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Sample records for no-carrier-added radioactive scandium

  1. Carrier-added and no-carrier-added syntheses of [18F]spiroperidol and [18F]haloperidol

    International Nuclear Information System (INIS)

    Kilbourn, M.R.; Welch, M.J.; Dence, C.S.; Tewson, T.J.; Saji, H.; Maeda, M.

    1984-01-01

    Syntheses of [ 18 F]haloperidol and [ 18 F]spiroperidol in both no-carrier-added and carrier-added forms have been accomplished. The no-carrier-added [ 18 F]butyrophenone neuroleptics were prepared in low ( 18 F-neuroleptics were prepared in better (5-17%) yields by 18 F-for- 19 F nucleophilic aromatic substitution. The preparation of all synthetic precursors, and procedures for radiolabeling are fully described. (author)

  2. Carrier-added and no-carrier-added syntheses of (/sup 18/F)spiroperidol and (/sub 18/F)haloperidol

    Energy Technology Data Exchange (ETDEWEB)

    Kilbourn, M R; Welch, M J; Dence, C S; Tewson, T J; Saji, H; Maeda, M

    1984-07-01

    Syntheses of (18F)haloperidol and (18F)spiroperidol in both no-carrier-added and carrier-added forms have been accomplished. The no-carrier-added (18F)butyrophenone neuroleptics were prepared in low (less than 2%) yield by acid decomposition of aryl piperidine triazenes. Carrier-added 18F-neuroleptics were prepared in better (5-17%) yields by 18F-for-19F nucleophilic aromatic substitution. The preparation of all synthetic precursors, and procedures for radiolabeling are fully described.

  3. Carrier-added and no-carrier-added syntheses of (/sup 18/F)spiroperidol and (/sup 18/F)haloperidol

    Energy Technology Data Exchange (ETDEWEB)

    Kilbourn, M R; Welch, M J; Dence, C S; Tewson, T J; Saji, H; Maeda, M [Washington Univ., St. Louis, MO (USA). Edward Mallinckrodt Inst. of Radiology

    1984-07-01

    Syntheses of (/sup 18/F)haloperidol and (/sup 18/F)spiroperidol in both no-carrier-added and carrier-added forms have been accomplished. The no-carrier-added (/sup 18/F)butyrophenone neuroleptics were prepared in low (<2%) yield by acid decomposition of aryl piperidine triazenes. Carrier-added /sup 18/F-neuroleptics were prepared in better (5-17%) yields by /sup 18/F-for-/sup 19/F nucleophilic aromatic substitution. The preparation of all synthetic precursors, and procedures for radiolabeling are fully described.

  4. Synthesis of no-carrier-added alpha-[11C]methyl-L-tryptophan

    International Nuclear Information System (INIS)

    Chaly, T.; Diksic, M.

    1988-01-01

    Described here is a synthesis of no-carrier-added alpha-[ 11 C]methyl-L-tryptophan based on alkylation with 11 CH 3 I of an anion generated by reacting the Schiff base of L-tryptophan methyl ester with di-isopropylamine. The synthesis requires approximately 30 min after the end of 11 CO 2 collection and gives alpha-[ 11 C]methyl-L-tryptophan in a 20-25% radiochemical yield calculated at the end of the synthesis and without correction for radioactive decay. The specific activity of the final radiopharmaceutical, measured at the end of the synthesis, was around 2000 Ci/mmol. Data confirming the stereospecificity of the synthesis are also presented

  5. Direct no-carrier-added 18F-labelling of arenes via nucleophilic substitution on aryl(2-thienyl)iodonium salts

    International Nuclear Information System (INIS)

    Ross, T.L.

    2006-01-01

    For in vivo imaging of molecular processes via positron emission tomography (PET) radiotracers of high specific activity are demanded. In case of the most commonly used positron emitter fluorine-18, this is only achievable with no-carrier-added [ 18 F]fluoride, which implies nucleophilic methods of 18 F-substitution. Whereas electron deficient aromatic groups can be labelled in one step using no-carrier-added [ 18 F]fluoride, electron rich 18 F-labelled aromatic molecules are only available by multi-step radiosyntheses or carrier-added electrophilic reactions. Here, diaryliodonium salts represent an alternative, since they have been proven as potent precursor for a direct nucleophilic 18 F-introduction into aromatic molecules. Furthermore, as known from non-radioactive studies, the highly electron rich 2-thienyliodonium leaving group leads to a high regioselectivity in nucleophilic substitution reactions. Consequently, a direct nucleophilic no-carrier-added 18 F-labelling of electron rich arenes via aryl(2-thienyl)iodonium precursors was developed in this work. The applicability of direct nucleophilic 18 F-labelling was examined in a systematic study on eighteen aryl(2-thienyl)iodonium salts. As electron rich precursors the ortho-, meta- and para-methoxyphenyl(2-thienyl)iodonium bromides, iodides, tosylates and triflates were synthesised. In addition, para-substituted (R=BnO, CH 3 , H, Cl, Br, I) aryl(2-thienyl)iodonium bromides were prepared as precursors with a systematically varying electron density. As first approach, the general reaction conditions of the nucleophilic 18 F-substitution procedure were optimised. The best conditions for direct nucleophilic no-carrier-added 18 F-labelling via aryl(2-thienyl)iodonium salts were found with dimethylformamide as solvent, a reaction temperature of 130±3 C and 25 mmol/l as concentration of the precursor. (orig.)

  6. Direct no-carrier-added {sup 18}F-labelling of arenes via nucleophilic substitution on aryl(2-thienyl)iodonium salts

    Energy Technology Data Exchange (ETDEWEB)

    Ross, T L

    2006-01-15

    For in vivo imaging of molecular processes via positron emission tomography (PET) radiotracers of high specific activity are demanded. In case of the most commonly used positron emitter fluorine-18, this is only achievable with no-carrier-added [{sup 18}F]fluoride, which implies nucleophilic methods of {sup 18}F-substitution. Whereas electron deficient aromatic groups can be labelled in one step using no-carrier-added [{sup 18}F]fluoride, electron rich {sup 18}F-labelled aromatic molecules are only available by multi-step radiosyntheses or carrier-added electrophilic reactions. Here, diaryliodonium salts represent an alternative, since they have been proven as potent precursor for a direct nucleophilic {sup 18}F-introduction into aromatic molecules. Furthermore, as known from non-radioactive studies, the highly electron rich 2-thienyliodonium leaving group leads to a high regioselectivity in nucleophilic substitution reactions. Consequently, a direct nucleophilic no-carrier-added {sup 18}F-labelling of electron rich arenes via aryl(2-thienyl)iodonium precursors was developed in this work. The applicability of direct nucleophilic {sup 18}F-labelling was examined in a systematic study on eighteen aryl(2-thienyl)iodonium salts. As electron rich precursors the ortho-, meta- and para-methoxyphenyl(2-thienyl)iodonium bromides, iodides, tosylates and triflates were synthesised. In addition, para-substituted (R=BnO, CH{sub 3}, H, Cl, Br, I) aryl(2-thienyl)iodonium bromides were prepared as precursors with a systematically varying electron density. As first approach, the general reaction conditions of the nucleophilic {sup 18}F-substitution procedure were optimised. The best conditions for direct nucleophilic no-carrier-added {sup 18}F-labelling via aryl(2-thienyl)iodonium salts were found with dimethylformamide as solvent, a reaction temperature of 130{+-}3 C and 25 mmol/l as concentration of the precursor. (orig.)

  7. Method for chromatographically recovering scandium and yttrium

    International Nuclear Information System (INIS)

    Snyder, T.S.; Stoltz, R.A.

    1991-01-01

    This paper describes a method for chromatographically recovering scandium and yttrium from the residue of a sand chlorinator. It comprises: providing a residue from a sand chlorinator, the residue containing scandium, yttrium, sodium, calcium and at least one radioactive metal of the group consisting of radium, thorium and uranium; digesting the residue with an acid to produce an aqueous liquid containing scandium, yttrium, sodium, calcium and at least one radioactive metal of the group consisting of radium, thorium and uranium; feeding the metal containing liquid through a cation exchanger; eluding the cation exchanger with an acid eluant to to produce: a first eluate containing at least half of the total weight of the calcium and sodium in the feed liquid; a second eluate containing at least half of the total weight of the one or more radioactive metals in the feed liquid; a third eluate containing at least half of the yttrium in the feed liquid, and a fourth eluate containing at least half of the weight of the scandium in the feed liquid

  8. Studies on low-carrier radiofluorination of non-active aromatics with no-carrier-added [18F]fluoride

    International Nuclear Information System (INIS)

    Cardinale, Jens

    2013-01-01

    In vivo imaging with positron emission tomography generally demands radiotracers with a high specific activity. In case of fluorine-18 the required no-carrier-added (n.c.a.) starting material is only available in form of fluoride. This and the short half-life of 109.7 minutes of the radionuclide lead to the demand of special methods for radiosyntheses. The only practical procedure for manufacturing n.c.a. [ 18 F]fluoro-compounds is therefore nucleophilic substitution. There is, however, still a lack of effective procedures for the labelling of electron rich aromatic molecules starting from n.c.a. [ 18 F]fluoride. A process for n.c.a. radiofluorination of these compounds is offered by the reaction of iodonium compounds as starting materials. In this study modern procedures for the synthesis of iodoniumsalts and -ylides were investigated. Several precursor molecules for the versatile synthetic building block 4-[ 18 F]fluoroiodobenzene were synthesised. In this course, a new one-pot procedure for the synthesis of iodoniumylides was developed. Further on, the syntheses of suitable iodonium precursors for two fluorophenoxy-derivatives, which are possible antidepressants, were investigated. Due to their binding profile these compounds can be considered as ligands for the serotonin reuptake transporter (SERT) and the norepinephrin reuptake transporter (NET), respectively. The preparation of appropriate iodonium salts proved to be too problematic, while the synthesis of suitable iodoniumylides could be accomplished with satisfactory yields of about 30% and 40 %, respectively. Both compounds were labelled with n.c.a. [ 18 F]fluoride and deprotected to the desired target compounds 4-((3-[ 18 F]fluorophenoxy)(phenyl)methyl)piperidine and 4-((4-[ 18 F]fluorophenoxy)(phenyl)methyl)piperidine in radiochemical yields of about 40 % and 25 %, respectively. Those are now available for preclinical evaluation studies. Furthermore, a process for the palladium catalysed synthesis of 18

  9. Automated chemoenzymatic synthesis of no-carrier-added [carbonyl-11C]propionyl L-carnitine for pharmacokinetic studies

    International Nuclear Information System (INIS)

    Davenport, R.J.; Pike, V.W.; Dowsett, K.; Turton, D.R.; Poole, K.

    1997-01-01

    Propionyl-L-carnitine (PLC) is under development as a therapeutic for the treatment of peripheral artery disease, coronary heart disease and chronic heart failure. Three methods were examined for labelling PLC in its propionyl group with positron-emitting carbon-11 (t 1/2 = 20.3 min), one chemical and two chemoenzymatic. The former was based on the preparation of [ 11 C]propionyl chloride as labelling agent via 11 C-carboxylation of ethylmagnesium bromide with cyclotron-produced [ 11 C]carbon dioxide and subsequent chlorination. Reaction of carrier-added [ 11 C]propionyl chloride with L-carnitine in trifluoroacetic acid gave [ 11 C]PLC in 12% radiochemical yield (decay-corrected) from cyclotron-produced [ 11 C]carbon dioxide. However, the radiosynthesis was unsuccessful at the no-carrier added (NCA) level of specific radioactivity. [ 11 C]Propionate, as a radioactive precursor for chemoenzymatic routes, was prepared via carboxylation of ethylmagnesium bromide with [ 11 C]carbon dioxide and hydrolysis. NCA [ 11 C]PLC was prepared in 68 min in 14% radiochemical yield (decay-corrected) from [ 11 C]propionate via sequential conversions catalysed by acetate kinase, phosphotransacetylase and carnitine acetyltransferase. A superior chemoenzymatic synthesis of NCA [ 11 C]PLC was developed, based on the use of a novel supported Grignard reagent for the synthesis of [ 11 C]propionate and conversions by S-acetyl-CoA synthetase and carnitine acetyltransferase. This gave an overall radiochemical yield of 30-48% (decay-corrected). This synthesis was automated for radiation safety and provides pure NCA [ 11 C]PLC in high radioactivities ready for intravenous administration within 25 min from radionuclide production. The [ 11 C]PLC is suitable for pharmacokinetic studies in human subjects with PET and the elucidation of the fate of the propionyl group of PLC in vivo. (Author)

  10. Methods for chemical recovery of non-carrier-added radioactive tin from irradiated intermetallic Ti-Sb targets

    Science.gov (United States)

    Lapshina, Elena V [Troitsk, RU; Zhuikov, Boris L [Troitsk, RU; Srivastava, Suresh C [Setauket, NY; Ermolaev, Stanislav V [Obninsk, RU; Togaeva, Natalia R [Obninsk, RU

    2012-01-17

    The invention provides a method of chemical recovery of no-carrier-added radioactive tin (NCA radiotin) from intermetallide TiSb irradiated with accelerated charged particles. An irradiated sample of TiSb can be dissolved in acidic solutions. Antimony can be removed from the solution by extraction with dibutyl ether. Titanium in the form of peroxide can be separated from tin using chromatography on strong anion-exchange resin. In another embodiment NCA radiotin can be separated from iodide solution containing titanium by extraction with benzene, toluene or chloroform. NCA radiotin can be finally purified from the remaining antimony and other impurities using chromatography on silica gel. NCA tin-117m can be obtained from this process. NCA tin-117m can be used for labeling organic compounds and biological objects to be applied in medicine for imaging and therapy of various diseases.

  11. Automated chemoenzymatic synthesis of no-carrier-added [carbonyl-{sup 11}C]propionyl L-carnitine for pharmacokinetic studies

    Energy Technology Data Exchange (ETDEWEB)

    Davenport, R.J.; Pike, V.W.; Dowsett, K.; Turton, D.R.; Poole, K. [Hammersmith Hospital, London (United Kingdom). MRC Cyclotron Unit

    1997-07-30

    Propionyl-L-carnitine (PLC) is under development as a therapeutic for the treatment of peripheral artery disease, coronary heart disease and chronic heart failure. Three methods were examined for labelling PLC in its propionyl group with positron-emitting carbon-11 (t{sub 1/2} = 20.3 min), one chemical and two chemoenzymatic. The former was based on the preparation of [{sup 11}C]propionyl chloride as labelling agent via {sup 11}C-carboxylation of ethylmagnesium bromide with cyclotron-produced [{sup 11}C]carbon dioxide and subsequent chlorination. Reaction of carrier-added [{sup 11}C]propionyl chloride with L-carnitine in trifluoroacetic acid gave [{sup 11}C]PLC in 12% radiochemical yield (decay-corrected) from cyclotron-produced [{sup 11}C]carbon dioxide. However, the radiosynthesis was unsuccessful at the no-carrier added (NCA) level of specific radioactivity. [{sup 11}C]Propionate, as a radioactive precursor for chemoenzymatic routes, was prepared via carboxylation of ethylmagnesium bromide with [{sup 11}C]carbon dioxide and hydrolysis. NCA [{sup 11}C]PLC was prepared in 68 min in 14% radiochemical yield (decay-corrected) from [{sup 11}C]propionate via sequential conversions catalysed by acetate kinase, phosphotransacetylase and carnitine acetyltransferase. A superior chemoenzymatic synthesis of NCA [{sup 11}C]PLC was developed, based on the use of a novel supported Grignard reagent for the synthesis of [{sup 11}C]propionate and conversions by S-acetyl-CoA synthetase and carnitine acetyltransferase. This gave an overall radiochemical yield of 30-48% (decay-corrected). This synthesis was automated for radiation safety and provides pure NCA [{sup 11}C]PLC in high radioactivities ready for intravenous administration within 25 min from radionuclide production. The [{sup 11}C]PLC is suitable for pharmacokinetic studies in human subjects with PET and the elucidation of the fate of the propionyl group of PLC in vivo. (Author).

  12. Species dependent studies of no-carrier-added 93mMo: A green method

    International Nuclear Information System (INIS)

    Mandal, Swadesh; Nayak, Dalia

    2010-01-01

    The present paper reports a combination of radioanalytical and green methodology for the ultra-trace scale speciation of molybdenum. The differential attitude of iron-doped calcium alginate (Fe-CA) and chitosan biopolymers towards no-carrier-added 93m Mo radionuclide was studied to develop environmentally sustainable speciation methodology in ultra-trace scale. The affinity of 93m Mo towards the Fe-CA beads is greater than that of chitosan. Species information was obtained by comparing the adsorption profile of 93m Mo on Fe-CA and chitosan biopolymer with the software code CHEAQS PRO program. From the experimental results it is concluded that no-carrier-added 93m Mo radionuclide form mononuclear species instead of polynuclear species in aqueous solution. Use of biodegradable, non-toxic biopolymer makes this method a step forward towards green chemistry.

  13. Synthesis of 'no-carrier-added' sup(11)C-labelled nitrosoureas

    International Nuclear Information System (INIS)

    Diksic, M.; Farrokhzad, S.; Yamamoto, Y.L.; Feindel, W.

    1985-01-01

    Syntheses for sup(11)C-labelled chemotherapeutic drugs CCNU, BFNU and CFNU (analogs of BCNU) as well as an improved synthesis for sup(11)C-BCNU are described. The procedures for the separation of dual isomers in the case of sup(11)C-labelled CCNU and CFNU are discussed. The specific activity of these 'no-carrier-added' radiopharmaceuticals was approximately 10sup(4) lower than expected for a carrier-free product. The syntheses were normally finished 20-25 min after the end of the collection of sup(11)C-COClsub(2). Chemical and radiochemical purity of the final products as determined by HPLC and TLRC, respectively, was at least 98%. The syntheses yielded 10-25 mCi of nitrosourea ready for use in PET studies. (author)

  14. Production of no carrier added residue free /sup 22/Na

    Energy Technology Data Exchange (ETDEWEB)

    Britto, J L.Q. de; Bastos, M A.V.; Silva, R.F. da; Silva, A.G. da

    1988-05-02

    A method for the production of no carrier added and residue free /sup 22/Na, was developed via the /sup 24/Mg(d,..cap alpha..)/sup 22/Na nuclear reaction applying 14 MeV deuterons and a high current MG-Cu target. The yield for the reaction was measured and the chemical separation was performed using a Dowex 50WX8 resin in H/sup +/ form. The overall yield was higher than 98%. Residue could not be detected. All experiments were carried out at IEN's CV-28 cyclotron. (author) 13 refs.; 2 figs.

  15. Characterization and excitation behaviour studies of radionuclide (scandium) in glass matrix

    International Nuclear Information System (INIS)

    Rehana, Ishrat; Shahid, K.A.; Husain, S.; Muhammad, Din

    1999-01-01

    Directional movements of bed load in marine sediments are studied using a radioactive tracer, scandium, similar to the natural sediment in the area. Scandium glass prepared for this purpose was analyzed by atomic emission spectrography for quality assurance purposes. A buffer composed of graphite with 5% germanium oxide was used for accurate and reproducible analyses. The role of this buffer in the excitation behavior of scandium and variations in spectral line intensity with respect to various influencing parameters are reported. Volatilization of scandium was observed using the moving plate technique, with a dc-arc as the excitation source

  16. No-carrier-added labeling of the neuroprotective Ebselen with selenium-73 and selenium-75.

    Science.gov (United States)

    Helfer, Andreas; Ermert, Johannes; Humpert, Sven; Coenen, Heinz H

    2015-03-01

    Selenium-73 is a positron emitting non-standard radionuclide, which is suitable for positron emission tomography. A copper-catalyzed reaction allowed no-carrier-added labeling of the anti-inflammatory seleno-organic compound Ebselen with (73) Se and (75) Se under addition of sulfur carrier in a one-step reaction. The new authentically labeled radioselenium molecule is thus available for preclinical evaluation and positron emission tomography studies. Copyright © 2015 John Wiley & Sons, Ltd.

  17. An 131I iodotamoxifen: no carrier added iodination via a diazonium salt

    International Nuclear Information System (INIS)

    Hunter, D.H.; Strickland, L.A.

    1986-01-01

    An 131 I-labeled iodotamoxifen has been prepared by a ''no carrier added'' procedure in a 40% radiochemical yield via an aryl diazonium ion salt intermediate. Two approaches were used to produce high specific activity iodotamoxifen: nonaqueous solvents and copper catalysis. The use of the nonaqueous solvent acetonitrile has proved successful while neither copper powder, copper-bronze, copper(I)oxide nor Cu(II) sulphate showed any catalytic effects. (author)

  18. Synthesis of no-carrier-added L- and D-[1-11C]-DOPA

    International Nuclear Information System (INIS)

    Bolster, J.M.; Vaalburg, W.; Veen, W. van; Dijk, Th. van; Molen, H.D. van der; Wynberg, H.; Woldring, M.G.; Rijksuniversiteit Groningen

    1983-01-01

    No-carrier-added DL-[1- 11 C]-DOPA has been synthesized by carboxylation of an α-lithioisocyanide with a radiochemical yield of up to 15% without correction for decay. The total synthesis time is 30 min. The resolution of the D- and L-isomers was accomplished within 16 min by HPLC using a chiral stationary phase and a phosphate buffer of pH 4.5 as eluent. (author)

  19. Synthesis of no-carrier-added fluorine-18 2-fluoro-2-deoxy-d-glucose

    International Nuclear Information System (INIS)

    Tewson, T.J.

    1983-01-01

    A new synthetic procedure for the preparation of fluorine-18 2-fluoro-2-deoxy-glucose has been developed. This procedure offers the advantages of flexibility in the source of the fluorine-18, high yields, and short synthesis times. The procedure works at the no-carrier-added level and gives a product of very high specific activity

  20. Adsorption and desorption of hydrolyzed metal ions. 3. Scandium and chromium

    International Nuclear Information System (INIS)

    Gray, B.; Matijevic, E.; Clarkson Univ., Potsdam, NY

    1987-01-01

    Adsorption of scandium(III) and chromium(III) species on a PVC latex was measured using radioactive isotopes; the uptake increased with increasing pH. The data were interpreted by combining aspects of the models of James and Healy and also of Anderson and Bockris. The experimental and calculated results agree quite well for scandium, but not for chromium. The deviation in the latter case is believed to be due to polymerization of the hydrolyzed chromium cations and to the interaction of chromium with the anionic surface groups of the latex. Neither of these interactions occur with scandium. Hydrolyzed scandium species adsorbed on the latex were removed by acidifying the dispersion, while chromium complexes were not, substantiating the proposed difference in the chemical nature of chromium and scandium species at the solid/solution interface. 32 refs.; 8 figs.; 8 tabs

  1. The synthesis of no-carrier-added DL-4-[18F]fluorodeprenyl via the nucleophilic aromatic substitution reaction

    International Nuclear Information System (INIS)

    Plenevaux, Alain; Guillaume, Marcel

    1991-01-01

    No-carrier-added DL-α-methyl-β-4-[ 18 F]fluorophenyl-N-methyl-N-propynylethylamine (DL-4-[ 18 F]fluorodeprenyl) was synthesized via a 3-step procedure. The overall yield was 11%, the synthesis time was 90 min and the specific activity >0.57 Ci/μmol (end of synthesis). This synthesis approach, the conversion of an aromatic aldehyde to a homologous methyl ketone, extends the flexibility of the nucleophilic aromatic substitution reaction by applying it to the synthesis of radiotracers which do not bear electron-withdrawing activating groups on the aromatic ring. The tissue distribution of DL-4-[ 18 F]fluorodeprenyl in mice at 1, 10 and 50 min was also measured and showed that metabolic defluorination was not significant. Clearance or radioactivity from brain after injection of DL-4-[ 18 F]fluorodeprenyl was more rapid than that previously observed for [ 11 C]L-deprenyl. (author)

  2. Bottom sediment transport study at Haiphong port using radioactive scandium as tracer

    International Nuclear Information System (INIS)

    Pham Ngoc Chuong; Phan Son Hai; Pham Duy Hien

    1993-01-01

    A radioisotope tracer experiment was performed for investigating the bedload movement at the site near the access channel to Haiphong port, North Vietnam. The scandium glass and a number of mechanical devices were manufactured locally for the experiment. Simple and safe procedures were adopted for the production, transportation and injection of radioactive tracer materials. Five tracking experiments were carried out covering the period of 84 days in winter 1992-1993. The experimental results provide a firm basis for elaborating appropriate measures against the siltation problem at Haiphong port, especially for the design of a new access channel with a better orientation with respect to the directions of the water flow and bedload transport, as proposed recently by the Port Authority. (Author). 2 refs, 4 figs

  3. Synthesis of 'no-carrier-added' sup(11)C-labelled nitrosoureas

    Energy Technology Data Exchange (ETDEWEB)

    Diksic, M.; Farrokhzad, S.; Yamamoto, Y.L.; Feindel, W. (Montreal Neurological Inst., Quebec (Canada))

    1985-03-01

    Syntheses for sup(11)C-labelled chemotherapeutic drugs CCNU, BFNU and CFNU (analogs of BCNU) as well as an improved synthesis for sup(11)C-BCNU are described. The procedures for the separation of dual isomers in the case of sup(11)C-labelled CCNU and CFNU are discussed. The specific activity of these 'no-carrier-added' radiopharmaceuticals was approximately 10sup(4) lower than expected for a carrier-free product. The syntheses were normally finished 20-25 min after the end of the collection of sup(11)C-COClsub(2). Chemical and radiochemical purity of the final products as determined by HPLC and TLRC, respectively, was at least 98%. The syntheses yielded 10-25 mCi of nitrosourea ready for use in PET studies.

  4. Production of no-carrier-added {sup 123}I via heavy-ion activation of natural antimony oxide

    Energy Technology Data Exchange (ETDEWEB)

    Maji, S. [The Univ. of Burdwan (India). Dept. of Chemistry; Lahiri, S. [Saha Institute of Nuclear Physics, Kolkata (India). Chemical Sciences Div.

    2007-07-01

    Activation of natural Sb{sub 2}O{sub 3} with 48 MeV {sup 7}Li{sup 3+} beam results in the formation of no-carrier-added {sup 123}I in the matrix along with the radionuclides {sup 123,125}Xe and {sup 122}Sb. The {sup 123}I yield amounts to about 400 kBq/{mu}Ah and the radionuclidic impurity of {sup 124}I to {proportional_to}1.2% of {sup 123}I. Attempts to separate no-carrier-added iodine from bulk antimony target involved liquid-liquid extraction with TOA and HDEHP as well as precipitation of Sb{sub 2}S{sub 3} with thioacetamide. The precipitation technique was found to be the most effective for quantitative separation of {sup 123}I from the bulk antimony oxide target. (orig.)

  5. Solvent extraction of no-carrier-added 103Pd from irradiated rhodium target with α-furyldioxime

    International Nuclear Information System (INIS)

    Mahdi Sadeghi; Behrouz Shirazi; Nami Shadanpour

    2006-01-01

    Solvent extraction of no-carrier-added 103 Pd was investigated from irradiated rhodium target with a-furyldioxime in chloroform from diluted hydrochloric acid. Extraction yield was 85.3% for a single extraction from 0.37M HCl and 103 Pd purity was better than 99%. (author)

  6. Low temperature heat capacity of scandium and alloys of scandium

    Energy Technology Data Exchange (ETDEWEB)

    Tsang, T. W.E.

    1977-12-01

    The heat capacity of three electrotransport purified scandium samples has been measured from 1 to 20/sup 0/K. The resultant electronic specific heat constant and Debye temperature are 10.337 +- 0.015 mJ/gm-atom K/sup 2/ and 346.7 +- 0.8/sup 0/K respectively, and these values are believed to be truly representative of intrinsic scandium. Alloying studies have also been carried out to investigate the band structure of scandium based on the rigid band model, with zirconium to raise the electron concentration and magnesium to lower it. The results are then compared to the theoretical band structure calculations. Low temperature heat capacity measurements have also been made on some dilute Sc-Fe alloys. An anomaly is observed in the C/T vs. T/sup 2/ plot, but the C vs. T curve shows no evidence of magnetic ordering down to 1/sup 0/K, and electrical resistance measurement from 4 to 0.3/sup 0/K also indicates that no magnetic ordering took place.

  7. Preparation and in vitro evaluation of ''no-carrier-added'' 18F-labeled biotin

    International Nuclear Information System (INIS)

    Najafi, A.; Peterson, A.

    1993-01-01

    This paper will describe the preparation of ''no-carrieradded'' 18 F-labeled biotin where the radiolabel bound to an aromatic moiety is described. This has been accomplished by preparation of [ 18 F]fluoro-benzylbromide (yield 20-30%) and its reaction with biotin-LC-hydrazide. This yielded ''no-carrier-added'' radiolabeled biotin (5-10%) which was then purified by reversed phase HPLC. The pure product was found to bind to avidin, thereby demonstrating retention of its biological integrity. Thus this product is potentially useful for imaging tumor tissue following injection of avidin coupled MoAbs. (author)

  8. Synthesis of no-carrier-added radiobrominated n-alkylated analogues of spiperone

    International Nuclear Information System (INIS)

    Moerlein, S.M.; Laufer, P.; Stoecklin, G.

    1985-01-01

    The synthesis of a series of p-bromo-3-N-alkyl spiperone analogues is described. N-alkylation was achieved via reaction of the potassium salt of the spiperone lactam ring with alkyl iodide; subsequent reactions with elemental bromine gave the p-brominated isomers. Optimization studies using no-carrier-added (n.c.a.) 77 Br - indicated that radio-bromination of N-alkyl spiperone analogues occurs with higher yields and in shorter reaction times when dichloramine-T (DCT) is used rather than H 2 0 2 /acetic acid as an oxidant. The production of the title compounds in high effective specific activity with radiochemical yields of 20-30 % using n.c.a. 77 Br - and DCT is reported. (author)

  9. Separation of no-carrier-added 107,109Cd from proton induced silver target. Classical chemistry still relevant

    International Nuclear Information System (INIS)

    Moumita Maiti; Susanta Lahiri; Tomar, B.S.

    2011-01-01

    The classical chemistry like precipitation technique is relevant even in modern days trans-disciplinary research from the view point of green chemistry. A definite demand of no-carrier-added (nca) cadmium tracers, namely, 107,109 Cd, has been realized for diverse applications. Development of efficient separation technique is therefore important to address the purity of the tracers for various applications. No-carrier-added 107,109 Cd radionuclides were produced by bombarding natural silver target matrix with 13 MeV protons, which gave ∼15 MBq/μA h yield for nca 107 Cd. The nca cadmium radionuclides were separated from the natural silver target matrix by precipitating Ag as AgCl. The developed method is an example wherein green chemistry is used in trans-disciplinary research. The method is also simple, fast, cost effective and environmentally benign. (author)

  10. Development of carrier usage for the treatment of radioactive effluent

    International Nuclear Information System (INIS)

    Kahraman, A.

    1997-01-01

    Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of 137 Cs makes about 3·10 -10 g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of 137 Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs

  11. Ion exchange purification of scandium

    Science.gov (United States)

    Herchenroeder, Laurie A.; Burkholder, Harvey R.

    1990-10-23

    An improvement in purification of scandium through ion exchange chromatography is disclosed in which the oxidation potential of the eluting solution is altered by the addition of potassium chlorate or ammonium chloride so that removal of contaminants is encouraged. The temperature, pH and concentration of the eluent HEDTA are controlled in order to maintain the scandium in the column while minimizing dilution of the scandium band. Recovery of scandium is improved by pumping dilute scandium over the column prior to stripping the scandium and precipitation. This eliminates the HEDTA ion and other monovalent cations contaminating the scandium band. This method maximizes recovery of scandium while maintaining purity.

  12. New syntheses of No-carrier-added 123I-labeled agents via organoborane chemistry

    International Nuclear Information System (INIS)

    Kabalka, G.W.

    1985-01-01

    No-carrier-added 123 I-labeled agents are readily prepared via the reaction of organoboranes with sodium iodide- 123 I in the presence of mild oxidizing agents. The reactions are rapid and regiospecific, and they produce excellent yields of the labeled products. The organoboranes are readily prepared from alkenes and alkynes via the hydroboration reaction. A wide variety of functional groups are tolerated by the hydroboration-iodination sequence. The sequence has been utilized to prepare 123 I-labeled steroids and fatty acids, as well as a number of labeled esters, and aromatic derivatives

  13. Development of carrier usage for the treatment of radioactive effluent

    Energy Technology Data Exchange (ETDEWEB)

    Kahraman, A [Cekmece Nuclear Research and Training Center, Istanbul (Turkey)

    1997-02-01

    Low level radioactive liquid wastes are produced in many nuclear applications. Their physico-chemical characteristics may very considerably. Chemical precipitation is a convenient treatment method for the liquid streams of high salinity or solid content containing different radionuclide types. Generally, the concentrations of nuclides in liquid wastes are extremely low. For example, 1000 Bq of {sup 137}Cs makes about 3{center_dot}10{sup -10} g of caesium. Therefore conventional precipitation cannot be applied since the solubility product value is not exceeded. The carriers which are capable to adsorb the nuclides are used to achieve the nuclide removal. Stable isotopes of the nuclide are usually added as the carriers but any reagent which has similar chemical specifications with the nuclide can also be used as the carrier. Precipitation of these non-radioactive carriers ion together with the radionuclide is called co-precipitation. The operational steps of the chemical precipitation process should be established and applied in a treatment facility. Thus, the most suitable carrier for a particular nuclide and its usage conditions are required to be determined. In this study, the carriers for removal of {sup 137}Cs and uranium, their accurate amounts and usage conditions to achieve highest decontamination factors (DF) have been investigated. Residual sludge volumes were evaluated for cementation purposes. The cement composite samples were prepared for each set of experiments and hardening times were measured. 9 refs, 9 figs.

  14. On safety of radioactive waste carrier

    International Nuclear Information System (INIS)

    Kondo, Toshikazu

    1995-01-01

    The waste generated by reprocessing the spent fuel from Japanese nuclear power stations in France and U.K. is to be returned to Japan. The first return transport was carried out from February to April when the waste management facility in Rokkasho, Aomori Prefecture, was completed. Most of this return transport was the sea transport using the exclusively used carrier, Pacific Pintail, from Cherbourg, France, to Mutsu Ogawara, Japan. Ministry of Transport carried out the examination on the safety of this method of transport including the safety of the carrier based on the rule for the sea transport and storage of dangerous substances. The international rule on the sea transport of high level radioactive waste, the course of adopting the INF code and its outline, and the Japanese safety standard for the carriers exclusively used for high level radioactive waste are explained. The Pacific Pintail is the ship of 5087 GT, which was built in 1987 as the carrier exclusively used for radioactive substances, owned by Pacific Nuclear Transport Ltd. of U.K. The main features related to the safety of the Pacific Pintail are explained, and the sufficient countermeasures are taken. (K.I.)

  15. Cu(I) assisted radioiodination of hippuran with no carrier added 131I

    International Nuclear Information System (INIS)

    Al-Kolaly, M.T.; El-Bayoumy, S.; Raieh, M.; El-Mothy, A.

    1993-01-01

    A study on the labeling of hippuran with no-carrier-added 131 I assisted by Cu(I) and excess of ascorbic acids is described. The role of ascorbic acid is to prevent the oxidation of Cu(I) to Cu(II) which activates the hydrolysis of o-iodohippuric acid to o-iodobenzoic acid. The use of Cu(I) allows an almost quantitative (97-99%) labeling yield to be obtained within 10-15 minutes at 100 deg C. The reaction is assumed to take place via the formation of an organocopper complex favoring the exchange reaction between radioiodine and inactive iodine in the hippuran molecule. The activation energy of the reaction was calculated to be E = 12.2 kcal/mol. (author) 21 refs.; 8 figs

  16. A basic evaluated neutronic data file for elemental scandium

    International Nuclear Information System (INIS)

    Smith, A.B.; Meadows, J.W.; Howerton, R.J.

    1992-01-01

    This report documents an evaluated neutronic data file for elemental scandium, presented in the ENDF/B-VI format. This file should provide basic nuclear data essential for neutronic calculations involving elemental scandium. No equivalent file was previously available

  17. Cu(I) assisted radioiodination of hippuran with no carrier added [sup 131]I

    Energy Technology Data Exchange (ETDEWEB)

    Al-Kolaly, M T; El-Bayoumy, S; Raieh, M; El-Mothy, A [Atomic Energy Authority, Cairo (Egypt). Dept. of Radioisotope Production and Labelled Compounds

    1993-11-01

    A study on the labeling of hippuran with no-carrier-added [sup 131]I assisted by Cu(I) and excess of ascorbic acids is described. The role of ascorbic acid is to prevent the oxidation of Cu(I) to Cu(II) which activates the hydrolysis of o-iodohippuric acid to o-iodobenzoic acid. The use of Cu(I) allows an almost quantitative (97-99%) labeling yield to be obtained within 10-15 minutes at 100 deg C. The reaction is assumed to take place via the formation of an organocopper complex favoring the exchange reaction between radioiodine and inactive iodine in the hippuran molecule. The activation energy of the reaction was calculated to be E = 12.2 kcal/mol. (author) 21 refs.; 8 figs.

  18. The synthesis of no-carrier-added [11C]urea from [11C]carbon dioxide and application to [11C]uracil synthesis

    International Nuclear Information System (INIS)

    Chakraborty, P.K.; Mangner, T.J.; Chugani, H.T.

    1997-01-01

    No-carrier-added [ 11 C]urea has been synthesized by bubbling cyclotron-produced [ 11 C]-carbon dioxide directly into a tetrahydrofuran solution of lithium bis(trimethylsilyl)amide, followed by hydrolysis of the C-11 labeled adduct with aqueous ammonium chloride. Using this simple, one-pot method, [ 11 C]urea was produced in 55-70% radiochemical yield (decay-corrected) in 16 min following end-of-bombardment (or in 10 min following the introduction of the [ 11 C]carbon dioxide. The [ 11 C]urea thus produced was converted to [ 11 C]uracil (carrier-added) in 40-75% decay-corrected radiochemical yield by condensation with diethyl malate in presence of fuming sulfuric acid. (author)

  19. Production of no-carrier-added 64Cu from zinc metal irradiated under boron shielding.

    Science.gov (United States)

    Zinn, K R; Chaudhuri, T R; Cheng, T P; Morris, J S; Meyer, W A

    1994-02-01

    Positron emission tomography offers advantages for radioimmunodiagnosis of cancer but requires radionuclides of appropriate half-life that have high specific activity and high radio-purity. This work was designed to develop a viable method to produce and purify 64Cu, which has high specific activity, for positron emission tomography. 64Cu was produced at the University of Missouri Research Reactor by the nuclear reaction, 64Zn(n,p)64Cu. Highly pure zinc metal (99.9999%) was irradiated in a specially designed boron nitrite lined container, which minimized thermal neutron reactions during irradiation. A new two-step procedure was developed to chemically separate the no-carrier-added 64Cu from the zinc metal target. 64Cu recovery for 24 runs averaged 0.393 (+/- 0.007) mCi per milligram of zinc irradiated. The boron-lined irradiation container reduced unwanted zinc radionuclides 14.3-fold. Zinc radionuclides and non-radioactive zinc were separated successfully from the 64Cu. The new separation technique was fast (2 hours total time) and highly efficient for removing the zinc. The zinc separation factor for this technique averaged 8.5 x 10(-8), indicating less than 0.0000085% of the zinc remained after separation. Thus far, the highest 64Cu specific activity at end of irradiation was 683 Ci/mg Cu, with an average of 512 Ci/mg Cu for the last six analyzed runs. The boron-lined irradiation container has sufficient capacity for 75-fold larger-sized zinc targets (up to 45 g). The new separation technique was excellent for separating 64Cu, which appears to be a radionuclide with great potential for positron emission tomography.

  20. Complexation study on no-carrier-added astatine with insulin: A candidate radiopharmaceutical

    Energy Technology Data Exchange (ETDEWEB)

    Lahiri, Susanta [Chemical Sciences Division, Saha Institute of Nuclear Physics, 1/AF Bidhannagar, Kolkata 700 064 (India)], E-mail: susanta.lahiri@saha.ac.in; Roy, Kamalika [Chemical Sciences Division, Saha Institute of Nuclear Physics, 1/AF Bidhannagar, Kolkata 700 064 (India); Sen, Souvik [Berhampur Sadar Hospital, Berhampur, Murshidabad 742 101 (India)

    2008-12-15

    No-carrier-added astatine radionuclides produced in the {sup 7}Li-irradiated lead matrix were separated from bulk lead nitrate target by complexing At with insulin, followed by dialysis. The method offers simultaneous separation of At from lead as well as its complexation with insulin. The At-insulin complex might be a potential radiopharmaceutical in the treatment of hepatocellular carcinoma. The stability of At-insulin complex was checked by dialysis against deionized water and Ringer lactate (RL) solution. It has been found that the half-life of At-insulin complex is about {approx}12 h, when dialyzed against deionized water and is only 6 h, when dialyzed against RL solution having the same composition as blood serum. The 6 h half-life of this Insulin-At complex is perfect for killing cancer cells from external cell surfaces as the half-life of internalization of insulin molecule inside the cell is 7-12 h.

  1. Complexation study on no-carrier-added astatine with insulin: A candidate radiopharmaceutical

    International Nuclear Information System (INIS)

    Lahiri, Susanta; Roy, Kamalika; Sen, Souvik

    2008-01-01

    No-carrier-added astatine radionuclides produced in the 7 Li-irradiated lead matrix were separated from bulk lead nitrate target by complexing At with insulin, followed by dialysis. The method offers simultaneous separation of At from lead as well as its complexation with insulin. The At-insulin complex might be a potential radiopharmaceutical in the treatment of hepatocellular carcinoma. The stability of At-insulin complex was checked by dialysis against deionized water and Ringer lactate (RL) solution. It has been found that the half-life of At-insulin complex is about ∼12 h, when dialyzed against deionized water and is only 6 h, when dialyzed against RL solution having the same composition as blood serum. The 6 h half-life of this Insulin-At complex is perfect for killing cancer cells from external cell surfaces as the half-life of internalization of insulin molecule inside the cell is 7-12 h

  2. Use of liquid chromatography for separation and determination of carrier species associated with the synthesis of no carrier-added sup(11)C labelled compounds

    International Nuclear Information System (INIS)

    Emran, Ali M.; Boothe, Th.E.; Finn, R.D.; Vora, M.M.; Kothari, P.J.

    1985-01-01

    An analytical technique using reversed-phase liquid chromatography was developed for the determination of urea at quantities as low as 1 ng to quantitate the amount of non-labelled urea produced during the synthesis of no-carrier-added [sup(11)C] urea starting from sup(11)CNsup(-). As a result, the specific activity of the [sup(11)C] urea thus prepared was calculated to be as high as 3.5+-0.8 Ci/μmol. (author)

  3. Analysis of separation quality of scandium-46 and titanium using silica gel column

    International Nuclear Information System (INIS)

    Muhamad Basit Febrian; Yanuar Setiadi; Duyeh Setiawan; Titin Sri Mulyati; Nana Suherman

    2015-01-01

    In this study, quality test of scandium and titanium mixture separation system using a silica gel column has been conducted. This system will be used in the separation of medical radioisotopes of 47 Sc from TiO 2 enriched targets. 20 mg of TiO 2 and 5 mg of Sc 2 O 3 dissolved using 0.5 mL of 50% HF solvent with gentle heating at 60°C - 80°C for 1 hour then 4.5 mL H 2 O was added. Sc and Ti mixture is separated by passing it through a column of silica gel. In the determination of scandium released from silica gel, Sc-46 radiotracer was used. Only 51.60 ± 4.5% of 5 mg of scandium could be retained in the silica gel column. From 51.60% of absorbed scandium in the column, 98.29 ± 3.4% were eluted with 5 mL of H 2 O eluent. During elution of scandium from silica gel column, 2.81 grams of 20 mg of titanium came apart as breakthrough. In determination of recovery of titanium from silica gel, 51.76 ± 5.5% of the 20 mg Ti can be recovered from silica gel column using 5M HCl eluent, whereas remaining Ti were eluted using 40 ml of HCl 5M. Based on those result, it can be concluded that there are still titanium portion in scandium after the separation using a silica gel column. Further purification step using fresh silica gel column, can separate escaped titanium from scandium. (author)

  4. Automated production of no carrier added holmium-166

    International Nuclear Information System (INIS)

    Izard, M.E.; Dadchova, E.

    1996-01-01

    Full text: An automated system has been developed to produce no carrier added 166 Ho from the decay of 166 Dy produced by neutron activation of 164 Dy 2 O 3 . Targets consisting of 5-10 mg of 164 Dy 2 O 3 are irradiated in HIFAR at 5 x 10 13 n.s -1 .cm -2 for 12h then allowed to cool for 2 days. The irradiation can is then transferred to the automated system located in a 'hot' cell in the radiopharmaceutical research building. A two dimension robotic arm encompassing a grab and motorized screwdriver is used to open the irradiation can. A second arm carrying a teflon tube introduces 9M HCI into the can to dissolve the target. A second tube carries the dissolved target via a peristaltic pump to a heated vial where it is evaporated to dryness under a flow of N 2 . A Peltier cooled trap is used to prevent release of HCl fumes into the cell. A motorized syringe pump dispenses 1 mL of 0.1 M HNO 3 to redissolve the digest which is then transferred by peristaltic pump via a hollow fibre filter and auto injector into an Aminex- A5 HPLC column. 166 Dy is eluted from the column in 0.132 M α-HIBA into a heated cyclone flask and evaporated to dryness under a stream of N 2 heated to about 50 deg C. After two days the evaporated Dy/ 166 Ho digest is dissolved in another 1 mL of 0.1 M HNO 3 and injected onto the HPLC column. 166 Ho is collected in 20-25 mL of α-HIBA and evaporated to dryness as before at about 400 C to ensure complete decomposition of the α-HIBA. The product is finally dissolved in about I mL of 0.1 M HCI and pumped through a 0.22 μM filter to a product vial

  5. Studies on low-carrier radiofluorination of non-active aromatics with no-carrier-added [{sup 18}F]fluoride; Untersuchungen zur traegerarmen Radiofluorierung nicht-aktiver Aromaten mit n.c.a. [{sup 18}F]Fluorid

    Energy Technology Data Exchange (ETDEWEB)

    Cardinale, Jens

    2013-01-15

    In vivo imaging with positron emission tomography generally demands radiotracers with a high specific activity. In case of fluorine-18 the required no-carrier-added (n.c.a.) starting material is only available in form of fluoride. This and the short half-life of 109.7 minutes of the radionuclide lead to the demand of special methods for radiosyntheses. The only practical procedure for manufacturing n.c.a. [{sup 18}F]fluoro-compounds is therefore nucleophilic substitution. There is, however, still a lack of effective procedures for the labelling of electron rich aromatic molecules starting from n.c.a. [{sup 18}F]fluoride. A process for n.c.a. radiofluorination of these compounds is offered by the reaction of iodonium compounds as starting materials. In this study modern procedures for the synthesis of iodoniumsalts and -ylides were investigated. Several precursor molecules for the versatile synthetic building block 4-[{sup 18}F]fluoroiodobenzene were synthesised. In this course, a new one-pot procedure for the synthesis of iodoniumylides was developed. Further on, the syntheses of suitable iodonium precursors for two fluorophenoxy-derivatives, which are possible antidepressants, were investigated. Due to their binding profile these compounds can be considered as ligands for the serotonin reuptake transporter (SERT) and the norepinephrin reuptake transporter (NET), respectively. The preparation of appropriate iodonium salts proved to be too problematic, while the synthesis of suitable iodoniumylides could be accomplished with satisfactory yields of about 30% and 40 %, respectively. Both compounds were labelled with n.c.a. [{sup 18}F]fluoride and deprotected to the desired target compounds 4-((3-[{sup 18}F]fluorophenoxy)(phenyl)methyl)piperidine and 4-((4-[{sup 18}F]fluorophenoxy)(phenyl)methyl)piperidine in radiochemical yields of about 40 % and 25 %, respectively. Those are now available for preclinical evaluation studies. Furthermore, a process for the palladium

  6. Stability constants of scandium complexes, 1

    International Nuclear Information System (INIS)

    Itoh, Hisako; Itoh, Naomi; Suzuki, Yasuo

    1984-01-01

    The stability constants of scandium complexes with some carboxylate ligands were determined potentiometrically at 25.0 and 40.0 0 C and at an ionic strength of 0.10 with potassium nitrate as supporting electrolyte. The constants of the scandium complexes were appreciably greater than those of the corresponding lanthanoid complexes, as expected. The changes in free energy, enthalpy, and entropy for the formation of the scandium complexes were calculated from the stability constants at two temperatures. (author)

  7. Pilot-scale recovery of rare earths and scandium from phosphogypsum and uranium leachates

    Directory of Open Access Journals (Sweden)

    Mashkovtsev Maxim

    2016-01-01

    Full Text Available Ural Federal University (UrFU and VTT have performed joint research on development of industrial technologies for the extraction of REM and Scandium compounds from phosphogypsum and Uranium ISL leachate solutions. Leaching-absorption experiments at UrFU have been supported with multicomponent solution modelling by VTT. The simulations have been performed with VTT’s ChemSheet/Balas program and can be used for speciation calculations in the lixiviant solution. The experimental work combines solvent extraction with advanced ion exchange methodology in a pilot facility capable of treating 5 m3 solution per hour. Currently, the plant produces cerium carbonate, lanthanum oxide, neodymium oxide and concentrate of heavy rare earth metals. A batch of 45 t solids has been processed with the gain of 100 kg’s of REM concentrate. A mini-pilot plant with productivity above 50 liters per hour has been applied to recover scandium oxide and REE concentrates from the uranium ISL solution. As the preliminary product contains radioactivity (mainly strontium, an additional decontamination and cleaning of both concentrates by extraction has rendered a necessity. Finally a purified 99% concentrate of scandium oxide as well as 99% rare earth concentrate are received.

