mean and standard deviation of (8.35 ± 0.20) x 10 14 atoms.cm -2 (relative standard deviation = 2.35 %), in agreement with both the nominal

  20. Isotopic separation

    International Nuclear Information System (INIS)

    Castle, P.M.

    1979-01-01

    This invention relates to molecular and atomic isotope separation and is particularly applicable to the separation of 235 U from other uranium isotopes including 238 U. In the method described a desired isotope is separated mechanically from an atomic or molecular beam formed from an isotope mixture utilising the isotropic recoil momenta resulting from selective excitation of the desired isotope species by radiation, followed by ionization or dissociation by radiation or electron attachment. By forming a matrix of UF 6 molecules in HBr molecules so as to collapse the V 3 vibrational mode of the UF 6 molecule the 235 UF 6 molecules are selectively excited to promote reduction of UF 6 molecules containing 235 U and facilitate separation. (UK)