  8. Conversion of no-carrier-added [11C]carbon dioxide to [11C]carbon monoxide on molybdenum for the synthesis of 11C-labelled aromatic ketones

    International Nuclear Information System (INIS)

    Zeisler, S.K.; Nader, M.; Theobald, A.; Oberdorfer, F.

    1997-01-01

    A new method for the efficient conversion of no-carrier-added [ 11 C]carbon dioxide into [ 11 C]carbon monoxide is described. [ 11 C]Carbon dioxide produced by proton bombardment of ultra high purity nitrogen is pre-concentrated in a cryo trap and then passed through a quartz tube filled with a mesh of thin molybdenum wire heated to 850 o C. [ 11 C]Carbon dioxide readily reacts with molybdenum to form [ 11 C]carbon monoxide and molybdenum(IV) oxide. The latter also reduces carbon dioxide to carbon monoxide and helps improve the performance of the converter. [ 11 C]Carbon monoxide is purified from remaining [ 11 C]carbon dioxide and collected in a small silica trap from which it is eluted into a reaction mixture for the palladium-mediated synthesis of a 11 C-labelled aromatic ketone. Radiochemical yields of up to 81% (decay-corrected) for [ 11 C]carbon monoxide were obtained. Radiochemical purity and specific radioactivity of both [ 11 C]carbon monoxide and the 11 C-labelled ketone are sufficient for nuclear medical studies with PET. (Author)

  9. 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)

  10. Scandium, yttrium and the lanthanide metals

    International Nuclear Information System (INIS)

    Brown, Paul L.; Ekberg, Christian

    2016-01-01

    The hydroxide and oxide phases that exist for scandium(III) include scandium hydroxide, which likely has both amorphous and crystalline forms, ScOOH(s), and scandium oxide. This chapter presents the data selected for the stability constants of the polymeric hydrolysis species of scandium at zero ionic strength. The behaviour of yttrium, and the lanthanide metals, in the environment is largely dependent on their solution equilibria. Hydrolysis and other complexation reactions of yttrium and the lanthanide metals are important in the disposal of nuclear waste. The trivalent lanthanide metals include lanthanum(III) through lutetium(III). A number of studies have reported a tetrad effect for the geochemical behaviour of the lanthanide series, including stability constants and distribution coefficients. The solubility of many of the lanthanide hydroxide phases has been studied at fixed ionic strength. In studying the hydrolysis of cerium(IV), a number of studies have utilised oxidation-reduction reactions in determining the relevant stability constants.

  11. Scandium, yttrium and the lanthanides

    International Nuclear Information System (INIS)

    Hart, F.A.

    1987-01-01

    This chapter on the chemistry of the coordination complexes of scandium, yttrium and the lanthanides includes sections on the nitrogen and oxygen donor ligands and complex halides of scandium, and the phosphorus and sulfur donor ligands of yttrium and the lanthanides. Complexes with the macrocylic ligands and with halides are also discussed. Sections on the NMR and electronic spectra of the lanthanides are also included. (UK)

  12. Extraction of scandium by organic substance melts

    International Nuclear Information System (INIS)

    Gladyshev, V.P.; Lobanov, F.I.; Zebreva, A.I.; Andreeva, N.N.; Manuilova, O.A.; Il'yukevich, Yu.A.

    1984-01-01

    Regularities of scandium extraction by the melts of octadecanicoic acid, n-carbonic acids of C 17 -C 20 commerical fraction and mixtures of tributylphosphate (TBP) with paraffin at (70+-1) deg C have been studied. The optimum conditions for scandium extraction in the melt of organic substances are determined. A scheme of the extraction by the melts of higher carbonic acids at ninitial metal concentrations of 10 -5 to 10 -3 mol/l has been suggested. The scandium compound has been isolated in solid form, its composition having been determined. The main advantages of extraction by melts are as follows: a possibility to attain high distribution coefficients, distinct separation of phases after extraction, the absence of emulsions, elimination of employing inflammable and toxic solvents, a possibility of rapid X-ray fluorescence determinatinon of scandium directly in solid extract

  13. Alternative labelling of the cocaine analogue isomers α-CIT and β-CIT by direct iodination with no-carrier-added Na125I

    International Nuclear Information System (INIS)

    Mueller, L.; Foged, C.; Halldin, C.; Swahn, C.-G.

    1994-01-01

    An alternative labelling of the cocaine analogue isomers α-CIT and β-CIT with no-carrier-added 125 I by direct iodination of 2α- and 2β-carbomethoxy-3β-phenyltropane with Na 125 I/sulfuric acid/nitric acid/acetic acid and peracetic acid under different reaction conditions, is described. The maximum radiolabelling yield obtained with the two isomers was 48% for [ 125 I]α-CIT and 28% for [ 125 I]β-CIT. (author)

  14. Poisoning of liquid membrane carriers in extraction of metal ions

    International Nuclear Information System (INIS)

    Wang, Yuchun; Wang, Dexian

    1992-01-01

    As means of effective separation and preconcentration, emulsion liquid membranes (ELMs) have found application in many fields including biochemical separation, wastewater treatment, hydrometallurgy, and preconcentration in analytical chemistry. In the extraction of desired metal (scandium, mixed rare earths) ions using chelating extractants (TTA, HDEHP) as liquid membrane carriers, the carriers will become poisoned owing to the presence of even minute quantity of certain high ionic potential ions in the feed solution. The reason for the poisoning of carriers is that those ions have so much greater affinity than the desired ions for the membrane carrier that the ion-carrier coordination compound cannot be stripped at the interior interface of the membrane and gradually no more free carrier transports any metal ions across the membrane. The calculated results are in agreement with the experiments, and methods to avoid the poisoning are given in the paper

  15. Application of scandium oxide in an electron emission material

    International Nuclear Information System (INIS)

    Suqiu, Y.; Zhizheng, Z.; Yongde, W.

    1985-01-01

    Modern microwave devices impose a number of harsh requirements on the cathodes. For instance, they require cathodes having low working temperature, high emissive current density, slow evaporation rate of the emissive-active material, long lifetime, quick heating and so on. The commercial B-cathode is no longer able to meet these requirements completely. A scandate cathode may be a promising one for use in these devices. Adding rare-earth elements in the electron emission material has been reported in many papers. Based on a B-cathode we add a little amount of scandium oxide (about 3%) into emission material to manufacture a scandate cathode. The emission property of such a cathode has been improved greatly. If the composition is controlled correctly, the emission level of such a cathode may be five times more as high as the B-cathode

  16. Synthesis and properties of scandium ortho-phosphate

    International Nuclear Information System (INIS)

    Eshchenko, L.S.; Pechkovskij, V.V.; Dvoskina, R.N.

    1979-01-01

    With the aim to elucidate the influence of synthesis conditions on the chemical composition and properties of orthophosphates of scandium, the interaction of orthophosphoric acid and scandium-containing component (oxide or salt) was studied under various conditions. In the interaction of scandium salt, phosphoric acid and ammonia at room temperature and pH 3.0; 5.0; 7.0 and 9.0 amorphous scandium phosphates have been obtained with the composition of x Sc 2 O 3 xY P 2 O 5 xz NH 3 xn H 2 O. After prolonged staying in mother liquor, roentgenoamorphous precipitates of phosphates transform into the crystalline state. The dependences are studied of the specific surface of amorphous phosphates on pH of precipitation and temperature of the heat treatment (200-800 deg C). Precipitates obtained in a neutral medium at 400 deg C temperature of thermal treatment, show a maximum specific surface. At a temperature of 820-840 deg C the crystallization of amorphous phase occurs followed by the recrystallization and formation of anhydrous SePO 4 of zircon type

  17. In situ observation of the reaction of scandium and carbon by neutron diffraction

    Energy Technology Data Exchange (ETDEWEB)

    Juarez-Arellano, Erick A., E-mail: eajuarez@unpa.edu.m [Institut fuer Geowissenschaften, Universitaet Frankfurt, Altenhoeferallee 1, 60438 Frankfurt a.M. (Germany); Universidad del Papaloapan, Circuito Central 200, Parque Industrial, Tuxtepec 68301 (Mexico); Winkler, Bjorn [Institut fuer Geowissenschaften, Universitaet Frankfurt, Altenhoeferallee 1, 60438 Frankfurt a.M. (Germany); Vogel, Sven C. [Los Alamos National Laboratory, Lujan Center. Mail Stop H805, Los Alamos, NM 87545 (United States); Senyshyn, Anatoliy [Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), Technische Universitaet Muenchen, Lichtenbergstr. 1, D-85747 Garching (Germany); Materialwissenschaft, TU Darmstadt, Petersensstr. 23, D-64287 Darmstadt (Germany); Kammler, Daniel R. [Sandia National Laboratories, Albuquerque, NM 87185 (United States); Avalos-Borja, Miguel [CNyN, UNAM, A. Postal 2681, Ensenada, B.C. (Mexico)

    2011-01-05

    Research highlights: {yields} Exist two ScC cubic phases with B1-structure type differing in site occupancy of C. {yields} A new orthorhombic scandium carbide phase is formed at 1473(50) K. {yields} The recrystallization of alpha-Sc occurs between 1000 and 1223 K. - Abstract: The formation of scandium carbides by reaction of the elements has been investigated by in situ neutron diffraction up to 1823 K. On heating, the recrystallization of {alpha}-Sc occurs between 1000 and 1223 K. The formation of Sc{sub 2}C and ScC (NaCl-B1 type structure) phases has been detected at 1323 and 1373 K, respectively. The formation of a new orthorhombic scandium carbide phase was observed at 1473(50) K. Once the scandium carbides are formed they are stable upon heating or cooling. No other phases were detected in the present study, in which the system was always carbon saturated. The thermal expansion coefficients of all phases have been determined, they are constant throughout the temperature interval studied.

  18. Extraction of scandium by aromatic carboxylic acids

    Energy Technology Data Exchange (ETDEWEB)

    Kamenev, V F; Fadeeva, V I [Moskovskij Gosudarstvennyj Univ. (USSR)

    1977-04-01

    Extraction of complex compounds af scandium with salicylic, phenyl- and diphenylacetic acids with chloroform solutions of tetraethyldiamideheptylphosphate as a donor-active additive in relation to the pH and reagent concentration has been studied. Extraction of salicylates of some elements (Ta, Nb, Zr, Hf, Mo) by solutions of tetraethyldiamideheptylphosphate in chloroform has been investigated, and the possibility of their extraction separation from scandium is shown.

  19. Extraction of scandium by aromatic carboxylic acids

    International Nuclear Information System (INIS)

    Kamenev, V.F.; Fadeeva, V.I.

    1977-01-01

    Extraction of complex compounds af scandium with salicylic, phenyl- and diphenylacetic acids with chloroform solutions of tetraethyldiamideheptylphosphate as a donor-active additive in relation to the pH and reagent concentration has been studied. Extraction of salicylates of some elements (Ta, Nb, Zr, Hf, Mo) by solutions of tetraethyldiamideheptylphosphate in chloroform has been investigated, and the possibility of their extraction separation from scandium is shown

  20. Analogs of N-cynnamoylphenylhydroxylamine as reagents for amperometric determination of scandium

    International Nuclear Information System (INIS)

    Shvedene, N.V.; Gallaj, Z.A.; Sheina, N.M.; Zujkova, N.V.

    1978-01-01

    To decrease the detection limit of scandium and increase selectivity of amperometric determination, oxidation of 2-furylacryloyl-N-p-chlorophenylhydroxylamine (FACPhHA) and 3-styrylacryloyl-N-phenylhydroxylamine (SAPhHA) on a graphite electrode has been studied by volt-amperometry. The possibility has been established of using the oxidation current of the reagent for plotting the titration curves. The solubility of scandium complexes with FACPhHA and SAPhHA under conditions of titration against the background with pH 6.0 has been determined and equals (2.1+-0.3)x10 -6 and (5.3+-0.3)x10 -7 , respectively. The methods have been developed of amperometric determination of scandium with the use of the considered reagents against backgrounds with pH 5.5-6.5. The use of SAPhHA has decreased the limit of scandium detection down to 0.1 mgk/ml. Besides, the amperometric method makes it possible to titrate in turbid and coloured media what is an advantage of this method. The developed method is used for determination of scandium in scandium silicide

  1. New separation method of no-carrier-added {sup 47}Sc from titanium targets

    Energy Technology Data Exchange (ETDEWEB)

    Bartos, B.; Majkowska, A.; Kasperek, A.; Krajewski, S.; Bilewicz, A. [Institute of Nuclear Chemistry and Technology, Warszawa (Poland). Nuclear Chemistry and Radiochemistry Center

    2012-07-01

    Radionuclides with medium energy beta emission and a several day half-life are attractive candidates for radioimmunotherapy. Among the most promising in this category is {sup 47}Sc produced by fast neutron irradiation (E{sub n} > 1 MeV) of titanium target with high energy neutrons in {sup 47}Ti(n,p){sup 47}Sc nuclear reaction. In the previously reported production scheme the dissolution of the TiO{sub 2} target in hot concentrated H{sub 2}SO{sub 4} and evaporation of the resulting solution were the most time-consuming steps. The present paper describes new, simple and efficient production method of {sup 47}Sc, where the slow dissolution of the target is avoided. After irradiation in fast neutron flux {sup 47}TiO{sub 2} and Li{sub 2}{sup 47}TiF{sub 6} targets were dissolved in HF solutions. Next {sup 47}Sc was separated from the target using anion exchange resin Dowex 1 with 0.4 M HF + 0.06 M HNO{sub 3} solution as eluent. The eluted {sup 47}Sc was adsorbed on cation exchange resin and eluted with 0.5 M of ammonium acetate. The 47Sc separation yield in the proposed procedure is about 90% with the separation time less than 2 h. The obtained no-carrier-added {sup 47}Sc was used to label DOTATATE conjugate with 96% labeling yield. (orig.)

  2. Scandium and zirconium ion complexing with salicylic acid

    International Nuclear Information System (INIS)

    Fadeeva, V.I.; Kochetkova, S.K.

    1979-01-01

    A study has been made of the extraction of complexes containing scandium and zirconium compounds and salicylic acid by using benzene, nitrobenzene, chloroform and isoamyl alcohol. It is shown that in the metal concentration range 10 -5 -10 -3 mole/l scandium forms mononuclear complexes composed of Sc(HSal) 3 (pH 2 (pH>4), zirconium - polynuclear complexes Zrsub(x)(OH)sub(y)(HSal)sub(n), where the x:n ratio varies from 0.5 to 1.5. Stability constants have been calculated for the salicylate scandium complexes in aqueous solution, equal to β 1 =(3+-1)x10 2 ; β 2 =(5.0+-0.6)x10 4 ; β 3 =(5.3+-0.3)x10 6

  3. Scandium - problem of ultra-trace-element essentiality

    International Nuclear Information System (INIS)

    Kist, A.A.; Zkuk, L.I.; Danilova, E.A.; Makhmudov, E.A.

    2006-01-01

    Full text: Role of constitutional and essential elements in Life is known quite well. It is also well known that all chemical elements present in the living matter. Nevertheless essentiality of at least 55 chemical elements (more than a half of number of natural elements) is still not accepted. In many cases these elements presumably play important role in the Life. On the other hand their essentiality is still under doubt. One of the 'strange' elements in this connection is scandium. Scandium is an element which is very 'simple' for instrumental neutron activation analysis (INAA). For many years in our laboratory were carried out studies on animals and human tissues and fluids elemental composition using INAA in which data for scandium were obtained as 'redundant' information. Essentiality of scandium was newer proven using accepted criteria of elements. Nevertheless in our studies were found various regularities, statistically significant inter-elemental correlations and correlations between elements in tissues and fluids versus clinic and biochemical data. There are some examples. There were found correlations of scandium hair concentration and blood glucose (r=0.68±0.13), body mass index (r=0.86±0.07), leukocyte with phagocytic activity migration inhibition test (r=0.68±0.18), size of cavity of the left heart auricle (r=-0.65±0.16), final systolic bulk (r=0.80±0.12), stroke output of heart (r=-0.79±0.12), final diastolic bulk (0.88±0.0080) etc. In addition using gel filtration in rat liver cytosol was found peak of scandium in elution curve. Examples and correlations given in the paper say in favor that scandium may play quite important role in biological processes and that the biological role of scandium should be studied more intensive. The most important criterion is an appearance of the organism dysfunction in case of removal of the studied elements from the diet (intake) which in all other sides remains completely valuable and disappearance of all

  4. Automated radiosynthesis of no-carrier-added 4-[18F]fluoroiodobenzene: a versatile building block in 18F radiochemistry.

    Science.gov (United States)

    Way, Jenilee Dawn; Wuest, Frank

    2014-02-01

    4-[18F]Fluoroiodobenzene ([18F]FIB) is a versatile building block in 18F radiochemistry used in various transition metal-mediated C-C and C-N cross-coupling reactions and [18F]fluoroarylation reactions. Various synthesis routes have been described for the preparation of [18F]FIB. However, to date, no automated synthesis of [18F]FIB has been reported to allow access to larger amounts of [18F]FIB in high radiochemical and chemical purity. Herein, we describe an automated synthesis of no-carrier-added [18F]FIB on a GE TRACERlab™ FX automated synthesis unit starting from commercially available(4-iodophenyl)diphenylsulfonium triflate as the labelling precursor. [18F]FIB was prepared in high radiochemical yields of 89 ± 10% (decay-corrected, n = 7) within 60 min, including HPLC purification. The radiochemical purity exceeded 95%, and specific activity was greater than 40 GBq/μmol. Typically, from an experiment, 6.4 GBq of [18F]FIB could be obtained starting from 10.4 GBq of [18F]fluoride.

  5. Concentration and Separation of Scandium from Ni Laterite Ore Processing Streams

    Directory of Open Access Journals (Sweden)

    Şerif Kaya

    2017-12-01

    Full Text Available The presence of a considerable amount of scandium in lateritic nickel-cobalt ores necessitates the investigation of possible processing alternatives to recover scandium as a byproduct during nickel and cobalt production. Therefore, in this study, rather than interfering with the main nickel-cobalt production circuit, the precipitation-separation behavior of scandium during a pH-controlled precipitation process from a synthetically prepared solution was investigated to adopt the Sc recovery circuit into an already existing hydrometallurgical nickel-cobalt hydroxide processing plant. The composition of the synthetic solution was determined according to the hydrometallurgical nickel laterite ore processing streams obtained from a HPAL (high-pressure sulphuric acid leaching process. In order to selectively precipitate and concentrate scandium with minimum nickel and cobalt co-precipitation, the pH of the solution was adjusted by CaCO3, MgO, Na2CO3, and NaOH. It was found that precipitation with MgO or Na2CO3 is more advantageous to obtain a precipitate containing higher amounts of scandium with minimum mass when compared to the CaCO3 route, which makes further processing more viable. As a result of this study, it is proposed that by a simple pH-controlled precipitation process, scandium can be separated from the nickel and cobalt containing process solutions as a byproduct without affecting the conventional nickel-cobalt hydroxide production. By further processing this scandium-enriched residue by means of leaching, SX (solvent extraction, and precipitation, an intermediate (NH42NaScF6 product can be obtained.

  6. Scandium and zirconium ion complexing with salicylic acid

    Energy Technology Data Exchange (ETDEWEB)

    Fadeeva, V I; Kochetkova, S K [Moskovskij Gosudarstvennyj Univ. (USSR)

    1979-08-01

    A study has been made of the extraction of complexes containing scandium and zirconium compounds and salicylic acid by using benzene, nitrobenzene, chloroform and isoamyl alcohol. It is shown that in the metal concentration range 10/sup -5/-10/sup -3/ mole/l scandium forms mononuclear complexes composed of Sc(HSal)/sub 3/ (pH<=4) and Sc(OH)(HSal)/sub 2/ (pH>4), zirconium - polynuclear complexes Zrsub(x)(OH)sub(y)(HSal)sub(n), where the x:n ratio varies from 0.5 to 1.5. Stability constants have been calculated for the salicylate scandium complexes in aqueous solution, equal to ..beta../sub 1/=(3+-1)x10/sup 2/; ..beta../sub 2/=(5.0+-0.6)x10/sup 4/; ..beta../sub 3/=(5.3+-0.3)x10/sup 6/.

  7. Carving a Niche for the No-Frills Carrier, Air Arabia, in Oil-Rich Skies

    Science.gov (United States)

    McKechnie, Donelda S.; Grant, Jim; Fahmi, Mona

    2007-01-01

    The concept of introducing a no-frills airline to the wealthy Arab region presented its risks. This independent study sought to position the new airline in the marketplace. After three focus groups and 400 self-administered surveys, safety (#1) and price (#2) are low-fare carrier considerations whereas safety (#1), punctuality (#2) and price (#3) apply for full-fare airlines. Recommended ways for the no-frills carrier to reach the market include newspaper ads, travel agent sales, online bookings, and call centers. Additionally, respondents appeared to evaluate this low-fare carrier as if it is a full-service airline.

  8. The Y-12 Plant No Rad-Added Program for off-site shipment of nonradioactive hazardous waste

    International Nuclear Information System (INIS)

    Cooper, K.H.; Mattie, B.K.; Williams, J.L.; Jacobs, D.G.; Roberts, K.A.

    1994-01-01

    On May 17, 1991, the US Department of Energy (DOE) issued a directive for DOE operations to cease off-site shipments of non-radioactive hazardous waste pending further clarification and approvals. A DOE Performance Objective for Certification of Non-Radioactive Hazardous Waste was issued in November 1991. In response to these directives, the Waste Management Division of Oak Ridge Y-12 Plant, with assistance from Roy F. Weston, Inc., has developed a No Rad-Added Program to provide small programmatic guidance and a set of procedures, approved by DOE, which will permit hazardous waste to be shipped from the Y-12 Plant to commercial treatment, storage, or disposal facilities after ensuring and certifying that hazardous waste has no radioactivity added as a result of DOE operations. There are serious legal and financial consequences of shipping waste containing radioactivity to an off-site facility not licensed to receive radioactive materials. Therefore, this program is designed with well-defined responsibilities and stringent documentation requirements

  9. Heat capacity and solid solubility of iron in scandium

    International Nuclear Information System (INIS)

    Tsang, T.-W.E.

    1981-01-01

    The maximum solid solubility of iron in scandium was determined to be between 50 and 85 at.ppm in the as-cast condition. As the concentration of iron increases, it segregates along the grain boundary, as is evident from optical metallography and electron microprobe examinations. Annealing also causes the iron dissolved in scandium to separate out and cluster along the grain boundary. Heat capacity measurements show an anomaly in the C/T versus T 2 plots for iron concentrations of 19 at.ppm or greater. For iron dissolved in solid scandium the excess entropy due to the iron impurity is in agreement with the theoretical prediction of ck ln(2S + 1) for an impurity-conduction electron (Kondo) interaction, but is 4 - 8 times larger than the theoretical prediction when iron segregates along the grain boundary. Furthermore, our results suggest that most of the previously reported low temperature physical properties of scandium are probably in error because of either iron impurity-conduction electron interactions or Fe-Fe interactions in the precipitated second-phase Sc-Fe compound. (Auth.)

  10. Speciation of no-carrier-added 68Ga prior to its labeling for PET imaging

    International Nuclear Information System (INIS)

    Kamalika Sen; Breeman, W.A.P.; Wolterbeek, H.Th.

    2012-01-01

    The present article describes the probable speciation of 68 Ga radionuclide just before labeling to DOTA peptides for PET imaging. The 68 Ga eluted from an anion exchange column after its purification was analyzed for its elemental composition and pH at several stages. Neutron activation analysis of the eluted fractions yields the concentrations of Na and Cl, pH measurements indicate the concentration of free H + ions in the medium and specific activity calculations indicate the concentration of 68 Ga in the solution. Using all these information we get the idea of speciation of no carrier added Ga in the eluted fractions from CHEAQS programme. The estimations indicate that Ga is mostly present as GaCl 2+ in the total MiliQ eluate. However, just before labeling of DOTA the pH of the Ga-containing eluate is adjusted to ∼3.5 using HEPES buffer and at that condition Ga remains as Ga 3+ species which is responsible for a successful and efficient labeling. The MilliQ eluate collected before actual labeling was estimated for trace elements using inductively coupled plasma atomic emission spectrometry was found to contain a few ppb of Al, Co, Pd and Pt that did not interfere in the actual labeling. A clear idea about the prerequisite of 68 Ga species before labeling to a peptide might be of special interest for its judicious application as a radiopharmaceutical. (author)

  11. Production of no-carrier-added 139Pr via precursor decay in the proton bombardment of natPr

    International Nuclear Information System (INIS)

    Steyn, G.F.; Vermeulen, C.; Nortier, F.M.; Szelecsenyi, F.; Kovacs, Z.; Qaim, S.M.

    2006-01-01

    Excitation functions and production rates are presented for various Pr and Nd radionuclides formed in the bombardment of Pr with protons, from their respective thresholds up to 100 MeV. The indirect production route 141 Pr(p, 3n) 139m Nd → 139 Pr is investigated as an alternative to the direct production route 140 Ce(p, 2n) 139 Pr for producing no-carrier-added 139 Pr of high radionuclidic purity. The simultaneous production of 139 Pr and 140 Nd using Pr as target is investigated. The advantages and disadvantages of both production routes are discussed. Experimental thick-target production rates are presented for selected Pr radionuclides formed in the bombardment of nat Ce with protons at incident energies of 20, 26 and 32 MeV. All the experimental excitation functions obtained in this work are compared with theoretical predictions by means of the geometry-dependent hybrid (GDH) model as implemented in the code ALICE-IPPE. The results of this work are also compared with previous literature experimental data, if available

  12. Highly sensitive luminescence method of scandium determination in the products of metallurgical reprocessing

    International Nuclear Information System (INIS)

    Matveets, M.A.; Akhmetova, S.D.

    1988-01-01

    Highly sensitive reaction of scandium with 1,10-phenanthroline and eosin is used for the development of luminescence method of its determination in metallurgical products. The effect of interfering elements is eliminated by scandium extraction with monocarboxylic acids. The method permits to determine scandium content from 5 x 10 -5 % (Sr 0.15 - 0.25)

  13. Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2

    International Nuclear Information System (INIS)

    Klima, B.B.; Shappert, L.B.; Seagren, R.D.; Box, W.D.

    1978-04-01

    An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations. The package is designed to ship large quantities of fissile and radioactive materials as solids

  14. Size Effects on Deformation and Fracture of Scandium Deuteride Films.

    Energy Technology Data Exchange (ETDEWEB)

    Teresi, C. S. [Univ. of Minnesota, Minneapolis, MN (United States); Hintsala, E. [Univ. of Minnesota, Minneapolis, MN (United States); Hysitron, Inc., Eden Prairie, MN (United States); Adams, David P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Yang, Nancy Y. C. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kammler, Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Moody, N. R. [Univ. of Minnesota, Minneapolis, MN (United States); Gerberich, W. W. [Univ. of Minnesota, Minneapolis, MN (United States)

    2017-07-01

    Metal hydride films have been observed to crack during production and use, prompting mechanical property studies of scandium deuteride films. The following focuses on elastic modulus, fracture, and size effects observed in the system for future film mechanical behavior modeling efforts. Scandium deuteride films were produced through the deuterium charging of electron beam evaporated scandium films using X-ray diffraction, scanning Auger microscopy, and electron backscatter diffraction to monitor changes in the films before and after charging. Scanning electron microscopy, nanoindentation, and focused ion beam machined micropillar compression tests were used for mechanical characterization of the scandium deuteride films. The micropillars showed a size effect for flow stress, indicating that film thickness is a relevant tuning parameter for film performance, and that fracture was controlled by the presence of grain boundaries. Elastic modulus was determined by both micropillar compression and nanoindentation to be approximately 150 GPa, Fracture studies of bulk film channel cracking as well as compression induced cracks in some of the pillars yielded a fracture toughness around 1.0 MPa-m1/2. Preliminary Weibull distributions of fracture in the micropillars are provided. Despite this relatively low value of fracture toughness, scandium deuteride micropillars can undergo a large degree of plasticity in small volumes and can harden to some degree, demonstrating the ductile and brittle nature of this material

  15. Complexonometric photometric titration of scandium in the presence of xylenol orange

    International Nuclear Information System (INIS)

    Kornev, V.I.

    1977-01-01

    Possibility has been studied of using xylenol orange (XO) for chelatometric determination of scandium by means of various chelates with the aid of photometric techniques. It has been established that the chelates applicable for the purpose are ethylenediamineteraacetic acid (EDTA), diethylenediaminetetraacetic acid (DEDTA), diethylenetriaminepentaacetic acid (DETPA), upon introducing of which into a solution containing a complex of scandium with XO (maximum light adsorption at 550 nm) the optical density gradually diminishes. Weakening of the light absorption is, evidently, associated with the destruction of the scandium complex with XO and formation of a colourless chelate acetate with one of the chelates. Chelatometric determination of scandium, using EDTA, DEDTA and DEPTA solutions with XO should be carried out in an acidic medium at pH=2.5-3.0. In this range of pH values interferences caused by the appearance of the Sc-XO complex in the solution are insignificant

  16. Production and separation of no-carrier-added 73As and 75Se from 7Li irradiated germanium oxide target

    International Nuclear Information System (INIS)

    Mandal, A.; Lahiri, S.

    2012-01-01

    This work reports for the first time 7 Li-induced accelerator based production of 71,72,73,74 As, 75,76,77 Br and 73,75 Se radionuclides in their no-carrier-added (nca) state. After the decay of all short-lived radionuclides 75 Se and 73 As were only existing radionuclides in germanium oxide target, which were subsequently separated by liquid-liquid extraction (LLX) using trioctylamine (TOA) dissolved in cyclohexane as liquid ion exchanger. The presence of stable germanium in various fractions was examined by Inductively Coupled Plasma Optical Spectrometry (ICP-OES). At 0.1 M TOA and 10 M HCl concentration, 75 Se and stable Ge were extracted into the organic phase leaving 73 As in the aqueous phase. The bulk Ge was stripped back to the aqueous phase by 1 M NaOH, keeping 75 Se in the organic phase. Therefore complete separation between 73 As, 75 Se and bulk Ge was achieved. (orig.)

  17. Lifetime measurements and oscillator strengths in singly ionized scandium and the solar abundance of scandium

    Science.gov (United States)

    Pehlivan Rhodin, A.; Belmonte, M. T.; Engström, L.; Lundberg, H.; Nilsson, H.; Hartman, H.; Pickering, J. C.; Clear, C.; Quinet, P.; Fivet, V.; Palmeri, P.

    2017-12-01

    The lifetimes of 17 even-parity levels (3d5s, 3d4d, 3d6s and 4p2) in the region 57 743-77 837 cm-1 of singly ionized scandium (Sc II) were measured by two-step time-resolved laser induced fluorescence spectroscopy. Oscillator strengths of 57 lines from these highly excited upper levels were derived using a hollow cathode discharge lamp and a Fourier transform spectrometer. In addition, Hartree-Fock calculations where both the main relativistic and core-polarization effects were taken into account were carried out for both low- and high-excitation levels. There is a good agreement for most of the lines between our calculated branching fractions and the measurements of Lawler & Dakin in the region 9000-45 000 cm-1 for low excitation levels and with our measurements for high excitation levels in the region 23 500-63 100 cm-1. This, in turn, allowed us to combine the calculated branching fractions with the available experimental lifetimes to determine semi-empirical oscillator strengths for a set of 380 E1 transitions in Sc II. These oscillator strengths include the weak lines that were used previously to derive the solar abundance of scandium. The solar abundance of scandium is now estimated to logε⊙ = 3.04 ± 0.13 using these semi-empirical oscillator strengths to shift the values determined by Scott et al. The new estimated abundance value is in agreement with the meteoritic value (logεmet = 3.05 ± 0.02) of Lodders, Palme & Gail.

  18. Scandium effect on mechanical properties of Al-6.5 % Mg alloy

    International Nuclear Information System (INIS)

    Drits, M.E.; Toropova, L.S.; Bykov, Yu.G.

    1982-01-01

    Quantitative evaluation of influence of small scandium additions (up to 0.5 wt%) on properties of Al-6.5% Mg binary alloy are carried out depending on test temperature in the range of -196 to 310 deg C. Alloys were tested on ''Instron'' machine at 1.3x10 - 3 s - 1 strain rate. Scandium additions are shown to increase plasticity at -196 deg C. Yield strength also increases with introduction of 0.2% Sc if deformation temperature does not exceed 250 deg C. The growth of ultimate strength is less significant. Elevated strength properties of alloys with scandium additions can be explained by a fine-grained structure

  19. Quantitative determination of sediment movement at the landward spoil ground in the Yangtze Estuary with radioactive tracer

    International Nuclear Information System (INIS)

    Li Zhangsu

    1993-01-01

    A radioactive tracer experiment was carried out at the landward spoil ground of the North Passage in the Yangtze Estuary in June of 1991. The scandium-46 was selected as the tracer, the total activity released is 17.95 x 10 10 Bq(4.85 Ci), the amount of the scandium-46 glass is 495 g. The purpose of the experiment is to determine the sediment movement direction, path, velocity and transport rate. The experiment provides the direct evidence for using the landward spoil ground in the future. The experiment results show the sediment movement was governed by the ebb tide current during the period of middle and neap tides when the radioactive tracer was injected both on the flood and ebb tides, and the sediment moved from the injection points to the middle of the North Passage near the navigation buoy No. 269. The direction of the sediment movement is 110 degree, the particle velocity is 758 m/d, and the sediment transport rate per unit width is 47.8 m 3 /md

  20. Scandium fluorides

    International Nuclear Information System (INIS)

    Melnikov, P.; Nalin, M.; Messaddeq, Y.

    1997-01-01

    A new modification of scandium fluoride has been synthesised. The compound is deficient in fluorine, with the composition ScF 2.76 . It belongs to the tetragonal system, lattice parameters being a=3.792 and c=6.740 A and may be obtained at low temperatures by the decomposition of the precursor NH 4 ScF 4 . The reaction is topotactic, tetragonal parameters of the precursor are a=4.021 and c=6.744 A. Structural relationships with various fluorides and ammonium aminofluorides are discussed. This synthesis route with IR-assisted decomposition should be considered as a soft-chemistry approach. (orig.)

  1. Standard test of labelling efficiency for quality control of no carrier added 90YCl3

    International Nuclear Information System (INIS)

    Beran, M.; Eigner Henke, K.; Srank, J.; Melichar, F.

    2007-01-01

    Particle emitting radionuclides (e.g. beta-emitters 90 Y and 177 Lu, alpha-emitter 211 At, Auger electron emitter 165 Er or positron emitter 86 Y) are beeing more and more frequently used in research and clinical practice for imaging and targeted therapy in nuclear medicine. This radiometals, altogether three valent lanthanides or actinides with high specific radioactivity, coupled to biomolecule carriers (peptides or monoclonal antibodies) through chelating link (e.g. DTPA or DOTA) are targeted against specific antigens and receptors of diseased tissues in order to obtain their image or to cause their radiation ablation. The radionuclide precursor 90 YCl 3 (solution of hard β-emitter 90 Y in a diluted HCl) with high purity and specific activity is already commercially produced and successfully used in nuclear medicine, e.g. for radioimmunotherapy of Lymphoma. Specification and purity of our product obtained by extraction 90 Sr/ 90 Y generator (using technology of centrifuge extractors with di-2-ethylhexylphosphoric acid) is examined and compared to other similar products in this contribution. A standard method for determination of labelling efficiency of the precursor with DOTA Octreotide (DOTATATE) using ITLC/SG chromatography is also described and proposed for quality assesment. (Author)

  2. The characteristics of aluminum-scandium alloys processed by ECAP

    International Nuclear Information System (INIS)

    Venkateswarlu, K.; Rajinikanth, V.; Ray, Ajoy Kumar; Xu Cheng; Langdon, Terence G.

    2010-01-01

    Aluminum-scandium alloys were prepared having different scandium additions of 0.2, 1.0 and 2.0 wt.% and these alloys were processed by equal-channel angular pressing (ECAP) at 473 K. The results show the grain refinement of the aluminum matrix and the morphology of the Al 3 Sc precipitates depends strongly on the scandium concentration. The tensile properties were evaluated after ECAP by pulling to failure at initial strain rates from 1.0 x 10 -3 to 1.0 x 10 -1 s -1 . The Al-1% Sc alloy exhibited the highest tensile strength of ∼250 MPa at a strain rate of 1.0 x 10 -1 s -1 . This alloy also exhibited a superior grain refinement of ∼0.4 μm after ECAP where this is attributed to a smaller initial grain size and an optimum volume fraction of dispersed Al 3 Sc precipitates having both micrometer and nanometer sizes.

  3. A new model for prediction of dispersoid precipitation in aluminium alloys containing zirconium and scandium

    International Nuclear Information System (INIS)

    Robson, J.D.

    2004-01-01

    A model has been developed to predict precipitation of ternary Al 3 (Sc, Zr) dispersoids in aluminium alloys containing zirconium and scandium. The model is based on the classical numerical method of Kampmann and Wagner, extended to predict precipitation of a ternary phase. The model has been applied to the precipitation of dispersoids in scandium containing AA7050. The dispersoid precipitation kinetics and number density are predicted to be sensitive to the scandium concentration, whilst the dispersoid radius is not. The dispersoids are predicted to enrich in zirconium during precipitation. Coarsening has been investigated in detail and it has been predicted that a steady-state size distribution is only reached once coarsening is well advanced. The addition of scandium is predicted to eliminate the dispersoid free zones observed in scandium free 7050, greatly increasing recrystallization resistance

  4. Synthesis of a Potent Aminopyridine-Based nNOS-Inhibitor by Two Recent No-Carrier-Added 18F-Labelling Methods

    Directory of Open Access Journals (Sweden)

    Christian Drerup

    2016-09-01

    Full Text Available Nitric oxide (NO, an important multifunctional signaling molecule, is produced by three isoforms of NO-synthase (NOS and has been associated with neurodegenerative disorders. Selective inhibitors of the subtypes iNOS (inducible or nNOS (neuronal are of great interest for decoding neurodestructive key factors, and 18F-labelled analogues would allow investigating the NOS-function by molecular imaging with positron emission tomography. Especially, the highly selective nNOS inhibitor 6-((3-((3-fluorophenethylaminomethylphenoxymethyl-4-methylpyridin-2-amine (10 lends itself as suitable compound to be 18F-labelled in no-carrier-added (n.c.a. form. For preparation of the 18F-labelled nNOS-Inhibitor [18F]10 a “build-up” radiosynthesis was developed based on a corresponding iodonium ylide as labelling precursor. The such activated phenethyl group of the compound was efficiently and regioselectively labelled with n.c.a. [18F]fluoride in 79% radiochemical yield (RCY. After conversion by reductive amination and microwave assisted displacement of the protecting groups, the desired nNOS-inhibitor was obtained in about 15% total RCY. Alternatively, for a simplified “late-stage” 18F-labelling procedure a corresponding boronic ester precursor was synthesized and successfully used in a newer, copper(II mediated n.c.a. 18F-fluoro-deboroniation reaction, achieving the same total RCY. Thus, both methods proved comparatively suited to provide the highly selective NOS-inhibitor [18F]10 as probe for preclinical in vivo studies.

  5. Synthesis of a Potent Aminopyridine-Based nNOS-Inhibitor by Two Recent No-Carrier-Added (18)F-Labelling Methods.

    Science.gov (United States)

    Drerup, Christian; Ermert, Johannes; Coenen, Heinz H

    2016-09-01

    Nitric oxide (NO), an important multifunctional signaling molecule, is produced by three isoforms of NO-synthase (NOS) and has been associated with neurodegenerative disorders. Selective inhibitors of the subtypes iNOS (inducible) or nNOS (neuronal) are of great interest for decoding neurodestructive key factors, and (18)F-labelled analogues would allow investigating the NOS-function by molecular imaging with positron emission tomography. Especially, the highly selective nNOS inhibitor 6-((3-((3-fluorophenethylamino)methyl)phenoxy)methyl)-4-methylpyridin-2-amine (10) lends itself as suitable compound to be (18)F-labelled in no-carrier-added (n.c.a.) form. For preparation of the (18)F-labelled nNOS-Inhibitor [(18)F]10 a "build-up" radiosynthesis was developed based on a corresponding iodonium ylide as labelling precursor. The such activated phenethyl group of the compound was efficiently and regioselectively labelled with n.c.a. [(18)F]fluoride in 79% radiochemical yield (RCY). After conversion by reductive amination and microwave assisted displacement of the protecting groups, the desired nNOS-inhibitor was obtained in about 15% total RCY. Alternatively, for a simplified "late-stage" (18)F-labelling procedure a corresponding boronic ester precursor was synthesized and successfully used in a newer, copper(II) mediated n.c.a. (18)F-fluoro-deboroniation reaction, achieving the same total RCY. Thus, both methods proved comparatively suited to provide the highly selective NOS-inhibitor [(18)F]10 as probe for preclinical in vivo studies.

  6. Scandium Terminal Imido Chemistry.

    Science.gov (United States)

    Lu, Erli; Chu, Jiaxiang; Chen, Yaofeng

    2018-02-20

    Research into transition metal complexes bearing multiply bonded main-group ligands has developed into a thriving and fruitful field over the past half century. These complexes, featuring terminal M═E/M≡E (M = transition metal; E = main-group element) multiple bonds, exhibit unique structural properties as well as rich reactivity, which render them attractive targets for inorganic/organometallic chemists as well as indispensable tools for organic/catalytic chemists. This fact has been highlighted by their widespread applications in organic synthesis, for example, as olefin metathesis catalysts. In the ongoing renaissance of transition metal-ligand multiple-bonding chemistry, there have been reports of M═E/M≡E interactions for the majority of the metallic elements of the periodic table, even some actinide metals. In stark contrast, the largest subgroup of the periodic table, rare-earth metals (Ln = Sc, Y, and lanthanides), have been excluded from this upsurge. Indeed, the synthesis of terminal Ln═E/Ln≡E multiple-bonding species lagged behind that of the transition metal and actinide congeners for decades. Although these species had been pursued since the discovery of a rare-earth metal bridging imide in 1991, such a terminal (nonpincer/bridging hapticities) Ln═E/Ln≡E bond species was not obtained until 2010. The scarcity is mainly attributed to the energy mismatch between the frontier orbitals of the metal and the ligand atoms. This renders the putative terminal Ln═E/Ln≡E bonds extremely reactive, thus resulting in the formation of aggregates and/or reaction with the ligand/environment, quenching the multiple-bond character. In 2010, the stalemate was broken by the isolation and structural characterization of the first rare-earth metal terminal imide-a scandium terminal imide-by our group. The double-bond character of the Sc═N bond was unequivocally confirmed by single-crystal X-ray diffraction. Theoretical investigations revealed the presence

  7. Effects of iron on intermetallic compound formation in scandium modified Al–Si–Mg Alloys

    Energy Technology Data Exchange (ETDEWEB)

    Patakham, Ussadawut [National Metal and Materials Technology Center, National Science and Technology Development Agency, 114 Thailand Science Park, Klong Nueng, Klong Luang, Pathumthani 12120 (Thailand); Limmaneevichitr, Chaowalit, E-mail: chaowalit.lim@mail.kmutt.ac.th [Production Engineering Department, Faculty of Engineering, King Mongkut’s University of Technology Thonburi, 126 Pracha-Utid Rd., Bangmod, Tungkhru, Bangkok 10140 (Thailand)

    2014-12-15

    Highlights: • Iron reduces the modification effects of scandium in Al–Si–Mg alloys. • Morphologies of Sc-rich intermetallic phases vary with Fe and Sc contents and the cooling rates. • Sc neutralizes effects of Fe by changing Fe-rich intermetallic phases from platelets to more cubic. - Abstract: In general, iron has a strong tendency to dissolve in molten aluminum. Iron has very low solid solubility in aluminum–silicon casting alloys, so it will form intermetallic compounds that cause detrimental effects on mechanical properties. In this work, the effects of iron on intermetallic compound formations in scandium modified Al–Si–Mg alloys were studied. There were two levels of iron addition (0.2 and 0.4 wt.%) and two levels of scandium addition (0.2 and 0.4 wt.%). We found that the effects of scandium modification decreased with increasing iron addition. The morphologies of the complex intermetallic compounds were characterized by scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS) and electron backscatter diffraction (EBSD) techniques. It was found that scandium changes the morphology of Fe-rich intermetallic compounds from β-phase (plate-like) to α-phase, which reduces the harmful effects of β-phase.

  8. Preparation process of a stable non radioactive carrier intended for radiodiagnosis

    International Nuclear Information System (INIS)

    Molinski, V.J.; Wilczewski, J.A.

    1976-01-01

    The description is given of a stable non radioactive carrier with a pH of around 2 and around 4, for cardiological studies, exploring the blood in circulation and exploring the brain, after labelling with sup(99m)Tc. It includes human serum albumin (SAH) and stannous tartrate, the proportion in weight between the SAH and stannous tartrate being between around 50:1 and around 150:1 [fr

  9. Thermomechanical treatment of welded joints of aluminum-lithium alloys modified by scandium

    Science.gov (United States)

    Malikov, A. G.

    2017-12-01

    At present, the aeronautical equipment manufacture involves up-to-date high-strength aluminum alloys of decreased density resulting from the lithium admixture. Various technologies of fusible welding of these alloys are being developed. The paper presents experimental investigations of the optimization of the laser welding of aluminum alloys with the scandium-modified welded joint after thermomechanical treatment. The effect of scandium on the micro- and macrostructure is studied along with strength characteristics of the welded joint. It is found that thermomechanical treatment allows us to obtain the strength of the welded joint 0.89 for the Al-Mg-Li system and 0.99 for the Al-Cu-Li system with the welded joint modified by scandium in comparison with the base alloy after treatment.

  10. Safety requirements for the Pu carriers

    International Nuclear Information System (INIS)

    Mishima, H.

    1993-01-01

    Ministry of Transport of Japan has now set about studying requirements for Pu carriers to ensure safety. It was first studied what the basic concept of safe carriage of Pu should be, and the basic ideas have been worked out. Next the requirements for the Pu carriers were studied based on the above. There are at present no international requirements of construction and equipment for the nuclear-material carriers, but MOT of Japan has so far required special construction and equipment for the nuclear-material carriers which carry a large amount of radioactive material, such as spent fuel or low level radioactive waste, corresponding to the level of the respective potential hazard. The requirements of construction and equipment of the Pu carriers have been established considering the difference in heat generation between Pu and spent fuel, physical protection, and so forth, in addition to the above basic concept. (J.P.N.)

  11. Separation and purification of no-carrier-added arsenic from bulk amounts of germanium for use in radiopharmaceutical labelling

    Energy Technology Data Exchange (ETDEWEB)

    Jahn, M.; Radchenko, V.; Roesch, F.; Jennewein, M. [Mainz Univ. (Germany). Inst. of Nuclear Chemsistry; Filosofov, D. [Joint Inst. for Nuclear Research, Dubna (Russian Federation). Lab. of Nuclear Problems; Hauser, H.; Eisenhut, M. [Deutsches Krebsforschungszentrum, Heidelberg (Germany). Radiopharmaceutical Chemistry

    2010-07-01

    Radioarsenic labelled radiopharmaceuticals could add special features to molecular imaging with positron emission tomography (PET). For example the long physical half-lives of {sup 72}As (T{sub 1/2}=26 h) and {sup 74}As (T{sub 1/2}=17.8 d) in conjunction with their high positron branching rates of 88% and 29%, respectively, allow the investigation of slow physiological or metabolical processes, like the enrichment and biodistribution of monoclonal antibodies in tumour tissue or the characterization of stem cell trafficking. A method for separation and purification of no-carrier-added (nca) arsenic from irradiated metallic germanium targets based on distillation and anion exchange is developed. It finally converts the arsenic into an {sup *}As(III) synthon in PBS buffer and pH 7 suitable for labelling of proteins via As-S bond formations. The method delivers radioarsenic in high purity with separation factors of 10{sup 6} from germanium and an overall yield from target to labelling synthon of > 40%. In a proof-of-principle experiment, the monoclonal antibody Bevacizumab, directed against the human VEGF receptor, was labelled with a radiochemical yield > 90% within 1 h at room temperature with nca {sup 72/74/77}As. (orig.)

  12. Study of competitive complexing in scandium(3)-xylenol-orange-hydroxyethyliminodiacetic acid system

    International Nuclear Information System (INIS)

    Kornev, V.I.; Mukanov, I.P.; Artem'eva, O.A.

    1976-01-01

    The competitive complexing in the system scandium(3)-xylene orange (XO)-hydroxyethyliminodiacetic acid (H 3 L) has been studied. Ligands act as competitive particles. It has been established preliminarily that introduction of H 3 L into the solution containing a mixture of Sc and Xo changes considerably the absorption spectra of the coloured complex. Weakening of light absorption indicates that the coloured complex with XO is destructed and colourless hydroxyethyliminodiacetate of scandium is formed. The formation of scandium hydroxyethyliminoacetate has been studied spectrophotometrically by equilibrium between the complexes. The dependence of optical density on pH, when the concentrations of reagents are constant, as well as on concetration of H 3 L has been studied. The composition of the complex (1:1) formed at pH 3.2 has been established graphically and the constant of the complex ScHL + instability has been calculated (PKsub(H)=10.69+-0.45). It has been shown that H 3 L, when interacting with scandium, behaves as dibasic ligand. It is most probable that during complex formation the hydrogen ion of the hydroxygroup is not replaced, although the participation of hydroxygroup in coordination is possible due to a donor-acceptor bond

  13. Fission neutron spectrum averaged cross sections of some threshold reactions on cadmium: production feasibility of no-carrier-added 103Pd in a nuclear reactor

    International Nuclear Information System (INIS)

    Abbasi, I.A.; Subhani, M.S.; Zaidi, J.H.; Arif, M.

    2006-01-01

    Systematic studies on fission neutron spectrum averaged cross sections of some threshold reactions like (n, p) and (n, α) on cadmium were carried out using the activation technique in combination with radiochemical separations and high-resolution γ-ray spectroscopy. Special attention was paid to the formation of 103 Pd via the 106 Cd(n,a α) 103 Pd reaction since it is an important therapeutic radionuclide. At a fast flux neutron density of 7.5 x 10 13 cm 2 s -1 and an irradiation time of 120 h, using 100% enriched 106 Cd target 340 MBq of no-carrier-added 103 Pd per batch could be produced. The method is thus suitable for medium-scale production of this radionuclide. (orig.)

  14. Formation of scandium carbides and scandium oxycarbide from the elements at high-(P, T) conditions

    International Nuclear Information System (INIS)

    Juarez-Arellano, Erick A.; Winkler, Bjoern; Bayarjargal, Lkhamsuren; Friedrich, Alexandra; Milman, Victor; Kammler, Daniel R.; Clark, Simon M.; Yan Jinyuan; Koch-Mueller, Monika; Schroeder, Florian; Avalos-Borja, Miguel

    2010-01-01

    Synchrotron diffraction experiments with in situ laser heated diamond anvil cells and multi-anvil press synthesis experiments have been performed in order to investigate the reaction of scandium and carbon from the elements at high-(P,T) conditions. It is shown that the reaction is very sensitive to the presence of oxygen. In an oxygen-rich environment the most stable phase is ScO x C y , where for these experiments x=0.39 and y=0.50-0.56. If only a small oxygen contamination is present, we have observed the formation of Sc 3 C 4 , Sc 4 C 3 and a new orthorhombic ScC x phase. All the phases formed at high pressures and temperatures are quenchable. Experimentally determined elastic properties of the scandium carbides are compared to values obtained by density functional theory based calculations. - Graphical Abstract Legend (TOC Figure): Table of Contents Figure Selected images recorded with a MAR345 image plate detector show the reaction of α-Sc and graphite at high-(P,T) conditions. Left: mixture of α-Sc and graphite. Right: recovered sample after laser heated the diamond anvil cell.

  15. Knight shift in scandium and its alloys with hafnium and titanium

    International Nuclear Information System (INIS)

    Chachkhiani, Z.B.; Chechernikov, V.I.; Martynova, L.F.; Nidel'ko, V.I.; Chachkhiani, L.G.; Georgadze, G.S.

    1981-01-01

    Results of the investigation of NMR on 45 Sc nuclei and magnetic susceptibility of scandium and its solid solutions with titanium and hafnium are presented. It is shown that the existing hybridization of S and d zones in pure scandium and its alloys with titanium and hafnium affects the Knight shift reducing the value of the contact contribution. The temperature behaviour of the Knight shift from the temperature dependence and spin susceptibility of collectivized d electrons [ru

  16. Biamperometric analysis of nonaqueous scandium solutions containing lanthanides, lead and thorium

    International Nuclear Information System (INIS)

    Gevorgyan, A.M.; Talipov, Sh.T.; Kostylev, V.S.; Khadeev, V.A.; Nadol'skij, M.Ya.

    1978-01-01

    Investigated was a possibility of direct scandium titration in the presence of large rare earth quantities, and also a possibility of complexonometric scandium and rare earth sum determination at their joint presence in non-aqueous acetic acid solution. The titration was carried out at electrode voltage of 0.95V, background electrolyte concentration of lithium perchlorate being 0.2M. Non-aqueous magnesium complexonate was used as titrating reagent. Th and Pb complexonates are shown to be less stable as compared to Sc complexonate, and consequently, Th and Pb ions must not interfere with biamperometric titration of Sc ion. A method applied to analysis of binary mixture, containing scandium, and a method for model alloy and thortveitite mineral was developed. Well reproducible and precise enough results are obtained in all the cases. Ions of Bi, Cu, Cd, Zn, In, Ga and Ti interfere with determination

  17. The enthalpy of solid scandium in the temperature range 406 - 1812 K

    International Nuclear Information System (INIS)

    Lyapunov, K.M.; Baginskij, A.V.; Stankus, S.V.

    2001-01-01

    Enthalpy of pure scandium was measured on massive calorimeter in the range from 406 to 1812 K by mixing method. The enthalpy of face centered close cubic lattice - body centered cubic lattice transformation is equal to ΔH t 4068 J/mol. Obtained value within the limits of error is compatible with the results given earlier (4009 J/mol). The dependence of the middle specific heat of scandium C p (T) on the temperature was shown in correlation with the results of other works. The results of the conducted experiments reinforce the conclusion made earlier about an absence (or a little) in the decomposition of an anharmonic component of the oscillation specific heat of scandium C p a (T) members proportional to the first or the second degrees of temperature [ru

  18. 3He release characteristics of metal tritides and scandium--tritium solid solutions

    International Nuclear Information System (INIS)

    Perkins, W.G.; Kass, W.J.; Beavis, L.C.

    1975-01-01

    Tritides of such metals as scandium, titanium, and erbium are useful materials for determining the effects of helium accumulation in metallic solids, for example, CTR first wall materials. Such effects include lattice strain and gross deformation, as reported elsewhere, which are related to 3 He retention and ultimate release. Long term gas release studies have indicated that, during the early life of a metal ditritide, a large fraction of the 3 He is retained in the solid. At more advanced ages (2 to 4 years, depending on the parent metal), the 3 He release rate becomes comparable to the generation rate. Statistical analysis of the data indicates that the acceleration in 3 He release rate depends on accumulated 3 He concentration rather than strictly on age. 3 He outgassing results are presented for thin films of ScT 2 , TiT 2 , and ErT 2 , and the critical 3 He concentrations are discussed in terms of a percolation model. Phase transformations which occur on tritide formation cast some doubt on the validity of extrapolating results obtained for metal tritides to predictions regarding the accumulation of helium in metals. Scandium is unique among the early transition and rare-earth metals in that the metal exhibits a very high room temperature tritium solubility (T/Sc = 0.4) with no phase transformation. Indeed, even the lattice parameters of the hcp scandium lattice are only minimally changed by tritium solution, and we have succeeded in obtaining single crystal ScT 0 . 3 samples in two crystallographic orientations. Using a very sensitive technique, we have measured 3 He emission from both these samples, as well as from fine-grained thin film scandium-tritium solid solution samples (ScT 0 . 3 - 0 . 4 ). The fine-grained film samples release 3 He at 2 to 3 percent of the generation rate, while the emission rate from the single-crystal samples is approximately 0.05 percent of the generation rate, indicating a strong grain size effect

  19. Effect of scandium additions on microstructure and mechanical properties of Al-Zn-Mg alloy welds

    International Nuclear Information System (INIS)

    Dev, Selvi; Stuart, A. Archibald; Kumaar, R.C. Ravi Dev; Murty, B.S.; Rao, K. Prasad

    2007-01-01

    The microstructure and mechanical properties of fusion zones of medium strength Al-Zn-Mg alloy (RDE-40) welds obtained by using different fillers containing various amount of scandium was investigated. It was observed that addition of scandium led to very significant grain refinement in the fusion zone especially for scandium levels greater than the eutectic composition (0.55 wt%). The grain refinement led to the reduction in solidification cracking and improved the tensile properties of fusion zone compared to the ones obtained by the commercial AA5556 filler

  20. Automated no-carrier-added synthesis of [1-11C]-labeled D- and L-enantiomers of lactic acid

    International Nuclear Information System (INIS)

    Drandarov, Konstantin; Schubiger, P. August; Westera, Gerrit

    2006-01-01

    The first purely chemical method for automated no-carrier-added synthesis of [1- 11 C]-labeled D(R)- and L(S)-2-hydroxypropanoic acid (lactic acid) was developed for experimental neurophysiology studies and position emission tomography (PET) diagnosis. Starting from sodium 1-hydroxyethanesulfonate and [ 11 C]HCN (trapped as [ 11 C]KCN) the intermediate DL-(R,S)-[1- 11 C]-2-hydroxypropanenitrile was prepared. Its rapid acid hydrolysis gave DL-(R,S)-[1- 11 C]lactic acid, which was isolated by preparative reversed phase HPLC and automatically injected on a second preparative C 18 HPLC column coated with a chiral selector, where both [1- 11 C]lactic acid enantiomers were separated by chiral ligand-exchange chromatography. Two novel chiral selectors for HPLC enantiomeric separation of α-hydroxy acids, namely D(R)- or L(S)-2-amino-3-methyl-3-(5-phenylpentylsulfanyl)-butanoic acid were utilized for the preparative HPLC separation of the [1- 11 C]lactic acid enantiomers. The preparation of the selectors and the coating procedure for the manufacturing of the preparative chiral HPLC columns are described. A highly efficient trap for [ 11 C]HCN is presented. The whole radiosynthesis is automated, takes about 45 min and leads to more than 80% decay corrected overall radiochemical yield of each enantiomer (up to 2.5 GBq) with over 99% radiochemical, chemical and enantiomeric purity. The specific activity at the end of the synthesis is about 400 GBq/μmol

  1. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

    International Nuclear Information System (INIS)

    Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Watson, C.D.; Aramayo, G.A.

    1979-08-01

    An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations

  2. Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory Garden Carrier No. 2. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Box, W.D.; Klima, B.B.; Seagren, R.D.; Shappert, L.B.; Watson, C.D.; Aramayo, G.A.

    1979-08-01

    An analytical evaluation of the Oak Ridge National Laboratory Garden Carrier No. 2 was made to demonstrate its compliance with the regulations governing off-site radioactive material shipping packages. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of the evaluation show that the cask complies with the applicable regulations.

  3. Preparation and in vitro evaluation of ''no-carrier-added'' 18F-labeled biotin

    International Nuclear Information System (INIS)

    Najafi, A.; Peterson, A.

    1993-01-01

    This paper will describe the preparation of ''no-carrieradded'' 18 F-labeled biotin where the radiolabel bound to an aromatic moiety is described. This has been accomplished by preparation of [ 18 F]fluorobenzylbromide (yield 20-30%) and its reaction with biotin-LC-hydrazide. This yielded ''nocarrier-added'' radiolabeled biotin(5-10%) which was then purified by reversed phase HPLC. The pure product was found to bind to avidin, thereby demonstrating retention of its biological integrity. Thus this product is potentially useful for imaging tumor tissue following injection of avidin coupled MoAbs. (Author)

  4. Characterisation of spray dried soy sauce powders made by adding crystalline carbohydrates to drying carrier.

    Science.gov (United States)

    Wang, Wei; Zhou, Weibiao

    2015-02-01

    This study aimed to reduce stickiness and caking of spray dried soy sauce powders by introducing a new crystalline structure into powder particles. To perform this task, soy sauce powders were formulated by using mixtures of cellulose and maltodextrin or mixtures of waxy starch and maltodextrin as drying carriers, with a fixed carrier addition rate of 30% (w/v) in the feed solution. The microstructure, crystallinity, solubility as well as stickiness and caking strength of all the different powders were analysed and compared. Incorporating crystalline carbohydrates in the drying carrier could significantly reduce the stickiness and caking strength of the powders when the ratio of crystalline carbohydrates to maltodextrin was above 1:5 and 1:2, respectively. X-ray Diffraction (XRD) results showed that adding cellulose or waxy starch could induce the crystallinity of powders. Differential Scanning Calorimetry (DSC) results demonstrated that the native starch added to the soy sauce powders did not fully gelatinize during spray drying. Copyright © 2014 Elsevier Ltd. All rights reserved.

  5. Ionic Liquid-salt based aqueous biphasic system for quick separation of no-carrier-added 203Pb from proton irradiated natTl2CO3 target

    International Nuclear Information System (INIS)

    Choudhury, Dibyasree; Ghosh, Kaustab; Lahiri, Susanta; Sarkar, Kangkana; Naskar, Nabanita

    2016-01-01

    In the present study, no-carrier-added (NCA) 203 Pb was radiochemically separated from bulk Tl target applying the ABS composing of 4 M K 2 HPO 4 and 0.1 mL of different strengths of IL (bmim)Cl ranging from 40% to 80% (w/v). Bulk Tl was spiked with 200Tl (T 1/2 = 26.1 h). A separation condition was achieved with 70% IL concentration and with 10 min shaking and 10 min settling time, where ∼84% of NCA 203 Pb was extracted into the IL rich phase with ∼10% contamination from bulk Tl. Therefore, further studies, i.e. variation in shaking and settling time were carried out keeping the concentration of IL fixed at 70%

  6. Scandium/carbon filters for soft x rays

    NARCIS (Netherlands)

    Artioukov, IA; Kasyanov, YS; Kopylets, IA; Pershin, YP; Romanova, SA

    2003-01-01

    This Note deals with thin-film soft x-ray filters for operation at the wavelengths near carbon K edge (similar to4.5 nm). The filters were fabricated by magnetron sputtering deposition of thin layers of scandium (total thickness 0.1-0.2 mum) onto films of polypropylene (thickness 1.5 mum) and

  7. Complexing of scandium with eriochromecyanine R and cetyltrimethylammonium

    International Nuclear Information System (INIS)

    Tikhonov, V.N.; Samarkina, T.V.

    1978-01-01

    Complexing of scandium with eriochromecyanine R (ECC) in the presence of cetyltrimethylammonium (CTA) is studied. At optimum value of pH 6.2 a three-component complex of blue colour is forming with the Sc:ECC:CTA = 1:3:5 relation of compounds. Lambdasub(max) for the complex varies from 585 to 615 nm, molarabsorption coefficient is equal to (1.48+-0.02)x10 5 . A method of photometric determination of Sc with ECC and CTA is suggested. Even considerable quantities of Mg, Ca, Sr, Zn, Cd, La, Mn, Ni do not affect the Sc determination, whereas Cu, Be, Al, Ga, Fe(3) and Pd(2) affect it to a great degree even in relation of 1:1. Camouflaging substances such as fluorides, citrates, tartrates and EDTA prevent from scandium complexing, that is why they should not be used to increase the determination selectivity

  8. An electro-amalgamation approach to isolate no-carrier-added 177Lu from neutron irradiated Yb for biomedical applications

    International Nuclear Information System (INIS)

    Chakravarty, Rubel; Das, Tapas; Dash, Ashutosh; Venkatesh, Meera

    2010-01-01

    Introduction: A novel two-step separation process for the production of no-carrier-added (NCA) 177 Lu from neutron irradiated Yb target through an electrochemical pathway employing mercury-pool cathode has been developed. Methods: A two-cycle electrolysis procedure was adopted for separation of 177 Lu from 177 Lu/Yb mixture in lithium citrate medium. The influence of different experimental parameters on the separation process was investigated and optimized for the quantitative deposition of Yb in presence of 177 Lu. The first electrolysis was performed for 50 min in the 177 Lu/Yb feed solution at pH 6 applying a potential of 8 V using platinum electrode as anode and mercury as the cathode. The second electrolysis was performed under the same conditions using fresh electrodes. The radionuclidic and chemical purity of 177 Lu was determined by using gamma ray spectrometry and atomic absorption spectrometry. The suitability of 177 Lu for biomedical applications was ascertained by labeling 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid D-Phe 1 -Tyr 3 -octreotate(DOTA-TATE) with 177 Lu. Results: This process could provide NCA 177 Lu with >99.99% radionuclidic purity and an overall separation yield of ∼99% was achieved within 3-4 h. The Hg content in the product was determined to be 98% was obtained with DOTA-TATE under the optimized reaction conditions. Conclusions: An efficient strategy for the separation of NCA 177 Lu, suitable for biomedical applications, has been developed.

  9. Studies on the preparation of low-carrier Se-73,75 tracers for in vivo examinations

    International Nuclear Information System (INIS)

    Helfer, Andreas

    2013-01-01

    With the growing importance of positron emission tomography (PET) for in vivo imaging in diagnostic medicine there is great interest of developing new labelling methods for the positron emitter selenium-73. As attractive application an examination of a no-carrier-added (n.c.a.) preparation of the analogous tracer Sulindac Selenid and of the selenium containing compound Ebselen was examined with 73,75 Se. First of all a labelling strategy for Sulindac Selenid based on a protected precursor was developed. This precursor should further be transformed into the corresponding standard compound for chomatographic identification of the n.c.a. product. This, however, was not possible. An alternative synthesis method also did not result in a product. Thus, a radioactive labelling in case of Sulindac Selenid was not indicated in spite of a successful synthesis of a precursor. The preparation of Ebselen was performed as earlier described by a sequential one-pot synthesis with a yield of 46 %. An adaption of the reaction parameters to a radiosynthesis with 75 Se failed on the n.c.a. state and also after adding carrier to the reaction mixture. The desired product could, however, be prepared in a copper catalysed one-pot radiosynthesis for the first time under carrier-added conditions. Here, optimized conditions resulted in radiochemical yields of 60 ± 18 %. A no-carrier-added product could finally be achieved using sulphur as nonisotopic carrier in the reaction mixture. After optimisation of reaction parameters n.c.a. [ 75 Se]Ebselen could be synthesized with radiochemical yields of 55 ± 7 % within 4 h. Furthermore the desired product could be separated by RHPL-chromatography from its co-produced sulfur-analogue. After transferring the conditions to radiosyntheses with the positron emitter 73 Se, n.c.a. [ 73 Se]Ebselen could be achieved with a radiochemical yield of 22 ± 1 % and can now be used as a potential radiotracer in preclinical evaluation studies with respect to

  10. Pressure-induced structural change from hexagonal to fcc metal lattice in scandium trihydride

    International Nuclear Information System (INIS)

    Ohmura, A.; Machida, A.; Watanuki, T.; Aoki, K.; Nakano, S.; Takemura, K.

    2007-01-01

    We synthesized scandium hydrides by hydrogenation of a scandium foil with hydrogen fluid under high pressure at ambient temperature. Scandium dihydride (ScH 2 ) and trihydride (ScH 3 ) were prepared near 4 and 5 GPa, respectively. The hydrogenation process and pressure-induced structural changes in ScH 3 were investigated by synchrotron radiation X-ray diffraction measurements up to 54.7 GPa. A structural transition from hexagonal to the fcc lattice began at 30 GPa and was completed at 46 GPa via an intermediate state similar to those reported for other hexagonal trihydrides. The intermediate state was not interpreted in terms of a coexisting state for the low-pressure hexagonal and the high-pressure fcc structures. The onset transition pressure of ScH 3 supported the previously proposed relation that the hexagonal-fcc transition pressure is inversely proportional to the ionic radius of the trihydride

  11. Scandium: its occurrence, chemistry, physics, metallurgy, biology, and technology

    International Nuclear Information System (INIS)

    Horovitz, C.T.

    1975-01-01

    This book describes the following aspects of scandium: discovery and history, occurrence in nature, geochemistry and mineralogy, chemical, physical and technological properties, fabrication and metallurgy, its biological significance and toxicology, and its uses. (Extensive references for each chapter)

  12. No-carrier-added (NCA) N-(3-[18F]fluoropropyl)-N-norbuprenorphine and N-(3-[18F]fluoropropyl)-N-nordiprenorphine -synthesis, anatomical distribution in mice and rats, and tomographic studies in a baboon

    International Nuclear Information System (INIS)

    Lanqin Bai; Renrui Teng; Chyngyann Shiue; Wolf, A.P.; Dewey, S.L.; Holland, M.J.; Simon, E.J.

    1990-01-01

    N-(3-Fluoropropyl)-N-norbuprenorphine (3a) and N-(3-fluoropropyl)-N-nordiprenorphine (4a) were synthesized by N-alkylation of norbuprenorphine (1) and nordiprenorphine (2) with 1-bromo-3-fluoropropane. The corresponding no-carrier-added (NCA) N-(3-[ 18 F]fluoropropyl)-N-norbuprenorphine (3b) and N-(3-[ 18 F]fluoropropyl)-N-nordiprenorphine (4b) were synthesized by N-alkylation of 1 and 2 with NCA 1-[ 18 F]fluoro-3-iodopropane. In vitro studies indicate that in the absence of sodium chloride, compounds 3a, 4a, N-propyl-N-norbuprenorphine (5), buprenorphine and diprenorphine are reasonably comparable in binding affinity for opioid receptors. In the presence of 100 mM sodium chloride, however, compounds 3a, 4a and 5, are clearly less potent than buprenorphine and diprenorphine. The anatomical distribution study of compound 3b in mice shows radioactivity accumulating in bone. Rat studies of both compounds 3b and 4b indicate the specific distribution of these two radioligands within certain cortical and subcortical regions of rat brain. However, the absolute uptake of compound 4b in rat brain was only half that of compound 3b. PET studies of 3b in a baboon revealed specific binding of compound 3b in striatum and cerebellum. At 1 h after injection, ratios of specific/non-specific binding of 3b in striatum and cerebellum of a baboon were 1.9 and 1.7 respectively. (author)

  13. Effects of scandium and zirconium combination alloying on as-cast microstructure and mechanical properties of Al-4Cu-1.5Mg alloy

    Directory of Open Access Journals (Sweden)

    Xiang Qingchun

    2011-02-01

    Full Text Available The influences of minor scandium and zirconium combination alloying on the as-cast microstructure and mechanical properties of Al-4Cu-1.5Mg alloy have been experimentally investigated. The experimental results show that when the minor elements of scandium and zirconium are simultaneously added into the Al-4Cu-1.5Mg alloy, the as-cast microstructure of the alloy is effectively modified and the grains of the alloy are greatly refined. The coarse dendrites in the microstructure of the alloy without Sc and Zr additions are refined to the uniform and fine equiaxed grains. As the additions of Sc and Zr are 0.4% and 0.2%, respectively, the tensile strength, yield strength and elongation of the alloy are relatively better, which are 275.0 MPa, 176.0 MPa and 8.0% respectively. The tensile strength is increased by 55.3%, and the elongation is nearly raised three times, compared with those of the alloy without Sc and Zr additions.

  14. Thermoelectric material comprising scandium doped zinc cadmium oxide

    DEFF Research Database (Denmark)

    2016-01-01

    There is presented a composition of scandium doped Zinc Cadmium Oxide with the general formula ZnzCdxScyO which the inventors have prepared, and for which material the inventors have made the insight that it is particularly advantageous as an n-type oxide material, such as particularly advantageous...

  15. No differences in brain microstructure between young KIBRA-C carriers and non-carriers.

    Science.gov (United States)

    Hu, Li; Xu, Qunxing; Li, Jizhen; Wang, Feifei; Xu, Xinghua; Sun, Zhiyuan; Ma, Xiangxing; Liu, Yong; Wang, Qing; Wang, Dawei

    2018-01-02

    KIBRA rs17070145 polymorphism is associated with variations in memory function and the microstructure of related brain areas. Diffusion kurtosis imaging (DKI) as an extension of diffusion tensor imaging that can provide more information about changes in microstructure, based on the idea that water diffusion in biological tissues is heterogeneous due to structural hindrance and restriction. We used DKI to explore the relationship between KIBRA gene polymorphism and brain microstructure in young adults. We recruited 100 healthy young volunteers, including 53 TT carriers and 47 C allele carriers. No differences were detected between the TT homozygotes and C-allele carriers for any diffusion and kurtosis parameter. These results indicate KIBRA rs17070145 polymorphism likely has little or no effect on brain microstructure in young adults.

  16. Comparison of carrier-added [99mTc] EDTMP and carrier-free preparations of [99mTc] EDTMP and [99mTc] DPD

    International Nuclear Information System (INIS)

    Krcal, A.; Kletter, K.; Dudczak, R.; Pirich, C.; Mitterhauser, M.

    2002-01-01

    Full text: High uptake of bone-seeking radiopharmaceuticals in malignant bone lesions is a prerequisite for adequate bone scanning. Visual image analysis is impaired due to high soft-tissue activity with currently available [ 99m Tc]-EDTMP-kits. This study aimed to compare carrier-added [ 99m Tc]-EDTMP with carrier-free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD preparations in clinical routine. 15 μg and 150 μg perrhenic acid respectively were added to [ 99m Tc]-pertechnetate (>6 GBq in 3 ml phys. saline). The solution was then transferred into a vial, containing 1 mg of EDTMP, 3.6 mg stannous(II)chloride and 10 mg ascorbic acid under inert conditions. Under vigorous stirring the reaction mixture was heated to 45 o C for 10 min. After cooling down to room temperature the labelling mixture was sterile filtrated (millipore 0.22 μm). Quality control was performed using radio-ITLC (Whatman SG; acetone or ethanol: R f perrhenate/pertechnetate 0.87, colloid/product 0.05; phys. saline: R f colloid 0.00, perrhenate/pertechnetate and product 0.9) allowing rapid and efficient assessment of the product. Carrier free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD were prepared according to instructions of the manufacturer. Clinical studies were performed in 29 patients according to a routine bone scanning protocol by injecting 700-800 MBq of the respective tracer and whole body imaging 3 h thereafter. Radiochemical purity and radiochemical yield relied on various parameters such as concentration of carrier and reducing agent and reaction conditions (pH, reaction time, temperature). Means of the labelling yield were 22 % for the preparation using 150 μg of carrier (5 preparations), 80 % for the preparation using 15 μpg of carrier (10 preparations) and 91 % for the carrier free products (5 preparations). Radiochemical purity was >96 % in all experiments. Colloid was formed in very low amounts, and was completely removed by sterile filtration. In clinical studies quantitative analysis

  17. Effect of scandium on the phase composition and mechanical properties of ABM alloys

    Science.gov (United States)

    Molchanova, L. V.

    2010-09-01

    The effect of scandium on the composition and mechanical properties of ABM-1 alloys (Al-30% Be-5% Mg) is studied. The scandium content is varied from 0.1 to 0.5 wt %. It is established that, in the studied part of the Al-Be-Mg-Sc system, an aluminum solid solution (Al) and the ScBe13 compound are in equilibrium with a beryllium solid solution (Be). Magnesium dissolves in both the aluminum component and the ScBe13 compound. The strengthening effect related to the decomposition of the solid solution and the precipitation of Al3Sc cannot be extended to the strengthening of ABM-type alloys. Additions of 0.1-0.15 wt % Sc only weakly improve the mechanical properties of the alloys due to the refinement of beryllium-component grains. At high scandium contents, the strength increases insignificantly due to primary precipitation of ScBe13 and the plasticity decreases simultaneously.

  18. Influence of scandium on the pitting behaviour of Al-Zn-Mg-Cu alloys

    Energy Technology Data Exchange (ETDEWEB)

    Wloka, J. [Department of Materials Sciences, University of Erlangen-Nuremberg, Martensstrasse 7, D-91058 Erlangen (Germany); Virtanen, S. [Department of Materials Sciences, University of Erlangen-Nuremberg, Martensstrasse 7, D-91058 Erlangen (Germany)], E-mail: virtanen@ww.uni-erlangen.de

    2007-11-15

    In this paper the influence of small scandium additions (<0.26 wt.%) on the corrosion properties of the high-strength Al-Zn-Mg-Cu alloy AA7010 is investigated. The addition of scandium (in combination with the grain refiner Zr) leads to the formation of Al{sub 3}Sc{sub x}Zr{sub 1-x} phases. These coarse particles disturb the grain structure near the particle/matrix interface, which facilitates the initiation of localized corrosion in potentio-dynamic scans. Microelectrochemical investigations revealed a slightly cathodic character of these particles and a passive range beyond the breakdown potential of the matrix. Mass loss measurements show that the addition of scandium increases the mass loss during the initial period. The corrosion morphology was investigated with optical and scanning electron microscopy. The composition of the phases was determined with energy-dispersive X-ray analysis. Micro-capillary measurements were performed to investigate the electrochemical properties of single phases surrounded by matrix.

  19. An electro-amalgamation approach to isolate no-carrier-added 177Lu from neutron irradiated Yb for biomedical applications.

    Science.gov (United States)

    Chakravarty, Rubel; Das, Tapas; Dash, Ashutosh; Venkatesh, Meera

    2010-10-01

    A novel two-step separation process for the production of no-carrier-added (NCA) (177)Lu from neutron irradiated Yb target through an electrochemical pathway employing mercury-pool cathode has been developed. A two-cycle electrolysis procedure was adopted for separation of (177)Lu from (177)Lu/Yb mixture in lithium citrate medium. The influence of different experimental parameters on the separation process was investigated and optimized for the quantitative deposition of Yb in presence of (177)Lu. The first electrolysis was performed for 50 min in the (177)Lu/Yb feed solution at pH 6 applying a potential of 8 V using platinum electrode as anode and mercury as the cathode. The second electrolysis was performed under the same conditions using fresh electrodes. The radionuclidic and chemical purity of (177)Lu was determined by using gamma ray spectrometry and atomic absorption spectrometry. The suitability of (177)Lu for biomedical applications was ascertained by labeling 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid D-Phe(1)-Tyr(3)-octreotate(DOTA-TATE) with (177)Lu. This process could provide NCA (177)Lu with >99.99% radionuclidic purity and an overall separation yield of ∼99% was achieved within 3-4 h. The Hg content in the product was determined to be 98% was obtained with DOTA-TATE under the optimized reaction conditions. An efficient strategy for the separation of NCA (177)Lu, suitable for biomedical applications, has been developed. Copyright © 2010 Elsevier Inc. All rights reserved.

  20. Automated no-carrier-added synthesis of [1-{sup 11}C]-labeled D- and L-enantiomers of lactic acid

    Energy Technology Data Exchange (ETDEWEB)

    Drandarov, Konstantin [Center for Radiopharmaceutical Sciences, Swiss Federal Institute of Technology Zurich, University Hospital Zuerich, CH-8091 Zurich (Switzerland); Paul Scherrer Institute, CH-5232 Villigen (Switzerland); Schubiger, P. August [Center for Radiopharmaceutical Sciences, Swiss Federal Institute of Technology Zurich, University Hospital Zuerich, CH-8091 Zurich (Switzerland); Paul Scherrer Institute, CH-5232 Villigen (Switzerland); Westera, Gerrit [Center for Radiopharmaceutical Sciences, Swiss Federal Institute of Technology Zurich, University Hospital Zuerich, CH-8091 Zurich (Switzerland) and Paul Scherrer Institute, CH-5232 Villigen (Switzerland)]. E-mail: gerrit.westera@usz.ch

    2006-12-15

    The first purely chemical method for automated no-carrier-added synthesis of [1-{sup 11}C]-labeled D(R)- and L(S)-2-hydroxypropanoic acid (lactic acid) was developed for experimental neurophysiology studies and position emission tomography (PET) diagnosis. Starting from sodium 1-hydroxyethanesulfonate and [{sup 11}C]HCN (trapped as [{sup 11}C]KCN) the intermediate DL-(R,S)-[1-{sup 11}C]-2-hydroxypropanenitrile was prepared. Its rapid acid hydrolysis gave DL-(R,S)-[1-{sup 11}C]lactic acid, which was isolated by preparative reversed phase HPLC and automatically injected on a second preparative C{sub 18} HPLC column coated with a chiral selector, where both [1-{sup 11}C]lactic acid enantiomers were separated by chiral ligand-exchange chromatography. Two novel chiral selectors for HPLC enantiomeric separation of {alpha}-hydroxy acids, namely D(R)- or L(S)-2-amino-3-methyl-3-(5-phenylpentylsulfanyl)-butanoic acid were utilized for the preparative HPLC separation of the [1-{sup 11}C]lactic acid enantiomers. The preparation of the selectors and the coating procedure for the manufacturing of the preparative chiral HPLC columns are described. A highly efficient trap for [{sup 11}C]HCN is presented. The whole radiosynthesis is automated, takes about 45 min and leads to more than 80% decay corrected overall radiochemical yield of each enantiomer (up to 2.5 GBq) with over 99% radiochemical, chemical and enantiomeric purity. The specific activity at the end of the synthesis is about 400 GBq/{mu}mol.

  1. Complexometric determination of scandium and aluminium

    International Nuclear Information System (INIS)

    Tikhonov, V.N.

    1980-01-01

    Described is the complexometric determination of scandium and aluminium by the method of reverse titration of EDTA excess by indium salt solution in the presence of the xylenol orange indicator. For the method selectivity increase fluorides are used as a camouflage substance at low pH values (2.5-3.0). The excess fluoride-ions preventing titration are bound by boric acid. Y, Tb, Ti, Zr, Cu, Zn, V, Mo, Co, Cr prevent the determination of Sc and Al

  2. Use of scandium ionic associates with salicylic- or 2-phenylquinoline-4-carboxylic acid and rhodamine C

    Energy Technology Data Exchange (ETDEWEB)

    Kononenko, L.I.; Bel' tyukova, S V; Drobyazko, V N; Poluehktov, N S [AN Ukrainskoj SSR, Kiev. Inst. Obshchej i Neorganicheskoj Khimii; AN Ukrainskoj SSR, Odessa. Inst. Obshchej i Neorganicheskoj Khimii)

    1975-09-01

    With salicylic or 2-phenylquinoline-4-carboxylic acid and rhodamine C scandium forms ion associations whose benzene solutions are capable of luminescence. Optimum conditions for the formation of complexes and the composition of the complex with the ratio of Sc:acid:rhodamine C = 1:2:1 are established. A possibility of luminescence determination of scandium in the presence of rare earths is shown.

  3. Hardening mechanisms of spray formed Al-Zn-Mg-Cu alloys with scandium and other elemental additions

    International Nuclear Information System (INIS)

    Sharma, M.M.; Amateau, M.F.; Eden, T.J.

    2006-01-01

    The hardening mechanisms in spray formed Al-Zn-Mg-Cu alloys with additions of chromium, zinc and scandium were studied. The microstructure of the spray formed alloys was analyzed by transmission electron microscopy. A range of tensile strengths were achieved, and varied based on elemental additions, and second phase particle strengthening. To explain the significantly higher strength in one alloy with scandium, theoretical results due to the yield stress of Al-Zn-Mg-Cu alloys as a function of volume fraction and precipitate particle size, were compared to experimental data. Both the possibilities of coherency and order strengthening are examined. The significant additional hardening achieved in the alloy with scandium is attributed to small ordered particles of Al 3 Sc, which precipitated during aging

  4. Motor carrier evaluation program

    International Nuclear Information System (INIS)

    Portsmouth, James

    1992-01-01

    The U.S. Department of Energy-Headquarters (DOE-HQ), Transportation Management Program (TMP) has the overall responsibility to provide a well-managed transportation program for the safe, efficient, and economical transportation of DOE-owned materials. The DOE-TMP has established an excellent safety record in the transportation of hazardous materials including radioactive materials and radioactive wastes. This safety record can be maintained only through continued diligence and sustained effort on the part of the DOE-TMP, its field offices, and the contractors' organizations. Key elements in the DOE'S effective hazardous and radioactive materials shipping program are (1) integrity of packages, (2) strict adherence to regulations and procedures, (3) trained personnel, (4) complete management support, and (5) use of the best commercial carriers. The DOE Motor Carrier Evaluation Program was developed to better define the criteria and methodology needed to identify motor carriers for use in the transportation of Highway Route Controlled Quantities (HRCQ), Truck Load (TL) quantities of radioactive materials, hazardous materials and waste. (author)

  5. The BRST quantization and the no-ghost theorem for AdS3

    International Nuclear Information System (INIS)

    Asano, Masako; Natsuume, Makoto

    2003-01-01

    In our previous papers, we prove the no-ghost theorem without light-cone directions. We point out that our results are valid for more general backgrounds. In particular, we prove the no-ghost theorem for AdS 3 in the context of the BRST quantization (with the standard restriction on the spin). We compare our BRST proof with the OCQ proof and establish the BRST-OCQ equivalence for AdS 3 . The key in both approaches lies in the certain structure of the matter Hilbert space as a product of two Verma modules. We also present the no-ghost theorem in the most general form. (author)

  6. Incommensurate composite crystal structure of scandium-II

    International Nuclear Information System (INIS)

    Fujihisa, Hiroshi; Gotoh, Yoshito; Yamawaki, Hiroshi; Sakashita, Mami; Takeya, Satoshi; Honda, Kazumasa; Akahama, Yuichi; Kawamura, Haruki

    2005-01-01

    The long-unknown crystal structure of the high pressure phase scandium-II was solved by powder x-ray diffraction and was found to have tetragonal host channels along the c axis and guest chains that are incommensurate with the host, as well as the high pressure phases of Ba, Sr, Bi, and Sb. The pressure dependences of the lattice constants, the incommensurability, the atomic distances, and the atomic volume were investigated

  7. Preparation of no-carrier-added [1-11C]ethylene and [1-11C]1,2-dibromoethane as new labelling agents

    International Nuclear Information System (INIS)

    Shah, F.; Pike, V.W.; Dowsett, K.

    1997-01-01

    A method is described for the preparation of NCA [1- 11 C] ethylene based on the passage of [1- 11 C]ethanol over heated (550 o C) quartz glass in a stainless steel tube (in preference to dehydration by catalysis on γ-alumina or pyrolysis). The [1- 11 C]ethanol is prepared from cyclotron-produced NCA [ 11 C]carbon dioxide by 11 C-carboxylation of methylmagnesium bromide, freshly prepared in dibutyl ether, and reduction of the adduct with lithium aluminium hydride in diglyme. The use of involatile solvents avoids the formation of carrier ethylene and radioactive and stable diethyl ether by cracking processes over the heated catalyst. The preparation takes 21 min from the end of radionuclide production and has a radiochemical yield of 44%, decay-corrected from [ 11 C]carbon dioxide. NCA [1- 11 C] ethylene is converted quantitatively into [1- 11 C]1,2-dibromoethane when collected in a solution of bromine in carbon tetrachloride. The NCA [1- 11 C]ethylene and [1- 11 C]1,2-dibromoethane may serve as new and useful labelling agents. (Author)

  8. No-carrier-added (NCA) N-(3-( sup 18 F)fluoropropyl)-N-norbuprenorphine and N-(3-( sup 18 F)fluoropropyl)-N-nordiprenorphine -synthesis, anatomical distribution in mice and rats, and tomographic studies in a baboon

    Energy Technology Data Exchange (ETDEWEB)

    Bai, Lanqin; Teng, Renrui; Shiue, Chyngyann; Wolf, A P; Dewey, S L [Brookhaven National Lab., Upton, NY (USA); Holland, M J; Simon, E J [New York Univ., NY (USA). Medical Center

    1990-01-01

    N-(3-Fluoropropyl)-N-norbuprenorphine (3a) and N-(3-fluoropropyl)-N-nordiprenorphine (4a) were synthesized by N-alkylation of norbuprenorphine (1) and nordiprenorphine (2) with 1-bromo-3-fluoropropane. The corresponding no-carrier-added (NCA) N-(3-({sup 18}F)fluoropropyl)-N-norbuprenorphine (3b) and N-(3-({sup 18}F)fluoropropyl)-N-nordiprenorphine (4b) were synthesized by N-alkylation of 1 and 2 with NCA 1-({sup 18}F)fluoro-3-iodopropane. In vitro studies indicate that in the absence of sodium chloride, compounds 3a, 4a, N-propyl-N-norbuprenorphine (5), buprenorphine and diprenorphine are reasonably comparable in binding affinity for opioid receptors. In the presence of 100 mM sodium chloride, however, compounds 3a, 4a and 5, are clearly less potent than buprenorphine and diprenorphine. The anatomical distribution study of compound 3b in mice shows radioactivity accumulating in bone. Rat studies of both compounds 3b and 4b indicate the specific distribution of these two radioligands within certain cortical and subcortical regions of rat brain. However, the absolute uptake of compound 4b in rat brain was only half that of compound 3b. PET studies of 3b in a baboon revealed specific binding of compound 3b in striatum and cerebellum. At 1 h after injection, ratios of specific/non-specific binding of 3b in striatum and cerebellum of a baboon were 1.9 and 1.7 respectively. (author).

  9. Reactor production and separation of no-carrier added 32P for medical applications

    International Nuclear Information System (INIS)

    Vimalnath, K.V.; Shetty, P.; Rajeswari, A.; Chirayil, V.; Chakraborty, S.; Dash, A.

    2014-01-01

    Phosphorous-32 is an attractive and widely used therapeutic radionuclide owing to its favorable nuclear characteristics. The major application of 32 P is the treatment option for a distinct subgroup of elderly patients with polycythemia vera and leukemia. The tremendous prospects associated with the use of 32 P along with the challenge of providing 32 P of acceptable specific activity and purity amenable for in vivo therapy, led to development of a 32 P production strategy. The 32 S(n,p) 32 P route of production provide the scope of obtaining high specific activities or no carrier added (NCA) 32 P. In a typical batch of 14 nos. of neutron irradiated Al containers, each containing 18 g of sulphur, were processed. In the quest for an effective separation method to isolate micro gram of 32 P formed during the neutron irradiation of sulphur, the prospect of using distillation under reduced pressure to achieve complete removal of sulfur seemed to be an effective proposition and motivated us to adopt. The experimental parameters that influence the distillation were identified and a careful control has been exercised to ensure complete removal of sulphur from 32 P within reasonable time period. The 32 P remained in the distillation flask was quantitatively collected by leaching with 0.05 N HCl with gentle heating at 80℃ for 3 hours. In the light of the perceived need to remove cationic impurities from the 32 P leachate, it was passed through an ion-exchange chromatography column containing a cation exchange resin (Dowex 50 x 8 H + , 100-200 mesh) wherein all the cationic impurities get trapped and H 3 32 PO 4 solution was collected as effluent. Recognizing the fact that H 3 32 PO 4 produced is to be used for clinical applications, a thorough quality assessment was carried out. Radionuclidic purity was ascertained by a measurement of its half-life. In order to establish the absence of extraneous gamma emitting radionuclide impurities, gamma spectrum of the appropriately

  10. An electro-amalgamation approach to isolate no-carrier-added {sup 177}Lu from neutron irradiated Yb for biomedical applications

    Energy Technology Data Exchange (ETDEWEB)

    Chakravarty, Rubel; Das, Tapas [Radiopharmaceuticals Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Dash, Ashutosh, E-mail: adash@barc.gov.i [Radiopharmaceuticals Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Venkatesh, Meera [Radiopharmaceuticals Division, Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2010-10-15

    Introduction: A novel two-step separation process for the production of no-carrier-added (NCA) {sup 177}Lu from neutron irradiated Yb target through an electrochemical pathway employing mercury-pool cathode has been developed. Methods: A two-cycle electrolysis procedure was adopted for separation of {sup 177}Lu from {sup 177}Lu/Yb mixture in lithium citrate medium. The influence of different experimental parameters on the separation process was investigated and optimized for the quantitative deposition of Yb in presence of {sup 177}Lu. The first electrolysis was performed for 50 min in the {sup 177}Lu/Yb feed solution at pH 6 applying a potential of 8 V using platinum electrode as anode and mercury as the cathode. The second electrolysis was performed under the same conditions using fresh electrodes. The radionuclidic and chemical purity of {sup 177}Lu was determined by using gamma ray spectrometry and atomic absorption spectrometry. The suitability of {sup 177}Lu for biomedical applications was ascertained by labeling 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid D-Phe{sup 1}-Tyr{sup 3}-octreotate(DOTA-TATE) with {sup 177}Lu. Results: This process could provide NCA {sup 177}Lu with >99.99% radionuclidic purity and an overall separation yield of {approx}99% was achieved within 3-4 h. The Hg content in the product was determined to be <1 ppm. Radiolabeling yield of >98% was obtained with DOTA-TATE under the optimized reaction conditions. Conclusions: An efficient strategy for the separation of NCA {sup 177}Lu, suitable for biomedical applications, has been developed.

  11. Solvent extraction of tricomponent complexes of zirconium and scandium with salicylic acid and collidine

    International Nuclear Information System (INIS)

    Kochetkova, S.K.; Fadeeva, V.I.; Kalistratova, V.P.

    1976-01-01

    Extraction of tricomponent compounds of zirconium and scandium with salicylic acid (Sal) and collidine (Col) has been studied. Addition of Col widens considerably the pH range of maximum extraction of zirconium salicylate and makes it possible to extract quantitatively both zirconium and scandium in the following pH range: scandium at pH 3.8-5.2; zirconium at pH 2-4. Optimum concentrations of salicylic acid and collidine are 0.05 mol/l and 0.375 mol/l, respectively. The composition of the complexes being extracted has been studied by the shift equilibrium method. Chloroform extracts complexes having the ratio Zr:Sal:Col=1:2:1(pH=3); Sc:Sal:Col=1:3:1(pH=4), and 1:2:1(pH=5). The composition of the complexes being formed is assumed to be [Zr(OH) 3 (HSal) 2 ] - [ColH + ] (pH=3); Sc(HSal) 3 xCol (pH=4.0); Sc(OH)(HSal) 2 xCol (pH=5.0). Extraction of collidine-salicylate complexes of Hf, Th, La, and Y under the conditions of optimum extraction of zirconium and scandium has been investigated when concentration of Zr and Sc in the solution is 3.0.10μ- 5 -1.37.10 -4 mol/l, respectively. It has been shown that hafnium is extracted quantitatively (95-100%) at pH 2.3-4.6; thorium at pH 3.0-6.4; 60% of yttrium is extracted at pH 4.0-4.8; 25% of lanthanum is extracted at pH 3.3-4.9. At pH 2.0 it is possible to separate Zr from Sc,Y, and La; at pH 1.4-1.5 from small amounts of Hf and Tn. Separation of zirconium, from small amounts of hafnium, 10-fold amounts of thorium, 100-fold amounts of scandium and lanthanum is also possible

  12. Solvent extraction of tricomponent complexes of zirconium and scandium with salicylic acid and collidine

    Energy Technology Data Exchange (ETDEWEB)

    Kochetkova, S K; Fadeeva, V I; Kalistratova, V P [Moskovskij Gosudarstvennyj Univ. (USSR)

    1976-01-01

    Extraction of tricomponent compounds of zirconium and scandium with salicylic acid (Sal) and collidine (Col) has been studied. Addition of Col widens considerably the pH range of maximum extraction of zirconium salicylate and makes it possible to extract quantitatively both zirconium and scandium in the following pH range: scandium at pH 3.8-5.2; zirconium at pH 2-4. Optimum concentrations of salicylic acid and collidine are 0.05 mol/l and 0.375 mol/l, respectively. The composition of the complexes being extracted has been studied by the shift equilibrium method. Chloroform extracts complexes having the ratio Zr:Sal:Col=1:2:1(pH=3); Sc:Sal:Col=1:3:1(pH=4), and 1:2:1(pH=5). The composition of the complexes being formed is assumed to be (Zr(OH)/sub 3/(HSal)/sub 2/)/sup -/(ColH/sup +/) (pH=3); Sc(HSal)/sub 3/xCol (pH=4.0); Sc(OH)(HSal)/sub 2/xCol (pH=5.0). Extraction of collidine-salicylate complexes of Hf, Th, La, and Y under the conditions of optimum extraction of zirconium and scandium has been investigated when concentration of Zr and Sc in the solution is 3.0.10..mu..-/sup 5/-1.37.10/sup -4/ mol/l, respectively. It has been shown that hafnium is extracted quantitatively (95-100%) at pH 2.3-4.6; thorium at pH 3.0-6.4; 60% of yttrium is extracted at pH 4.0-4.8; 25% of lanthanum is extracted at pH 3.3-4.9. At pH 2.0 it is possible to separate Zr from Sc,Y, and La; at pH 1.4-1.5 from small amounts of Hf and Tn. Separation of zirconium, from small amounts of hafnium, 10-fold amounts of thorium, 100-fold amounts of scandium and lanthanum is also possible.

  13. Preparation of carrier-free radioactive thallium for medical use

    International Nuclear Information System (INIS)

    Comar, D.; Crouzel, C.

    1975-01-01

    Radioactive thallium for medical use have been prepared by proton or deuteron bombardment of HgO or metallic Hg. The carrier free thallium is separated from mercury by ether extraction of the chloride. The yield of production for the isotopes 198m to 202 is given for different energies of protons and deuterons. The irradiated substances consisted of red mercury oxide containing less than 1 ppm iron, and high-purity (99.999%) metallic mercury. The red mercury oxide targets were irradiated with 15 MeV deuterons (M.R.C. cyclotron, Hammersmith Hospital-London and Saclay Van de Graff tandem) or 50 and 14 MeV protons (Grenoble Nuclear Physics Institute cyclotron and S.H.F.J. compact cyclotrons). The metallic mercury target was irradiated with 14, 16 and 20 MeV protons (S.H.F.J. compact cyclotron and Saclay variable-energy cyclotron). The particle current never exceeded 10 μA for irradiation times between 15 minutes and a few hours. (F.Gy.)

  14. Motor carrier evaluation program plan

    International Nuclear Information System (INIS)

    Portsmouth, J.H.; Maxwell, J.E.; Boness, G.O.; Rice, L.E.

    1991-04-01

    The US Department of Energy (DOE) Transportation Management Program (TMP) has established a program to assist the DOE field offices and their contractors in evaluating the motor carriers used to transport DOE-owned hazardous and radioactive materials. This program was initiated to provide the DOE field offices with the tools necessary to help ensure, during this period of motor carrier deregulation, that only highly qualified carriers transport radioactive and hazardous commodities for the DOE. This program will assist DOE in maintaining their excellent performance record in the safe transportation of hazardous commodities. The program was also developed in response to public concern surrounding the transportation of hazardous materials. Representatives of other federal agencies, states, and tribal governments, as well as the news media, have expressed concern about the selection and qualification of carriers engaged in the transportation of Highway Route-Controlled Quantities (HRCQ) and Truckload (TL) quantities of radioactive material for the DOE. 8 refs

  15. Radioactive dust from No. 5 Fukuryu Maru

    Energy Technology Data Exchange (ETDEWEB)

    Yamatera, H

    1954-01-01

    Analysis of radioactive dust collected on board No. 5 Fukuryu Maru were done by chemical separation and measurement of ..gamma..-ray energy and half-life of each species. Results are summarized as follows, radioactive nuclide and approximate percentage of radioactivity given: /sup 103/Ru, 4.3 to 57; /sup 106/Ru, 1.4; /sup 129/Te, 1.3; /sup 131/I, 4.5; /sup 132/I, 1.0; /sup 132/Te, 1.0; etc.

  16. Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

    International Nuclear Information System (INIS)

    Rohe, M.J.; Rankin, W.N.; Postles, R.L.

    1985-01-01

    Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

  17. Extraction of scandium salicylate by tetraethyldiamidoheptyl phosphate

    Energy Technology Data Exchange (ETDEWEB)

    Kamenev, V F; Fadeeva, V I; Zyk, N V [Moskovskij Gosudarstvennyj Univ. (USSR). Kafedra Analiticheskoj Khimii

    1976-11-01

    Scandium salicylate is extracted with chloroform in a narrow pH range 3-4 and at the maximum concentration of salicylic acid (H/sub 2/A) in an organic phase, the distribution coefficient reaches 0.1. In the presence of tetraethyldiamideheptylphosphate (DAHP) the zone of maximum extraction grows and the distribution coefficient increases. The ratio of the components in the complex extracted is Sc:H/sub 2/A:DAHPh=1:3:2. The extraction constant is Ksub(ex)=(2.00+-0.02).

  18. Synthesis of no-carrier-added and carrier-added YF-labelled haloperidol

    Energy Technology Data Exchange (ETDEWEB)

    Farrokhzad, S; Diksic, M

    1985-07-01

    Fluorine-18 labelled haloperidol ( YF-HP) was synthesized by a fluorine-fluorine exchange reaction on haloperidol, fluorine-chlorine exchange on a chloro-analog of haloperidol, and from YF-labelled p-fluorobenzonitrile prepared by two different exchange reactions. Nucleophilic fluorine was used in the form of tetra n-butylammonium fluoride. The overall radiochemical yield, expressed at the end of syntheses was 5% for exchange in haloperidol and about 2%-3% for exchange in chloroanalog in a 40 min synthesis (from the end of the irradiation). Specific activities up to 1 Ci/mmol for haloperidol and up to 5000 Ci/mmol for chloro-analog as substrates were obtained. The syntheses using p-substituted chloro-and nitro-benzonitriles as starting materials for the exchange reaction gave a product with an average specific activity of about 2000 Ci/mmol and in general an overall radiochemical yield of 5%-10%. Purification of ( YF)haloperidol was done by HPLC on a C-18 column. The radiochemical purity as assessed by thin layer radiochromatography (TLRC) of the final product was at least 95%, with high chemical purity.

  19. Ternary scandium and transition metals germanides

    International Nuclear Information System (INIS)

    Kotur, B.Ya.

    1992-01-01

    Brief review of data on phase diagram of ternary Sc-Me-Ge systems (Me-d - , f-transition element) is given. Isothermal sections at 870 and 1070 K of 17 ternary systems are plotted. Compositions and their structural characteristics are presented. Variability of crystal structure is typical for ternary scandium germanides: 70 compounds with the studied structure belong to 23 structural types. Ternary germanides isostructural to types of Sm 4 Ge 4 , ZrCrSi 2 , ZrNiAl, ScCeSi, TiNiSi U 4 Re 7 Si 6 145 compounds from 70 under investigation are mostly formed in studied systems

  20. Radioactive Substances Act, 1957, No 5

    International Nuclear Information System (INIS)

    1982-01-01

    This Act as amended regulates the possession, sale and use of radioactive materials and irradiating apparatus. It sets up a Radiological Advisory Council to advise the competent authorities on questions within the scope of the Act, also with a view to radiation protection. The Council's rules of procedure are laid down. The Act also provides that, subject to prescribed exemptions, no person may hold, use or sell radioactive materials without a licence. (NEA) [fr

  1. Scandium interaction with diantipyrylmethane homologues and 2-(n-sulphophenylazo)-1,8-dihydroxynaphthalene-3,6 sodium disulphonate

    Energy Technology Data Exchange (ETDEWEB)

    Ganago, L I; Alinovskaya, L A [AN Belorusskoj SSR, Minsk. Inst. Fiziki Tverdogo Tela i Poluprovodnikov

    1979-01-01

    The reactions of scandium with homologs of diantipyrilmethane (DAM)-propyldiantipyrilmethane (PDAM) and phenyldiantipyrilmethane (PhDAM) - are studied. The relationship of components in the complexes formed is found, and chemism of their formation is established. The complexes Sc-SPADNE (sodium salt 2-(n-sulphophenylazo)-1,8-dioxynaphthalene-3,6-disulphonic acid) are shown to form within a wide pH range. The maximum yield of complexes is observed at 6.0-7.5 pH. By the ion-exchange method the anion character of heteroligand scandium complexes is established. The complex Sc-SPADNE-PDAM is faster as compared with the complexes Sc-SPADNE-DAM and Sc-SPADNE-PhDAM. The decrease in amine excess and increase in the sensitivity of heteroligand formation of the complexes of scandium with SPADNE and PDAM make them better suited for analysis. The technique is developed for the determination of Sc/sub 2/O/sub 3/ in perovskites using the complete differential spectrophotometry method.

  2. Determination of scandium with salicylaldehyde and 2-aminobenzenearsonic acid

    International Nuclear Information System (INIS)

    Farias, P.A.M.; Hainberger, L.; Andrade, H.A.S.

    1984-01-01

    A new method for the spectrophotometric determination of scandium by means of a coloured complex formed with salicylaldehyde and 2-aminobenzenearsonic acid is described. Lambert-Beer's law is followed in the range of 0.2 - 2.0 μg/ml of the final solution. The maximum amounts of 39 ions that may be present without interfering in the method are listed. (Author) [pt

  3. Thermodynamic and kinetic study of scandium(III) complexes of DTPA and DOTA: a step toward scandium radiopharmaceuticals.

    Science.gov (United States)

    Pniok, Miroslav; Kubíček, Vojtěch; Havlíčková, Jana; Kotek, Jan; Sabatie-Gogová, Andrea; Plutnar, Jan; Huclier-Markai, Sandrine; Hermann, Petr

    2014-06-23

    Diethylenetriamine-N,N,N',N'',N''-pentaacetic acid (DTPA) and 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA) scandium(III) complexes were investigated in the solution and solid state. Three (45)Sc NMR spectroscopic references suitable for aqueous solutions were suggested: 0.1 M Sc(ClO4)3 in 1 M aq. HClO4 (δSc =0.0 ppm), 0.1 M ScCl3 in 1 M aq. HCl (δSc =1.75 ppm) and 0.01 M [Sc(ox)4](5-) (ox(2-) = oxalato) in 1 M aq. K2C2O4 (δSc =8.31 ppm). In solution, [Sc(dtpa)](2-) complex (δSc = 83 ppm, Δν = 770 Hz) has a rather symmetric ligand field unlike highly unsymmetrical donor atom arrangement in [Sc(dota)](-) anion (δSc = 100 ppm, Δν = 4300 Hz). The solid-state structure of K8[Sc2(ox)7]⋅13 H2O contains two [Sc(ox)3](3-) units bridged by twice "side-on" coordinated oxalate anion with Sc(3+) ion in a dodecahedral O8 arrangement. Structures of [Sc(dtpa)](2-) and [Sc(dota)](-) in [(Hguanidine)]2[Sc(dtpa)]⋅3 H2O and K[Sc(dota)][H6 dota]Cl2⋅4 H2O, respectively, are analogous to those of trivalent lanthanide complexes with the same ligands. The [Sc(dota)](-) unit exhibits twisted square-antiprismatic arrangement without an axial ligand (TSA' isomer) and [Sc(dota)](-) and (H6 dota)(2+) units are bridged by a K(+) cation. A surprisingly high value of the last DOTA dissociation constant (pKa =12.9) was determined by potentiometry and confirmed by using NMR spectroscopy. Stability constants of scandium(III) complexes (log KScL 27.43 and 30.79 for DTPA and DOTA, respectively) were determined from potentiometric and (45)Sc NMR spectroscopic data. Both complexes are fully formed even below pH 2. Complexation of DOTA with the Sc(3+) ion is much faster than with trivalent lanthanides. Proton-assisted decomplexation of the [Sc(dota)](-) complex (τ1/2 =45 h; 1 M aq. HCl, 25 °C) is much slower than that for [Ln(dota)](-) complexes. Therefore, DOTA and its derivatives seem to be very suitable ligands for scandium

  4. Potential for photocatalytic degradation of the potassic diclofenac using scandium and silver modified titanium dioxide thin films

    International Nuclear Information System (INIS)

    Ciola, R.A.; Oliveira, C.T.; Lopes, S.A.; Cavalheiro, A.A.

    2011-01-01

    The potential for photocatalytic degradation of the potassic diclofenac drug was investigated using titanium dioxide thin films modified with two modifier types, scandium and silver, both prepared by Sol-Gel method. It was demonstrated by UVVis spectroscopy analysis of the solutions containing the drug, under UV-A light irradiation that the degradation efficiency of the titanium dioxide photocatalyst is dependent of the semiconductor nature and that the scandium accelerates the first step of the degradation when compared to the silver. This result seems to be related to the redox potential of the electron-hole pair, once the scandium modifying sample generates a p type semiconductor that reduces the band gap. The extra holes attract more strongly the chorine ion present in diclofenac and leading to the releasing more easily. However, after the first byproducts degradation the following steps are not facilitated, making the silver modifying more advantageous. (author)

  5. The influence of the diluent nature on scandium extraction by the phenol-formaldehyde resol oligomer yarrezin B

    International Nuclear Information System (INIS)

    Semenov, S.A.; Valkina, E.M.; Reznik, A.M.

    1996-01-01

    The paper studies the effect of diluent nature on scandium extraction by Yarrezin B phenol-formaldehyde resol oligomer using n-octan, toluene, chloroform, n-octanol and kerosene as an example. Correlation coefficients of dependences of scandium distribution factor on some parameters of diluents are calculated. Possibility to use some parameters of diluents to predict their effect on extraction indices is determined. Hildebrandt solubility parameter of extracting agent and parameters of extracting agent-diluent interaction according to Flory-Haggins are calculated. 13 refs., 2 figs., 4 tabs

  6. The effects of aluminum or scandium on the toughness, density and ...

    African Journals Online (AJOL)

    The effects of the substitution of aluminum or scandium on the density, toughness as well as the stability of the phases formed by such an addition on platinum, iridium, rhodium and palladium metals were evaluated with the density functional quantum mechanical calculation methods. All the metals had four atoms per ...

  7. Synthesis and characterization of scandium oxide microspheres for their application in radioactive particle tracking experiments

    International Nuclear Information System (INIS)

    Goswami, Sunil; Biswal, Jayashree; Pant, H.J.; Pillai, K.T.; Bamankar, Y.R.

    2012-01-01

    Radioactive particle tracking (RPT) technique, proposed by Lin et al., is a noble technique for understanding mixing mechanisms of fluids and; evaluation and improvement of design of multiphase flow systems. In RPT technique the motion of a single radioactive particle is tracked in a flow system using an array of strategically mounted NaI(Tl) scintillation detectors around the system. The gamma emitting radioactive tracer particle being tracked is designed to be hydrodynamically similar to that of the phase being traced

  8. Complexometric determination of aluminium and scandium using fluorides as masking agent at low pH value

    International Nuclear Information System (INIS)

    Tikhonov, V.N.

    1978-01-01

    A complexometric method is suggested to determine Al and Sc by back titration of Bi(NO 3 ) 3 solution with xylenol orange indicator at low pH values. To increase selectivity fluoride additions were used which were masked by boron acid at the end titration point. EDTA was used as a complexing agent. Metals which create at low pH values stable complexes with EDTA undestroyed by fluoride, do not interfere with Al and Sc determination. Scandium is shown to be determined more selectively than aluminium

  9. PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER

    Science.gov (United States)

    King, E.L.

    1959-04-28

    The separation and purification of plutonium from the radioactive elements of lower atomic weight is described. The process of this invention comprises forming a 0.5 to 2 M aqueous acidffc solution containing plutonium fons in the tetravalent state and elements with which it is normally contaminated in neutron irradiated uranium, treating the solution with a double thorium compound and a soluble pyrophosphate compound (Na/sub 4/P/sub 2/O/sub 7/) whereby a carrier precipitate of thorium A method is presented of reducing neptunium and - trite is advantageous since it destroys any hydrazine f so that they can be removed from solutions in which they are contained is described. In the carrier precipitation process for the separation of plutonium from uranium and fission products including zirconium and columbium, the precipitated blsmuth phosphate carries some zirconium, columbium, and uranium impurities. According to the invention such impurities can be complexed and removed by dissolving the contaminated carrier precipitate in 10M nitric acid, followed by addition of fluosilicic acid to about 1M, diluting the solution to about 1M in nitric acid, and then adding phosphoric acid to re-precipitate bismuth phosphate carrying plutonium.

  10. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

    1984-01-01

    Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

  11. Influence of scandium on the microstructure and strength properties of the welded joint at the laser welding of aluminum-lithium alloys

    Science.gov (United States)

    Malikov, A. G.; Golyshev, A. A.; Ivanova, M. Yu.

    2017-10-01

    Today, aeronautical equipment manufacture involves up-to-date high-strength aluminum alloys of decreased density resulting from lithium admixture. Various technologies of fusible welding of these alloys are being developed. Serious demands are imposed to the welded joints of aluminum alloys in respect to their strength characteristics. The paper presents experimental investigations of the optimization of the laser welding of aluminum alloys with the scandium-modified welded joint. The effect of scandium on the micro-and macro-structure has been studied as well as the strength characteristics of the welded joint. It has been found that scandium under in the laser welding process increases the welded joint elasticity for the system Al-Mg-Li, aluminum alloy 1420 by 20 %, and almost doubles the same for the system Al-Cu-Li, aluminum alloy 1441.

  12. Tetragonal ternary borides: superconductivity, ferromagnetism and the role of scandium

    International Nuclear Information System (INIS)

    Matthias, B.T.; Patel, C.K.N.; Barz, H.; Corenzwit, E.; Vandenberg, J.M.

    1978-01-01

    The authors report and discuss two discoveries made while studying the condensation phenomena of ternary rhodium borides, MRh 4 B 4 . M is generally a trivalent transition metal, usually a rare earth element RE. An exception is scandium which by itself does not form an isomorphous boride, but in combination with many other elements will do just that. A suprising correlation between ferromagnetic and superconducting transition temperatures has been found. (Auth.)

  13. Synthesis of no carrier added F-18 16-fluorohexadecanoic acid (FHDA) and investigation of its labeled metabolites and its kinetics in the heart

    International Nuclear Information System (INIS)

    DeGrado, T.R.; Bernstein, D.R.; Gatley, S.J.; Ng, C.K.; Holden, J.E.

    1984-01-01

    No carrier added FHDA was prepared via saponification of the product of silver oxide assisted reaction of near-anhydrous tetraethylammonium fluoride with methyl 16-iodohexadecanoate. The labeled fatty acid was injected into isolated perfused rat hearts. Coronary perfusate was collected for 4-9 minutes, when hearts were chilled and homogenized. F-18 in perfusate was analysed by HPLC (NH column; 50mM amm. acetate in 50% acetonitrile). Material with the same retention time as F-18 fluoroacetate (prepared by F-for-I exchange with ethyl iodoacetate) was found. Some F-18 stuck permanently to the column and was assigned as fluoride since the same fraction of label in perfusate was retained on alumina columns eluted with water. Anion exchange HPLC (SAX column; 20mM pot. phosphate, pH 7) of homogenates gave peaks corresponding to fluoroacetate plus fluoride and minor peaks which could be fluoroacetylCoA and fluorocitrate. The authors interpret their data as follows. Beta-oxidation of FHDA results in fluoroacetylCoA which either undergoes ''lethal synthesis'' to fluorocitrate or is hydrolysed to fluoroacetate which diffuses out of the heart. The source of the fluoride is not yet clear, but could complicate interpretation of FHDA kinetics measured in vivo with positron tomography. Clearance of label from FHDA in isolated perfused hearts was faster than for labeled 16-iodohexadecanoic acid, indicating that the F-18 tracer may be a more sensitive probe of myocardial fatty acid metabolism

  14. Production of non carrier added (n.c.a.) {sup 177}Lu for radiopharmaceutical applications

    Energy Technology Data Exchange (ETDEWEB)

    Barkhausen, Christoph

    2011-09-06

    The goal of this dissertation was the development of a process to produce non carrier added {sup 177}Lu at the FRM II. For this purpose, preparative chromatographic methods were evaluated and applied. The highest quality of the nuclide which could only be achieved through a complex chemical process, has been already been proven by clinical studies to be very advantageous. The process has been built up in a hot cell as a semi-automated process and is now being adapted to the requirements of the 'Arzneimittelgesetz' in order to establish n.c.a. {sup 177}Lu as a pharmaceutical product.

  15. Kinetics and mechanism of hydrolysis of scandium sulfate

    International Nuclear Information System (INIS)

    Koshchej, E.V.; Stryapkov, A.V.; Podosenov, D.E.; Makarov, G.V.; Razdobreev, D.A.

    1998-01-01

    The Sc 2 (SO 4 ) 3 -H 2 SO 4 -H 2 O system is studied through the methods of pH-potentiometry, conductometry and turbidimetry at 298 and 318 K and ion force 0.01, 0.1 and 1.0. The hydrolysis mechanism including the processes in the system homogenous and heterogeneous constituents. The hydrolysis rates of scandium salts and their dependences on OH-ions concentration, solution ions force and temperature are found; the constants of the processes rate with participation of OH - and SO 4 2- ions and constants of the solid phase formation rate are calculated [ru

  16. Interaction of scandium sesquioxide with carbon

    International Nuclear Information System (INIS)

    Vodop'yanov, A.G.; Zakharov, R.G.

    1986-01-01

    In the range of 2350-2470 degrees K at a PCO = 0.0 MPa, interaction in Sc 2 O 3 with carbon mixtures initially occurs by CO chemisorption at the scandium oxide surface and disproportionation into CO 2 and C, with subsequent replacement of oxygen in the oxide anion sublattice by carbon to form ScC. The carbide melt, creating a contact between the reagents, then transforms the process to a diffusion-based one. At 1820-2220 K in vacuum, reduction of the studied mixtures occurs by dissociative vaporization of the oxide, with precipitation of ScC at the carbon surface and generation of CO. The appearance of CO in the vapors of mixture leads to formation of an oxycarbide phase and to the partial occurrence of oxide dissociation

  17. Vibrational spectra of double oxides of calcium and scandium

    International Nuclear Information System (INIS)

    Porotnikov, N.V.; Kondratov, O.I.; Petrov, K.I.; Olikov, I.I.

    1981-01-01

    The vibrational spectra of calcium and scandium double oxides 40 CaSc 2 O 4 and 44 CaSc 2 O 4 in the range of 30-1000 cm -1 are studied. In the approximation of the polymer chains of the method of valent-force field the calculation of the theoretical vibrational spectrum of isotope-substituted compounds is made, the attribution of the experimental spectra is suggested, the frequency branches of the vibrations of periodic chains are built, the force field of crystals is evaluated [ru

  18. Exhibit of ADS transmutation system to-Handle MA contained in Highly Radioactive Waste

    International Nuclear Information System (INIS)

    Marsodi; Lasman, A.N.; Nishihara, K.; Marsongkohadi; Su'ud, Z.

    2002-01-01

    This ADS transmutation system consists of a high intensity proton beam accelerator, spallation target, and sub-critical reactor core. The general approach was conducted using N-15 fuel to choose a strategy for destroying or minimizing the dangerously radioactive waste using a fast neutron spectrum. The fuel of this system was put surrounding the target with the some composition, i.e. the composition of MOX from PWR reactor spent-fuel with 5 year cooling time. Basic characteristics of this system have been conducted based on analysis of neutronics calculation results using ATRAS codes system

  19. Diagrammatic Representation of Electronic Correlations in Photoionization Process: Application to Scandium

    International Nuclear Information System (INIS)

    Liu Mengmeng; Ma Xiaoguang

    2011-01-01

    The conversion rules under which an algebraic expression can be obtained from a corresponding photoionization Goldstone diagram have been given systematically in the present work. The electronic correlations in the photoionization processes then could be studied diagrammatically. The application to atomic scandium shows that the present theoretical scheme can give reasonable photoionization cross sections, which agree well with the experimental results. (atomic and molecular physics)

  20. Structural differences of half-sandwich complexes of scandium and yttrium containing bulky substituents

    Czech Academy of Sciences Publication Activity Database

    Fridrichová, Adéla; Růžička, A.; Lamač, Martin; Horáček, Michal

    2017-01-01

    Roč. 76, FEB 2017 (2017), s. 62-66 ISSN 1387-7003 R&D Projects: GA ČR(CZ) GAP207/12/2368 Institutional support: RVO:61388955 Keywords : scandium * yttrium * half-sandwich Subject RIV: CF - Physical ; Theoretical Chemistry OBOR OECD: Physical chemistry Impact factor: 1.640, year: 2016

  1. Inert carrier drying and coating process

    International Nuclear Information System (INIS)

    1980-01-01

    An inert carrier process is described for drying radioactive (particularly low level) waste material and for incorporating the dry material into a binder matrix from which the dried material will not be leached. Experimental details, and examples of the carrier and binder materials, are given. (U.K.)

  2. Stakeholder opinions on the use of the added value approach in siting radioactive waste management facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kojo, Matti [University of Tampere, School of ManagementTampere (Finland); Richardson, Phil [Galson Sciences Ltd, Oakham (United Kingdom)

    2013-07-01

    In some countries nuclear waste facility siting programs include social and economic benefits, compensation, local empowerment and motivation measures and other incentives for the potential host community. This can generally be referred to as an 'added value approach'. Demonstration of the safety of a repository is seen as a precondition of an added value approach. Recently much focus has been placed on studying and developing public participation approaches but less on the use of such incentive and community benefit packages, although they are becoming a more common element in many site selection strategies for nuclear waste management facilities. The primary objective of this paper is to report on an ongoing study of stakeholders' opinions of the use of an added value approach in siting a radioactive waste facility in the Czech Republic, Poland and Slovenia. The paper argues that an added value approach should adapt to the interests and needs of stakeholders during different stages of a siting process. The main question posed in the study is as follows: What are the measures which should be included in 'added value approach' according to the stakeholders? The research data consists of stakeholders' responses to a survey focusing on the use of added value (community benefits) and incentives in siting nuclear waste management facilities. The survey involved use of a questionnaire developed as part of the EU-funded IPPA* project in three countries: the Czech Republic, Poland and Slovenia. (* Implementing Public Participation Approaches in Radioactive Waste Disposal, FP7 Contract Number: 269849). The target audiences for the questionnaires were the stakeholders represented in the national stakeholder groups established to discuss site selection for a nuclear waste repository in their country. A total of 105 questionnaires were sent to the stakeholders between November 2011 and January 2012. 44 questionnaires were returned, resulting in a

  3. Stakeholder opinions on the use of the added value approach in siting radioactive waste management facilities

    International Nuclear Information System (INIS)

    Kojo, Matti; Richardson, Phil

    2013-01-01

    In some countries nuclear waste facility siting programs include social and economic benefits, compensation, local empowerment and motivation measures and other incentives for the potential host community. This can generally be referred to as an 'added value approach'. Demonstration of the safety of a repository is seen as a precondition of an added value approach. Recently much focus has been placed on studying and developing public participation approaches but less on the use of such incentive and community benefit packages, although they are becoming a more common element in many site selection strategies for nuclear waste management facilities. The primary objective of this paper is to report on an ongoing study of stakeholders' opinions of the use of an added value approach in siting a radioactive waste facility in the Czech Republic, Poland and Slovenia. The paper argues that an added value approach should adapt to the interests and needs of stakeholders during different stages of a siting process. The main question posed in the study is as follows: What are the measures which should be included in 'added value approach' according to the stakeholders? The research data consists of stakeholders' responses to a survey focusing on the use of added value (community benefits) and incentives in siting nuclear waste management facilities. The survey involved use of a questionnaire developed as part of the EU-funded IPPA* project in three countries: the Czech Republic, Poland and Slovenia. (* Implementing Public Participation Approaches in Radioactive Waste Disposal, FP7 Contract Number: 269849). The target audiences for the questionnaires were the stakeholders represented in the national stakeholder groups established to discuss site selection for a nuclear waste repository in their country. A total of 105 questionnaires were sent to the stakeholders between November 2011 and January 2012. 44 questionnaires were returned, resulting in a

  4. The synthesis of no-carrier-added and carrier-added 18F-labelled haloperidol

    International Nuclear Information System (INIS)

    Farrokhzad, S.; Diksic, M.

    1985-01-01

    Fluorine-18 labelled haloperidol ( 18 F-HP) was synthesized by a fluorine-fluorine exchange reaction on haloperidol, fluorine-chlorine exchange on a chloro-analog of haloperidol, and from 18 F-labelled p-fluorobenzonitrile prepared by two different exchange reactions. Nucleophilic fluorine was used in the form of tetra n-butylammonium fluoride. The overall radiochemical yield, expressed at the end of syntheses was 5% for exchange in haloperidol and about 2%-3% for exchange in chloroanalog in a 40 min synthesis (from the end of the irradiation). Specific activities up to 1 Ci/mmol for haloperidol and up to 5000 Ci/mmol for chloro-analog as substrates were obtained. The syntheses using p-substituted chloro-and nitro-benzonitriles as starting materials for the exchange reaction gave a product with an average specific activity of about 2000 Ci/mmol and in general an overall radiochemical yield of 5%-10%. Purification of [ 18 F]haloperidol was done by HPLC on a C-18 column. The radiochemical purity as assessed by thin layer radiochromatography (TLRC) of the final product was at least 95%, with high chemical purity. (author)

  5. Study on the coextraction of scandium-yttrium-lumogallion complex

    International Nuclear Information System (INIS)

    Okada, T.; Shimoishi, Y.; Miyata, H.; Toei, K.

    1977-01-01

    The coextraction of scandium-yttrium-lumogallion [LMG;4-chloro-6-(2,4-dihydroxyphenylazo)-1-hydroxybenzene-2-sulfonic acid] into diethyl ether has been studied. The acid dissociation constants of LMG, pKsub(a2) and pKsub(a3), were estimated to be 6.24 and 8.05 respectively. The composition of the complex extracted was determined by using the radioisotopes 46 Sc and 90 Y and by spectrophotometry of LMG and the ratio of the components was Sc:Y:LMG = 1:1:3. The coextraction scheme was discussed briefly. (author)

  6. Bulletin of the radioactivity. No. 83. January-December, 1999

    International Nuclear Information System (INIS)

    2001-01-01

    This report contains the result of observations by the Japan Meteorological Agency (JMA) of atmospheric and seawater radioactivity for the year 1999. The sampling, measurement methods and results of gross beta-radioactivity in precipitation, radioactivity in airborne dust, monthly mean 90 Sr concentration in airborne dust, gross beta-radioactivity in seawater, deposition of 89 Sr, 90 Sr and 137 Cs, natural background radioactivity and vertical distribution of atmospheric radioactivity are described. The results of special observations on the criticality accident at an uranium processing plant, Tokai-mura, Japan showed that gamma-ray spectrum analysis in airborne dust indicated Cs-137 ND (lower than detection limit) and I-131 ND in Sendai and Tokyo at sampling at 99/10/1. 09h-99/10/1,14h and in Tsukuba at sampling 99/09/30, 09h-99/10/01, 09h. Gross beta-radioactivity in precipitation showed 40 MBq/km 2 deposition in Hachijo-jima at sampling 99/09/30,09h-99/10/01, 09h, but no precipitation in Sendai, Akita, Tokyo and Wajima. Mean gamma-radiation dose rate in Wajima indicated 9.8 cps at monitoring 99/09/30-99/10/01,15h. (S.Y.)

  7. Neutron activation analysis of rare earths in uranium containing rocks

    International Nuclear Information System (INIS)

    May, S.; Pinte, G.

    1984-01-01

    The determination of rare earths by activation analysis in uranium rocks is disturbed either by fission-produced rare earths, or by neptunium-239 originating from uranium-238. In order to eliminate these interferencies, the chemical separation of rare earths from uranium prior to activation should be performed. The chemical process is as follows: the rock sample is fused with sodium borate, then, after addition of hydrochloric acid, the resulting solution is passed through a Dowex 1x8 column. Uranium is retained on the resin, and rare earths and scandium are eluted. Aluminium is added as a carrier to the solution, and rare earths and scandium are coprecipitated with aluminium hydroxide. This precipitate is irradiated in the nuclear reactor. Gamma spectrometry is used for the determination of earth radionuclide. Activity measurements are performed in successive steps during one month. The following elements are determined: Pr, La, Sm, Nd, Yb, Lu, Ce, Tb, Eu and Sc. The chemical yield is measured by using scandium as an internal standard. (author)

  8. Fostering a Durable Relationship between a Radioactive Waste Management Facility and its Host Community. Adding Value through Design and Process. 2015 Edition

    International Nuclear Information System (INIS)

    2015-01-01

    In the field of long-term radioactive waste management, repository projects last from decades to centuries. Such projects will inevitably have an effect on the host community from the planning stage to the end of construction and beyond. The key to a long-lasting and positive relationship between a facility and its host community is ensuring that solutions are reached together throughout the entire process. The sustainability of radioactive waste management solutions can potentially be achieved through design and implementation of a facility that provides added cultural and amenity value, as well as economic opportunities, to the local community. This edition of Fostering a Durable Relationship between a Waste Management Facility and its Host Community: Adding Value through Design and Process highlights new innovations in siting processes and in facility design - functional, cultural and physical - from different countries, which could be of added value to host communities and their sites in the short to long term. These new features are examined from the perspective of sustainability, with a focus on increasing the likelihood that people will both understand the facility and its functions, and remember over very long timescales what is located at the site. This 2015 update by the NEA Forum on Stakeholder Confidence will be beneficial in designing paths forward for local or regional communities, as well as for national radioactive waste management programmes. Section 2 of this report summarises the value of developing a sustainable relationship between a community and a radioactive waste management facility through added cultural and amenity value. In Section 3, the report identifies design considerations - functional, cultural and physical - that may help facilities to fit into the community in a sustainable manner. Each design feature is illustrated with examples. Section 4 discusses the benefits that may be gained from the very process of planning radioactive

  9. Radioactive kryptonates in the analysis of environmental samples

    International Nuclear Information System (INIS)

    Tolgyessy, J.

    1986-01-01

    The term ''radioactive Kryptonates'' is used for substances into which atoms or ions of the radioactive nuclide 85 Kr are incorporated. The basis of the use of radioactive Kryptonates in analytical chemistry is that during a chemical reaction the crystalline lattice of the kryptonated carrier is destroyed, the carrier consumed, and the radioactive krypton released (radio-release method). Analysis can be made with a calibration curve or by comparison with a standard. Radio-release methods with the aid of radioactive Kryptonates as analytical reagents are very useful for the analysis of environmental samples, e.g. for the determination of air pollutants (ozone, sulphur dioxide, fluorine, hydrogen fluoride, mercury); and water pollutants (oxygen, dichromate, vanadium, hydrochloric acid, sulphur dioxide). (author)

  10. Studies on the preparation of low-carrier Se-73,75 tracers for in vivo examinations; Untersuchungen zur Darstellung traegerarm 73,75Se-markierter Tracer fuer in vivo Untersuchungen

    Energy Technology Data Exchange (ETDEWEB)

    Helfer, Andreas

    2013-04-03

    With the growing importance of positron emission tomography (PET) for in vivo imaging in diagnostic medicine there is great interest of developing new labelling methods for the positron emitter selenium-73. As attractive application an examination of a no-carrier-added (n.c.a.) preparation of the analogous tracer Sulindac Selenid and of the selenium containing compound Ebselen was examined with {sup 73,75}Se. First of all a labelling strategy for Sulindac Selenid based on a protected precursor was developed. This precursor should further be transformed into the corresponding standard compound for chomatographic identification of the n.c.a. product. This, however, was not possible. An alternative synthesis method also did not result in a product. Thus, a radioactive labelling in case of Sulindac Selenid was not indicated in spite of a successful synthesis of a precursor. The preparation of Ebselen was performed as earlier described by a sequential one-pot synthesis with a yield of 46 %. An adaption of the reaction parameters to a radiosynthesis with {sup 75}Se failed on the n.c.a. state and also after adding carrier to the reaction mixture. The desired product could, however, be prepared in a copper catalysed one-pot radiosynthesis for the first time under carrier-added conditions. Here, optimized conditions resulted in radiochemical yields of 60 ± 18 %. A no-carrier-added product could finally be achieved using sulphur as nonisotopic carrier in the reaction mixture. After optimisation of reaction parameters n.c.a. [{sup 75}Se]Ebselen could be synthesized with radiochemical yields of 55 ± 7 % within 4 h. Furthermore the desired product could be separated by RHPL-chromatography from its co-produced sulfur-analogue. After transferring the conditions to radiosyntheses with the positron emitter {sup 73}Se, n.c.a. [{sup 73}Se]Ebselen could be achieved with a radiochemical yield of 22 ± 1 % and can now be used as a potential radiotracer in preclinical evaluation

  11. Massless radioactivity: a medical must?

    International Nuclear Information System (INIS)

    Wolterbeek, H.Th

    2013-01-01

    Full text: The authoritative body in the field of nomenclature for radiochemistry is the International Union of Pure and Applied Chemistry (IUPAC). The concepts of specific activity, radioactivity concentration, carrier, carrier-free, and no-carrier-added have been) and are also recently discussed as to their correctness, relevance, clarity and consistency. Here, specific activity (sa) is suggested as to be defined as the activity (a) of a specified radioisotope in an amount of substance divided by the mass (m) of the total number of atoms (sa=a/m). Qaim, in a recent review of the future of medical radionuclides, justly argues that both yield, radionuclide purity and specific activity should be increased: here, again, however, the term specific activity deserves attention. What should be the goal in increasing specific activity? Up to as near as possible to massless? Approaching massless in terms of the smallest achievable m value? Taking the radionuclide n X, in physics specific activity is defined as both activity and mass related to n X, in radiochemistry specific activity is defined as the activity of n X related to the mass of all X, but in nuclear medicine most interest is in what IUPAC calls activity concentration, that is, the activity of n X in relation to the mass or volume of the material in which n X is present. This means that, apparently, nuclear medicine asks for high activity concentration of n X in non-isotopic carriers. Does this always imply the highest possible n X specific activity? The presentation focuses on this issue: examples are given that show both the absence of any need for the highest possible specific activity (e.g. 99 Mo, 166 Ho) and the need for 'as-near-as-possible to massless' (e.g. 99m Tc, 177 Lu, α-particles), in all cases in dependence of the radionuclide's position in the production chain and its eventual application in nuclear diagnostics or - therapy

  12. Solvent extraction of anionic chelate complexes of lanthanum(III), europium(III), lutetium(III), scandium(III), and indium(III) with 2-thenoyltrifluoroacetone as ion-pairs with tetrabutylammonium ions

    International Nuclear Information System (INIS)

    Noro, Junji; Sekine, Tatsuya.

    1992-01-01

    The solvent extraction of lanthanum(III), europium(III), lutetium(III), scandium(III), and indium(III) in 0.1 mol dm -3 sodium nitrate solutions with 2-thenoyltrifluoroacetone (Htta) in the absence and presence of tetrabutylammonium ions (tba + ) into carbon tetrachloride was measured. The extraction of lanthanum(III), europium(III), and lutetium(III) was greatly enhanced by the addition of tba + ; this could be explained in terms of the extraction of a ternary complex, M(tta) 4 - tba + . However, the extractions of scandium(III) and indium(III) were nearly the same when tba + was added. The data were treated on the basis of the formation equilibrium of the ternary complex from the neutral chelate, M(tta) 3 , with the extracted ion-pairs of the reagents, tta - tba + , in the organic phase. It was concluded that the degree of association of M(tta) 3 with the ion-pair, tta - tba + , is greater in the order La(tta) 3 ≅ Eu(tta) 3 > Lu(tta) 3 , or that the stability of the ternary complex in the organic phase is higher in the order La(tta) 4 - tba + ≅ Eu(tta) 4 - tba + > Lu(tta) 4 - tba + . This is similar to those of adduct metal chelates of Htta with tributylphosphate (TBP) in synergistic extraction systems. (author)

  13. Method of solidifying and disposing radioactive waste plastic

    International Nuclear Information System (INIS)

    Matsuura, Hiroyuki; Yasumura, Keijiro

    1981-01-01

    Purpose: To solidify radioactive waste as it is with plastic by forming a W/O (Water-in-Oil) emulsion with the radioactive waste and a plastic solidifier, and treating it with a polymerization starting agent, an accelerator, and the like. Method: A predetermined amount of alkaline substance such as sodium hydroxide, triethanol, or the like is added quantitatively to radioactive waste and it is mixed by an agitator. A predetermined amount of solidifier such as unsaturated polyester or the like is added to the mixture and it is further mixed by the agitator to form a stable W/O emulsion. Subsequently, predetermined amounts of polymerization starting agent such as methyl ethyl ketone peroxide and polymerization accelerator such as cobalt naphthenate or the like are added thereto, the mixture is mixed, and is then allowed to stand for at room temperature for the plastic solidification thereof. No reaction occurs after the solidification. (Sekiya, K.)

  14. Double tungstates of metals of scandium and ammonium subgroups

    Energy Technology Data Exchange (ETDEWEB)

    Maksin, V I [AN Ukrainskoj SSR, Kiev. Inst. Kolloidnoj Khimii i Khimii Vody

    1980-06-01

    The methods of pH-potentiometry, conductometry, determination of residual concentrations of liquid phases and precipitations, selected by chemical analysis have been used for investigation R(NO/sub 3/)/sub 3/-(NH/sub 4/)/sub 2/WO/sub 2/-H/sub 2/O systems, (where R=Sc, Y, La). The formation of double tungstates NH/sub 4/R(WO/sub 4/)/sub 2/xnH/sub 2/O is established. The NH/sub 4/Sc(WO/sub 4/)/sub 2/x4.5H/sub 2/O, NH/sub 4/Yx(WO/sub 4/)/sub 2/x3H/sub 2/O, NH/sub 4/La(WO/sub 4/)/sub 2/x1.5H/sub 2/O compounds are synthesized in individual form. Precipitation conditions (pH, concentration ratio) and composition of the solid phase are determined. The behaviour of synthesized slats at thermolysis up to 880 deg C is studied. Physicochemical properties (color, solubility of the simple and double tungstates of scandium, yttrium and lanthanum with ammonium) is studied. IR spectra and X-ray diffraction analysis give idea about double salts structural transformations.

  15. Study of strength properties of semi-finished products from economically alloyed high-strength aluminium-scandium alloys for application in automobile transport and shipbuilding

    Science.gov (United States)

    Baranov, Vladimir; Sidelnikov, Sergey; Zenkin, Evgeny; Frolov, Viktor; Voroshilov, Denis; Yakivyuk, Olga; Konstantinov, Igor; Sokolov, Ruslan; Belokonova, Irina

    2018-04-01

    The results of a study on the strength of rolled products from aluminium alloys doped with scandium under various processing conditions of hot and cold rolling are presented. The regularities of metal flow and the level of strength of deformed semi-finished products from aluminum-scandium alloys are established, depending on the total degree of deformation and the various modes of single reduction during rolling. It is shown that when using one heating of a cast billet to obtain high-quality semi-finished products, the temperature during the rolling process should not be lower than 350-370°, and the total degree of deformation does not exceed 50-60%. It was found that the semi-finished products from alloys with a content of scandium in the range 0.11-0.12% in the deformed state had elevated values of ultimate tensile strength and yield strength of the metal, which allows them to be recommended for industrial production of sheet metal products.

  16. Multiscale Study of Hydrogen Adsorption on Six Designed Covalent Organic Frameworks Based on Porphyrazine, Cyclobutane and Scandium

    International Nuclear Information System (INIS)

    Li Le-Le; Gao Teng-Fei; Zhang Ruan-Yu; Zhang Hong

    2014-01-01

    The first-principles method of hydrogen adsorption is used to investigate the interaction of H_2 with the scandium-porphyrazine (Sc-Pz) and porphyrazine (Pz) clusters. The result shows that the interaction of H_2 with Sc-Pz is stronger than with Pz. Then grand canonical Monte Carlo simulations are used to investigate hydrogen adsorption in six designed covalent organic frameworks (COFs), which are designed based on porphyrazine, cyclobutane and scandium. When the pressure is from 0.1 to 100 bar and the temperature is 298 K and 77 K, the hydrogen adsorption capacities of the six COFs are calculated. We further study the importance of Sc and fillers to improve the H_2 uptake in the modified COFs by analyzing the isosteric heat of hydrogen adsorption. (condensed matter: electronic structure, electrical, magnetic, and optical properties)

  17. Scandium sorption by immobilized microdispersed forms of phosporus-containing ion exchangers

    International Nuclear Information System (INIS)

    Sokolova, Yu.V.; Kurdyumov, G.M.; Smirnov, A.V.; Mezhirov, M.S.

    1991-01-01

    The possibility to improve considerably kinetics of scandium sorption by phosphate ion exchangers, immobilized into polyacrylonitrile (PAN) fibers, as compared with granular samples of ion exchangers, was shown. The influence of dispersion degree of immobilized ionite particles on sorption rate was studied. It is ascertained that the ionite grinding to the particle size ≤ 52 μm is sufficient for the rate increase by 1-1.5 orders. A lower swelling of the immobilized ion exchanger is its additional advantage as compared with granular form

  18. Studies on radioactivity distribution and radioactive mineral identification in uranium ores from Espinharas (PB), Brazil

    International Nuclear Information System (INIS)

    Oliveira, G.N.M. de.

    1979-01-01

    Studies about the identification of radioactive minerals in uranium bearing rocks from Espinharas (PB), Brazil are presented. Autoradiography with α-sensitive nuclear emulsions was utilized for determining radioctivity distributions and for localizing radioactive minerals, in combination with microscopy, X-ray diffractometry, PIXE and eletron microprobe analysis for its identification. Mineralized gneisse and feldspatic rock, the two principal samples studied, show distinct differences in radioactive distribution patterns, however the main carriers for U and Th seem to be the same. Microanalysis shows that elements are associated with Si, Ca, Fe and Al an some trace elements like Y, Zr, Ti, etc. U and Th are distributed uniformly in feldspatic rock and inhomogeneously in mineralized gneisse, indicating that the zonary structure of the radioactive cristals, frequently observed in gneisse, could be due to variable U:Th ratios. Chemical analysis, X-ray diffraction datas and microscopic studies indicates that the principal carrier for radioactivity in the rocks of Espinharas is a silicate mineral of U and Th, probably situaded in the series of transition: Coffinite -> uraninite, thorogummite -> thorianite. Some additional experiments about leachability of uranium with diluted sulfuric acid are reported, which confirm the different nature of radioactivity distribution in feldspatic and gneissic rocks. (author) [pt

  19. Chemical processing for production of no-carrier-added selenium-73 from germanium and arsenic targets and synthesis of L-2-amino-4-([73Se]methylseleno) butyric acid (L-[73Se]selenomethionine)

    International Nuclear Information System (INIS)

    Plenevaux, A.; Guillaume, M.; Brihaye, C.; Lemaire, C.; Cantineau, R.

    1990-01-01

    The Ge( 4 He,xn) and 75 As(p,3n) reactions were compared as the best potential routes for routine production of selenium-73 ( 73 Se) for medical applications. With 26 MeV α particles, available with compact cyclotrons, the first reaction required an enriched 70 Ge target of sodium metagermanate to give a production yield of 1 mCi/μAh (0.037 GBq/μAh) in a 105 mg/cm 2 target. With 55 MeV protons the As(p,3n) reaction on natural arsenic yielded 20 mCi/μAh (0.74 GBq/μAh) in a 685 mg/cm 2 target. A simple method was developed and optimized for both targets in order to isolate and purify the no-carrier-added selenium in the elemental form with a radiochemical yield greater than 75% in less than 90 min. An automated radiochemical processing unit has been designed for the routine production of 100-150 mCi(3.7-5.5 GBq) batches of carrier-free 73 Se ready for radiopharmaceutical labeling. 30 mCi (1.11 GBq) (EOS) of L-2-amino-4-([ 73 Se]methylseleno) butyric acid (L-[ 73 Se]selenomethionine) ready for injection with a specific activity of 5 Ci/mmol (185 GBq/mmol) (EOS) were obtained through a fast chemical synthesis. Radiation absorbed dose estimates for L-[ 73 Se ]selenomethionine have been determined. A value of 0.70 rem/mCi (0.19 mSv/MBq) administered was calculated for the risk from irradiation in man. The first human PET investigation with [ 73 Se]selenomethionine showed a very good delineation between liver and pancreas. (author)

  20. The crystal structure of scandium dyhydrate triglycolate

    International Nuclear Information System (INIS)

    Dukareva, L.M.; Antishkina, A.S.; Porai-Koshits, M.A.; Ostrikova, V.N.; Arkhangel'skij, I.V.; Amanov, A.Z.

    1978-01-01

    The structure of colorless crystals of scandium glycolate dehydrate Sc(CH 2 OHCOO) 3 x2H 2 O, synthesized at the chemical department of MSU has been investigated. Parameters of the monoclinic lattice are determined according to roentgenograms of swing and Kforograms and are specified using the DRON-1 diffractor: a=14.624-+0.005 A; b=13.052-+0.003 A; c=5.730+-0.003 A; γ=96.26 deg+-0.01 deg; rhosub(exper.)=1.09 g/cm 3 ; Z=4; Sp.=P 2/b. Experimental photographic data are obtained using the KFOR chamber. Scannings of the layer lines h anti Ko-h anti K4, containing 742 independent reflexes are taken. Deciphering of the structure is carried out by means of analysis of the Paterson functions distribution and conventional and differential electron densities. Description of the system is presented

  1. Order-disorder phenomenon in lead scandium tantalate

    International Nuclear Information System (INIS)

    Wang, H.C.; Schulze, W.A.

    1990-01-01

    Lead scandium tatalate (PST) is a ferroelectric relaxor with the perovskite structure of A(B'B double-prime)O 3 . By suitable heat treatment, the B-site cations can be brought from a structurally disordered state into various degree of ordering. The degree of ordering is strongly affected by the amount of vacancies present in the materials. To suppress PbO loss during the sintering or annealing process, a PbO-rich atmosphere is supplied by materials having high PbO vapor pressure, such as PbZrO 3 . For PST ceramics with nearly zero weight loss, very long annealing times and higher annealing temperatures are required for ordering. The higher PbO-loss materials are found to be easily ordered. The introduction of a reducing atmosphere during annealing enhances the ordering process. The ordering process is characterized quantitatively by X-ray diffraction and qualitatively by Raman spectroscopy

  2. Multimedia instructions for carriers of radioactive material

    International Nuclear Information System (INIS)

    Sahyun, A.; Sordi, G. M.; Simpson, J.; Ghobril, C. N.; Perez, C. F.

    2014-08-01

    For some operators the transport regulations for transporting radioactive material are considered to be complicated and not user friendly and as a result for some operators it is difficult to identify all the transport regulatory requirements they must comply with for each type of package or radioactive material. These difficulties can result in self-checking being ineffective and as a consequence the first and important step in the safety chain is lost. This paper describes a transport compliance guide for operators that is currently under development for the South American market. This paper describes the scope and structure of the guide and examples of the information provided is given, which will be available in English, Portuguese and Spanish. It is intended that when the guide is launched before the end of 2013 it will be accessed using a bespoke software program that can run on Pc platform to provide a checklist for the operator before the shipment begins By identifying the regulatory requirements the guide is also intended to provide operators with an understanding of the structure of the transport regulations and an appreciation of the logic behind the regulatory requirements for each Un numbered package and material type listed in the transport regulations for radioactive material. It is foreseen that the interactive program can be used both operationally on a day-to-day basis and as a training tool, including refresher training, as the guide will be updated when the transport regulations are periodically changed. (Author)

  3. Multimedia instructions for carriers of radioactive material

    Energy Technology Data Exchange (ETDEWEB)

    Sahyun, A.; Sordi, G. M. [Instituto de Pesquisas Energeticas e Nucleares, Av. Prof. Lineu Prestes 2242, Cidade Universitaria, 05508-000 Sao Paulo (Brazil); Simpson, J. [Class 7 Limited, 9 Irk Vale Drive, Chadderton, Oldham OL1 2TW (United Kingdom); Ghobril, C. N. [Governo de Sao Paulo, Instituto de Economia Agricola, 04301-903 Sao Paulo (Brazil); Perez, C. F., E-mail: adelia@atomo.com.br [Centro Tecnologico da Marinha em Sao Paulo, Av. Prof. Lineu Prestes 2468, Cidade Universitaria, 05508-000 Sau Paulo (Brazil)

    2014-08-15

    For some operators the transport regulations for transporting radioactive material are considered to be complicated and not user friendly and as a result for some operators it is difficult to identify all the transport regulatory requirements they must comply with for each type of package or radioactive material. These difficulties can result in self-checking being ineffective and as a consequence the first and important step in the safety chain is lost. This paper describes a transport compliance guide for operators that is currently under development for the South American market. This paper describes the scope and structure of the guide and examples of the information provided is given, which will be available in English, Portuguese and Spanish. It is intended that when the guide is launched before the end of 2013 it will be accessed using a bespoke software program that can run on Pc platform to provide a checklist for the operator before the shipment begins By identifying the regulatory requirements the guide is also intended to provide operators with an understanding of the structure of the transport regulations and an appreciation of the logic behind the regulatory requirements for each Un numbered package and material type listed in the transport regulations for radioactive material. It is foreseen that the interactive program can be used both operationally on a day-to-day basis and as a training tool, including refresher training, as the guide will be updated when the transport regulations are periodically changed. (Author)

  4. Incident involving radioactive material at IAEA Safeguards Laboratory - No radioactivity released to environment

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Pressure build-up in a small sealed sample bottle in a storage safe resulted in plutonium contamination of a storage room at about 02:30 today at the IAEA's Safeguards Analytical Laboratory in Seibersdorf. All indications are that there was no release of radioactivity to the environment. Further monitoring around the laboratory will be undertaken. No one was working in the laboratory at the time. The Laboratory's safety system detected plutonium contamination in the storage room where the safe was located and in two other rooms - subsequently confirmed by a team of IAEA radiation protection experts. The Laboratory is equipped with multiple safety systems, including an air-filtering system to prevent the release of radioactivity to the environment. There will be restricted access to the affected rooms until they are decontaminated. A full investigation of the incident will be conducted. The IAEA has informed the Austrian regulatory authority. The IAEA's Laboratory in Seibersdorf is located within the complex of the Austrian Research Centers Seibersdorf (ARC), about 35 km southeast of Vienna. The laboratory routinely analyses small samples of nuclear material (uranium or plutonium) as part of the IAEA's safeguards verification work. (IAEA)

  5. Elimination of radioactivity after intratracheal instillation of tritiated 3, 4-benzopyrene in hamsters

    Energy Technology Data Exchange (ETDEWEB)

    Pylev, L N; Roe, F J.C.; Warwick, G P

    1969-01-01

    Injection and recovery experiments of tritiated 3,4-benzopyrene (BaP) injected alone or with particulate carriers into hamsters were performed. After 21 days, asbestos or carbon black carriers had significantly increased the retention of BaP in the lung. Elimination was rapid at first (2 weeks: and little influenced by carrier; slower rate of elimination was noted after that. Carriers increased recoverable macrophages but decreased the amount of radioactivity per macrophage. Radioactivity was similar in all groups for kidney, liver, blood, feces, and urine.

  6. Radioactive waste processing

    International Nuclear Information System (INIS)

    Curtiss, D.H.; Heacock, H.W.

    1976-01-01

    The description is given of a process for treating radioactive waste whereby a mud of radioactive waste and cementing material is formed in a mixer. This mud is then transferred from the mixer to a storage and transport container where it is allowed to harden. To improve transport efficiency an alkali silicate or an alkaline-earth metal silicate is added to the mud. For one hundred parts by weight of radioactive waste in the mud, twenty to one hundred parts by weight of cementing material are added and five to fifty parts by weight of silicate, the amount of waste in the mud exceeding the combined amount of cementing and silicate material [fr

  7. Thermodynamic stability of radioactivity standard solutions

    International Nuclear Information System (INIS)

    Iroulard, M.G.

    2007-04-01

    The basic requirement when preparing radioactivity standard solutions is to guarantee the concentration of a radionuclide or a radioelement, expressed in the form of activity concentration (Ac = A/m (Bq/g), with A: activity and m: mass of solution). Knowledge of the law of radioactive decay and the half-life of a radionuclide or radioelement makes it possible to determine the activity concentration at any time, and this must be confirmed subsequently by measurement. Furthermore, when radioactivity standard solutions are prepared, it is necessary to establish optimal conditions of thermodynamic stability of the standard solutions. Radioactivity standard solutions are prepared by metrology laboratories from original solutions obtained from a range of suppliers. These radioactivity standard solutions must enable preparation of liquid and/or solid radioactivity standard sources of which measurement by different methods can determine, at a given instant, the activity concentration of the radionuclide or radioelement present in the solution. There are a number of constraints associated with the preparation of such sources. Here only those that relate to the physical and chemical properties of the standard solution are considered, and therefore need to be taken into account when preparing a radioactivity standard solution. These issues are considered in this document in accordance with the following plan: - A first part devoted to the chemical properties of the solutions: - the solubilization media: ultra-pure water and acid media, - the carriers: concentration, oxidation state of the radioactive element and the carrier element. - A second part describing the methodology of the preparation, packaging and storage of standard solutions: - glass ampoules: the structure of glasses, the mechanisms of their dissolution, the sorption phenomenon at the solid-solution interface, - quartz ampoules, - cleaning and packaging: cleaning solutions, internal surface coatings and

  8. Thermodynamic stability of radioactivity standard solutions

    Energy Technology Data Exchange (ETDEWEB)

    Iroulard, M.G

    2007-04-15

    The basic requirement when preparing radioactivity standard solutions is to guarantee the concentration of a radionuclide or a radioelement, expressed in the form of activity concentration (Ac = A/m (Bq/g), with A: activity and m: mass of solution). Knowledge of the law of radioactive decay and the half-life of a radionuclide or radioelement makes it possible to determine the activity concentration at any time, and this must be confirmed subsequently by measurement. Furthermore, when radioactivity standard solutions are prepared, it is necessary to establish optimal conditions of thermodynamic stability of the standard solutions. Radioactivity standard solutions are prepared by metrology laboratories from original solutions obtained from a range of suppliers. These radioactivity standard solutions must enable preparation of liquid and/or solid radioactivity standard sources of which measurement by different methods can determine, at a given instant, the activity concentration of the radionuclide or radioelement present in the solution. There are a number of constraints associated with the preparation of such sources. Here only those that relate to the physical and chemical properties of the standard solution are considered, and therefore need to be taken into account when preparing a radioactivity standard solution. These issues are considered in this document in accordance with the following plan: - A first part devoted to the chemical properties of the solutions: - the solubilization media: ultra-pure water and acid media, - the carriers: concentration, oxidation state of the radioactive element and the carrier element. - A second part describing the methodology of the preparation, packaging and storage of standard solutions: - glass ampoules: the structure of glasses, the mechanisms of their dissolution, the sorption phenomenon at the solid-solution interface, - quartz ampoules, - cleaning and packaging: cleaning solutions, internal surface coatings and

  9. Waterproofing improvement of radioactive waste asphalt solid

    International Nuclear Information System (INIS)

    Adachi, Katsuhiko; Yamaguchi, Takashi; Ikeoka, Akira.

    1981-01-01

    Purpose: To improve the waterproofing of asphalt solid by adding an alkaline earth metal salt and, further, paraffin, into radioactive liquid waste when processing asphalt solidification of the radioactive liquid waste. Method: Before processing molten asphalt solidification of radioactive liquid waste, soluble salts of alkaline earth metal such as calcium chloride, magnesium chloride, or the like is added to the radioactive liquid waste. Paraffin having a melting point of higher than 60 0 C, for example, is added to the asphalt, and waterproofing can be remarkably improved. The waste asphalt solid thus fabricated can prevent the swelling thereof, and can improve its waterproofing. (Yoshihara, H.)

  10. Radioactive materials transport

    International Nuclear Information System (INIS)

    Talbi, B.

    1996-01-01

    The development of peaceful applications of nuclear energy results in the increase of transport operations of radioactive materials. Therefore strong regulations on transport of radioactive materials turns out to be a necessity in Tunisia. This report presents the different axes of regulations which include the means of transport involved, the radiation protection of the carriers, the technical criteria of security in transport, the emergency measures in case of accidents and penalties in case of infringement. (TEC). 12 refs., 1 fig

  11. Safe transport of radioactive material

    International Nuclear Information System (INIS)

    1994-01-01

    Delivering radioactive material to where it is needed is a vital service to industry and medicine. Millions of packages are shipped all over the world by all modes of transport. The shipments pass through public places and must meet stringent safety requirements. This video explains how radioactive material is safely transported and describes the rules that carriers and handlers must follow

  12. Bibliography in environmental radioactivity in foods. No. 28

    International Nuclear Information System (INIS)

    Fischer, E.; Kalus, W.; Mueller, H.; Schelenz, R.

    1979-05-01

    This latest volume of the bibliography series - which from no. 28, 1979, on goes under the title of 'Bibliography in Environmental Radioactivity in Foods' now that the ZEAD-bibl. series have been terminated - lists 197 bibliographic references, mainly from the last two years, with the emphasis on general environmental surveillance and surveillance of nuclear installations. (orig.) [de

  13. Regulations relevant to the transport of radioactive materials in Switzerland

    International Nuclear Information System (INIS)

    Smith, L.

    1996-01-01

    As is the case in many countries, the transport of radioactive materials in Switzerland is primarily regulated by the national regulations for the transport of dangerous goods. Currently these regulations, in the case of radioactive material, incorporate the 1985 IAEA Safety Series 6 Regulations for the Safe Transport of Radioactive Material (As amended 1990). However, as is also the case in some other countries, consignors, shippers and carriers of radioactive materials must also comply with additional laws when shipping radioactive materials. The most important of these other laws and their accompanying regulations are those concerned with radiation protection (import, export and carriers licences) and nuclear power (import, export, inland transport and transit licences). This paper sets out to describe the collective requirements resulting from all three of these sets of regulations. (Author)

  14. Synthesis, structures, and electroluminescent properties of scandium N,O-chelated complexes toward near-white organic light-emitting diodes.

    Science.gov (United States)

    Katkova, Marina A; Balashova, Tatyana V; Ilichev, Vasilii A; Konev, Alexey N; Isachenkov, Nikolai A; Fukin, Georgy K; Ketkov, Sergey Yu; Bochkarev, Mikhail N

    2010-06-07

    Three members of a new class of electroluminescent, neutral, and monomeric scandium N,O-chelate complexes, namely, Sc(III)-tris-2-(2-benzoimidazol-2-yl)phenolate (1), Sc(III)-tris-2-(2-benzoxyazol-2-yl)phenolate (2), and Sc(III)-tris-2-(2-benzothiazol-2-yl)phenolate (3), have been prepared and X-ray characterized. DFT calculations have been performed. In contrast to the most frequently applied dual or multiple dopants in multilayer white OLED devices, all our simpler devices with the configuration of indium tin oxide/N,N'-bis(3-methylphenyl)-N,N'-diphenylbenzidine/neat scandium complex/Yb exhibit close to near-white emission with a blue hue (CIE(x,y) = 0.2147, 0.2379) in the case of 1, a cyan hue (0.2702, 0.3524) in the case of 2, and a yellowish hue (0.3468; 0.4284) in the case of 3.

  15. Laboratory studies into the use of the scandium-46-EDTA complex as a tracer for groundwater flow

    International Nuclear Information System (INIS)

    Cheng, H.; Nixon, S.C.

    1988-01-01

    Gamma ray emitting metal radionuclides, when complexed with an appropriate complexing agent, provide a wide choice of water tracers particularly for groundwater studies where a radionuclide of appropriate half-life suited to the particular study can be selected. Scandium-46 has easily detectable gamma emission and a suitable half-life (84 days) for medium term studies. It has been widely and successfully used as a tracer in studies of sediment movement but has not yet been introduced as a groundwater tracer. In our experiments the chemical aspects of the preparation of Sc-46-EDTA were studied in some detail and its behaviour in various mineralogical environments was evaluated with reference to the standard tracer, tritiated water. The experimental results have shown that the scandium cation can be easily complexed with EDTA to form soluble SC-EDTA. The complex is very stable in a wide range of pH; the adsorptive properties of Sc-EDTA in the batch studies and the retardation and recovery in the column tests in comparison with tritiated water are quite satisfactory. In general Sc-46-EDTA is a promising tracer for groundwater studies. In the report the appropriate conditions, procedures and some rational and efficient methods for testing the purity of Sc-46-EDTA in the preparation of the tracer solution of Sc-46-EDTA are described. In addition, it has been found that the formation of the metal hydroxide colloids is the major reason for the great loss in groundwater aquifers of most trivalent metal nuclide tracers in the cationic form including scandium-46. (author). 29 refs, 11 figs, 12 tabs

  16. Spectrophotometric determination of Tl carrier in 201Tl-TlCl injection

    International Nuclear Information System (INIS)

    Gong Quansheng; Jing Lie

    1997-01-01

    A simple and sensitive method for the spectrophotometric determination of carrier content (Thallium) in 201 Tl-TlCl injection is described. Thallium (I) is oxidised to Thallium (III) by aqueous bromine, then excess bromine is removed by adding sulfosalicylic acid. In buffer solution (NH 4 Cl-NH 4 OH) at pH 11.7 with the presence of emulsifier OP, thallium (III) and cadion form a complex having an absorption maximum at 469 nm with a molar absorptivity of 1.37 x 10 4 m 2 /mol. Beer's law is obeyed in the concentration range of 0-7 μg/5 mL. The effect of impurity elements in 201 Tl-TlCl injection is examined. It is an ideal method for the analysis of radioactive solution

  17. Determination of aluminium, scandium and rare earth elements by emission flame spectrometry

    International Nuclear Information System (INIS)

    Otruba, V.; Sommer, L.

    1989-01-01

    Emission spectrometry in nitrous oxide-acetylene flames in combination with a highly resolving double monochromator and sensitive detecting system enables simple, sensitive and selective determinations of aluminium, scandium and all rare earth elements with exception of cerium in complicated matrices. Calibration plots are linear for a large concentration interval (≤ 100 μgxml -1 ), detection limits are in ngxml -1 level and RSD does not exceed 3% on the optimal concentration level of the particular element. The determination of Al, Sc, Eu and Yb showed particular advantages as to methods using ICP-spectrometry. (orig.)

  18. Promulgation order no. 546 of the 23rd June 1993. Executive order on transport of radioactive materials

    International Nuclear Information System (INIS)

    1993-01-01

    The Danish executive order no. 546 of June 23rd, 1993, concerning the transport of radioactive materials in pursuance of paragraph 2, section 1 of Law no. 94 of March 21, 1953 on the use etc. of radioactive materials are stipulated by order in accordance with paragraph 4 of the executive order no. 574 of November 20th, 1975, on precautionary measures related to the use etc. of radioactive materials. The 6 paragraphs comprising order no. 546 concern the transport of radioactive materials within Danish boundaries, transport of radioactive materials into Denmark from a country which is not a member of the European Community, transport of radioactive materials within the European Communities, the regulation that complaints with regard to decisions made by the (Danish) National Board of Health may be referred to the Ministry of the Interior within a period of four weeks and the regulation that violation of these regulations will be subject to punishment by fining in accordance with paragraph 5 of the law on use etc. of radioactive materials. The transport of radioactive materials into Denmark from a non-EC country can only take place as far as the National Board of Health (National Institute for Radiation Hygiene) has given authorization in each individual case, and transport of radioactive materials between the countries which are members of the European Community takes place under the regulatives of the Council of the European Communities' statutory order no. 93/1493 Euratom of June 8th, 1993 on transport of radioactive materials between member states. A supplementary text on the Council's statutory order (Euratom) no. 1493/93 is included. (AB)

  19. Process Design Aspects for Scandium-Selective Leaching of Bauxite Residue with Sulfuric Acid

    OpenAIRE

    Konstantinos Hatzilyberis; Theopisti Lymperopoulou; Lamprini-Areti Tsakanika; Klaus-Michael Ochsenkühn; Paraskevas Georgiou; Nikolaos Defteraios; Fotios Tsopelas; Maria Ochsenkühn-Petropoulou

    2018-01-01

    Aiming at the industrial scale development of a Scandium (Sc)-selective leaching process of Bauxite Residue (BR), a set of process design aspects has been investigated. The interpretation of experimental data for Sc leaching yield, with sulfuric acid as the leaching solvent, has shown significant impact from acid feed concentration, mixing time, liquid to solids ratio (L/S), and number of cycles of leachate re-usage onto fresh BR. The thin film diffusion model, as the fundamental theory for l...

  20. ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

    International Nuclear Information System (INIS)

    R.H. Little, P.R. Maul, J.S.S. Penfoldag

    2003-01-01

    This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible

  1. Method of disposing radioactive wastes

    International Nuclear Information System (INIS)

    Isozaki, Kei.

    1983-01-01

    Purpose : To enable safety ocean disposal of radioactive wastes by decreasing the leaching rate of radioactive nucleides, improving the quick-curing nature and increasing the durability. Method : A mixture comprising 2 - 20 parts by weight of alkali metal hydroxide and 100 parts by weight of finely powdered aqueous slags from a blast furnace is added to radioactive wastes to solidify them. In the case of medium or low level radioactive wastes, the solidification agent is added by 200 parts by weight to 100 parts by weight of the wastes and, in the case of high level wastes, the solidification agent is added in such an amount that the wastes occupy about 20% by weight in the total of the wastes and the solidification agent. Sodium hydroxide used as the alkali metal hydroxide is partially replaced with sodium carbonate, a water-reducing agent such as lignin sulfonate is added to improve the fluidity and suppress the leaching rate and the wastes are solidified in a drum can. In this way, corrosions of the vessel can be suppressed by the alkaline nature and the compression strength, heat stability and the like of the product also become excellent. (Sekiya, K.)

  2. Method for calibration measurement in a liquid scintillation counter and carrier used in the method

    International Nuclear Information System (INIS)

    Reunanen, M.A.

    1976-01-01

    The present invention relates to a method for use in liquid scintillation measurements to feed an accurately determined amount of radioactive substance to a fluid scintillation system for a calibration measurement. According to the invention an accurately determined amount of radioactive substance is adsorbed to a carrier, which is introduced into the fluid scintillation system. The invention also relates to a carrier for use in the method

  3. Method of processing radioactive liquid waste

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Kuribayashi, Hiroshi; Soda, Kenzo; Mihara, Shigeru.

    1988-01-01

    Purpose: To obtain satisfactory plastic solidification products rapidly and smoothly by adding oxidizers to radioactive liquid wastes. Method: Sulfuric acid, etc. are added to radioactive liquid wastes to adjust the pH value of the liquid wastes to less than 3.0. Then, ferrous sulfates are added such that the iron concentration in the liquid wastes is 100 mg/l. Then, after adjusting pH suitably to the drying powderization by adding alkali such as hydroxide, the liquid wastes are dried and powderized. The resultant powder is subjected to plastic solidification by using polymerizable liquid unsaturated polyester resins as the solidifying agent. The thus obtained solidification products are stable in view of the physical property such as strength or water proofness, as well as stable operation is possible even for those radioactive liquid wastes in which the content ingredients are unknown. (Takahashi, M.)

  4. Magnetic susceptibility of scandium-hydrogen and lutetium-hydrogen solid-solution alloys from 2 to 3000K

    International Nuclear Information System (INIS)

    Stierman, R.J.

    1982-12-01

    Results for pure Sc show that the maximum and minimum in the susceptibility discovered earlier are enhanced as the impurity level of iron in scandium decreases. The Stoner enhancement factor, calculated from low-temperature heat capacity data, susceptibility data, and band-structure calculations show Sc to be a strongly enhanced paramagnet. Below 2 0 K, the magnetic anisotropy between the hard and easy directions of scandium decreases linearly with decreasing temperature, tending toward zero at 0 K. The large increase in the susceptibility of Sc at lower temperatures indicates magnetic ordering. Pure Lu and Lu-H alloys showed an anisotropy in susceptibility vs orientation; thus the samples were not random polycrystalline samples. Pure Lu shows the shallow maximum and minimum, but the increase in susceptibility at low temperatures is larger than previously observed. The susceptibility-composition dependence of the Lu-H alloys also did not match other data. The susceptibility-composition dependence does not match the composition dependence of the electronic specific heat constant below 150 K, showing the electronic specific heat is being affected by terms other than phonon-electron and pure electron-electron interactions

  5. Hydrogen storage in thin film magnesium-scandium alloys

    International Nuclear Information System (INIS)

    Niessen, R.A. H.; Notten, P.H. L.

    2005-01-01

    Thorough electrochemical materials research has been performed on thin films of novel magnesium-scandium hydrogen storage alloys. It was found that palladium-capped thin films of Mg x Sc (1-x) with different compositions (ranging from x=0.50 -0.90) show an increase in hydrogen storage capacity of more than 5-20% as compared to their bulk equivalents using even higher discharge rates. The maximum reversible hydrogen storage capacity at the optimal composition (Mg 80 Sc 20 ) amounts to 1795-bar mAh/g corresponding to a hydrogen content of 2.05 H/M or 6.7-bar wt.%, which is close to five times that of the commonly used hydride-forming materials in commercial NiMH batteries. Galvanostatic intermittent titration technique (GITT) measurements show that the equilibrium pressure during discharge is lower than that of bulk powders by one order of magnitude (10 -7 -bar mbar versus 10 -6 -bar mbar, respectively)

  6. Development of methods for the selective separation of scandium, zirconium and tin for radiopharmaceutical applications; Entwicklung von Methoden zur selektiven Trennung von Scandium, Zirkonium und Zinn fuer radiopharmazeutische Anwendungen

    Energy Technology Data Exchange (ETDEWEB)

    Dirks-Fandrei, Carina

    2014-07-01

    The subject of the present work is the development of fast and highly selective methods for the separation and purification of scandium, zirconium and tin radionuclides from potential target materials for use in nuclear medicine. A number of selected resins (TrisKem International) were first characterized with respect to their extraction behaviour towards a large number of cations. Characterization studies were performed in batch experiments by determination of weight distribution ratios D{sub w} and further the influence of interferences on the uptake of these elements was evaluated. Weight distribution ratios were determined in different acids and acid concentrations with main focus on scandium, tin or zirconium. The interference of macro amounts of Calcium and Ti on the Sc extraction was evaluated as well as the interference of macro amounts of Y on the Zr extraction. Best suited uptake conditions were found for Scandium on DGA were determined to be 2.5 M HNO{sub 3} for Ti-Targets and 0.1 M HNO{sub 3} for Calcium-Targets. Otherwise it is also possible to extract Sc with TRU Resin. High uptakes were obtained at 2.5 M HNO{sub 3} for simulated Ti- and Calcium-targets. Separation methods were developed using elution studies; employed conditions were chosen according to parameters evaluated in the batch-experiment. The developed methods allowed separating Sc very rapidly in high purity very rapidly from Ti- or Calcium-targets. For Zr a separation method based on UTEVA Resin has been developed. Following results of batch experiments simulated Y-target solution were loaded onto a UTEVA resin column from 6 M HNO{sub 3}; the elution of Zr could be performed in 0.01 M oxalic acid. Decontamination factors in the order of 10{sup 4}-10{sup 5} could be obtained applying the developed method; the method thus allowed separating Zr in a high purity. Initial testing of a method for the separation of Sn from Cd targets based on the use of TBP Resin showed that the TBP resin seems

  7. Regulation on the manufacture of radioactive medicines

    International Nuclear Information System (INIS)

    1977-01-01

    This is the latest revision of the regulation which provides for the control of the manufacture of the said medicines in accordance with the Medical Drugs Act (Law No. 145, 1960). Schedule 1 to Article 1 which specifies the items of the radioactive medicines has been modified: several substances including their compounds and medicines made from them are added to, or omitted from the Schedule, such as; (added to) 11 C, 13 N, 15 O, sup(85m)Kr, 81 Rb and 123 I, (omitted from) 89 Sr, 91 y and 137 Cs. (Matsushima, A.)

  8. Smelting of Scandium by Microwave Irradiation

    Directory of Open Access Journals (Sweden)

    Satoshi Fujii

    2017-09-01

    Full Text Available Scandium is being explored as an alloying element for aluminum alloys, which are gaining importance as high-performance lightweight structural alloys in the transportation industry. A few years ago, Sc was also found to be suitable for use in electrical devices. High-Sc-content ScAlN thin films have attracted significant attention because of their strong piezoelectricity. The piezoelectric response of ScAlN suggests that ScAlN thin films formed on a hard substrate would be suitable surface acoustic wave wideband filters for next-generation wireless communication systems. However, it is often difficult to use ScAlN thin films in MEMS devices—including acoustic ones—because of the extremely high price of metallic Sc, given the difficulty associated with smelting it. Here, we propose a novel process for smelting Sc metal by microwave irradiation. Sc metal was able to be obtained successfully from ScF3 through a microwave-irradiation-based carbon reduction reaction. The reaction temperature for this reduction process was approximately 880°C, which is half of that for the conventional smelting process involving reduction with Ca. Thus, the proposed microwave irradiation process has significant potential for use in the smelting of Sc metal.

  9. Minimization of zirconium chlorinator residues

    International Nuclear Information System (INIS)

    Green, G.K.; Harbuck, D.D.

    1995-01-01

    Zirconium chlorinator residues contain an array of rare earths, scandium, unreacted coke, and radioactive thorium and radium. Because of the radioactivity, the residues must be disposed in special waste containment facilities. As these sites become more congested, and with stricter environmental regulations, disposal of large volumes of wastes may become more difficult. To reduce the mass of disposed material, the US Bureau of Mines (USBM) developed technology to recover rare earths, thorium and radium, and unreacted coke from these residues. This technology employs an HCl leach to solubilize over 99% of the scandium and thorium, and over 90% of the rare earths. The leach liquor is processed through several solvent extraction stages to selectively recover scandium, thorium, and rare earths. The leach residue is further leached with an organic acid to solubilize radium, thus allowing unreacted coke to be recycled to the chlorinator. The thorium and radium waste products, which comprise only 2.1% of the original residue mass, can then be sent to the radioactive waste facility

  10. Effect of carrier on labeling and biodistribution of Re-188-Hydroxyethylidene diphosphonate

    International Nuclear Information System (INIS)

    Chang, Young Soo; Jeong, Jae Min; Kim, Bo Kwang; Cho, Jung Hyuk; Lee, Dong Soo; Chung, June Key; Lee, Myung Chul; Lee, Seung Jin; Jin, Ren Jie; Lee, Sang Eun

    2000-01-01

    Re-188-Hydroxyethylidene diphosphonate (HEDP) is a new cost-effective agent for systemic radioisotope therapy of metastatic bone pain. We investigated the influence of carrier for labeling and biodistribution of Re-188-HEDP using HEDP kit with or without carrier (KReO 4 ). The kits (HEDP 15 mg, gentisic acid 4 mg and SnC1 2 .2H 2 O 4.5 mg) with or without carrier (KReO 4 0.1 mg) were labeled with Re-188 solution, made available from an in-house generator by boiling for 15 min. We compared the labeling efficiency and stability of carrier-added and carrier-free preparations of Re-188-HEDP. Biodistribution and imaging studies of each preparation were performed in ICR mice (1.85-3.7 MBq/0.1 ml) and SD rats (74.1-85.2 MBq/0.5 ml). The carrier-added preparation showed high labeling efficiency (95% at pH 5) and high stability in serum (88%, 3hr). However, the carrier-free preparation showed low labeling efficiency (59% at pH 5) and low stability (43%, 3 hr). The carrier-added preparation showed high uptake in bone and low uptake in stomach and kidneys. However, the carrier-free preparation showed lower uptake in bone and higher uptake in both stomach and kidneys, which is supposed to be due to released perrhenate. The carrier-added preparation also showed better images with higher skeletal accumulation, lower uptake in other organs and lower soft tissue uptake than the carrier-free preparation. The results of these studies clearly demonstrate that addition of carrier perrhenate is required for high labeling efficiency, stability, bone uptake and good image quality of Re-188-HEDP.=20

  11. 1st Quarter Transportation Report FY 2015: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    Energy Technology Data Exchange (ETDEWEB)

    Gregory, Louis [National Security Technologies, LLC, Las Vegas, NV (United States)

    2015-02-20

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 1st quarter of Fiscal Year (FY) 2015 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report include minor volumes of non-radioactive classified waste/material that were approved for disposal (non-radioactive classified or nonradioactive classified hazardous). Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to rounding conventions for volumetric conversions from cubic meters to cubic feet.

  12. Planning and Preparing for Emergency Response to Transport Accidents Involving Radioactive Material. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    This Safety Guide provides guidance on various aspects of emergency planning and preparedness for dealing effectively and safely with transport accidents involving radioactive material, including the assignment of responsibilities. It reflects the requirements specified in Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, and those of Safety Series No. 115, International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. Contents: 1. Introduction; 2. Framework for planning and preparing for response to accidents in the transport of radioactive material; 3. Responsibilities for planning and preparing for response to accidents in the transport of radioactive material; 4. Planning for response to accidents in the transport of radioactive material; 5. Preparing for response to accidents in the transport of radioactive material; Appendix I: Features of the transport regulations influencing emergency response to transport accidents; Appendix II: Preliminary emergency response reference matrix; Appendix III: Guide to suitable instrumentation; Appendix IV: Overview of emergency management for a transport accident involving radioactive material; Appendix V: Examples of response to transport accidents; Appendix VI: Example equipment kit for a radiation protection team; Annex I: Example of guidance on emergency response to carriers; Annex II: Emergency response guide.

  13. Effect of composition on the superplasticity of aluminium scandium alloys

    International Nuclear Information System (INIS)

    Bradley, E.L. III; Morris, J.W. Jr.

    1992-01-01

    Several aluminum alloys have been shown to exhibit superplasticty in the as-rolled condition. Previous work has shown that aluminum-scandium alloys also exhibit this behavior, but only with the addition of ternary alloying elements such as lithium and magnesium. These additions raised the strain-rate sensitivity of these alloys to 0.4-0.5 for selected strain rates at temperatures above 400 degrees C. A systematic study was undertaken of five Al-Sc alloys with varying lithium and magnesium concentrations in order to fully characterize the high temperature deformation mechanism. Specimens were deformed at a constant strain rate to predetermined true strains for textural and microstructural characterization. In this paper work is presented that will elucidate the effect of these different ternary additives on the superplastic deformation mechanism in these alloys

  14. Synthesis of 'no carrier added' carbon-11 fotemustine

    International Nuclear Information System (INIS)

    Lasne, M.C.; Piarraud, A.; Lalaoui, K.; Barre, L.; Derlon, J.M.; Giroux, B.

    1990-01-01

    Nitrosoureas are commonly used for chemotherapeutic treatment of some tumors and the search for new drugs less toxic amd more selective is always under investigation. Efficacy of fotemustine, a nitrosourea type compound in the treatment of malignant gliomas prompted us to label it with carbon-11 so that its pharmacokinetics and metabolic behavior in human brain tumors could be studied in vivo using PET. The synthetic pathway for labelling with carbon-11 is outlined

  15. Treating agent for urea containing radioactive materials

    International Nuclear Information System (INIS)

    Ogawa, Hiroshi; Maki, Kentaro.

    1973-01-01

    Object: To add a coagulant into urea containing radioactive material to precipitate and remove the radioactive material in the urea. Structure: Iodosalt is added into urea and next, a mixed reagent in which silver ion or silver acetic ion and iron hydroxide precipitation or ferrite ion coexist is added therein. The urea is treated to have a sufficient alkaline, after which it is introduced into a basket type centrifuge formed with a filter layer in combination of an upper glass fiber layer and a lower active carbon layer. The treating agent can uniformly remove radioactive ion and radioactive chelate within urea containing inorganic salt and various metabolites. (Nakamura, S.)

  16. BEARS: Radioactive ion beams at LBNL

    International Nuclear Information System (INIS)

    Powell, J.; Guo, F.Q.; Haustein, P.E.

    1998-01-01

    BEARS (Berkeley Experiments with Accelerated Radioactive Species) is an initiative to develop a radioactive ion-beam capability at Lawrence Berkeley National Laboratory. The aim is to produce isotopes at an existing medical cyclotron and to accelerate them at the 88 inch Cyclotron. To overcome the 300-meter physical separation of these two accelerators, a carrier-gas transport system will be used. At the terminus of the capillary, the carrier gas will be separated and the isotopes will be injected into the 88 inch Cyclotron's Electron Cyclotron Resonance (ECR) ion source. The first radioactive beams to be developed will include 20-min 11 C and 70-sec 14 O, produced by (p,n) and (p,α) reactions on low-Z targets. A test program is currently being conducted at the 88 inch Cyclotron to develop the parts of the BEARS system. Preliminary results of these tests lead to projections of initial 11 C beams of up to 2.5 x 10 7 ions/sec and 14 O beams of 3 x 10 5 ions/sec

  17. Fluoro-2-deoxy-D-glucose (FDG)-PET in APOEepsilon4 carriers in the Australian population.

    Science.gov (United States)

    Rimajova, Mira; Lenzo, Nat P; Wu, Jing-Shan; Bates, Kristyn A; Campbell, Andrew; Dhaliwal, Satvinder S; McCarthy, Michael; Rodrigues, Mark; Paton, Athena; Rowe, Christopher; Foster, Jonathan K; Martins, Ralph N

    2008-03-01

    Apolipoprotein E-epsilon4 (APOEepsilon4) has been associated with increased risk of developing Alzheimer's disease (AD) and regional cerebral glucose hypometabolism, as measured by fluoro-2-deoxy-D-glucose-positron emission tomography (FDG-PET). We report here preliminary data from studies that aim to determine whether cerebral glucose hypometabolism is observed in APOEepsilon4 positive, cognitively intact individuals between the ages of 50 and 80, and whether there is an additional impact of subjective memory complainer (SMC) status on glucose metabolism determined by NeuroStat analysis. FDG-PET was conducted in 30 community dwelling, APOE-epsilon4 carriers without clinical evidence of dementia and objective cognitive impairment as assessed using a neuropsychological battery. Neurological soft-signs (NSS) were also assessed. Glucose hypometabolism was demonstrated in the anterior and posterior cingulate cortex and in the temporal association cortices in APOEepsilon4 carriers compared to the normative NeuroStat database. This pattern was particularly evident in APOEepsilon4 heterozygous individuals. SMC showed hypometabolism in the aforementioned brain regions, whereas non-SMC showed no significant pattern of glucose hypometabolism. FDG-PET with NeuroStat analysis showed that APOEepsilon4 carriers have mild glucose hypometabolism in areas associated with AD. SMC may be associated with AD-related differences in regional cerebral glucose metabolism. These findings are currently being investigated in a larger group of APOEepsilon4 carriers.

  18. 3rd Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    International Nuclear Information System (INIS)

    Gregory, Louis

    2014-01-01

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. This report summarizes the 3rd quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014 in Tables 4 and 5. Tabular summaries are provided which include the following: Sources of and carriers for LLW and MLLW shipments to and from the NNSS; Number and external volume of LLW and MLLW shipments; Highway routes used by carriers; and Incident/accident data applicable to LLW and MLLW shipments. In this report shipments are accounted for upon arrival at the NNSS, while disposal volumes are accounted for upon waste burial. The disposal volumes presented in this report do not include minor volumes of non-radioactive materials that were approved for disposal. Volume reports showing cubic feet generated using the Low-Level Waste Information System may vary slightly due to differing rounding conventions.

  19. Method of processing low-level radioactive liquid wastes

    International Nuclear Information System (INIS)

    Matsunaga, Ichiro; Sugai, Hiroshi.

    1984-01-01

    Purpose: To effectively reduce the radioactivity density of low-level radioactive liquid wastes discharged from enriched uranium conversion processing steps or the likes. Method: Hydrazin is added to low-level radioactive liquid wastes, which are in contact with iron hydroxide-cation exchange resins prepared by processing strongly acidic-cation exchange resins with ferric chloride and aqueous ammonia to form hydrorizates of ferric ions in the resin. Hydrazine added herein may be any of hydrazine hydrate, hydrazine hydrochloride and hydranine sulfate. The preferred addition amount is more than 100 mg per one liter of the liquid wastes. If it is less than 100 mg, the reduction rate for the radioactivety density (procession liquid density/original liquid density) is decreased. This method enables to effectively reduce the radioactivity density of the low-level radioactive liquid wastes containing a trace amount of radioactive nucleides. (Yoshihara, H.)

  20. Do methicillin resistant staphylococcus (MRSA) carrier patients influence MRSA infection more than MRSA-carrier medical officers and MRSA-carrier family?

    Science.gov (United States)

    Dilogo, Ismail H; Arya, Abikara; Phedy; Loho, Tony

    2013-07-01

    to determine the rate of MRSA-carrier among patients, family members and health care providers, and the association between MRSA-carrier family members and health care providers on MRSA infection patient after orthopaedic surgery. this is a cross-sectional analytical study. Samples were taken consecutively during December 2010 to December 2011, consisting of postoperative patients infected with MRSA, attending family members, and the medical officers with history of contact with the patient. Swab culture were taken from nasal and axilla of all subjects. The incidence of MRSA infection, and MRSA-carrier on the patient, family members and medical officers were presented descriptively, while their association with MRSA infection was statistically tested using Fischer exact test. during the study period, there were 759 surgeries, with 4 (0.5%) patients were identified to have MRSA infection. Of these four cases, 48 subjects were enrolled. The rate of MRSA-carrier among patients, family and health care providers were 50%, 25% and 0% respectively. There were no significant association between MRSA and the rates of MRSA-carrier on the family member or health care providers. the incidence of MRSA infection, MRSA-carrier patient, MRSA-carrier health care providers, and family member carrier were 0.5%, 50%, 0%, and 25% respectively. No significant association found between MRSA-carrier on the family member or health care providers and MRSA infection patient. There were no MRSA infection found on the health care provider.

  1. Aluminum-Scandium: A Material for Semiconductor Packaging

    Science.gov (United States)

    Geissler, Ute; Thomas, Sven; Schneider-Ramelow, Martin; Mukhopadhyay, Biswajit; Lang, Klaus-Dieter

    2016-10-01

    A well-known aluminum-scandium (Al-Sc) alloy, already used in lightweight sports equipment, is about to be established for use in electronic packaging. One application for Al-Sc alloy is manufacture of bonding wires. The special feature of the alloy is its ability to harden by precipitation. The new bonding wires with electrical conductivity similar to pure Al wires can be processed on common wire bonders for aluminum wedge/wedge (w/w) bonding. The wires exhibit very fine-grained microstructure. Small Al3Sc particles are the main reason for its high strength and prevent recrystallization and grain growth at higher temperatures (>150°C). After the wire-bonding process, the interface is well closed. Reliability investigations by active power cycling demonstrated considerably improved lifetime compared with pure Al heavy wires. Furthermore, the Al-Sc alloy was sputter-deposited onto silicon wafer to test it as chip metallization in copper (Cu) ball/wedge bonding technology. After deposition, the layers exhibited fine-grained columnar structure and small coherent Al3Sc particles with dimensions of a few nanometers. These particles inhibit softening processes such as Al splashing in fine wire bonding processes and increase the thickness of remnant Al under the copper balls to 85% of the initial thickness.

  2. Effect of flow rate on the adsorption coefficient of radioactive krypton on activated carbon

    International Nuclear Information System (INIS)

    Sun, L.S.C.; Underhill, D.W.

    1981-01-01

    For some time, there have been questions relative to the effect of carrier gas velocity on the adsorption coefficient for radioactive noble gases on activated charcoal. Resolution of these questions is particularly important in terms of developing standard procedures for determining such coefficients under laboratory conditions. Studies at the Harvard Air Cleaning Laboratory appear to confirm that the adsorption coefficient for radioactive krypton on activated charcoal is independent of the velocity of the carrier gas

  3. Scandium-doped zinc cadmium oxide as a new stable n-type oxide thermoelectric material

    DEFF Research Database (Denmark)

    Han, Li; Christensen, Dennis Valbjørn; Bhowmik, Arghya

    2016-01-01

    Scandium-doped zinc cadmium oxide (Sc-doped ZnCdO) is proposed as a new n-type oxide thermoelectric material. The material is sintered in air to maintain the oxygen stoichiometry and avoid instability issues. The successful alloying of CdO with ZnO at a molar ratio of 1 : 9 significantly reduced...... is a good candidate for improving the overall conversion efficiencies in oxide thermoelectric modules. Meanwhile, Sc-doped ZnCdO is robust in air at high temperatures, whereas other n-type materials, such as Al-doped ZnO, will experience rapid degradation of their electrical conductivity and ZT....

  4. Radioactive wastes transport. A safety logic

    International Nuclear Information System (INIS)

    2005-01-01

    The safety principle which applies to transport operations of radioactive wastes obeys to a very strict regulation. For the conditioning of wastes in package, the organisation of shipments and the qualification of carriers, the ANDRA, the French national agency of radioactive wastes, has implemented a rigorous policy based on the respect of a quality procedure and on the mastery of delivery fluxes. This brochure presents in a simple, illustrated and detailed manner the different steps of these transports. (J.S.)

  5. [Enterotoxin genes occurance among S. aureus strains isolated from inpatients and carriers].

    Science.gov (United States)

    Lawrynowicz-Paciorek, Maja; Kochman, Maria; Piekarska, Katarzyna; Wyrebiak, Agata; Potracka, Ewa; Leniak-Chmiel, Urszula; Magdziak, Agnieszka

    2006-01-01

    We examined 44 inpatients and 66 carriers Staphylococcus aureus strains, isolated in years 2002-2005, for the presence of 18 enterotoxin genes (se/sel) (by PCR), the ability for A-D enterotoxin production (by SET-RPLA) and antibiotic resistance distribution (by disc diffusion method). se/sel genes were detected in 90,9% of all strains, sea (70,5%) and selk and selq (52,3%) - among inpatients strains and egc (65,2%) - among carriers strains were the most frequently se/sel genes found. Positive results of SET-RPLA were consistent with PCR results. There was no correlation observed between antibiotic resistance and se/sel genes distribution among tested S. aureus strains.

  6. Regulation on radioactive waste management, Governmental Agreement No. 559-98

    International Nuclear Information System (INIS)

    1998-01-01

    This regulation defines the responsibilities on the radioactive waste management in Guatemala including the requirements of users, handling of radioactive wastes, authorization of radioactive waste disposal, transport of radioactive wastes and penalties

  7. Transport of radioactive materials

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-04-15

    The increasing use of radioactive substances, not only in reactor operations but also in medicine, industry and other fields, is making the movement of these materials progressively wider, more frequent and larger in volume. Although regulations for the safe transport of radioactive materials have been in existence for many years, it has now become necessary to modify or supplement the existing provisions on an international basis. It is essential that the regulations should be applied uniformly by all countries. It is also desirable that the basic regulations should be uniform for all modes of transport so as to simplify the procedures to be complied with by shippers and carriers

  8. Evaluation of added phosphorus in six volcanic ash soils

    International Nuclear Information System (INIS)

    Pino N, I.; Casas G, L.; Urbinsa P, M.C.

    1984-01-01

    The behaviour of added phosphorus in six volcanic ash soils (Andepts) was studied. Two phosphate retention solution were used; one of them labeled with 32 P carrier free. The phosphate retention solution (25 ml) was added to 5 gr of air dry soil. The remainder phosphorus in solution was measured through colorimetry and liquid scintillation. Over 85% phosphorus retention was measured in five soils. A phosphate retention solution labeled with 32 P carrier free proved to be efficient for the determination of phosphorus retention rates in the volcanic ash soils studied. (Author)

  9. Decontaminating method for radioactive contaminant

    International Nuclear Information System (INIS)

    Suzuki, Ken-ichi.

    1994-01-01

    After decontamination of radioactive contaminates with d-limonene, a radioactive material separating agent not compatible with liquid wastes caused by decontamination is added to the liquid wastes. Then after stirring, they are stood still to be separated into two phases, and the radioactive materials in the liquid waste phase caused by decontamination are transferred to the phase of the radioactive material separating agent. With such procedures, they can satisfactorily be separated into two phases of d-limonene and the radioactive material separating agent. Further, d-limonene remaining after the separation can be used again as a decontaminating agent for radioactive contaminates. Therefore, the amount of d-limonene to be used can be reduced, to lower the cost for cleaning, thereby enabling to reduce the amount of radioactive wastes formed. (T.M.)

  10. The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang No 3 and 4 and No 5 and 6

    International Nuclear Information System (INIS)

    Yeom, Yu Sun; Kim, Soong Pyung; Lee, Seung Jin

    2004-01-01

    Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP No 5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473 mCi and 1.098 mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was 2.97 x 10 -6 mSv for the evaporating system, and 6.47 x 10 -6 mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

  11. The Comparison on Treatment Method of Liquid Radioactive Waste in Yonggwang No 3 and 4 and No 5 and 6

    Energy Technology Data Exchange (ETDEWEB)

    Yeom, Yu Sun; Kim, Soong Pyung [Chosun University, Gwangju (Korea, Republic of); Lee, Seung Jin [RedTek CO., LTD., Daejeon (Korea, Republic of)

    2004-09-15

    Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), and into radiochemical and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foam, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED), instead of the current evaporation process, has been introduced into the Yonggwang NPP No 5 and 6. These two methods have been compared to understand the differences in this study. Aspects compared here were the released radioactivity amount of the liquid radioactive wastes, the dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. The IED system is designed to discharge higher radioactivity about 20% than the evaporating system, and the actual radioactivity released from the evaporating and IED system were 0.473 mCi and 1.098 mCi, respectively. The radioactivity released from the IED was 2.32 times higher than that of the evaporating system. The dose of off-site residents was 2.97 x 10{sup -6} mSv for the evaporating system, and 6.47 x 10{sup -6} mSv for IED. The decontamination factor(DF) of the evaporator is, in most cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the low concentration of the liquid wastes collected from the liquid waste system, the decontamination factor of IED is very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation system, the comparison on these two systems has been conducted on the basis of the design, and the comparison result was that the evaporating system generated more wastes about 40% than IED.

  12. Environments with elevated radiation levels from natural radioactive substances

    International Nuclear Information System (INIS)

    Sohrabi, M.

    2000-01-01

    Some areas in the world have elevated levels of radioactive substances in the environment forming elevated radiation areas (ERAs) where public potential annual effective doses can exceed even the dose limit of radiation workers. Such radioactive substances are either terrestrial natural radioactivity added naturally in the soil or natural and/or man-made radioactivity from human activities added into the environment. If radioactivity is added naturally, elevated natural radiation areas (ENRAs) are formed. Based on the classification criteria introduced by the author, such regions are divided into static and dynamic areas. They are also classified in accordance with their level of potential effective dose to the public. Some main ENRAs are classified. Highlights are presented of the results of activity studies carried out in selected areas. The concepts discussed can also be applied to areas formed by human activities. The author suggests some guidelines for future studies, regulatory control and decision making, bearing in mind the need for harmonization of policies for regulatory control and remedial actions at sites to protect the public from environmental chronic exposures. (author)

  13. Insights into the mantle geochemistry of scandium from a meta-analysis of garnet data

    Science.gov (United States)

    Chassé, Mathieu; Griffin, William L.; Alard, Olivier; O'Reilly, Suzanne Y.; Calas, Georges

    2018-06-01

    The meta-analysis of about 13,000 analyses of scandium content in garnet grains shows that, below the spinel-garnet transition, this phase carries about three-quarters of the Sc budget of the mantle, indicating its control on Sc mobility. The Sc content of garnets in mafic rocks is low, due to a dilution effect resulting from their high modal content in garnet. Garnets from ultramafic rocks exhibit a wider range of Sc concentrations. We assess the relative influence of thermobarometry, crystal chemistry and fluid-related events on the distribution of Sc in garnet from such rocks to improve the tracking of geochemical processes in the mantle. Pressure and temperature of equilibration in the mantle are second-order factors influencing the Sc content of garnet, while crystal chemistry, in particular Cr/Cr+Al and Ca/Ca+Mg, is the main parameter controlling the compatibility of Sc. Scandium is incorporated in both X and Y sites of Cr-Ca-rich garnets, resulting in a behaviour intermediate between rare-earth elements, incorporated in the X site, and trivalent transition elements, occupying the Y site. This affinity for both sites results in a mild compatibility of Sc in the garnet stability field of the mantle; hence Sc concentration in garnet increases with melt extraction and can be reduced by silicate-melt metasomatism. In contrast, metasomatism by volatile-rich fluids increases the Sc concentration in garnet. The control of garnet on the compatibility of Sc in deep lithospheric rocks demonstrates the potential of using Sc to track the conditions of formation of magmas and their residual rocks, as well as the origin and nature of metasomatic fluids.

  14. Sor/89-426, 24 August 1989, transport packaging of radioactive materials regulations, amendment

    International Nuclear Information System (INIS)

    1989-09-01

    These Regulations of 24 September 1983 were amended mainly to clarify the original text and further specify certain requirements. In particular, the definitions of A 1 , A 2 , Fissile Class III package and special Form Radioactive Material have been revoked and replaced by new definitions. Also, a new condition has been added regarding Special Form Radioactive Material. Henceforth, no such material may be transported without a certificate attesting that the material meets the requirements set out in Schedule XII of the Regulations [fr

  15. Potential for photocatalytic degradation of the potassic diclofenac using scandium and silver modified titanium dioxide thin films; Potencial de degradacao fotocatalitica do diclofenaco potassico utilizando filmes finos de dioxido de titanio modificado com escandio e prata

    Energy Technology Data Exchange (ETDEWEB)

    Ciola, R.A.; Oliveira, C.T.; Lopes, S.A.; Cavalheiro, A.A., E-mail: rafaelciola@hotmail.com [Universidade Estadual de Mato Grosso do Sul (UFMS), Navirai, MS (Brazil). Centro de Pesquisas Tecnologicas em Recursos Naturais

    2011-07-01

    The potential for photocatalytic degradation of the potassic diclofenac drug was investigated using titanium dioxide thin films modified with two modifier types, scandium and silver, both prepared by Sol-Gel method. It was demonstrated by UVVis spectroscopy analysis of the solutions containing the drug, under UV-A light irradiation that the degradation efficiency of the titanium dioxide photocatalyst is dependent of the semiconductor nature and that the scandium accelerates the first step of the degradation when compared to the silver. This result seems to be related to the redox potential of the electron-hole pair, once the scandium modifying sample generates a p type semiconductor that reduces the band gap. The extra holes attract more strongly the chorine ion present in diclofenac and leading to the releasing more easily. However, after the first byproducts degradation the following steps are not facilitated, making the silver modifying more advantageous. (author)

  16. Radon generator and the method of radium carrier fabrication

    International Nuclear Information System (INIS)

    Czerski, B.

    1992-01-01

    The radon generator construction and the method of radium carrier fabrication has been the subject of the patent. The generator is a cylindrical vessel with gas valves system and two filters inside. Between them the radium carrier has been located. As a carrier polyurethane foam has been used. The carrier is obtained in a generator vessel from polyester resin in the presence of activated mixture of engine oil, zinc-organic catalyst and toluene. To the obtained mixture the radium chloride in the solution of hydrochloric acid is added. The carrier foam is produced by mechanical stirring of substrates inside the vessel and drying in 50 C in a heater. 1 fig

  17. Guide to the design, testing and use of packaging for the safe transport of radioactive materials

    International Nuclear Information System (INIS)

    1976-01-01

    This guide gives to designers, manufacturers and users of packaging, advice supplementary to, or in amplification of, the recommendations made by the International Atomic Energy Agency for the safe transport of radioactive materials as given in IAEA Safety Series No. 6 (1973) and the advisory material given in IAEA Safety Series No. 37 (1973). This guide should be read and used in conjunction with these recommendations, the appropriate national regulations and any applicable regulations or requirements of the carriers concerned. (author)

  18. Dielectric matrix, dynamical matrix and phonon dispersion in hcp transition metal scandium

    International Nuclear Information System (INIS)

    Singh, Joginder; Singh, Natthi; Prakash, S.

    1976-01-01

    Complete dielectric matrix is evaluated for hcp transition metal scandium using the non-interacting s- and d-band model. The local field corrections which are consequence of the non-diagonal part of the dielectric matrix are calculated explicitly. The free electron approximation is used for the s-electrons and the simple tight-binding approximation is used for the d-electrons. The theory developed by Singh and others is used to invert the dielectric matrix and the explicit expressions for the dynamical matrix are obtained. The phonon dispersion relations are investigated by using the renormalized Animalu transition metal model potential (TMMP) for bare ion potential. The contribution due to non-central forces which arise due to local fields is found to be 20%. The results are found in resonably good agreement with the experimental values. (author)

  19. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

    Gablin, K.A.; Hansen, L.J.

    1979-01-01

    A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container. 30 claims

  20. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

    Gablin, K.A.; Hansen, L.J.

    1977-01-01

    A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container

  1. Radioactivity survey data in Japan, no. 55

    International Nuclear Information System (INIS)

    1980-12-01

    Gamma-ray spectrometry with Ge (Li) detectors was applied to all samples. Artificial radionuclides such as Cs-137, Mn-54 and Co-60 were identified, and their concentrations were determined. Samples were cultured fish, caught fish and marine sediment. The important species were selected in consideration of their importance as ecological indicators and natural resources. The indicator species were selected in consideration of their significant characteristics of accumulating the radionuclides. The treatment of fish and sediment for the measurement is described. The radioactivity of the samples was measured with Ge (Li) detectors for 20 to 24 hours. Radioactive background was measured for 40 to 48 hours at intervals of one week. The radionuclides were identified by analyzing the observed gamma-ray spectra. The corresponding peak area of each radionuclide was calculated, and radioactive background was subtracted. The amounts of the radioactive nuclides were estimated from these net peak areas by correcting them with the counting efficiency of the detectors, sample geometry and others. Besides the detectors, a pulse height analyzer and data output equipments were used. The criteria for the precision of measurement are defined, and the results of analysis are reported for the samples collected from December, 1978, to February, 1980. This report was drawn up by the National Institute of Radiological Sciences. (Kako, I.)

  2. Radioactive Decay

    Science.gov (United States)

    Radioactive decay is the emission of energy in the form of ionizing radiation. Example decay chains illustrate how radioactive atoms can go through many transformations as they become stable and no longer radioactive.

  3. Research on energy efficiency design index for sea-going LNG carriers

    Science.gov (United States)

    Lin, Yan; Yu, Yanyun; Guan, Guan

    2014-12-01

    This paper describes the characteristics of liquefied natural gas (LNG) carriers briefly. The LNG carrier includes power plant selection, vapor treatment, liquid cargo tank type, etc. Two parameters—fuel substitution rate and recovery of boil of gas (BOG) volume to energy efficiency design index (EEDI) formula are added, and EEDI formula of LNG carriers is established based on ship EEDI formula. Then, based on steam turbine propulsion device of LNG carriers, mathematical models of LNG carriers' reference line value are established in this paper. By verification, the EEDI formula of LNG carriers described in this paper can provide a reference for LNG carrier EEDI calculation and green shipbuilding.

  4. Influence of scandium on the microstructure and mechanical properties of A319 alloy

    International Nuclear Information System (INIS)

    Emadi, Daryoush; Rao, A.K. Prasada; Mahfoud, Musbah

    2010-01-01

    Recycling of aluminum scrap alloys by melting is gaining its importance in foundry sector. During recycling, some of the alloying elements present in scrap alloys eventually become trace/tramp impurities in the recycled alloy. These elements could potentially affect the alloy's microstructure and hence its mechanical properties. In the present work, an attempt has been made to investigate the effect of one of such trace elements on the microstructure and mechanical properties of A319 alloy. The element chosen for the present investigation is scandium (Sc). This paper discusses the effects of the additions of trace amount of Sc on the microstructure and mechanical properties of A319 alloy in as-cast, T6 and T7 heat treated conditions.

  5. Synthesis of {sup 188}Re-DMSA complex using carrier-free {sup 188}Re

    Energy Technology Data Exchange (ETDEWEB)

    Hashimoto, Kazuyuki; Izumo, Mishiroku [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Islam, M S

    1997-03-01

    The synthesis of rhenium-DMSA labelled compound using carrier-free {sup 188}Re from the {sup 188}W/{sup 188}Re generator has been carried out. Stannous chloride was used as the reducing agent for reduction of rhenium and ascorbic acid was used as an antioxidant in the reaction media. The dependence of the yield of Re-DMSA complex upon the concentration of reducing agent, pH, reaction time, anti-oxidant, carrier and temperature was investigated. Under optimum conditions, the yield of Re-DMSA complexes were more than 98% for the carrier-free as well as carrier-added {sup 188}Re. The stability of the Re-DMSA complexes at different pH and time were also investigated. It was found that the Re-DMSA complex was very stable and did not undergo any changes or decomposition with the changes of pH from its initial values even after 48 hours of pH change for carrier-free as well as carrier-added complexes. (author)

  6. Tungsten-188/carrier-free rhenium-188 perrhenic acid generator system

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Lisic, E.C.; Mirzadeh, S.; Callahan, A.P.

    1993-01-01

    A generator system for providing a carrier-free radioisotope in the form of an acid comprises a chromatography column in tandem fluid connection with an ion exchange column, the chromatography column containing a charge of a radioactive parent isotope. The chromatography column, charged with a parent isotope, is eluted with an alkali metal salt solution to generate the radioisotope in the form of an intermediate solution, which is passed through the ion-exchange column to convert the radioisotope to a carrier-free acid form

  7. Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

    International Nuclear Information System (INIS)

    2014-01-01

    This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

  8. A novel boron-rich quaternary scandium borocarbosilicide Sc3.67-xB41.4-y-zC0.67+zSi0.33-w

    International Nuclear Information System (INIS)

    Tanaka, Takaho; Yamamoto, Akiji; Sato, Akira

    2004-01-01

    A novel quaternary scandium borocarbosilicide Sc 3.67-x B 41.4-y-z C 0.67+z Si 0.33-w was found. Single crystallites were obtained as an intergrowth phase in the float-zoned single crystal of Sc 0.83-x B 10.0-y C 0.17+y Si 0.083-z that has a face-centered cubic crystal structure. Single crystal structure analysis revealed that the compound has a hexagonal structure with lattice constants a = b = 1.43055(8) nm and c = 2.37477(13) nm and space group P6-barm2 (No. 187). The crystal composition calculated from the structure analysis for the crystal with x = 0.52, y = 1.42, z = 1.17, and w = 0.02 was ScB 12.3 C 0.58 Si 0.10 and that agreed rather well with the composition of ScB 11.5 C 0.61 Si 0.04 measured by EPMA. In the crystal structure that is a new structure type of boron-rich borides, there are 79 structurally independent atomic sites, 69 boron and/or carbon sites, two silicon sites and eight scandium sites. Boron and carbon form seven structurally independent B 12 icosahedra, one B 9 polyhedron, one B 10 polyhedron, one irregularly shaped B 16 polyhedron in which only 10.7 boron atoms are available because of partial occupancies and 10 bridging sites. All polyhedron units and bridging site atoms interconnect each other forming a three-dimensional boron framework structure. Sc atoms reside in the open spaces in the boron framework structure

  9. Development of radioactivity estimation system considering radioactive nuclide movement

    International Nuclear Information System (INIS)

    Fukumura, Nobuo; Miyamoto, Yoshiaki

    2010-01-01

    A radioactivity estimation system considering radioactive nuclide movement is developed to integrate the established codes and the code system for decommissioning of sodium cooled fast reactor (FBR). The former are the codes for estimation of radioactivity movement in sodium coolant of fast reactor which are named SAFFIRE, PSYCHE and TTT. The latter code system is to estimate neutron irradiation activity (COSMARD-RRADO). It is paid special attention to keep the consistency of input data used among these codes and also the simplification of their interface. A new function is added to the estimation system, to estimate minor FP inventory caused by the fission of impurities contained in the coolant and slight fuel material attached on the fuel cladding. To check the evaluation system, the system is applied with radioactivity data of the preceding FBR such as BN-350, JOYO and Monju. Agreement between the analysis results and the measurement is well satisfactory. The uncertainty of the code system is within several tens per cent for the activation of primary coolant (Na-22) and factor of 2-4 for the estimation of radioactivity inventory in sodium coolant. (author)

  10. Aluminum-Scandium Alloys: Material Characterization, Friction Stir Welding, and Compatibility With Hydrogen Peroxide (MSFC Center Director's Discretionary Fund Final Report, Proj. No. 04-14)

    Science.gov (United States)

    Lee, J. A.; Chen, P. S.

    2004-01-01

    This Technical Memorandum describes the development of several high-strength aluminum (Al) alloys that are compatible with hydrogen peroxide (H2O2) propellant for NASA Hypersonic-X (Hyper-X) vehicles fuel tanks and structures. The yield strengths for some of these Al-magnesium-based alloys are more than 3 times stronger than the conventional 5254-H112 Al alloy, while maintaining excellent H2O2 compatibility similar to class 1 5254 alloy. The alloy development strategy is to add scandium, zirconium, and other transitional metals with unique electrochemical properties, which will not act as catalysts, to decompose the highly concentrated 90 percent H2O2. Test coupons are machined from sheet metals for H2O2 long-term exposure testing and mechanical properties testing. In addition, the ability to weld the new alloys using friction stir welding has also been explored. The new high-strength alloys could represent an enabling material technology for Hyper-X vehicles, where flight weight reduction is a critical requirement.

  11. Systemic Endoradiotherapy with Carrier Added 4 [131I] Iodo LPhenylalanine: Clinical Proof of principle in Refractory Glioma

    International Nuclear Information System (INIS)

    Baum, Richard P.; Schuchardt, Christiane; Senftleben, Stephan; Gildehaus, Franz Josef; Samnick, Samuel; Kluge, Andreas; Bronzel, Marcus; Schmidt, Karl

    2011-01-01

    To explore feasibility, tolerability, dosimetry and probable efficacy of intravenous endoradiotherapy with carrier added 4 [ 131I ]iodo Lp henylalanine (c.a. 131I IPA) in refractory high grade glioma. Two male patients (45 and 50 years), with long standing, extensively pretreated gliomas and evidence of progression underwent single intravenous injections of 2 and 4 GBq of c.a. 131I IPA, respectively. Tumor targeting was verified by 131I IPA single photon emission computed tomography (SPECT). Metabolic and morphological changes indicative of tumour response were assessed by sequential [ 18F ] fluoroethyltyrosine ( 18F FET) positron emission tomography (PET) and contrast enhanced magnetic resonance imaging (MRI) following therapy. Further monitoring included clinical state, safety laboratory, quality of life and dosimetry. Absorbed mean organ and whole body doses were determined according to the Medical Internal Radiation Dose (MIRD) scheme using OLINDAEXM based on serial planar scintigraphy. Both patients tolerated the treatment well. No evidence of acute of delayed organ toxicity was observed. 131I IPA accumulated in the tumour recurrences identified by MRI/ 18F FET. In patient 1, PET showed progressively decreasing maximum standardised uptake values (SUVmax) over 10 months, indicating metabolic response, paralleled by reduced contrast enhancement and tumour volume on MRI. Progression occurred 18 months after therapy. Treatment was repeated using 6.6 GBq of 131I IPA, to which no response was observed. Patient 2, followed up for 3 months after therapy, showed stable disease on MRI and PET. Mean absorbed whole body doses ranged from 0.13 to 0.17 mSv/MBq, with the highest absorbed organ doses to kidneys, bladder and heart (0.86-1.23; 0.49-0.6 and 0.45-0.56 mSv/MBq). Systemic endoradiotherapy using up to 6.6 GBq of c.a. 131I IPA is not associated with clinically detectable toxicity. Measurable anti tumour effects in gliomas were observed. 131I IPA warrants further

  12. Report on the evaluation under the Act No 24/2006 of Coll. Environmental Impact Assessment Law Extension of National Radioactive Waste Repository in Mochovce for disposal low-level radioactive waste and construction of very low-level radioactive waste repository

    International Nuclear Information System (INIS)

    Hanusik, V.; Moravek, J.; Kusovska, Z.

    2011-01-01

    The report elaborated assessment of the environmental impact of extension of the National Radioactive Waste Repository in Mochovce for disposal of low and intermediate level radioactive wastes. Within this repository also the premises for very low level radioactive waste deposition should be built. The assessment report was prepared according to the Act no. 24/2006 Coll, as amended 'On the assessment of environmental impacts' Annex No. 11 upon The scope of assessment issued by the competent authority on the basis of assessment of Intent for this action. The report was prepared in VUJE, Inc. Trnava for Nuclear and Decommissioning Company, Inc. Bratislava (JAVYS).

  13. There are no differences in IL-6, CRP and homocystein concentrations between women whose mothers had AD and women whose mothers did not have AD.

    Science.gov (United States)

    Devčić, Sanja; Glamuzina, Ljubomir; Ruljancic, Nedjeljka; Mihanovic, Mate

    2014-12-30

    A wide range of recent studies have detected inflammation as one of the most influent factors in the appearance and spreading of neurodegenerative brain diseases. We aimed to understand the influence of Interleukin-6 (IL-6), C-reactive protein (CRP) and homocysteine (Hcy) on patients suffering from Alzheimer׳s disease (AD) and on their descendants. Three groups of subjects were analyzed: 55 patients suffering from AD, 51 middle-aged daughters of the patients of the first group, and 53 subjects without positive family history of AD. The results of the conducted research are in accordance with the present scientific knowledge, namely a statistically significant difference for examined parameters has been determined between women suffering from AD and their daughters and control group examinees. No difference was found in serum concentrations of IL-6, highly sensitive C-reactive protein (hsCRP) and Hcy between the groups of the middle-aged descendants of patients with AD and healthy controls without family history of AD. This finding supports the hypothesis that these markers may not play causal role in the development of AD. This is supported by the obtained positive correlation between IL-6 and hsCRP and IL-6 and Hcy in AD patients while there is no such correlation between female subjects with or without a family history of AD. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  14. An overview of the transportation of radioactive waste at Ontario Power Generation facilities

    International Nuclear Information System (INIS)

    Holmes, P.

    2006-01-01

    The Radioactive Material Transportation Department (RMT) ensures regulatory compliance in radioactive material shipping within Ontario Power Generation (OPG). OPG provides a radioactive shipping program, high quality carrier service, stringent packaging maintenance, and quality assurance oversight to the corporation's nuclear facilities and its customers. This paper will speak to the transport of radioactive waste in Ontario Power Generation. It will also mention non-waste shipments and the quality assurance programme used at Ontario Power Generation to ensure a high quality transportation system. (author)

  15. New devices for better understanding of radioactive waste by general public

    International Nuclear Information System (INIS)

    Stritar, A.; Gortnar, O.; Kovacic, J.; Kozelj, M.; Mele, I.; Zeleznik, N.

    1999-01-01

    Several new exhibits, added to the nuclear information centre, are described. We have prepared a quiz about radioactive waste, interactive most frequently asked questions about radioactivity and radioactive waste, a World map of nuclear objects, a set of demonstration exercises and CD ROM about radioactive waste.(author)

  16. 'No thanks'-reasons why pregnant women declined an offer of cystic fibrosis carrier screening.

    Science.gov (United States)

    Ioannou, L; Massie, J; Lewis, S; McClaren, B; Collins, V; Delatycki, M B

    2014-04-01

    The objective of this study was to assess attitudes and opinions of women declining the offer of cystic fibrosis (CF) carrier screening through a population-based programme in Victoria, Australia. Between December 2009 and May 2011, women declining an offer of CF carrier screening were invited to participate in a questionnaire-based study. Recruitment was at two private obstetric ultrasound clinics and two private obstetric practices in Melbourne. Of the participants (n = 54), the majority were well educated (76%), aged 30-34 years (54%), with a household income of >AUD$100,000 (76%). Compared to those who accepted screening (reported in a previous study) (Ioannou et al., Public Health Genomics 13:449-56, 2010), knowledge levels were significantly lower in participants declining screening (t = 3.32, p < 0.01). The main reasons for declining screening were having no family history of CF (58%) and not considering a termination of pregnancy for CF (53%). Providers and consumers should be informed that most children born with autosomal-recessive conditions such as CF have no family history of the condition.

  17. Radioactive waste management

    International Nuclear Information System (INIS)

    Blomek, D.

    1980-01-01

    The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

  18. Preparation of highly specific radioactivity [18F]flumazenil and its evaluation in cynomolgus monkey by positron emission tomography

    International Nuclear Information System (INIS)

    Ryzhikov, Nikolaj N.; Seneca, Nicholas; Krasikova, Raisa N.; Gomzina, Natalia A.; Shchukin, Evgeny; Fedorova, Olga S.; Vassiliev, Dmitrij A.; Gulyas, Balazs; Hall, Hakan; Savic, Ivanka; Halldin, Christer

    2005-01-01

    A straightforward method for the preparation of no-carrier-added (n.c.a.) [ 18 F]flumazenil via standard nucleophilic radiofluorination of the corresponding nitro-analog Ro 15-2344 has been developed. The labeling was performed by employing the K 18 F/kryptofix complex in DMF at 160 deg. C for 30 min and equimolar ratio [K/K2.2.2] +18 F - /precursor. Under these conditions, an 18 F incorporation rate into flumazenil was in the range of 55-60%. The final product was isolated by HPLC purification within a total synthesis time of 75 min and a radiochemical yield of about 30% (EOB). Human post-mortem whole-hemisphere autoradiography of brain sections demonstrated selective uptake of the radioligand in the areas of high density of the central benzodiazepine receptors (BZR). PET studies in a cynomolgus monkey and metabolite studies by HPLC demonstrated similar results by [ 18 F]flumazenil as for [ 11 C]flumazenil. In blocking experiments, almost all radioactivity was inhibited by the addition of unlabeled flumazenil. [ 18 F]Flumazenil is a suitable radioligand for PET assessment of the BZR

  19. Biogenesis of tritiated and carbon-14 methane from low-level radioactive waste

    International Nuclear Information System (INIS)

    Francis, A.J.; Dobbs, S.; Doering, R.F.

    1980-01-01

    Methane bacteria were detected in leachate samples collected from commercial low-level radioactive waste disposal sites. Significant amounts of tritiated and carbon-14 methane were generated by a mixed methanogenic culture from a leachate sample collected from the low-level radioactive waste disposal site, Maxey Flats, KY. Tritiated methane was produced by methane bacteria from synthetic media containing 2 mCi of tritium as tritiated water or tritiated acetate, and the level of tritium added to the medium had no effect on methanogenesis. Under anaerobic conditions the organic compounds containing 14 C and 3 H activity and tritiated water in the waste are metabolized by microorganisms and they produce radioactive gases which escape into the environment from the disposal sites. 4 figures, 3 tables

  20. Enantioselective synthesis of no-carrier added (NCA) 6-[18F]Fluoro-L-Dopa

    International Nuclear Information System (INIS)

    Duanzhi Yin; Lan Zhang; Yongxian Wang; Ganghua Tang; First Military Medical Univ., Guangzhou; Xiaolan Tang

    2003-01-01

    6-[ 18 F]Fluoro-L-Dopa (6-FDOPA) is the analogue of L-Dopa, the biosynthesis precursor for dopamine. As a PET tracer, it was widely applied for the presynaptic dopamine function studies in human brain. The application of a chiral phase-transfer-catalyst (PTC) in enantioselective synthesis of N.C.A. 6-[ 18 F]Fluoro-L-Dopa has been developed recently. An improved procedure was described. The labeling precursor (6-Trimethylammoniumveratraldehyde Triflate) and PTC (O-Allyl-N-(9)-anthracenylcinchonidinium Bromide) were synthesized. A successful synthesis route was developed for the preparation of 6-[ 18 F]Fluoro-L-Dopa with high radiochemical yields (4-9%, decay uncorrected) and short synthesis time(80min). The radiochemical purity was over 99% and no D-isomer was detected by HPLC analysis using a chiral mobile phase. (author)

  1. A FDG-PET Study of Metabolic Networks in Apolipoprotein E ε4 Allele Carriers.

    Directory of Open Access Journals (Sweden)

    Zhijun Yao

    Full Text Available Recently, some studies have applied the graph theory in brain network analysis in Alzheimer's disease (AD and Mild Cognitive Impairment (MCI. However, relatively little research has specifically explored the properties of the metabolic network in apolipoprotein E (APOE ε4 allele carriers. In our study, all the subjects, including ADs, MCIs and NCs (normal controls were divided into 165 APOE ε4 carriers and 165 APOE ε4 noncarriers. To establish the metabolic network for all brain regions except the cerebellum, cerebral glucose metabolism data obtained from FDG-PET (18F-fluorodeoxyglucose positron emission tomography were segmented into 90 areas with automated anatomical labeling (AAL template. Then, the properties of the networks were computed to explore the between-group differences. Our results suggested that both APOE ε4 carriers and noncarriers showed the small-world properties. Besides, compared with APOE ε4 noncarriers, the carriers showed a lower clustering coefficient. In addition, significant changes in 6 hub brain regions were found in between-group nodal centrality. Namely, compared with APOE ε4 noncarriers, significant decreases of the nodal centrality were found in left insula, right insula, right anterior cingulate, right paracingulate gyri, left cuneus, as well as significant increases in left paracentral lobule and left heschl gyrus in APOE ε4 carriers. Increased local short distance interregional correlations and disrupted long distance interregional correlations were found, which may support the point that the APOE ε4 carriers were more similar with AD or MCI in FDG uptake. In summary, the organization of metabolic network in APOE ε4 carriers indicated a less optimal pattern and APOE ε4 might be a risk factor for AD.

  2. Interaction of scandium and titanium atoms with a carbon surface containing five- and seven-membered rings

    International Nuclear Information System (INIS)

    Krasnov, P. O.; Eliseeva, N. S.; Kuzubov, A. A.

    2012-01-01

    The use of carbon nanotubes coated by atoms of transition metals to store molecular hydrogen is associated with the problem of the aggregation of these atoms, which leads to the formation of metal clusters. The quantum-chemical simulation of cluster models of the carbon surface of a graphene type with scandium and titanium atoms has been performed. It has been shown that the presence of five- and seven-membered rings, in addition to six-membered rings, in these structures makes it possible to strongly suppress the processes of the migration of metal atoms over the surface, preventing their clustering.

  3. Partitioning of Iron and Scandium in Soils Having Water Drainage Limitations

    International Nuclear Information System (INIS)

    Aide, M.; Braden, I.; Mueller, W.

    2010-01-01

    Soil chemistry of Fe includes weathering reactions, adsorption, hydrolysis, complexation, and oxidation-reduction reactions. Soil chemistry for scandium (Sc) is similar, but Sc does not include oxidation-reduction reactions. To determine if geochemical analysis may be used to identify Sc partitioning with respect to Fe among the particle size fractions, two Alfisol and two Ultisol soils were assessed using an aqua-regia digestion to estimate Sc and Fe concentrations for whole soil and particle size separates. Aqua-regia digestion data showed Sc depletion relative to Fe in sand separate. Sand separate is largely composed on quartz sand and Fe-Mn-bearing nodules, which are redoximorphic features produced by alternating oxic and suboxic/anoxic conditions associated with seasonally fluctuating water tables. Relative partitioning of Fe and Sc in these soils warrants further study to assess if selective extractions could quantify the extent of modern or ancestral oxidation-reduction processes responsible in some soil features involved in soil genesis.

  4. BIOACTIVE COMPOUNDS IN CONVENTIONAL AND NO ADDED SUGARS RED STRAWBERRY GUAVA (Psidium cattleianum Sabine JELLIES

    Directory of Open Access Journals (Sweden)

    GABRIELA NIEMEYER REISSIG

    Full Text Available ABSTRACT This study aimed to prepare jellies of conventional type of red strawberry guava (with added sucrose and no added sugar and evaluate the physical and chemical composition and content of bioactive compounds in them. Four jellies formulations were prepared: conventional with addition of sucrose (F1, aspartame (F2, saccharin and cyclamate (F3, acesulfame and sucralose (F4. Physicochemical analysis of pH were carried out, as well as analysis of titratable acidity, total soluble solids, ashes, proteins, lipids, moisture, carbohydrates, calories, lightness, color tone, total phenols, anthocyanins, carotenoids, ascorbic acid and antioxidant activity, by the capture of DPPH and ABTS radicals. Conventional and no added sugars jellies did not differ for total phenols, total anthocyanins and ascorbic acid. However, processing exerted significant influence (p=0.05 on total carotenoids and antioxidant activity. It is feasible to use red strawberry guava for the preparation of conventional and no added sugar jellies. The products, however, show a significant difference in carotenoids content, with the highest content of these and higher antioxidant activity in processed jellies without sugars addition.

  5. Synthesis and evaluation of radioiodinated 6-Iodo-L-DOPA as a cerebral L-amino acid transport marker

    International Nuclear Information System (INIS)

    Kawai, K.; Ohta, H.; Kubodera, A.; Channing, M.A.; Eckelman, W.C.

    1996-01-01

    Regioselective radioiodination of N-trifluoroacetyl 3,4-dimethoxy-6-trifluoroacetoxymercurio-L-phenylalanine ethyl ester 1 under no-carrier-added condition gave 6-[ 125 I]iodo protected L-DOPA with a labeling efficiency of more than 85%, and no-carrier-added 6-[ 125 I]I-L-DOPA was obtained with a radiochemical purity of over 95% after hydrolysis and chromatography. A nonradioactive standard of 6-iodo protected L-DOPA was synthesized by the iododemercuration of 6-mercuric trifluoroacetate protected L-DOPA 1 using I 2 in chloroform. 6-[ 125 I]I-L-DOPA showed high brain accumulation and rapid blood clearance in mice. The rat brain slice studies indicated high affinity of 6-[ 125 I]I-L-DOPA for carrier-mediated and stereoselective active transport systems. The tissue homogenate analysis revealed that most of the accumulated radioactivity was intact 6-[ 125 I]I-L-DOPA. Thus, 6-[ 123 I]I-L-DOPA appears to be a suitable single photon emission computed tomography (SPECT) tracer for the selective measurement of cerebral L-amino acid transport, having no affinity for dopamine metabolism

  6. A new method for the labelling of proteins with radioactive arsenic isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Jennewein, M. [Institute of Nuclear Chemistry, Johannes Gutenberg University of Mainz, Fritz-Strassmann-Weg 2, 55128 Mainz (Germany); Hermanne, A. [VUB Cyclotron, University of Brussels, Laarbeeklaan 103, 1090 Brussels (Belgium); Mason, R.P. [Department of Radiology, Advanced Radiological Sciences, University of Texas Southwestern Medical Center at Dallas, Dallas, Texas (United States); Thorpe, P.E. [Department of Pharmacology and Simmons and Hamon Cancer Centers, University of Texas Southwestern Medical Center at Dallas, Dallas, TX (United States); Roesch, F. [Institute of Nuclear Chemistry, Johannes Gutenberg University of Mainz, Fritz-Strassmann-Weg 2, 55128 Mainz (Germany)]. E-mail: frank.roesch@uni-mainz.de

    2006-12-20

    Radioarsenic labelled radiopharmaceuticals could be a valuable asset to positron emission tomography. In particular, the long half-lives of {sup 72}As (T{sub 1/2}=26h) and {sup 74}As (T{sub 1/2}=17.8d) allow to investigate slow physiological or metabolical processes, like the enrichment and distribution of monoclonal antibodies (mab) in tumour tissue. In this work, a new method for the labelling of proteins with various radioactive arsenic isotopes was developed. For this purpose, two proteins, namely a chimeric IgG{sub 3} monoclonal antibody, ch3G4, directed against anionic phospholipids, and Rituxan (Rituximab), were labelled as a proof of principle with no-carrier-added radioarsenic isotopes ({sup 74}As and {sup 77}As). The developed labelling chemistry gives high yields (>99.9%), is reliable and could easily be transferred to automated labelling systems in a clinical environment. At least for the mab used in this work, this route of radioarsenic labelling does not affect the immunoreactivity of the product. The arsenic label stays stable for up to 72h at the molecular mass of the monoclonal antibody, which is in particular relevant to follow the pharmacology and pharmacokinetics of the labelled mab for several days.

  7. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Takahashi, Toshihiko; Maruko, Morihisa; Takamura, Yoshiyuki.

    1981-01-01

    Purpose: To effectively separate radioactive claddings from the slurry of wasted ion exchange resins containing radioactive claddings. Method: Wasted ion exchange resins having radioactive claddings (fine particles of iron oxides or hydroxide adhered with radioactive cobalt) are introduced into a clad separation tank. Sulfuric acid or sodium hydroxide is introduced to the separation tank to adjust the pH value to 3 - 6. Then, sodium lauryl sulfate is added for capturing claddings and airs are blown from an air supply nozzle to generate air bubbles. The claddings are detached from the ion exchange resins and adhered to the air bubbles. The air bubbles adhered with the claddings float up to the surface of the liquid wastes and then forced out of the separation tank. (Ikeda, J.)

  8. Radioactive waste management status and trends - Issue no. 4, February 2005

    International Nuclear Information System (INIS)

    2005-03-01

    The purpose of this publication is to compile and disseminate information about the status of and trends in radioactive waste management in IAEA Member States in a timely manner. The publication is suitable for radioactive waste managers and regulators, and decision making organizations in both governmental and private sectors. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. It addresses national systems for radioactive waste management, classification of radioactive waste, sources of radioactive waste, decommissioning of nuclear facilities, predisposal management of radioactive waste, managing the consequences of best practices, data collection and reporting and highlights of the work of the IAEA and other international organizations in 2003. It ends with achievements and challenges, acronyms, abbreviations, symbols and expressions. The plan is to have the publication evolve to serve a broader audience using easy-to-understand graphical and tabular data

  9. Radioactive waste management status and trends - Issue no. 4, February 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-03-15

    The purpose of this publication is to compile and disseminate information about the status of and trends in radioactive waste management in IAEA Member States in a timely manner. The publication is suitable for radioactive waste managers and regulators, and decision making organizations in both governmental and private sectors. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. It addresses national systems for radioactive waste management, classification of radioactive waste, sources of radioactive waste, decommissioning of nuclear facilities, predisposal management of radioactive waste, managing the consequences of best practices, data collection and reporting and highlights of the work of the IAEA and other international organizations in 2003. It ends with achievements and challenges, acronyms, abbreviations, symbols and expressions. The plan is to have the publication evolve to serve a broader audience using easy-to-understand graphical and tabular data.

  10. Thermodynamic study of sublimation, melting and vaporization of scandium(III) dipivaloylmethanate derivatives

    International Nuclear Information System (INIS)

    Zherikova, Kseniya V.; Zelenina, Ludmila N.; Chusova, Tamara P.; Gelfond, Nikolay V.; Morozova, Natalia B.

    2016-01-01

    Highlights: • Thermal properties of two volatile fluorinated Sc(III) beta-diketonates were studied. • Saturated and unsaturated vapor pressures were measured. • DSC analysis was carried out. • Sublimation, evaporation and melting enthalpies and entropies were derived. • Effect of fluorine introduction on volatility and thermal stability was established. - Abstract: The present work deals with the investigation of thermal properties of two volatile scandium(III) beta-diketonates with 2,2,6,6-tetramethyl-4-fluoro-3,5-heptanedione and 1,1,1-trifluoro-5,5-dimethyl-2,4-hexanedione which have been synthesized and purified. Using the static method with glass membrane gauge-manometer the temperature dependencies of saturated and unsaturated vapor pressure were measured for the first time. The temperatures and enthalpies of melting were measured for these compounds by differential scanning calorimetry. The standard thermodynamic characteristics of enthalpy and entropy for sublimation, vaporization and melting processes were derived.

  11. Environmental radioactive monitoring in Itu, Sao Paulo, Brazil; Monitoramento de radioatividade ambiental no municipio de Itu

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The results of the environmental monitoring of a region near to a radioactive materials deposit in Sao Paulo State, Brazil, are presented. The radioactive materials are uranium and thorium hydroxides from monazite processing. The temporal variation of {sup 226} Ra was determined in the superficial and underground water, showing no increase for the former and a maximum concentration of 0,306 Bq/L for the latter. 21 figs., 17 tabs.

  12. Modification mechanism of eutectic silicon in Al–6Si–0.3Mg alloy with scandium

    Energy Technology Data Exchange (ETDEWEB)

    Patakham, Ussadawut [Manufacturing and Systems Engineering Program, Department of Production Engineering, Faculty of Engineering, King Mongkut’s University of Technology Thonburi, 126 Pracha-Utid Rd., Bangmod, Tungkhru, Bangkok 10140 (Thailand); Kajornchaiyakul, Julathep [National Metal and Material Technology Center, National Science and Technology Development Agency, 114 Thailand Science Park, Klong Nueng, Klong Luang, Pathumthani 12120 (Thailand); Limmaneevichitr, Chaowalit, E-mail: chaowalit.lim@kmutt.ac.th [Manufacturing and Systems Engineering Program, Department of Production Engineering, Faculty of Engineering, King Mongkut’s University of Technology Thonburi, 126 Pracha-Utid Rd., Bangmod, Tungkhru, Bangkok 10140 (Thailand)

    2013-10-25

    Highlights: •Morphologies and growth of Sc and Sr-modified eutectic silicon resemble those of dendrites. •Crystal orientation of eutectic aluminum depends on growth characteristics of eutectic silicon. •We report strong evidence of the occurrence of an impurity-induced twinning mechanism. -- Abstract: The modification mechanism of eutectic silicon in Al–6Si–0.3Mg alloy with scandium was studied. The crystallographic orientation relationships between primary dendrites and the eutectic phase of unmodified and modified Al–6Si–0.3 Mg alloys were determined using electron backscatter diffraction (EBSD). The orientation of aluminum modified with scandium in the eutectic phase was different from that of the neighboring primary dendrites. This result implies that eutectic aluminum grows epitaxially from the surrounding primary aluminum dendrites in the unmodified alloy and that eutectic aluminum grows competitively from the surrounding primary aluminum dendrites in the modified alloy. The pole figure maps of eutectic Si in the [1 0 0], [1 1 0] and [1 1 1] axes of the unmodified and Sc-modified alloys were different, suggesting that the eutectic Al and Si crystals in modified alloy growth are more isotropic and cover a larger set of directions. The lattice fringes of Si of the alloys with and without Sc modification were different in the TEM results. The lattice fringes of Si in modified alloy were found to be multiple twins. However, this was not observed in the unmodified alloy. The growth characteristic of eutectic Si crystal in modified alloy suggests the occurrence of multiple twinning reactions and the formation of a high density of twins. This modification mechanism by Sc is explained by the results of scanning electron microscopy (SEM), electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) analysis, which provide strong evidence of the occurrence of the impurity-induced twinning (IIT) mechanism.

  13. Where are the radioactive wastes in France? Brochure no 3

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 3 concerns the Nord-Pas-de-Calais, Picardie, Champagne-Ardenne, Bourgogne, Alsace, Lorraine, Franche-Comte regions. (J.S.)

  14. Where are the radioactive wastes in France? Brochure no 1

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 1 concerns the Ile-de-France region (Paris region). (J.S.)

  15. Where are the radioactive wastes in France? Brochure no 6

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 6 concerns the Aquitaine, Limousin, Midi-Pyrenees and Poitou-Charentes regions. (J.S.)

  16. Where are the radioactive wastes in France? Brochure no 2

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 2 concerns the Bretagne (Brittany), Pays de la Loire, Haute-Normandie, Basse-Normandie and Centre regions. (J.S.)

  17. Subjective perception of radioactivity. No change post successful treatment with radioiodine

    International Nuclear Information System (INIS)

    Freudenberg, L.S.; Mueller, S.P.; Beyer, T.; Bockisch, A.

    2009-01-01

    We assess the attitude of patients with thyroid disease towards radiation and radioactivity before and after radioiodine therapy by means of a cultural-anthropological approach. We evaluate in patient interviews how their subjective attitude towards radioactivity as an abstract term and towards radioactivity in the medical context on the basis of their personal experiences with radionuclide therapy. 29 patients with autonomously functioning thyroid lesions (17 women, 12 men, 35-79 years) were included in this study. All patients were interviewed prior to and 22-27 month post radioiodine therapy in an open dialogue with the principal investigator. Patients were asked to describe their attitude towards radioactivity in general and towards radioiodine therapy in particular. Patients were asked to use a scoring system (1: positive, 5: negative) to quantify their perception of radioactivity. The personal perception of radioactivity as an abstract term does not change significantly (p = 0.15) before and after radioiodine therapy. This perception is linked to mostly negative impressions of radiactivity. However, patients become more positive when assessing the value of radioactivity as part of their therapy regimen. Thus, we observe a significant increase in percepted value of radioactivity post radioiodine therapy (p = 0.03). Patients continue to view radioactivity as something negative despite treatment success following radioiodine therapy. Our results provide useful information for patient information by the nuclear medicine physician prior to a radioiodine therapy. (orig.)

  18. Guidelines for carriers (by road) in Canada and the United States

    International Nuclear Information System (INIS)

    1983-08-01

    Atomic Energy of Canada Limited has provided this booklet for the purpose of simplifying, for the carrier, the complexity of the regulations that relate to the transportation of type 'A' and type 'B' packages of radioactive materials by road, in Canada. The carrier should make every effort to become familiar with the pertinent regulations and should take all measures necessary to ensure that the regulations are complied with. In particular, he should familiarize himself with the 'emergency procedures'. This booklet is not intended to be an official interpretation or restatement of the regulations

  19. Determination of rare-earth elements, yttrium and scandium in manganese nodules by inductively-coupled argon-plastma emission spectrometry

    Science.gov (United States)

    Fries, T.; Lamothe, P.J.; Pesek, J.J.

    1984-01-01

    A sequential-scanning, inductively-coupled argon plasma emission spectrometer is used for the determination of the rare-earth elements, plus yttrium and scandium, in manganese nodules. Wavelength selection is optimized to minimize spectral interferences from manganese nodule components. Samples are decomposed with mixed acids in a sealed polycarbonate vessel, and elements are quantified without further treatment. Results for U.S. Geological Survey manganese nodule standards A-1 and P-1 had average relative standard deviations of 6.8% and 8.1%, respectively, and results were in good agreement with those obtained by other methods. ?? 1984.

  20. Decree no. 2003-30 of the 10 january 2003 authorizing the national agency for the radioactive wastes management (ANDRA) to modify, for the survey step, the radioactive wastes storage center of the Manche (base nuclear installation no. 66), located on the Digulleville municipality territory (Manche)

    International Nuclear Information System (INIS)

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the decree no. 2003-30 of the 10 january 2003 authorizing the national agency for the radioactive wastes management (ANDRA) to modify, for the survey step, the radioactive wastes storage center of the Manche (base nuclear installation no. 66), located on the Digulleville municipality territory (Manche). (A.L.B.)

  1. Dynamics of charge carrier trapping in NO 2 sensors based on ZnO field-effect transistors

    NARCIS (Netherlands)

    Andringa, A.-M.; Vlietstra, N.; Smits, E.C.P.; Spijkman, M.-J.; Gomes, H.L.; Klootwijk, J.H.; Blom, P.W.M.; Leeuw, D.M. de

    2012-01-01

    Nitrogen dioxide (NO 2) detection with ZnO field-effect transistors is based on charge carrier trapping. Here we investigate the dynamics of charge trapping and recovery as a function of temperature by monitoring the threshold voltage shift. The threshold voltage shifts follow a

  2. Processing method of radioactive cleaning drain

    International Nuclear Information System (INIS)

    Otsuka, Shigemitsu; Murakami, Tadashi; Kitao, Hideo

    1998-01-01

    Upon processing of radioactive cleaning drains, contained Co-60 is removed by a selectively adsorbing adsorbent. In addition, after removing suspended materials by a filtering device, Co-60 as predominant nuclides in the drain is selectively adsorbed. The concentration of objective Co-60 is in the order of 0.1 Bq/cc, and non-radioactive metal ions such as Na + ions are present in the order of ppm in addition to Co-60. A granular adsorbent for selectively adsorbing Co-60 is oxine-added activated carbon, and has a grain size of from 20 to 48 mesh. The granular adsorbent is used while being filled in an adsorbing tower. Since a relatively simple device comprising the filtering device and the adsorbing tower in combination is provided, the reduction of the construction cost can be expected. In addition, since no filtering aid is used in the filtering device, the amount of secondary wastes is small. (N.H.)

  3. Method of reprocessing radioactive asphalt solidification products

    International Nuclear Information System (INIS)

    Nakaya, Iwao; Murakami, Tadashi; Miyake, Takafumi; Inagaki, Yuzo.

    1986-01-01

    Purpose: To obtain heat-stable solidification products and decrease the total volume thereof by modifying the solidified form by the reprocessing of existent radioactive asphalt solidification products. Method: Radioactive asphalt solidification products are heated into a fluidized state. Then, incombustible solvents such as perchloroethylene or trichloroethylene are added to a dissolving tank to gradually dissolve the radioactive asphalt solidification products. Thus, organic materials such as asphalts are transferred into the solvent layer, while inorganic materials containing radioactive materials remain as they are in the separation tank. Then, the inorganic materials containing the radioactive materials are taken out and then solidified, for example, by converting them into a rock or glass form. (Kawakami, Y.)

  4. Determination of scandium in acid mine drainage by ICP-OES with flow injection on-line preconcentration using oxidized multiwalled carbon nanotubes.

    Science.gov (United States)

    Jerez, Javier; Isaguirre, Andrea C; Bazán, Cristian; Martinez, Luis D; Cerutti, Soledad

    2014-06-01

    An on-line scandium preconcentration and determination system implemented with inductively coupled plasma optical emission spectrometry associated with flow injection was studied. Trace amounts of scandium were preconcentrated by sorption on a minicolumn packed with oxidized multiwalled carbon nanotubes, at pH 1.5. The retained analyte was removed from the minicolumn with 30% (v/v) nitric acid. A total enrichment factor of 225-fold was obtained within a preconcentration time of 300 s (for a 25 mL sample volume). The overall time required for preconcentration and elution of 25 mL of sample was about 6 min; the throughput was about 10 samples per hour. The value of the detection limit was 4 ng L(-1) and the precision for 10 replicate determinations at 100 ng L(-1) Sc level was 5% relative standard deviation, calculated from the peak heights obtained. The calibration graph using the preconcentration system was linear with a correlation coefficient of 0.9996 at levels near the detection limits up to at least 10 mg L(-1). After optimization, the method was successfully applied to the determination of Sc in an acid drainage from an abandoned mine located in the province of San Luis, Argentina. Copyright © 2014 Elsevier B.V. All rights reserved.

  5. Scandium complexes with the tetraphenylethylene and anthracene dianions.

    Science.gov (United States)

    Ellis, John E; Minyaev, Mikhail E; Nifant'ev, Ilya E; Churakov, Andrei V

    2018-06-01

    The structural study of Sc complexes containing dianions of anthracene and tetraphenylethylene should shed some light on the nature of rare-earth metal-carbon bonding. The crystal structures of (18-crown-6)bis(tetrahydrofuran-κO)sodium bis(η 6 -1,1,2,2-tetraphenylethenediyl)scandium(III) tetrahydrofuran disolvate, [Na(C 4 H 8 O) 2 (C 12 H 24 O 6 )][Sc(C 26 H 20 ) 2 ]·2C 4 H 8 O or [Na(18-crown-6)(THF) 2 ][Sc(η 6 -C 2 Ph 4 ) 2 ]·2(THF), (1b), (η 5 -1,3-diphenylcyclopentadienyl)(tetrahydrofuran-κO)(η 6 -1,1,2,2-tetraphenylethenediyl)scandium(III) toluene hemisolvate, [Sc(C 17 H 13 )(C 26 H 20 )(C 4 H 8 O)]·0.5C 7 H 8 or [(η 5 -1,3-Ph 2 C 5 H 3 )Sc(η 6 -C 2 Ph 4 )(THF)]·0.5(toluene), (5b), poly[[(μ 2 -η 3 :η 3 -anthracenediyl)bis(η 6 -anthracenediyl)bis(η 5 -1,3-diphenylcyclopentadienyl)tetrakis(tetrahydrofuran)dipotassiumdiscandium(III)] tetrahydrofuran monosolvate], {[K 2 Sc 2 (C 14 H 10 ) 3 (C 17 H 13 ) 2 (C 4 H 8 O) 4 ]·C 4 H 8 O} n or [K(THF) 2 ] 2 [(1,3-Ph 2 C 5 H 3 ) 2 Sc 2 (C 14 H 10 ) 3 ]·THF, (6), and 1,4-diphenylcyclopenta-1,3-diene, C 17 H 14 , (3a), have been established. The [Sc(η 6 -C 2 Ph 4 ) 2 ] - complex anion in (1b) contains the tetraphenylethylene dianion in a symmetrical bis-η 3 -allyl coordination mode. The complex homoleptic [Sc(η 6 -C 2 Ph 4 ) 2 ] - anion retains its structure in THF solution, displaying hindered rotation of the coordinated phenyl rings. The 1D 1 H and 13 C{ 1 H}, and 2D COSY 1 H- 1 H and 13 C- 1 H NMR data are presented for M[Sc(Ph 4 C 2 ) 2 ]·xTHF [M = Na and x = 4 for (1a); M = K and x = 3.5 for (2a)] in THF-d 8 media. Complex (5b) exhibits an unsymmetrical bis-η 3 -allyl coordination mode of the dianion, but this changes to a η 4 coordination mode for (1,3-Ph 2 C 5 H 3 )Sc(Ph 4 C 2 )(THF) 2 , (5a), in THF-d 8 solution. A 45 Sc NMR study of (2a) and UV-Vis studies of (1a), (2a) and (5a) indicate a significant covalent contribution to the Sc-Ph 4 C 2 bond character. The unique Sc ate complex, (6

  6. Method for ultimate disposition of borate containing radioactive wastes by vitrification

    International Nuclear Information System (INIS)

    Bege, D.; Faust, H.J.; Puthawala, A.; Stunkel, H.

    1984-01-01

    Method for the ultimate disposition of radioactive wastes by vitrification, in which weak to medium radioactive waste concentrates from borate-containing radioactive liquids are mixed with added glass-forming materials, maximally in a ratio of 1:3, and the mixture heated to obtain a glass-forming melt

  7. Labile soil phosphorus as influenced by methods of applying radioactive phosphorus

    International Nuclear Information System (INIS)

    Selvaratnam, V.V.; Andersen, A.J.; Thomsen, J.D.; Gissel-Nielsen, G.

    1980-03-01

    The influence of different methods of applying radioactive phosphorus on the E- and L-values was studied in four foil types using barley, buckwheat, and rye grass for the L-value determination. The four soils differed greatly in their E- and L-values. The experiment was carried out both with and without carrier-P. The presence of carrier-P had no influence on the E-values, while carrier-P in some cases gave a lower L-value. Both E- and L-values dependent on the method of application. When the 32 P was applied on a small soil or sand sample and dried before mixing with the total amount of soil, the E-values were higher than at direct application most likely because of a stronger fixation to the soil/sand particles. This was not the case for the L-values that are based on a much longer equilibrium time. On the contrary, the direct application of the 32 p-solution to the whole amount of soil gave higher L-values of a non-homogeneous distribution of the 32 p in the soil. (author)

  8. Regulations under the Radioactive Substances Act of 1958, No. 115, 1961

    International Nuclear Information System (INIS)

    1961-01-01

    These very detailed regulations lay down the licensing system for the use of radioactive materials. They provide for monitoring and control of radiation and radiation contamination, storage, labelling and transport of radioactive materials and also for the disposal of radioactive waste. (NEA) [fr

  9. Healthy versus Entorhinal Cortical Atrophy Identification in Asymptomatic APOE4 Carriers at Risk for Alzheimer's Disease.

    Science.gov (United States)

    Konishi, Kyoko; Joober, Ridha; Poirier, Judes; MacDonald, Kathleen; Chakravarty, Mallar; Patel, Raihaan; Breitner, John; Bohbot, Véronique D

    2018-01-01

    Early detection of Alzheimer's disease (AD) has been challenging as current biomarkers are invasive and costly. Strong predictors of future AD diagnosis include lower volume of the hippocampus and entorhinal cortex, as well as the ɛ4 allele of the Apolipoprotein E gene (APOE) gene. Therefore, studying functions that are critically mediated by the hippocampus and entorhinal cortex, such as spatial memory, in APOE ɛ4 allele carriers, may be key to the identification of individuals at risk of AD, prior to the manifestation of cognitive impairments. Using a virtual navigation task developed in-house, specifically designed to assess spatial versus non-spatial strategies, the current study is the first to differentiate functional and structural differences within APOE ɛ4 allele carriers. APOE ɛ4 allele carriers that predominantly use non-spatial strategies have decreased fMRI activity in the hippocampus and increased atrophy in the hippocampus, entorhinal cortex, and fimbria compared to APOE ɛ4 allele carriers who use spatial strategies. In contrast, APOE ɛ4 allele carriers who use spatial strategies have grey matter levels comparable to non-APOE ɛ4 allele carriers. Furthermore, in a leave-one-out analysis, grey matter in the entorhinal cortex could predict navigational strategy with 92% accuracy.

  10. Resolution No. 58/03 Concerning the use of radioactive lightning rods

    International Nuclear Information System (INIS)

    2003-01-01

    This resolution provides that the importation and purchase of radioactive lightning rods throughout the national territory is prohibited also not the assembly of new radioactive lightning rod is allowed although these have in storage. All currently employs radioactive lightning rods should replace conventional, within ten (10) years from the entry into force of this Resolution. The radioactive lightning rods in use, for any reason lose tightness sources must be removed immediately. In all cases should proceed to the safe management of radioactive lightning rod as disused source with the Center for Health and Safety of Radiation or other entity authorized to do so, in order to avoid undue risk to lives, property and the environment environment.

  11. Nonlinear realization of supersymmetric AdS space isometries

    International Nuclear Information System (INIS)

    Clark, T. E.; Love, S. T.

    2006-01-01

    The isometries of AdS 5 space and supersymmetric AdS 5 xS 1 space are nonlinearly realized on four-dimensional Minkowski space. The resultant effective actions in terms of the Nambu-Goldstone modes are constructed. The dilatonic mode governing the motion of the Minkowski space probe brane into the covolume of supersymmetric AdS 5 space is found to be unstable and the bulk of the AdS 5 space is unable to sustain the brane. No such instability appears in the nonsupersymmetric case

  12. Outlook of the accident at Fukushima No.1 Nuclear Power Plants and issues concerning radioactive materials in environments

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    2011-01-01

    Fukushima No.1 Nuclear Power Plants (NPPs) affected by a great earthquake finally suffered reactor core meltdown with loss of all cooling capability and discharged a large amount of radioactive materials to the environment. Local areas in the northwest direction from NPPs were highly contaminated with radioactive materials. In order to reduce radiation exposure, several kinds of decontamination works had been tested in contaminated areas of primary school and kindergarten or residential houses with no evacuation. Radiation mini-hotspots were scattered. Contaminated soils and rubbles having cesium of high concentration in the order of several ten or hundreds kBq/kg were accumulated in large amounts of radioactive wastes and their disposal became a big issue. Related safety guidelines were proposed based on radioactive waste disposal for nuclear facilities as well as radiation dose control of neighboring residents and disposal workers, which would not be applicable to current state of Fukushima in a high radiation background. Establishment of new radiation protection rule was highly needed to deal with this emergency based on reality within and outside the Fukushima NPPs. (T. Tanaka)

  13. Method to produce sintered carriers for electrodes of galvanic elements

    Energy Technology Data Exchange (ETDEWEB)

    Jost, E M

    1978-03-24

    Carrier plates of precisely uniform thickness can be produced according to the invention by firstly thickening a solution of polyethylene oxide and (preferably) methanol by adding water and then, by adding nickel powder, obtaining an essentially homogeneous suspension of considerable viscosity. This slurry is coated on both sides of a nickel grid, dried and sintered.

  14. Where are the radioactive wastes in France? Brochure no 5

    International Nuclear Information System (INIS)

    2004-01-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 5 concerns the Languedoc-Roussillon and Provence-Alpes-Cote d'Azur regions, Corsica, and the overseas departements and territories. (J.S.)

  15. Feasibility of high-speed power line carrier system to Japanese overhead low voltage distribution lines; Teiatsu haidensen hanso no kosokuka no kanosei (hanso sningo denpa purogram no kanosei)

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, T.; Takeshita, K.; Ishino, R.

    2000-06-01

    The high-speed distribution line carrier systems on underground distribution lines are being developed in Germany. To estimate these systems on Japanese overhead low voltage distribution lines, the Carrier Propagation Program has been developed and applicability of OFDM system was roughly estimated. 1. Carrier Propagation Program Carrier Propagation Program that calculates the carrier propagation characteristics of any line structure was developed. 2. Carrier propagation characteristics Carrier propagation characteristics on typical Japanese overhead low voltage distribution lines were calculated 3.Rough estimation of OFDM system Electric fields caused by carrier at near point were calculated on the basis on carrier propagation characteristics. Results of rough estimation are as follows: - Electric field caused by carrier of more than 2Mbps system exceeds the value of the regulation. (author)

  16. Descendit ad [in] inferna:'A matter of no small moment in bringing ...

    African Journals Online (AJOL)

    Descendit ad [in] inferna:'A matter of no small moment in bringing about redemption' ... and make one suspicious about certain ecclesiastical biases. Spatial terms in the Creed should therefore not be demythologised, but rather be transformed in accordance with the insights of the contemporary physics of time and space.

  17. Why does the lumen maintenance of sodium-scandium metal halide lamps improve by VHF operation?

    International Nuclear Information System (INIS)

    Van Erk, W; Luijks, G M J F; Hitchcock, W

    2011-01-01

    Lifetime experiments show that sodium-scandium metal halide lamps perform better on very high frequency (VHF) drivers than on low frequency (LF) constant wattage autotransformer (CWA) ballasts. The question why, will be addressed with focus on arc tube aspects. It is argued that at high frequency operation sodium loss is less, and that the absence of thermal fluctuations in the electrode tip causes less damage and cracking to this part of the electrode. Sudden lm W -1 drops, observed with CWA-operated lamps, most probably occur when the arc attaches on such a corroded and cracked surface. Thorium is effective as an emitter both in the CWA and the VHF operation mode, despite the absence of cataphoretic transport to the cathode in the VHF case.

  18. Why does the lumen maintenance of sodium-scandium metal halide lamps improve by VHF operation?

    Energy Technology Data Exchange (ETDEWEB)

    Van Erk, W [Philips Lighting, Sondervick 47, 5505 NB Veldhoven (Netherlands); Luijks, G M J F [Advanced Development Lighting, Philips Lighting, PO Box 80020, 5600 JM Eindhoven (Netherlands); Hitchcock, W, E-mail: Gerard.luijks@philips.com [Philips Lighting Company, 7265 Route 54, Bath, NY 14810 (United States)

    2011-06-08

    Lifetime experiments show that sodium-scandium metal halide lamps perform better on very high frequency (VHF) drivers than on low frequency (LF) constant wattage autotransformer (CWA) ballasts. The question why, will be addressed with focus on arc tube aspects. It is argued that at high frequency operation sodium loss is less, and that the absence of thermal fluctuations in the electrode tip causes less damage and cracking to this part of the electrode. Sudden lm W{sup -1} drops, observed with CWA-operated lamps, most probably occur when the arc attaches on such a corroded and cracked surface. Thorium is effective as an emitter both in the CWA and the VHF operation mode, despite the absence of cataphoretic transport to the cathode in the VHF case.

  19. Concentrations of radioactive elements in lunar materials

    Science.gov (United States)

    Korotev, Randy L.

    1998-01-01

    As an aid to interpreting data obtained remotely on the distribution of radioactive elements on the lunar surface, average concentrations of K, U, and Th as well as Al, Fe, and Ti in different types of lunar rocks and soils are tabulated. The U/Th ratio in representative samples of lunar rocks and regolith is constant at 0.27; K/Th ratios are more variable because K and Th are carried by different mineral phases. In nonmare regoliths at the Apollo sites, the main carriers of radioactive elements are mafic (i.e., 6-8 percent Fe) impact-melt breccias created at the time of basin formation and products derived therefrom.

  20. Placarding of road vehicles carrying radioactive materials

    International Nuclear Information System (INIS)

    1977-09-01

    The purpose of this Code is to give guidance on the placarding requirements for vehicles carrying radioactive materials by road in Great Britain and on the continent of Europe. Additional placards may be required regarding dangerous properties other than radioactivity. The labelling of packages for transport is dealt with in AECP 1030. This Code deals with two aspects of road vehicle placarding:-(a) placarding on the outside of road vehicles in Great Britain and on the continent of Europe, (b) a fireproof placard fixed in the driver's cab. Responsibility for placarding the vehicle rests with the carrier, but in practice the consignor may need to provide the placards. (U.K.)

  1. Interference in wireless ad hoc networks with smart antennas

    KAUST Repository

    Alabdulmohsin, Ibrahim

    2014-08-01

    In this paper, we show that the use of directional antennas in wireless ad hoc networks can actually increase interference due to limitations of virtual carrier sensing. We derive a simple mathematical expression for interference in both physical and virtual carrier sense networks, which reveals counter-intuitively that receivers in large dense networks with directional antennas can experience larger interference than in omnidirectional networks unless the beamwidth is sufficiently small. Validity of mathematical analysis is confirmed using simulations.

  2. Healthy versus Entorhinal Cortical Atrophy Identification in Asymptomatic APOE4 Carriers at Risk for Alzheimer’s Disease

    Science.gov (United States)

    Konishi, Kyoko; Joober, Ridha; Poirier, Judes; MacDonald, Kathleen; Chakravarty, Mallar; Patel, Raihaan; Breitner, John; Bohbot, Véronique D.

    2018-01-01

    Early detection of Alzheimer’s disease (AD) has been challenging as current biomarkers are invasive and costly. Strong predictors of future AD diagnosis include lower volume of the hippocampus and entorhinal cortex, as well as the ɛ4 allele of the Apolipoprotein E gene (APOE) gene. Therefore, studying functions that are critically mediated by the hippocampus and entorhinal cortex, such as spatial memory, in APOE ɛ4 allele carriers, may be key to the identification of individuals at risk of AD, prior to the manifestation of cognitive impairments. Using a virtual navigation task developed in-house, specifically designed to assess spatial versus non-spatial strategies, the current study is the first to differentiate functional and structural differences within APOE ɛ4 allele carriers. APOE ɛ4 allele carriers that predominantly use non-spatial strategies have decreased fMRI activity in the hippocampus and increased atrophy in the hippocampus, entorhinal cortex, and fimbria compared to APOE ɛ4 allele carriers who use spatial strategies. In contrast, APOE ɛ4 allele carriers who use spatial strategies have grey matter levels comparable to non-APOE ɛ4 allele carriers. Furthermore, in a leave-one-out analysis, grey matter in the entorhinal cortex could predict navigational strategy with 92% accuracy. PMID:29278888

  3. The esophageal transit in normal persons and in carrier of Chagas disease and progressive systemic sclerosis. A scintiscanning study

    International Nuclear Information System (INIS)

    Oliveira, R.B. de.

    1985-01-01

    The aim of this study is determine, by a scintiscanning method, how 10 ml of water, swallowed at one time, transit by the esophagus of normal persons and carriers of diseases, that attacking the esophagus motility. The other aim was determine the characteristics of the transit by the esophagus in carriers of chagasic esophagus diseases and of progressive systemic sclerosis. The study of esophageal transit was made by the technetium 99, with a gamma camera for detecting and quantifying the radioactivity. Several images of the esophageal transit, with persons in supine and seat positions, for processing the radioactivity curves x time are studied and compared. (C.G.C.)

  4. Process for treatment of detergent-containing radioactive liquid wastes

    International Nuclear Information System (INIS)

    Kamiya, K.; Chino, K.; Funabashi, K.; Horiuchi, S.; Motojima, K.

    1984-01-01

    A detergent-containing radioactive liquid waste originating from atomic power plants is concentrated to have about 10 wt. % detergent concentration, then dried in a thin film evaporator, and converted into powder. Powdered activated carbon is added to the radioactive waste in advance to prevent the liquid waste from foaming in the evaporator by the action of surface active agents contained in the detergent. The activated carbon is added in accordance with the COD concentration of the radioactive liquid waste to be treated, and usually at a concentration 2-4 times as large as the COD concentration of the liquid waste to be treated. A powdery product having a moisture content of not more than 15 wt. % is obtained from the evaporator, and pelletized and then packed into drums to be stored for a predetermined period

  5. The spectrum of four times ionized scandium, Sc V

    International Nuclear Information System (INIS)

    Smitt, R.; Ekberg, J.O.

    1985-01-01

    The spectrum of four times ionized scandium emitted from a sliding spark discharge has been observed using a 3 m normal incidence spectrograph and a 5 m grazing incidence spectrograph. About 450 lines in the wavelength region 160 A to 220 A have been identified as combinations between 46 odd levels belonging to the 3s 2 3p 5 , 3s 2 3p 4 4p and 3s3p 5 3d configurations and 72 even levels of the 3s3p 6 , 3s 2 3p 4 3d, 4d, 4s and 5s configurations. Of the previous identifications we have confirmed 18 levels. The level structure of the observed configurations has been theoretically interpreted by including configuration interaction effects. The inclusion of 3s 2 3p 3 3d 2 in the calculations of the odd parity configurations is found to be important. Almost all levels of 3s3p 5 3d show a considerable mixing with levels of 3s 2 3p 3 3d 2 , in some cases by as much as 50%. The energy parameters determined from least-squares fits to the observed level values are compared with Hartree-Fock calculations. The ionization energy is estimated to be 739 500 +- 1000 cm -1 . (91.65 +- 0,12 eV). (orig.)

  6. Methods of surveying and monitoring marine radioactivity. Report of an ad hoc panel of experts

    International Nuclear Information System (INIS)

    1965-01-01

    An effective control of the radioactive pollution of the sea depends partly on the availability of adequate technical methods for surveying and monitoring the sea and marine products with regard to the presence of radioactive substances. The purpose of this manual is to offer such methods.

  7. Open strings on AdS2 branes

    International Nuclear Information System (INIS)

    Lee, Peter; Ooguri, Hirosi.; Park, Jongwon; Tannenhauser, Jonathan

    2001-01-01

    We study the spectrum of open strings on AdS 2 branes in AdS 3 in an NS-NS background, using the SL(2,R) WZW model. When the brane carries no fundamental string charge, the open string spectrum is the holomorphic square root of the spectrum of closed strings in AdS 3 . It contains short and long strings, and is invariant under spectral flow. When the brane carries fundamental string charge, the open string spectrum again contains short and long strings in all winding sectors. However, branes with fundamental string charge break half the spectral flow symmetry. This has different implications for short and long strings. As the fundamental string charge increases, the brane approaches the boundary of AdS 3 . In this limit, the induced electric field on the worldvolume reaches its critical value, producing noncommutative open string theory on AdS 2

  8. Interference in wireless ad hoc networks with smart antennas

    KAUST Repository

    Alabdulmohsin, Ibrahim

    2014-01-01

    In this paper, we show that the use of directional antennas in wireless ad hoc networks can actually increase interference due to limitations of virtual carrier sensing. We derive a simple mathematical expression for interference in both physical

  9. In the presence of fluoride, free Sc³⁺ is not a good predictor of Sc bioaccumulation by two unicellular algae: possible role of fluoro-complexes.

    Science.gov (United States)

    Crémazy, Anne; Campbell, Peter G C; Fortin, Claude

    2014-08-19

    We investigated the effect of fluoride complexation on scandium accumulation by two unicellular algae, Chlamydomonas reinhardtii and Pseudokirchneriella subcapitata. This trivalent metal was selected for its chemical similarities with aluminum and for its convenient radioisotope (Sc-46), which can be used as a tracer in short-term bioaccumulation studies. Scandium surface-bound concentrations (Sc(ads)) and uptake fluxes (J(int)) were estimated in the two algae over short-term (organisms.

  10. Solidification of aqueous radioactive waste using insoluble compounds of magnesium oxide

    International Nuclear Information System (INIS)

    Carlson, J.E.

    1986-01-01

    A process is described for the treatment of radioactive waste which comprises: (a) first adding, under continuous agitation, a sufficient amount of a powdered magnesium oxide or magnesium hydroxide to an aqueous radioactive waste solution containing boric acid, the temperature of the water solution being 55-95 degrees C. to produce a magnesium borate derivative; (b) adding cement, under continuous agitation, to the magnesium borate derivative; and (c) then adding, under continuous agitation, after the cement has been dispersed, a sufficient amount of a compound selected from the group consisting of calcium oxide and calcium hydroxide to (b) to produce a gel matrix structure

  11. An international approach to radioactive waste management

    International Nuclear Information System (INIS)

    Barlett, J.W.

    1994-01-01

    Needs and opportunities for an international approach to management and disposal of radioactive wastes are discussed. Deficiencies in current national radioactive waste management programs are described, and the impacts of management of fissile materials from nuclear weapons on waste management are addressed. Value-added services that can be provided by an international organization for waste management are identified, and candidate organizations that could provide these services are also identified

  12. Carrier Screening

    Science.gov (United States)

    ... How accurate is carrier screening? No test is perfect. In a small number of cases, test results ... in which an egg is removed from a woman’s ovary, fertilized in a laboratory with the man’s ...

  13. Preparation of highly specific radioactivity [{sup 18}F]flumazenil and its evaluation in cynomolgus monkey by positron emission tomography

    Energy Technology Data Exchange (ETDEWEB)

    Ryzhikov, Nikolaj N. [Institute of Human Brain, Russian Academy of Science, 9, Pavlov str, 197376, Saint Petersburg (Russian Federation); Seneca, Nicholas [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden); National Institute of Mental Health, National Institutes of Health, Molecular Imaging Branch, Bethesda, MD 20892 (United States); Krasikova, Raisa N. [Institute of Human Brain, Russian Academy of Science, 9, Pavlov str, 197376, Saint Petersburg (Russian Federation); Gomzina, Natalia A. [Institute of Human Brain, Russian Academy of Science, 9, Pavlov str, 197376, Saint Petersburg (Russian Federation); Shchukin, Evgeny [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden); Fedorova, Olga S. [Institute of Human Brain, Russian Academy of Science, 9, Pavlov str, 197376, Saint Petersburg (Russian Federation); Vassiliev, Dmitrij A. [Institute of Human Brain, Russian Academy of Science, 9, Pavlov str, 197376, Saint Petersburg (Russian Federation); Gulyas, Balazs [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden); Hall, Hakan [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden); Savic, Ivanka [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden); Halldin, Christer [Department of Clinical Neuroscience, Karolinska Institutet, Psychiatry Section, Karolinska Hospital, S-17176 Stockholm (Sweden)]. E-mail: christer.halldin@cns.ki.se

    2005-02-01

    A straightforward method for the preparation of no-carrier-added (n.c.a.) [{sup 18}F]flumazenil via standard nucleophilic radiofluorination of the corresponding nitro-analog Ro 15-2344 has been developed. The labeling was performed by employing the K{sup 18}F/kryptofix complex in DMF at 160 deg. C for 30 min and equimolar ratio [K/K2.2.2]{sup +18}F{sup -}/precursor. Under these conditions, an {sup 18}F incorporation rate into flumazenil was in the range of 55-60%. The final product was isolated by HPLC purification within a total synthesis time of 75 min and a radiochemical yield of about 30% (EOB). Human post-mortem whole-hemisphere autoradiography of brain sections demonstrated selective uptake of the radioligand in the areas of high density of the central benzodiazepine receptors (BZR). PET studies in a cynomolgus monkey and metabolite studies by HPLC demonstrated similar results by [{sup 18}F]flumazenil as for [{sup 11}C]flumazenil. In blocking experiments, almost all radioactivity was inhibited by the addition of unlabeled flumazenil. [{sup 18}F]Flumazenil is a suitable radioligand for PET assessment of the BZR.

  14. Carrier-interleaved orthogonal multi-electrode multi-carrier resistivity-measurement tool

    International Nuclear Information System (INIS)

    Cai, Yu; Sha, Shuang

    2016-01-01

    This paper proposes a new carrier-interleaved orthogonal multi-electrode multi-carrier resistivity-measurement tool used in a cylindrical borehole environment during oil-based mud drilling processes. The new tool is an orthogonal frequency division multiplexing access-based contactless multi-measurand detection tool. The tool can measure formation resistivity in different azimuthal angles and elevational depths. It can measure many more measurands simultaneously in a specified bandwidth than the legacy frequency division multiplexing multi-measurand tool without a channel-select filter while avoiding inter-carrier interference. The paper also shows that formation resistivity is not sensitive to frequency in certain frequency bands. The average resistivity collected from N subcarriers can increase the measurement of the signal-to-noise ratio (SNR) by N times given no amplitude clipping in the current-injection electrode. If the clipping limit is taken into account, with the phase rotation of each single carrier, the amplitude peak-to-average ratio can be reduced by 3 times, and the SNR can achieve a 9/ N times gain over the single-carrier system. The carrier-interleaving technique is also introduced to counter the carrier frequency offset (CFO) effect, where the CFO will cause inter-pad interference. A qualitative analysis and simulations demonstrate that block-interleaving performs better than tone-interleaving when coping with a large CFO. The theoretical analysis also suggests that increasing the subcarrier number can increase the measurement speed or enhance elevational resolution without sacrificing receiver performance. The complex orthogonal multi-pad multi-carrier resistivity logging tool, in which all subcarriers are complex signals, can provide a larger available subcarrier pool than other types of transceivers. (paper)

  15. Method for processing radioactive wastes containing sodium

    International Nuclear Information System (INIS)

    Kubota, Takeshi.

    1975-01-01

    Object: To bake, solidify and process even radioactive wastes highly containing sodium. Structure: H and or NH 4 zeolites of more than 90g per chemical equivalent of sodium present in the waste is added to and left in radioactive wastes containing sodium, after which they are fed to a baker such as rotary cylindrical baker, spray baker and the like to bake and solidify the wastes at 350 to 800 0 C. Thereby, it is possible to bake and solidify even radioactive wastes highly containing sodium, which has been impossible to do so previously. (Kamimura, M.)

  16. Watching termites

    International Nuclear Information System (INIS)

    Carrard, G.

    1983-01-01

    Radioactive tracking techniques are being used to aid the investigation and control of termites. Studies include work related to the restoration of historic buildings when the damage inflicted on the timbers needs to be determined with minimum disturbance to the building. Another investigation has been the radioactive monitoring of pest-control techniques. Scandium-46, lanthanum-140 and gold-198 have been used in different investigations

  17. Cellular retention of radioactivity and increased radiation dose. Model experiments with EGF-dextran

    International Nuclear Information System (INIS)

    Sundberg, Aasa Liljegren; Blomquist, Erik; Carlsson, Joergen; Steffen, Ann-Charlott; Gedda, Lars

    2003-01-01

    Targeting of tumor cells with radiolabeled biomolecules is a possible approach to inactivate disseminated tumor cells. However, rapid degradation of the biomolecules after cellular internalization and subsequent excretion of the radioactivity is a problem. We studied the possibility of using dextran as a carrier of radionuclides to improve the intracellular retention. An EGF-dextran conjugate, aimed for targeting of tumor cells overexpressing the EGF-receptor, was used as model. Retention tests were performed with 125 I on different parts: [ 125 I]-EGF-dextran-[ 125 I], [ 125 I]-EGF-dextran and EGF-dextran-[ 125 I]. Comparisons were made with [ 125 I]-EGF. The radiolabeled compounds were incubated with cultured glioma cells for different times. The cellular retention of radioactivity was then measured for up to 24 h. Expected radiation doses at the cellular level were calculated assuming that 131 I, instead of 125 I, was coupled to EGF and EGF-dextran. The results indicated that the EGF-part of the conjugate was degraded and the EGF-attached radioactivity was rapidly excreted, whereas radioactivity on dextran was retained intracellularly to a high degree, i.e. 70-80% of the radioactivity bound to dextran was still cell-associated after 24 h. The retention after 24 h was significantly higher (p < 0.001) when the radioactivity was on the dextran instead of the EGF-part. The radiolabeled EGF-dextran had a notably high specific radioactivity; up to 11 MBq/μg. There was potential for at least hundred times increased radiation dose per receptor interaction when the radioactivity was on the dextran part. The advantage with radioactivity on the dextran part was the high cellular retention and the high specific radioactivity (higher than previously reported for other residualizing labels) without severe loss of receptor specific binding. Thus, dextran seems suitable as a carrier of radionuclides aimed for therapy and gives potential for a highly increased radiation dose

  18. Evaluation of radiation exposure from shoe-deodorants as radioactive consumer products

    International Nuclear Information System (INIS)

    Furuta, Etsuko; Yokota, Shigeaki; Aburai, Tamaru; Yoshizawa, Yukio

    2007-01-01

    Six shoe-deodorants on the market were analyzed using gamma-ray spectroscopy and radionuclide imaging techniques. The results reveal that at least three deodorants were 'radioactive consumer products' containing radionuclides of thorium (Th) series, uranium series, and potassium-40 that were added intentionally. Equivalent dose rates and effective dose rates were calculated using the activities in these deodorants. There were no samples breaking the nuclear reactor and fuel regulation law. Radioactive concentration of the deodorant for a shoe-shelf is higher than other deodorants, and the total concentrations of daughter nuclides of Th which are radioactive equilibrium with 224 Ra exceeded 90 Bq·g -1 . The effective dose rate at one meter from the shoe-shelf-deodorant is 8.6x10 -4 μSv·h -1 . Another type of shoe-deodorants is an insole that causes the surface dose of plantar skin. The equivalent dose was calculated as 1.9 μSv·h -1 at one millimeter from the insole. This study suggested that it needs to watch severely over the deodorants because many kinds of deodorants are used in home and some deodorants are radioactive consumer products. (author)

  19. Wess-Zumino terms for AdS D-branes

    International Nuclear Information System (INIS)

    Hatsuda, Machiko; Kamimura, Kiyoshi

    2004-01-01

    We show that Wess-Zumino terms for Dp branes with p>0 in the anti-de Sitter (AdS) space are given in terms of 'left-invariant' currents on the super-AdS group or the 'expanded' super-AdS group. As a result there is no topological extension of the super-AdS algebra. In the flat limit the global Lorentz rotational charges of the AdS space turn out to be brane charges of the supertranslation algebra representing the BPS mass. We also show that a D-instanton is described by the GL(1) degree of freedom in the Roiban-Siegel formalism based on the GL(4 vertical bar 4)/[Sp(4)xGL(1)]2 coset

  20. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorizing carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspections of the carriers and during storage in transit and handling. (Author)

  1. Regulations for the transport of radioactive material in Italy: the role of the Italian Competent Authority (ANPA)

    International Nuclear Information System (INIS)

    Orsini, A.; Trivelloni, S.

    1995-01-01

    In Italy four Ministries, Industry, Transport, Marine Merchandise and Interior, have the legal responsibility to issue and apply the transport safety regulations for radioactive material. ANPA, the National Agency for Environmental Protection, has the technical duty to issue the approval certificates and to support the various Ministries in authorising carriers for all modes of transport, in updating the regulations and advising in the case of emergency conditions. ANPA is monitoring the quantity of radioactive material transported in Italy, the radiation doses of workers and public, and verifying the implementation of transport regulations through inspection of the carriers and during storage in transit and handling. (author)

  2. Denials of Shipments for Radioactive Material - Indian Perspective

    International Nuclear Information System (INIS)

    Singh, Khaidem Ranjankumar; Hussain, S.A; Panda, G.K.; Singh, T. Dewan; Dinakaran, M.C.

    2016-01-01

    Radioactive material (RAM) needs to be transported for use in public health and industry and for production of nuclear power. In India, transport of RAM is governed by national and international regulations which are based on the IAEA Regulations for the safe transport of RAM. However, recently there were increasing numbers of instances of denials and delays of shipment of RAM, reported by many countries worldwide including India, despite compliance with regulations. In Indian experience, the reasons for denials of shipment of RAM by the carriers are varied in nature. From the feedback received from the participants (airport operators, airlines, courier and cargo service providers, cargo forwarding agents, port authorities and sea carriers) of awareness programmes on safe transport of RAM conducted from year 2008 onwards by Atomic Energy Regulatory Board (AERB) it became clear that the denials of shipments in India are mainly due to (1) perception of unnecessary fear for transport of RAM (2) lack of confidence and awareness on the procedures for acceptance of shipment of RAM (3) fear of risk during accidents with packages containing RAM (4) policy of the carriers not to accept consignment of dangerous goods (5) poor infrastructure at the major/transit ports (6) problems of transshipments and (7) shippers not having undergone dangerous goods training. In this paper, the Indian experience in dealing with the problems of denial/delay of shipments containing radioactive material and identified possible consequences of such denials including economical impact are discussed in detail. (author)

  3. Systemic Endoradiotherapy with Carrier Added 4 [{sup 131I}] Iodo {sup LP}henylalanine: Clinical Proof of principle in Refractory Glioma

    Energy Technology Data Exchange (ETDEWEB)

    Baum, Richard P.; Schuchardt, Christiane; Senftleben, Stephan; Gildehaus, Franz Josef; Samnick, Samuel [PET Centre, Bad Berka (Germany); Kluge, Andreas; Bronzel, Marcus; Schmidt, Karl [ABX CRO Advanced Pharmaceutical Services, Dresden (Germany)

    2011-12-15

    To explore feasibility, tolerability, dosimetry and probable efficacy of intravenous endoradiotherapy with carrier added 4 [{sup 131I}]iodo {sup Lp}henylalanine (c.a. {sup 131I} IPA) in refractory high grade glioma. Two male patients (45 and 50 years), with long standing, extensively pretreated gliomas and evidence of progression underwent single intravenous injections of 2 and 4 GBq of c.a. {sup 131I} IPA, respectively. Tumor targeting was verified by {sup 131I} IPA single photon emission computed tomography (SPECT). Metabolic and morphological changes indicative of tumour response were assessed by sequential [{sup 18F}] fluoroethyltyrosine ({sup 18F} FET) positron emission tomography (PET) and contrast enhanced magnetic resonance imaging (MRI) following therapy. Further monitoring included clinical state, safety laboratory, quality of life and dosimetry. Absorbed mean organ and whole body doses were determined according to the Medical Internal Radiation Dose (MIRD) scheme using OLINDAEXM based on serial planar scintigraphy. Both patients tolerated the treatment well. No evidence of acute of delayed organ toxicity was observed. {sup 131I} IPA accumulated in the tumour recurrences identified by MRI/{sup 18F} FET. In patient 1, PET showed progressively decreasing maximum standardised uptake values (SUVmax) over 10 months, indicating metabolic response, paralleled by reduced contrast enhancement and tumour volume on MRI. Progression occurred 18 months after therapy. Treatment was repeated using 6.6 GBq of {sup 131I} IPA, to which no response was observed. Patient 2, followed up for 3 months after therapy, showed stable disease on MRI and PET. Mean absorbed whole body doses ranged from 0.13 to 0.17 mSv/MBq, with the highest absorbed organ doses to kidneys, bladder and heart (0.86-1.23; 0.49-0.6 and 0.45-0.56 mSv/MBq). Systemic endoradiotherapy using up to 6.6 GBq of c.a. {sup 131I} IPA is not associated with clinically detectable toxicity. Measurable anti tumour

  4. Process for recovering xenon from radioactive gaseous wastes

    International Nuclear Information System (INIS)

    Kishimoto, Tsuneo.

    1980-01-01

    Purpose: To recover pure xenon economically and efficiently by amply removing radioactive krypton mixed in xenon without changing the rectifying capacity of an xenon rectifying system itself. Method: Xe containing radioactive Kr(Kr-85) is rectified to reduce the concentration of radioactive Kr. Thereafter, non-radioactive Kr or Ar is added to Xe and further the rectification is carried out. The raw material Xe from the Xe adsorption system of, for example, a radioactive gaseous waste disposal system is cooled to about 100 0 C by a heat-exchanger and thereafter supplied to a rectifying tower to carry out normal rectification of Xe thereby to reduce the concentration of Kr contained in Xe at the tower bottom to the rectification limit concentration. Then, non-radioactive Kr is supplied via a precooler to the tower bottom to continue the rectification, thus the Xe fractions at the tower bottom, in which the concentration of radioactive Kr is reduced, being compressed and recovered. (Kamimura, M.)

  5. Method for storing radioactive combustible waste

    Science.gov (United States)

    Godbee, H.W.; Lovelace, R.C.

    1973-10-01

    A method is described for preventing pressure buildup in sealed containers which contain radioactively contaminated combustible waste material by adding an oxide getter material to the container so as to chemically bind sorbed water and combustion product gases. (Official Gazette)

  6. Method of melting and decontaminating radioactive contaminated aluminum material

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Miura, Noboru; Kawasaki, Katsuo; Iba, Hajime.

    1986-01-01

    Purpose: To improve the decontaminating efficiency upon melting decontamination of radioactive-contaminated aluminum materials. Method: This invention concerns an improvement for the method of melting decontamination by adding slug agent composed of organic compound to contaminated aluminum material and extracting the radioactive materials into the slug thereby decontaminating the aluminum material. Specifically metals effective for reducing the active amount of aluminum are added such that the content is greater than a predetermined value in the heat melting process. The metal comprises Mg, Cu or a mixture thereof and the content is more than 4 % including those previously contained in the aluminum material. (Ikeda, J.)

  7. Attention: no radioactive waste accepted on 7 September

    CERN Multimedia

    2012-01-01

    Anouncement by the RW section of the Radiation Protection Group: The Treatment Centre for Radioactive Waste will not be accepting waste on Friday, 7 September 2012. Thank you for adjusting your activities accordingly.

  8. Demand forecast for rail shipment of radioactive material in the United States

    International Nuclear Information System (INIS)

    Allen, G.C.; Cashwell, J.W.

    1981-01-01

    A summary of the market potential for radioactive material (in millions of ton-miles) is presented in tabular form. These include the following: milled uranium ore; mill tailings; natural uranium hexafluoride; enriched uranium hexafluoride; fresh fuel, spent fuel; low-level waste; transuranic waste; and high-level waste. The maximum realistic market share for rail carriers is always less than these values because of the lack of rail access to some shipping and receiving facilities, small material quantities which could most easily move by other modes, short shipping distances for certain transport segments and greater operational convenience of other modes for some material categories. While market share and revenues for radioactive material are presently small, rail carriers appear to have a market advantage for milled uranium ore, transuranic waste and high-level waste. The potential for a significantly increased market share exists for spent fuel and uranium hexafluoride. While more fresh fuel and low-level waste can be transported by rail, it is unlikely that rail market share for radioactive materials (RAM) in general will rise to the potential maximum because many of these materials have historically been moved by truck and transported in frequent, small shipments

  9. Sources of carrier F-19 in F-18 fluoride

    Energy Technology Data Exchange (ETDEWEB)

    Link, J. M.; Shoner, S. C.; Krohn, K. A. [University of Washington, Department of Radiology, Molecular Imaging Center, 1959 NE Pacific St., Box 356004, Seattle, WA 98195-6004 (United States)

    2012-12-19

    Fluorine-18 is used for many PET radiopharmaceuticals. Theoretically {sup 18}F should be carrier free and a good candidate for nanochemistry. However, {sup 18}F has 10 to 1000 times more stable fluorine atoms than radioactive atoms. In order to understand the source of carrier fluoride and other ions associated with {sup 18}F radiosynthesis, anion concentrations of different components of {sup 18}F target systems as well as solvents and chemicals used in radiosynthesis were measured. Results: The enriched water used for production of {sup 18}F had low levels of anions. In general, the sources of anions, particularly of fluoride, were the chemical reagents used for synthesis and trace contaminants in tubing, valves and fittings. A major component of contamination was nitrate from irradiation of dissolved nitrogen gas in the target water.

  10. A radioisotope technique for laboratory studies of the dispersal of rice weevil in grain

    International Nuclear Information System (INIS)

    Khan, M.Z.A.; Robertson, G.B.

    1979-01-01

    Adult rice weevils (Sitophilus oryzae (L.)) were marked with paint containing Scandium-46 and detected in a column of wheat 4.5 cm diam by means of a γ-scintillation counter. The radioactive paint had no effect on the mobility and longevity of the insects. Two weevils marked with Sc-46 could be located if they were more than 2.5 cm apart. An account is given of the use of the technique to follow the movements of a single pair of male and female weevils over 8 days. (Auth.)

  11. 78 FR 66801 - Motor Carrier Safety Advisory Committee; Charter Renewal

    Science.gov (United States)

    2013-11-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee; Charter Renewal AGENCY: Federal Motor Carrier Safety... and recommendations on motor carrier safety programs and motor carrier safety regulations through a...

  12. Ad gist : Ad communication in a single eye fixation

    NARCIS (Netherlands)

    Pieters, R.; Wedel, M.

    2012-01-01

    Most ads in practice receive no more than a single eye fixation. This study investigates the limits of what ads can communicate under such adverse exposure conditions. We find that consumers already know at maximum levels of accuracy and with high degree of certainty whether something is an ad or is

  13. Effect of truck and rail economic deregulation on radioactive material transportation

    International Nuclear Information System (INIS)

    Allen, G.C. Jr.

    1984-01-01

    An evaluation of the effect of truck and rail economic deregulation on radioactive material transportation is presented in this document. The evaluation is based on expected market performance that would be consistent with fundamental economic theories. The issues of transport safety, commodity discrimination and rates are addressed. Relative to transport safety, deregulation should not have any significant impact. While deregulation should not change commodity acceptance and may lower rates for motor carriage, it may allow increased discrimination by rail carriers in addition to raising rates. Consequently, it is likely that the radioactive material transportation industry will continue to place greater reliance on the competitive motor carrier industry. Positive steps that shippers can take are to maintain credible options to ship by alternate modes, to address issues that result in the perceived need for special risk premiums, and to reduce the cost of handling truck shipments by improvements in technology or procedures. 28 references, 3 figures, 6 tables

  14. Binding of rare earths to serum proteins and DNA

    International Nuclear Information System (INIS)

    Rosoff, B.; Spencer, H.

    1979-01-01

    In order to investigate further the physiological behavior of rare earths and rare earth chelates, studies of the binding of 46 Sc, 91 Y, and 140 La to serum proteins and to nucleic acids were performed using the methods of equilibrium dialysis and ultrafiltration. The binding of lanthanum and yttrium as the chlorides to α-globulin increased as the free rare earth concentration increased. When scandium and lanthanum were chelated in nitrilotriacetate (NTA) the binding to α-globulin was considerably less and there was no binding to albumin. The binding of 46 Sc chelated to ethylenediamine di(O-hydroxyphenylacetate) (EDDHA) was five times greater than of 46 Sc chloride. When the free scandium concentration was increased, the moles bound per mole of protein increased proportionally and the binding was reversible. Scandium was 100% filterable from a mixture of human serum and from the scandium chelates with high stability constants scandium diethylenetriaminepentaacetate (ScDTPA), scandium ethylenediaminetetraacetate (ScEDTA) and scandium cyclohexane trans-1,2-diaminetetraacetate (ScCDTA) respectively. In contrast, only 2% of the scandium was filterable when scandium nitrilotriacetate, a scandium chelate of low stability constant, was used. (Auth.)

  15. Compensation of native donor doping in ScN: Carrier concentration control and p-type ScN

    Science.gov (United States)

    Saha, Bivas; Garbrecht, Magnus; Perez-Taborda, Jaime A.; Fawey, Mohammed H.; Koh, Yee Rui; Shakouri, Ali; Martin-Gonzalez, Marisol; Hultman, Lars; Sands, Timothy D.

    2017-06-01

    Scandium nitride (ScN) is an emerging indirect bandgap rocksalt semiconductor that has attracted significant attention in recent years for its potential applications in thermoelectric energy conversion devices, as a semiconducting component in epitaxial metal/semiconductor superlattices and as a substrate material for high quality GaN growth. Due to the presence of oxygen impurities and native defects such as nitrogen vacancies, sputter-deposited ScN thin-films are highly degenerate n-type semiconductors with carrier concentrations in the (1-6) × 1020 cm-3 range. In this letter, we show that magnesium nitride (MgxNy) acts as an efficient hole dopant in ScN and reduces the n-type carrier concentration, turning ScN into a p-type semiconductor at high doping levels. Employing a combination of high-resolution X-ray diffraction, transmission electron microscopy, and room temperature optical and temperature dependent electrical measurements, we demonstrate that p-type Sc1-xMgxN thin-film alloys (a) are substitutional solid solutions without MgxNy precipitation, phase segregation, or secondary phase formation within the studied compositional region, (b) exhibit a maximum hole-concentration of 2.2 × 1020 cm-3 and a hole mobility of 21 cm2/Vs, (c) do not show any defect states inside the direct gap of ScN, thus retaining their basic electronic structure, and (d) exhibit alloy scattering dominating hole conduction at high temperatures. These results demonstrate MgxNy doped p-type ScN and compare well with our previous reports on p-type ScN with manganese nitride (MnxNy) doping.

  16. Effect of Radioactivity of Technetium-99m on the Autosterilization Process of non-sterile Tetrofosmin Kits

    Directory of Open Access Journals (Sweden)

    Widyastuti Widyastuti

    2017-03-01

    Full Text Available Technetium-99m labeled radiopharmaceutical is commonly used in nuclear medicines as a diagnostic agent, by mixing the sterile kit with Tc-99m. Manufacturing of kits requires an aseptic facility which need to be well designed and maintained according to cGMP, since mostly kits can not be terminally sterilized. Radiopharmaceuticals as pharmaceuticals containing radionuclide is assumed to have an autosterilization property, but correlation between radioactivity and capability of killing microorganisms has to be studied so far. The aim of this study is to investigate the effect of radioactivity on the autosterilization process of radiopharmaceuticals. The study was carried out by adding Tc-99m of various radioactivity into non-sterile tetrofosmin kits, then the samples were tested for sterility. Sterile tetrofosmin kit and non-sterile kit with no Tc-99m added will be used as a negative control and positive control respectively. The sterility was tested using standard direct inoculation method, by inoculating samples in culture media for both bacteria and fungi and observing qualitatively within 14 days. The results showed that the samples with radioactivity of 1, 3 and 5 mCi changed the clarity of the media to turbid, conformed with the performance of positive controls but samples with radioactivity of 10 mCi and 20 mCi did not change the clarity of the media, conformed with the performance of negative control, indicating neither growth of bacteria nor fungi. It is concluded that Tc-99m behaves as an autosterilizing agent at certain radioactivity. Therefore the preparation of Tc-99m radiopharmaceutical can be considered as terminal sterilization rather than aseptic preparation.

  17. Self-Assembled Nanocomposite Organic Polymers with Aluminum and Scandium as Heterogeneous Water-Compatible Lewis Acid Catalysts.

    Science.gov (United States)

    Miyamura, Hiroyuki; Sonoyama, Arisa; Hayrapetyan, Davit; Kobayashi, Shū

    2015-09-01

    While water-compatible Lewis acids have great potential as accessible and environmentally benign catalysts for various organic transformations, efficient immobilization of such Lewis acids while keeping high activity and without leaching of metals even under aqueous conditions is a challenging task. Self-assembled nanocomposite catalysts of organic polymers, carbon black, aluminum reductants, and scandium salts as heterogeneous water-compatible Lewis acid catalysts are described. These catalysts could be successfully applied to various C-C bond-forming reactions without leaching of metals. Scanning transmission electron microscopy analyses revealed that the nanocomposite structure of Al and Sc was fabricated in these heterogeneous catalysts. It is noted that Al species, which are usually decomposed rapidly in the presence of water, are stabilized under aqueous conditions. © 2015 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  18. Comparative microstructure and electrical property studies of lead scandium tantalate thin films as prepared by LDCVD, sol-gel and sputtering techniques

    International Nuclear Information System (INIS)

    Huang, Z; Donohue, P P; Zhang, Q; Williams, D J; Anthony, C J; Whatmore, R W; Todd, M A

    2003-01-01

    Lead scandium tantalate (PST) thin films for uncooled infrared (IR) detector applications have been deposited by liquid delivery chemical vapour deposition (LDCVD), sputtering and sol-gel techniques. The sol-gel and sputtered films were deposited at low temperature into a non-ferroelectric phase with the required perovskite structure being formed using a high temperature rapid thermal anneal (RTA). In contrast to this, the LDCVD films were deposited at high temperature directly into the perovskite phase but were found to still require a high temperature RTA step to optimize their merit for IR detection. Detailed structural and electrical characterization of the PST films deposited by these different methods have revealed that there is no simple relationship between microstructure and electrical properties. The sol-gel and LDCVD techniques produce thin films with excellent microstructures, as determined by x-ray diffraction analysis and transmission electron microscopy, but inferior electrical properties and relatively low merit figures. By contrast, the sputtered and then rapid thermal annealed films have inferior microstructures, characterized by extensive voiding, but excellent electrical properties and high merit figures

  19. Structural characteristics and physical properties of diortho(pyro)silicate crystals of lanthanides yttrium and scandium grown by the Czochralski technique

    Energy Technology Data Exchange (ETDEWEB)

    Anan' eva, G.V.; Karapetyan, V.E.; Korovkin, A.M.; Merkulyaeva, T.I.; Peschanskaya, I.A.; Savinova, I.P.; Feofilov, P.P. (Gosudarstvennyj Opticheskij Inst., Leningrad (USSR))

    1982-03-01

    Optically uniform monocrystals of diortho (pyro) silicates of lanthanides, yttrium, and scandium were grown by the Czochralski technique. Four structural types of Ln/sub 2/(Si/sub 2/O/sub 7/) crystals were determined by the roentgenographic method. The presence of structural subgroups was also supported by the method of spectroscopic probes. Structural parameters were determined and data on certain physical properties (fusion temperature, density, refractive indices, transparency) of investigated crystals were presented. The generation of induced emission at lambda=1.057 ..mu..m was obtained in La/sub 2/(Si/sub 2/O/sub 7/)-Nd/sup 3 +/ crystal.

  20. Personality traits in Huntington's disease: An exploratory study of gene expansion carriers and non-carriers.

    Science.gov (United States)

    Larsen, Ida Unmack; Mortensen, Erik Lykke; Vinther-Jensen, Tua; Nielsen, Jørgen Erik; Knudsen, Gitte Moos; Vogel, Asmus

    2016-12-01

    Huntington's disease (HD) is associated with risk for developing psychiatric symptoms. Vulnerability or resilience to psychiatric symptoms may be associated with personality traits. This exploratory study, aimed to investigate personality traits in a large cohort of HD carriers and at risk gene-expansion negative individuals (HD non-carriers), exploring whether carrying the HD gene or growing up in an HD family influences personality traits. Forty-seven HD carriers, Thirty-nine HD non-carriers, and 121 healthy controls answered the Danish version of the revised NEO personality inventory. Comparisons between HD carriers and HD non-carriers were mostly non-significant but the combined group of HD carriers and non-carriers showed significantly higher scores on the facets: "hostility," "assertiveness," and "activity" and on the trait "Conscientiousness" relative to controls, "Conscientiousness" have been associated with resilience to psychiatric symptoms. Twelve HD carriers and non-carriers were classified as depressed and showed significantly lower scores on "Extraversion" and "Conscientiousness" and significantly higher scores on "Neuroticism," which are associated with vulnerability to psychiatric symptoms. Our findings suggest that, there is no direct effect of the HD gene on personality traits, but that personality assessment may be relevant to use when identifying individuals from HD families who are vulnerable to develop psychiatric symptoms. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  1. Radioactive waste equivalence

    International Nuclear Information System (INIS)

    Orlowski, S.; Schaller, K.H.

    1990-01-01

    The report reviews, for the Member States of the European Community, possible situations in which an equivalence concept for radioactive waste may be used, analyses the various factors involved, and suggests guidelines for the implementation of such a concept. Only safety and technical aspects are covered. Other aspects such as commercial ones are excluded. Situations where the need for an equivalence concept has been identified are processes where impurities are added as a consequence of the treatment and conditioning process, the substitution of wastes from similar waste streams due to the treatment process, and exchange of waste belonging to different waste categories. The analysis of factors involved and possible ways for equivalence evaluation, taking into account in particular the chemical, physical and radiological characteristics of the waste package, and the potential risks of the waste form, shows that no simple all-encompassing equivalence formula may be derived. Consequently, a step-by-step approach is suggested, which avoids complex evaluations in the case of simple exchanges

  2. Phenomenological theory of the dielectric response of lead magnesium niobate and lead scandium tantalate

    International Nuclear Information System (INIS)

    Qian, H.; Bursill, L.A.

    1997-01-01

    The influence of the random field effects originating from charges chemical defects and non-domain textures of the formation and dynamics of polar clusters is analyzed. The spatial distribution of the local fields is not totally random but contains some correlations in direction and strength. Polar clusters are classified to be dynamic or frozen according to their dynamic characteristics in the random fields. The relaxation formula of a dipolar moment in an anisotropic double-well potential is deduced. Two percolation models are introduced, one to account for frustration effects associated with multiple orientations of polar clusters, which results in a broad diffuse dielectric response and the second to account for the case whereby there may be a phase transition to a ferroelectric state. The dielectric permittivity and dissipation factor of the typical relaxors lead magnesium niobate and lead scandium tantalate are predicted as a function of both temperature and frequency, which results are in good agreement with the experimental measurements. 30 refs., 9 figs

  3. Microstructure and age-hardening effects of aluminium alloys with additions of scandium and zirconium

    Energy Technology Data Exchange (ETDEWEB)

    Galun, R.; Mordike, B.L. [Inst. fuer Werkstoffkunde und Werkstofftechnik, Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany); Maiwald, T.; Smola, B. [Zentrum fuer Funktionswerkstoffe GmbH, Clausthal-Zellerfeld (Germany); Mergen, R.; Manner, M.; Uitz, W. [Miba Gleitlager GmbH, Laakirchen (Australia)

    2004-12-01

    The aim of the work presented in this report was to produce age-hardenable aluminium alloys containing scandium and zirconium by a casting process with similar cooling conditions like an industrial casting process. Microstructure, precipitation structure and age-hardening response of different alloys with up to 0.4 wt.% Sc and Zr were investigated. Age-hardening experiments from the as-cast condition without solution annealing showed a significant increase of hardness of about 100% for Sc-rich alloys and of 50% for Zr-rich alloys compared to the as-cast condition. TEM investigations revealed the formation of precipitates of ternary Al{sub 3}(Sc{sub x}Zr{sub 1-x}) phases with a cubic cP4 crystal structure. In addition to the strengthening effect, a high thermal stability especially of the precipitates in Zr-rich alloys up to 400 C let these alloys look very promising for high-temperature applications. (orig.)

  4. Method for treating radioactive liquids

    International Nuclear Information System (INIS)

    Komrow, R.R.; Pritchard, J.F.

    1980-01-01

    A process for treating and handling radioactive liquids and rendering such liquids safe for handling is disclosed. Transportation and disposal, the process comprises adding thereto a small amount of a water-insoluble alkali salt of an aqueous alkali saponified gelatinized-starch-polyacrylonitrile graft polymer, to form a solid, semi-solid or gel product

  5. Labelling of olive oil with radioactive iodine and radioactive technetium

    International Nuclear Information System (INIS)

    Al-Dayel, O.A.F.

    1988-03-01

    Investigates labelling of olive oil with 125 iodine and with the radioactive 99mTC. A radio analytical study for 99Mo-99mTC generator is also presented. Iodine monochloride and chlormine-T methods are used for labelling olive oil and oleic acid with radioactive iodine. Diethyl ether, benzene and n-heptane have been used as solvents, with diethyl ether giving best results using iodine monochloride method. Infrared spectroscopic studies show that labelling took place at the double bond. Use of milked 99mTc gave very low yield only. A fairly higher labelling yield was achieved when 20 mg of tin chloride has been added in acetone medium than diethyl ether medium. Thin layer chromatography and paper chromatography technique were used as quality control systems. The labelled oil can be used for diagnostic and study purposes. 140 Ref

  6. Removal of Radioactive Pollutants by Liquid Emulsion Membrane From Liquid Waste

    International Nuclear Information System (INIS)

    Yossef, Y.A.A.

    2013-01-01

    Radioactive liquid waste should be safely managed because it is potentially hazardous to human health and the environment. Several methods were used for treatment of liquid waste, such as liquid emulsion membrane (LEM). In this work, liquid emulsion membrane using Tri-butyl phosphate (TBP) plus Bis (2-ethylhexyl) phosphate (HDEHP) as mobile carriers, hydrochloric acid (HCl) as stripping agents and an emulsifying agent (span 80) was used for the extraction of uranium ions from radioactive liquid waste. Various parameters influencing the permeation of uranium ions through the membrane have been optimized to separate uranium ions from radioactive liquid waste such as: the effects of membrane material, carrier concentration, operating conditions, etc. were examined; moreover, the transport mechanism of this uranium was also studied. The internal mass transfer in the water/oil (W/O) emulsion drop, the external mass transfer around the drop, the rates of formation, and the decomposition of the complex at the external aqueous-organic interface were considered. The results show that, the liquid emulsion membrane which consists of (25% by volume HDEHP, 0.005 M + 75% by volume TBP, 0.01 M) as extractant (carrier), span 80, 4% (v/v) (sorbitan monooleate) as surfactant agent, hydrochloric acid (HCl), (1.0 M) as stripping agent. From the results, the maximum extraction percent of uranium ions (nearly about of 100%) occurred at the operating conditions: stirring speed =500 rpm, the ratio between LEM and feed phase (liquid waste) = 20 ml: 100 ml, the ratio between organic phase (membrane phase) to internal aqueous phase (stripping phase) = 1.0 and the ph value of the external aqueous phase equal to 5.0.

  7. Smoothed transitions in higher spin AdS gravity

    International Nuclear Information System (INIS)

    Banerjee, Shamik; Shenker, Stephen; Castro, Alejandra; Hellerman, Simeon; Hijano, Eliot; Lepage-Jutier, Arnaud; Maloney, Alexander

    2013-01-01

    We consider CFTs conjectured to be dual to higher spin theories of gravity in AdS 3 and AdS 4 . Two-dimensional CFTs with W N symmetry are considered in the λ = 0 (k → ∞) limit where they are conjectured to be described by continuous orbifolds. The torus partition function is computed, using reasonable assumptions, and equals that of a free-field theory. We find no phase transition at temperatures of order 1; the usual Hawking–Page phase transition is removed by the highly degenerate light states associated with conical defect states in the bulk. Three-dimensional Chern–Simons matter CFTs with vector-like matter are considered on T 3 , where the dynamics is described by an effective theory for the eigenvalues of the holonomies. Likewise, we find no evidence for a Hawking–Page phase transition at a large level k. (paper)

  8. Current status of radioactive waste management in Japan

    International Nuclear Information System (INIS)

    Amanuma, Tsuyoshi

    1985-01-01

    In Japan the nuclear power generation capacity now exceeds the level of 20,000 MW, 24.3 % of the total power generation. It constitutes the major position of energy source, a substitute for a petroleum. In the nuclear power, chemical engineering contributes significantly to treatment and disposal of the radioactive wastes. In the interim report by an ad hoc committee in the Atomic Energy Commission, for the future, rational grouping of the wastes and the direction of land disposal are stated. Contents are the following: basic ideas for the radioactive wastes, radioactive wastes countermeasures in Japan (wastes classification, low and high level and transuranic wastes), radioactive wastes in the nuclear fuel cycle (reactor and fuel reprocessing and reactor dismantling wastes). (Mori, K.)

  9. The minimization of radioactive releases to the sea from the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Sugiyama, T.; Yoshikawa, K.; Ishii, T.

    1996-01-01

    The Tokai Reprocessing Plant (TRP) started hot operation in September 1977. The total amount of about 790 tU of spent fuel, generated in Japan, has been successfully reprocessed as of December 1994. Low-level liquid wastes have been treated safely with the low-level waste treatment process. The design of TRP was based on foreign technology. In the early stage of designing, the radioactivity released to the sea was estimated at approximately 2.6 TBq/day (70 Ci/day) for beta activity (except for tritium). Later, PNC added an evaporator to the process to reduce the level down to 1/100, i.e. 9.6 TBq/year (260 Ci/year) or 2.6 x 10 -2 TBq/day (0.7 Ci/day). In addition, under the supervision of the government, PNC started R and D to further decrease the radioactivity released to the sea in terms of ALARA. Aiming at reducing the activity from 9.6 TBq/year (260 Ci/year) to 1/10 of that value (i.e. 26 Ci/year), the release reduction technology development facility was added. This facility was incorporated into the low-level waste treatment process in 1980, before starting the regular operation of TRP. Since the fuel reprocessing commenced, total radioactivity discharged to the sea has been 1.9 x 10 -2 TBq (0.51 Ci) for beta activity, as of December 1994. Before incorporating the release reduction technology development facility, the yearly level was 3.7 x 10 -3 - 7.4 x 10 -3 TBq (0.1 - 0.2 Ci). After incorporation of the facility, radioactivity released to the sea was greatly decreased to non-detection levels in recent years, in spite of increasing annual reprocessing amounts. Although serious equipment failures have occurred such as the acid recovery evaporator and the dissolvers, there was no influence on radioactivity released to the sea. (author)

  10. Model for the reduction of denials of expeditions of radioactive material in the region of the America

    International Nuclear Information System (INIS)

    Mallaupoma, Mario; Bruno, Natanael

    2013-01-01

    The denials, restraints and delays of shipments of radioactive material likely to have occurred and continue to occur. Reducing them to acceptable levels can be a tangible goal that senders and recipients can anticipate and get. The basis for resolving cases of denials and delays should consider not only the participation of the competent national nuclear authorities but also other government authorities. Carriers, shippers, transport companies and recipients should consider in their queries all the wide range of authorities apparently have no involvement but they really have. This paper describes the experience gained in the country of Brazil and provides the basis of a model that could prove useful to other countries and regions, including America, if we adopt and adapt, to reduce the incidence of denials and delays of shipments of radioactive material, according to its own conditions and characteristics

  11. Radiation sources and process

    International Nuclear Information System (INIS)

    Honious, H.B.; Janzow, E.F.; Malson, H.A.; Moyer, S.E.

    1980-01-01

    The invention relates to radiation sources comprising a substrate having an electrically-conductive non-radioactive metal surface, a layer of a metal radioactive isotope of the scandium group, which in addition to scandium, yttrium, lanthanum and actinium, includes all the lanthanide and actinide series of elements, with the actinide series usually being preferred because of the nature of the radioactive isotopes therein, particularly americium-241, curium-244, plutonium-238, californium-252 and promethium-147, and a non-radioactive bonding metal codeposited on the surface by electroplating the isotope and bonding metal from an electrolytic solution, the isotope being present in the layer in minor amount as compared to the bonding metal, and with or without a non-radioactive protective metal coating covering the isotoype and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating. The invention also relates to a process for providing radiation sources comprising codepositing a layer of the metal radioactive isotope with a non-radioactive bonding metal from an electrolytic solution in which the isotope is present in minor molar amount as compared to the bonding metal such that the codeposited layer contains a minor molar amount of the isotope compared to the bonding metal by electroplating on an electrically-conductive non-radioactive metal surface of a cathode substrate, and with or without depositing a nonradioactive protective metal coating over the isotope and bonding metal on the surface, the coating being sufficiently thin to permit radiation to pass through the coating

  12. Low-voltage and high-efficiency white organic light emitting devices with carrier balance

    International Nuclear Information System (INIS)

    Wei Fuxiang; Huang, Y.; Fang, L.

    2010-01-01

    White organic light emitting devices with the structure of ITO/m-MTDATA:x%4F-TCNQ/NPB/TBADN:EBDP:DCJTB/Bphen:Liq/LiF/Al have been demonstrated in this paper. High-mobility m-MTDATA:4F-TCNQ is added into the region between ITO and NBP to increase hole injection and transport. The high-mobility Bphen:Liq layer is added into the region between cathode and emission layers to lower cathode barrier and facilitate carrier injection. In the meanwhile, an effective carrier balance (number of holes is equal to number of electrons) between holes and electrons is considered to be one of the most important factors for improving OLEDs. During the experiment, by modulating the doping concentration of 4F-TCNQ, we can control hole injection and transport to make the carriers reach a high-level balance. The maximum current efficiency and power efficiency of devices were 9.3 cd/A and 4.6 lm/A, respectively.

  13. Adsorption of hydrogen in Scandium/Titanium decorated nitrogen doped carbon nanotube

    Energy Technology Data Exchange (ETDEWEB)

    Mananghaya, Michael, E-mail: mikemananghaya@gmail.com [De La Salle University, 2401 Taft Ave, 0922, Manila (Philippines); DLSU STC Laguna Boulevard, LTI Spine Road Barangays Biñan and Malamig, Biñan City, Laguna (Philippines); DOST-ASTHRDP, PCIEERD, Gen. Santos Ave., Bicutan, Taguig City 1631 (Philippines); Belo, Lawrence Phoa; Beltran, Arnel [De La Salle University, 2401 Taft Ave, 0922, Manila (Philippines); DLSU STC Laguna Boulevard, LTI Spine Road Barangays Biñan and Malamig, Biñan City, Laguna (Philippines)

    2016-09-01

    Nitrogen doped Carbon Nanotube with divacancy (4ND-CN{sub x}NT) that is decorated with Scandium and Titanium as potential hydrogen storage medium using the pseudo potential density functional method was investigated. Highly localized states near the Fermi level, which are derived from the nitrogen defects, contribute to strong Sc and Ti bindings, which prevent metal aggregation and improve the material stability. A detailed Comparison of the Hydrogen adsorption capability with promising system-weight efficiency of Sc over Ti was elucidated when functionalized with 4ND-CN{sub x}NT. Finally, the (Sc/4ND){sub 10}-CN{sub x}CNT composite material has a thermodynamically favorable adsorption and consecutive adsorption energy for ideal reversible adsorption and desorption of hydrogen at room temperature such that it can hold at least 5.8 wt% hydrogen molecules at the LDA and GGA level. - Highlights: • Carbon Nanotube with divacancy (4ND-CN{sub x}NT) decorated with Sc and Ti. • Nitrogen defects, contribute to strong Sc and Ti bindings. • H{sub 2} and (Sc/4ND){sub 10}-CN{sub x}CNT has a favorable adsorption. • 5.8 wt% adsorption at the LDA and GGA level.

  14. Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

    International Nuclear Information System (INIS)

    Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming

    2016-01-01

    Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment

  15. Environment assessing for airborne radioactive particulate release-introduction of methods in IAEA safety report series No.19

    Energy Technology Data Exchange (ETDEWEB)

    Meng, Dan; Yang, Liu; Shen, Fu; Yang, Yi; Ma, Yinghao; Ma, Tao; Zhang, Zhilong; Fu, Cuiming [China Institute for Radiation Protection, Taiyuan (China)

    2016-12-15

    Airborne radioactive particulate in many important nuclear facilities (particularly nuclear power plants) will have a strong impact on the relative public dose if they are released into the corresponding environment traversing the stack or vents. The radiation protection researchers have regarded the relative environment assessing and estimation of public doses. And the model of assessing impact of discharges radioactive substance to the environment have been recommended by many international organizations (e.g. IAEA) with the nuclear energy safety and radiation protection. This paper introduced the generic models that were suggested by International Atomic Energy Agency (IAEA), for use in assessing the impact of discharges of radioactive substances to the environment (e.g. IAEA Safety Report Series No.19). The writers of this paper, based on the recommend methods, assessed the discharge limits in some airborne radioactive substances discharging standards. The reasons that IAEA method are introduced are mainly the following considerations: IAEA is one of international organizations with some authorities in the nuclear energy safety and radiation protection; and, more important, the recommend modes are operational methods rather than the methods having little operations such as that have used by some researchers. It is wish that the introduced methods in this paper can be referenced in draft or revise of the standards related to discharges of radioactive substances to the environment.

  16. Observation of interface carrier states in no-common-atom heterostructures ZnSe/BeTe

    Science.gov (United States)

    Gurevich, A. S.; Kochereshko, V. P.; Bleuse, J.; Mariette, H.; Waag, A.; Akimoto, R.

    2011-09-01

    The existence of intrinsic carrier interface states in heterostructures with no common atom at the interface (such as ZnSe/BeTe) is shown experimentally by ellipsometry and photoluminescence spectroscopy. These states are located on interfaces and lie inside the effective bandgap of the structure; they are characterized by a high density and a long lifetime. A tight binding model confirms theoretically the existence of these states in ZnSe/BeTe heterostructures for a ZnTe-type interface, in contrast to the case of the BeSe-type interface for which they do not exist.

  17. Observation of interface carrier states in no-common-atom heterostructures ZnSe/BeTe

    Energy Technology Data Exchange (ETDEWEB)

    Gurevich, A S; Kochereshko, V P [A F Ioffe Physical-Technical Institute, St Petersburg 194021 (Russian Federation); Bleuse, J; Mariette, H [CEA-CNRS Group ' Nanophysique et Semiconducteurs' , CEA, INAC/SP2M, and Institut Neel, 17 rue des Martyrs, F-38054 Grenoble (France); Waag, A [Braunschweig Technical University, Hans-Sommer-Strasse 66, D-38106 Braunschweig (Germany); Akimoto, R, E-mail: vladimir.kochereshko@mail.ioffe.ru [National Institute of Advanced Industrial Science and Technology (AIST), AIST Tsukuba Central 2-1, Tsukuba 305-8568 (Japan)

    2011-09-07

    The existence of intrinsic carrier interface states in heterostructures with no common atom at the interface (such as ZnSe/BeTe) is shown experimentally by ellipsometry and photoluminescence spectroscopy. These states are located on interfaces and lie inside the effective bandgap of the structure; they are characterized by a high density and a long lifetime. A tight binding model confirms theoretically the existence of these states in ZnSe/BeTe heterostructures for a ZnTe-type interface, in contrast to the case of the BeSe-type interface for which they do not exist.

  18. The transport safety of radioactive matters; La surete des transports des matieres radioactives

    Energy Technology Data Exchange (ETDEWEB)

    Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

    2007-02-15

    Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

  19. 76 FR 32390 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2011-06-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee (MCSAC) Meeting. SUMMARY...

  20. 77 FR 46555 - Motor Carrier Safety Advisory Committee: Public Meeting

    Science.gov (United States)

    2012-08-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee: Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety Advisory Committee (MCSAC...

  1. 75 FR 2923 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-01-19

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  2. 75 FR 29384 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-05-25

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee meeting. SUMMARY: FMCSA...

  3. 75 FR 72863 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-11-26

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration, DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA announces...

  4. 75 FR 50797 - Motor Carrier Safety Advisory Committee Public Meeting

    Science.gov (United States)

    2010-08-17

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2010-0143] Motor Carrier Safety Advisory Committee Public Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Motor Carrier Safety Advisory Committee Meeting. SUMMARY: FMCSA...

  5. Radioactive waste management: An international perspective

    International Nuclear Information System (INIS)

    Chan, C.Y.

    1992-01-01

    Scientists, governments, and the general public have devoted considerable attention to the subject of radioactive waste over the past 35 years. The subject has gained even more attention of late, owing to heightened awareness of environmental protection. Potential transboundary effects have further added to this interest, which today extends beyond local domains to regional and global levels. Almost all of the IAEA's Member States generate some radioactive wastes. The type of waste they produce varies, however, as do the quantities, which range from a few grams to several hundred tonnes of wastes per year. This article will summarize the status of waste management and disposal activities in IAEA Member States as well as providing a brief background on what radioactive waste is, where it comes from, and how it is managed

  6. Bonding in scandium monosulfide a NaCl crystal type

    International Nuclear Information System (INIS)

    Merrick, J.A.

    1980-08-01

    The transition temperature of an order-disorder transition in Sc 0 81 S (R anti 3m to Fm3m) occurs at 700 0 C. A group of ordered sublattices on the NaCl-type lattice (Fm3m) was generated and a Madelung energy and configurational entropy were calculated for each sublattice assuming the ions to be Sc 2 48+ and S 2- . Mean field and pair interaction approximations were used to model long-range and short-range orderings, respectively. The electrostatic model fails to predict the observed short-range and long-range orderings. The high temperature vaporization of ScP was investigated by mass spectrometry and target collection Knudsen effusion at 1767 to 2209K. The composition ScP 1 00 vaporizes congruently to the gaseous species Sc, P, and P 2 . A temperature independent third law enthalpy of atomization (ΔH 0 /sub atom,298/ = 252.2 +- 2.8 kcal mole -1 ) has a value approx. 12 kcal larger than that reported for ScS. Nonrelativistic, nonself-consistent LAPW band structure calculations are reported for ScS. XPS and UPS measurements are reported for Sc 2 S 3 and several compositions Sc/sub 1-x/S (0.0 less than or equal to x less than or equal to 0.2). The Sc and S 2p binding energies (XPS) obtained for the defect scandium monosulfides are very close to those found in the pure elements, suggesting covalent bonding. The Sc 2p energy region has an interesting satellite structure

  7. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Seki, Shuji.

    1992-01-01

    Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

  8. Radioactive waste cementation

    International Nuclear Information System (INIS)

    Soriano B, A.

    1996-01-01

    This research was carried out to develop the most adequate technique to immobilize low and medium-activity radioactive waste. different brands of national cement were used, portland and pozzolanic cement. Prismatic and cylindrical test tubes were prepared with different water/cement (W/C) relationship. Additives such a as clay and bentonite were added in some other cases. Later, the properties of these test tubes were evaluated. Properties such as: mechanical resistance, immersion resistance, lixiviation and porosity resistance. Cement with the highest mechanical resistance values, 62,29 MPa was pozzolanic cement for a W/C relationship of 0,35. It must be mentioned that the other types of cements reached a mechanical resistance over 10 MPa, a value indicated by the international standards for transportation and storage of low and medium-activity radioactive waste at a superficial level. However, in the case of immersion resistance, Sol cement (portland type I) with a W/C relationship of 0,35 reached a compression resistance over 61,92 MPa; as in the previous cases, the other cements reached a mechanical resistance > 10 MPa. Regarding porosity, working with W/C relationships = 0,35 0,40 and 0,45, without additives and with additives, the percentage of porosity found for all cements is lower than 40% percentage indicated by international standards. With regard to the lixiviation test, pozzolanic cement best retained Cesium-137 and Cobalt-60, and increased its advantages when bentonite was added, obtaining a lixiviation rate of 2,02 x E-6 cm/day. Sol cement also improved its properties when bentonite was added and obtained a lixiviation rate of 2,84 x E-6 cm/day for Cesium-137. However, Cobalt-60 is almost completely retained with the 3 types of cement with or without additives, reaching the limits indicated by the international standards for the lixiviation rate of beta-gamma emitter < 5,00E-4 cm/day. Characterizing the final product involves the knowledge of its

  9. SI 1985 No. 1048 - The Radioactive Substances (Luminous Articles) Exemption Order 1985

    International Nuclear Information System (INIS)

    1985-01-01

    This Order, which came into force on 17 September 1985, is concerned with exemptions and exclusions under the Radioactive Substances Act 1960 in respect of radioactive luminous instruments and indicators. (NEA) [fr

  10. Radioautographic studies of the radioactive ashes obtained from the No. 5 Fukuryu Maru

    Energy Technology Data Exchange (ETDEWEB)

    Kikuchi, T; Akagi, H; Goto, H; Wakisaka, G

    1954-01-01

    Radioautographic studies have been made of the radioactive ashes obtained from the ship by use of x-ray film, radioautographic stripping plates, and plates of ..cap alpha..-emitters. The radioactivity was found not proportional to the size of the particle, and the distribution of radioactivity in each particle was not uniform.

  11. Interpolating from Bianchi attractors to Lifshitz and AdS spacetimes

    International Nuclear Information System (INIS)

    Kachru, Shamit; Kundu, Nilay; Saha, Arpan; Samanta, Rickmoy; Trivedi, Sandip P.

    2014-01-01

    We construct classes of smooth metrics which interpolate from Bianchi attractor geometries of Types II, III, VI and IX in the IR to Lifshitz or AdS 2 ×S 3 geometries in the UV. While we do not obtain these metrics as solutions of Einstein gravity coupled to a simple matter field theory, we show that the matter sector stress-energy required to support these geometries (via the Einstein equations) does satisfy the weak, and therefore also the null, energy condition. Since Lifshitz or AdS 2 ×S 3 geometries can in turn be connected to AdS 5 spacetime, our results show that there is no barrier, at least at the level of the energy conditions, for solutions to arise connecting these Bianchi attractor geometries to AdS 5 spacetime. The asymptotic AdS 5 spacetime has no non-normalizable metric deformation turned on, which suggests that furthermore, the Bianchi attractor geometries can be the IR geometries dual to field theories living in flat space, with the breaking of symmetries being either spontaneous or due to sources for other fields. Finally, we show that for a large class of flows which connect two Bianchi attractors, a C-function can be defined which is monotonically decreasing from the UV to the IR as long as the null energy condition is satisfied. However, except for special examples of Bianchi attractors (including AdS space), this function does not attain a finite and non-vanishing constant value at the end points

  12. Random-field Potts model for the polar domains of lead magnesium niobate and lead scandium tantalate

    Energy Technology Data Exchange (ETDEWEB)

    Qian, H.; Bursill, L.A

    1997-06-01

    A random filed Potts model is used to establish the spatial relationship between the nanoscale distribution of charges chemical defects and nanoscale polar domains for the perovskite-based relaxor materials lead magnesium niobate (PMN) and lead scandium tantalate (PST). The random fields are not set stochastically but are determined initially by the distribution of B-site cations (Mg, Nb) or (Sc, Ta) generated by Monte Carlo NNNI-model simulations for the chemical defects. An appropriate random field Potts model is derived and algorithms developed for a 2D lattice. It is shown that the local fields are strongly correlated with the chemical domain walls and that polar domains as a function of decreasing temperature is simulated for the two cases of PMN and PST. The dynamics of the polar clusters is also discussed. 33 refs., 9 figs.

  13. The transport of radioactive waste

    International Nuclear Information System (INIS)

    Appleton, P.R.; Poulter, D.R.

    1989-01-01

    Regulations have been developed to ensure the safe transport of all radioactive materials by all modes (road, rail, sea and air). There are no features of radioactive waste which set it aside from other radioactive materials for transport, and the same regulations control all radioactive material transport. These regulations and their underlying basis are described in this paper, and their application to waste transport is outlined. (author)

  14. Two anionically derivatized scandium oxoselenates(IV): ScF[SeO3] and Sc2O2[SeO3

    Science.gov (United States)

    Greiner, Stefan; Chou, Sheng-Chun; Schleid, Thomas

    2017-02-01

    Scandium fluoride oxoselenate(IV) ScF[SeO3] and scandium oxide oxoselenate(IV) Sc2O2[SeO3] could be synthesized through solid-state reactions. ScF[SeO3] was obtained phase-pure, by reacting mixtures of Sc2O3, ScF3 and SeO2 (molar ratio: 1:1:3) together with CsBr as fluxing agent in corundum crucibles embedded into evacuated glassy silica ampoules after firing at 700 °C for seven days. Sc2O2[SeO3] first emerged as by-product during the attempts to synthesize ScCl[SeO3] following aforementioned synthesis route and could later be reproduced from appropriate Sc2O3/SeO3 mixtures. ScF[SeO3] crystallizes monoclinically in space group P21/m with a=406.43(2), b =661.09(4), c=632.35(4) pm, β=93.298(3)° and Z=2. Sc2O2[SeO3] also crystallizes in the monoclinic system, but in space group P21/n with a=786.02(6), b=527.98(4), c=1086.11(8) pm, β=108.672(3)° for Z=4. The crystal structures of both compounds are strongly influenced by the stereochemically active lone pairs of the ψ1-tetrahedral [SeO3]2- anions. They also show partial structures, where the derivatizing F- or O2- anions play an important role. For ScF[SeO3] chains of the composition 2+∞ 1[FS c 2 / 2 ] form from connected [FSc2]5+ dumbbells, while [OSc3]7+ pyramids and [OSc4]10+ tetrahedra units are condensed to layers according to 2+ ∞ 2[O2Sc2 ] in Sc2O2[SeO3].

  15. Technical possibilities to support separation of radioactive elements from metallic waste

    International Nuclear Information System (INIS)

    Bjoerkvall, Johan; Ye, Guozhu; Lindberg, Maria

    2014-01-01

    In the nuclear industry metallic objects can be either surface or bulk contaminated. Surface contaminated objects are often decontaminated by chemical or mechanical means, but are there other possibilities? During melting slags are formed either spontaneously or by adding slag forming compounds. However, one question that frequently arises is: Can all nuclides be separated by adding slag forming compounds? This question is not entirely correct as it is not only the radioactive nuclides that are separated from the metal but all atoms of that element present in the melt, radioactive and stable isotopes alike. Part of the answer lays in thermodynamics. Thermodynamics cannot positively answer the question with yes, as there are also practical and economical aspects to take into account, but if the answer is no there will never be any practical or economical efforts that will override nature. This paper will describe the theoretical baseline for evaluating the possibilities to separate certain elements during the melting process, mainly from steel but other metals will also touched on. The most common elements that have radioactive isotopes of interest is of course cobalt (Co-60, Co-58), but other elements of interest are manganese (Mn-54), strontium (Sr- 90), antimony (Sb-125) and of course heavy elements such as uranium, plutonium and americium. The paper will also describe methods used in the normal metal melting industry to separate elements from the base metal melted. This section will cover practical methods used as well as developed methods that are very seldom used due to time or financial constraints. (authors)

  16. Evaluation of current prediction models for Lynch syndrome: updating the PREMM5 model to identify PMS2 mutation carriers.

    Science.gov (United States)

    Goverde, A; Spaander, M C W; Nieboer, D; van den Ouweland, A M W; Dinjens, W N M; Dubbink, H J; Tops, C J; Ten Broeke, S W; Bruno, M J; Hofstra, R M W; Steyerberg, E W; Wagner, A

    2018-07-01

    Until recently, no prediction models for Lynch syndrome (LS) had been validated for PMS2 mutation carriers. We aimed to evaluate MMRpredict and PREMM5 in a clinical cohort and for PMS2 mutation carriers specifically. In a retrospective, clinic-based cohort we calculated predictions for LS according to MMRpredict and PREMM5. The area under the operator receiving characteristic curve (AUC) was compared between MMRpredict and PREMM5 for LS patients in general and for different LS genes specifically. Of 734 index patients, 83 (11%) were diagnosed with LS; 23 MLH1, 17 MSH2, 31 MSH6 and 12 PMS2 mutation carriers. Both prediction models performed well for MLH1 and MSH2 (AUC 0.80 and 0.83 for PREMM5 and 0.79 for MMRpredict) and fair for MSH6 mutation carriers (0.69 for PREMM5 and 0.66 for MMRpredict). MMRpredict performed fair for PMS2 mutation carriers (AUC 0.72), while PREMM5 failed to discriminate PMS2 mutation carriers from non-mutation carriers (AUC 0.51). The only statistically significant difference between PMS2 mutation carriers and non-mutation carriers was proximal location of colorectal cancer (77 vs. 28%, p PMS2 mutation carriers (AUC 0.77) and overall (AUC 0.81 vs. 0.72). We validated these results in an external cohort of 376 colorectal cancer patients, including 158 LS patients. MMRpredict and PREMM5 cannot adequately identify PMS2 mutation carriers. Adding location of colorectal cancer to PREMM5 may improve the performance of this model, which should be validated in larger cohorts.

  17. Planning and preparing for emergency response to transport accidents involving radioactive material. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    The objective of this Safety Guide is to provide guidance to the public authorities and others (including consignors, carriers and emergency response authorities) who are responsible for developing and establishing emergency arrangements for dealing effectively and safely with transport accidents involving radioactive material. It may assist those concerned with establishing the capability to respond to such transport emergencies. It provides guidance for those Member States whose involvement with radioactive material is just beginning. It also provides guidance for those Member States that have already developed their radioactive material industries and the attendant emergency plans but that may need to review and improve these plans

  18. Statutory Instruments - 1984 No. 863 and 1985 No. 708. Public Health, England and Wales - Public Health Scotland. The Control of Pollution (Radioactive Waste) Regulations 1984, The Control of Pollution (Radioactive Waste) Regulations 1985

    International Nuclear Information System (INIS)

    1985-01-01

    The Regulations provide that radioactive waste is to be treated as any other waste for pollution control purposes as opposed to special radioactive control purposes. In the former respect, radioactive waste is subject to Part II of the Control of Pollution Act 1974, but in the latter, it remains subject to the Radioactive Substances Act 1960. (NEA) [fr

  19. Response to a radioactive materials release having a transboundary impact

    International Nuclear Information System (INIS)

    1989-01-01

    Compared with an accidental release of radioactive material which is confined to the accident State, a transboundary release has added dimensions which were not fully anticipated in publications dealing with response to accidents at nuclear facilities. The new aspects to the problem may be summarized as follows: (1) A transboundary release of radioactive material, as distinct from a release which affects only the accident State, has international repercussions in the following ways: Potentially at least, the difficulties associated with a transboundary release may be magnified in those States that have no nuclear facilities of their own and may, therefore, have foreseen no need for resources to assess and deal with radioactive contamination of their food supplies, their water and their environment appropriately. International trade, in food commodities particularly, may be severely affected. Issues of compensation may arise for which the dispute settlement mechanisms are weak or non-existent. (2) Many Member States are in such geographic locations that they could be affected by a transboundary release occurring in any of their surrounding neighbour States. Planning for and responding to such an event is necessarily more difficult than planning for an accidental release from a single, identified nuclear facility. (3) Deposits of radioactive material from a distant source are apt to be highly unpredictable. Depending on weather conditions, they may be localized in a random fashion or widespread. Because of the international dimension of the problem and its essentially unpredictable character it is recommended here that planning for such events should be carried at the national or federal government level rather than at provincial government level. 14 refs

  20. PROCESSING OF RADIOACTIVE WASTE

    Science.gov (United States)

    Johnson, B.M. Jr.; Barton, G.B.

    1961-11-14

    A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

  1. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

    Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references

  2. Methane biofiltration using autoclaved aerated concrete as the carrier material.

    Science.gov (United States)

    Ganendra, Giovanni; Mercado-Garcia, Daniel; Hernandez-Sanabria, Emma; Boeckx, Pascal; Ho, Adrian; Boon, Nico

    2015-09-01

    The methane removal capacity of mixed methane-oxidizing bacteria (MOB) culture in a biofilter setup using autoclaved aerated concrete (AAC) as a highly porous carrier material was tested. Batch experiment was performed to optimize MOB immobilization on AAC specimens where optimum methane removal was obtained when calcium chloride was not added during bacterial inoculation step and 10-mm-thick AAC specimens were used. The immobilized MOB could remove methane at low concentration (~1000 ppmv) in a biofilter setup for 127 days at average removal efficiency (RE) of 28.7 %. Unlike a plug flow reactor, increasing the total volume of the filter by adding a biofilter in series did not result in higher total RE. MOB also exhibited a higher abundance at the bottom of the filter, in proximity with the methane gas inlet where a high methane concentration was found. Overall, an efficient methane biofilter performance could be obtained using AAC as the carrier material.

  3. Effect Carrier Agent Formulation in Drying Rate and Antioxidant Activity of Roselle Extract

    Directory of Open Access Journals (Sweden)

    Utari Febiani Dwi

    2018-01-01

    Full Text Available Roselle (Hibiscus sabdarifa L contains anthocyanins as the natural colorant and antioxidant. Drying the roselle extract was aims to produce the dry product that easy consumption as antioxidant. The carrier agent was added in roselle extract to improve the drying rate and maintain the nutritional value. This research studied the effect of carrier agent in drying rate and antioxidant activity. The method consists of two step involving roselle extraction using ultrasonic and the drying process. The roselle extraction by ultrasonic use the water as the solvent. The carrier agent (0%,5%,10% of maltodextrin was added in roselle extract. The mixture was then dried in tray dryer dehumidification using zeolite in drying temperature 50,60, and 70⁰C. As the response, the moisture content was observed by gravimetry every 15 minutes for 150 minutes. The result showed that Page model was fitted to determine the constant of drying rate. Higher concentration of carrier agent enhanced the moisture evaporation process. Based on the DPPH analysis, the degradation of antioxidant activity in temperature 70⁰C was 2.14 times higher than in temperature 50⁰C. As the conclusion, addition of maltodextrin can speed up the drying process and retain the antioxidant activity of.

  4. Synthesis of studies for ADS development

    International Nuclear Information System (INIS)

    Alamo, A.; Balbaud, F.; Beauvais, P.Y.; Courouau, J.L.; Debu, P.; Granget, G.; Latge, Ch.; Leray, S.; Mellier, F.; Pillon, S.; Richard, P.; Rimbault, G.; Salvatores, M.; Terlain, A.; Varaine, F.; Warin, D.; Brissot, R.; Doubre, H.; Flocard, H.; Kirchner, Th.; Mueller, A.; Steckmeyer, J.C.; Carluec, B.; Giraud, B.

    2005-01-01

    One goal of the December 1991 law is the exploration of the separation-transmutation means to reduce the impact of minor actinides in high-level radioactive wastes. By 2040, the fourth generation of fast neutron reactors would be capable to entirely recycle their wastes and those previously generated. In the case of a delayed implementation of this type of reactor, a 'double-stratum' scenario foresees the recycling of plutonium in PWR-Mox reactors and the recycling of minor actinides in reactors dedicated to transmutation. The accelerator-driven systems (ADS) are well-adapted for this task and the share of such systems in the nuclear park would represent only 5 to 10% of the overall power. In this note, the technical data of this scenario and the physics of ADS are recalled first. Then, the status of researches in progress, the technological advances and the researches to carry on in the different domains are presented: nuclear data, in particular those linked with spallation phenomena; power accelerators, in particular the works in progress to warrant their reliability and maneuverability; spallation targets, in particular the Megapie experiment with a liquid lead-bismuth target submitted to a powerful proton beam and researches on the related materials technology; the fuels specific to transmutation with no uranium (replaced by an inert support); the project of subcritical facilities studied in the framework of the PDS-XADS European project (first design schemes of gas or lead-bismuth cooled subcritical reactors); the subcritical reactor physics, in particular the joint CNRS-CEA Muse program which has led to the construction of the very first ADS for the testing of measurement and reactivity control methods. Thanks to these studies carried out since about a decade, the design and part of the qualification of the elementary parts (accelerator, target, core) of ADS have made lot of progress. The PDS-XADS studies did not show any incompatibility of ADS principle for

  5. Effect of "no added salt diet" on blood pressure control and 24 hour urinary sodium excretion in mild to moderate hypertension

    Directory of Open Access Journals (Sweden)

    Rahimi Rahim

    2007-11-01

    Full Text Available Abstract Background The incidence of Hypertension as a major cardiovascular threat is increasing. The best known diet for hypertensives is 'no added salt diet'. In this study we evaluated the effect of 'no added salt diet' on a hypertensive population with high dietary sodium intake by measuring 24 hour urinary sodium excretion. Methods In this single center randomized study 80 patients (60 cases and 20 controls not on any drug therapy for hypertension with mild to moderate hypertension were enrolled. 24 hour holter monitoring of BP and 24 hour urinary sodium excretion were measured before and after 6 weeks of 'no added salt diet'. Results There was no statistically significant difference between age, weight, sex, Hyperlipidemia, family history of hypertension, mean systolic and diastolic BP during the day and at night and mean urinary sodium excretion in 24 hour urine of case and control groups. Seventy eight percent of all patients had moderate to high salt intake. After 6 week of 'no added salt diet' systolic and diastolic BP significantly decreased during the day (mean decrease: 12.1/6.8 mmhg and at night (mean decrease: 11.1/5.9 mmhg which is statistically significant in comparison to control group (P 0.001 and 0.01. Urinary sodium excretion of 24 hour urine decreased by 37.1 meq/d ± 39,67 mg/dl in case group which is statistically significant in comparison to control group (p: 0.001. Only 36% of the patients, after no added salt diet, reached the pretreatment goal of 24 hour urinary sodium excretion of below 100 meq/dl (P:0.001. Conclusion Despite modest effect on dietary sodium restriction, no added salt diet significantly decreased systolic and diastolic BP and so it should be advised to every hypertensive patient. Trial Registration Clinicaltrial.govnumber NCT00491881

  6. Where are the radioactive wastes in France? Brochure no 4; Ou sont les dechets radioactifs en France? Brochure no 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 4 concerns the Auvergne and Rhone-Alpes regions. (J.S.)

  7. Method of melting decontamination of radioactive contaminated metals

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Miura, Noboru; Tsuchiya, Hiroyuki.

    1984-01-01

    Purpose: To improve the transfer efficiency of radioactive materials into slags. Method: Contaminated metals are melt with adding slagging agent in order to transfer the radioactive materials into the slag, where the slagging agent holds less free energy than that of metal oxides contaminated with radioactive materials in order to promote the transfer of the contaminated materials into the slag layer. This effect can also be attained on metals or alloys other than iron contaminated with radioactive materials. In the case of alloy, the slagging agent is to containing such metal oxide that free energy is less than that of the oxide of metal being the main ingredient element of the alloy. The decontamination effect can further be improved by containing halogenide such as calcium fluoride together with the metal oxide into the slagging agent. (Ikeda, J.)

  8. Asymptotically AdS spacetimes with a timelike Kasner singularity

    Energy Technology Data Exchange (ETDEWEB)

    Ren, Jie [Racah Institute of Physics, The Hebrew University of Jerusalem, Jerusalem 91904 (Israel)

    2016-07-21

    Exact solutions to Einstein’s equations for holographic models are presented and studied. The IR geometry has a timelike cousin of the Kasner singularity, which is the less generic case of the BKL (Belinski-Khalatnikov-Lifshitz) singularity, and the UV is asymptotically AdS. This solution describes a holographic RG flow between them. The solution’s appearance is an interpolation between the planar AdS black hole and the AdS soliton. The causality constraint is always satisfied. The entanglement entropy and Wilson loops are discussed. The boundary condition for the current-current correlation function and the Laplacian in the IR is examined. There is no infalling wave in the IR, but instead, there is a normalizable solution in the IR. In a special case, a hyperscaling-violating geometry is obtained after a dimensional reduction.

  9. Factories Act 1961, Ionizing Radiations (Unsealed Radioactive Substances) Regulations 1968, Certificate of Approval No.1 (General)

    International Nuclear Information System (INIS)

    1969-01-01

    Under the Ionising Radiations (Unsealed Radioactive Substances) Regulations No. 780 of 1968, the Chief Inspector of Factories has wide powers to ensure the protection of workers. By this Certificate he approved, for the purpose of measuring radiation doses, any radiation dosemeter, based on the phenomenon of radiation-induced thermoluminescence, supplied by an approved laboratory. (NEA) [fr

  10. Primary fibroblasts from CSP? mutation carriers recapitulate hallmarks of the adult onset neuronal ceroid lipofuscinosis

    OpenAIRE

    Benitez, Bruno A.; Sands, Mark S.

    2017-01-01

    Mutations in the co- chaperone protein, CSP?, cause an autosomal dominant, adult-neuronal ceroid lipofuscinosis (AD-ANCL). The current understanding of CSP? function exclusively at the synapse fails to explain the autophagy-lysosome pathway (ALP) dysfunction in cells from AD-ANCL patients. Here, we demonstrate unexpectedly that primary dermal fibroblasts from pre-symptomatic mutation carriers recapitulate in vitro features found in the brains of AD-ANCL patients including auto-fluorescent sto...

  11. 76 FR 5424 - Motor Carrier Safety Advisory Committee; Request for Nominations

    Science.gov (United States)

    2011-01-31

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee; Request for Nominations AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Request for Nominations to the Motor Carrier Safety Advisory...

  12. Radioactive wastes processing and disposing container

    International Nuclear Information System (INIS)

    Wada, Jiro; Kato, Hiroaki.

    1987-01-01

    Purpose: To obtain a processing and disposing container at low level radioactive wastes, excellent in corrosion and water resistance, as well as impact shock resistance for the retrieval storage over a long period of time. Constitution: The container is constituted with sands and pebbles as aggregates and glass fiber-added unsaturated polyester resins as binders. The container may entirely be formed with such material or only the entire inner surface may be formed with the material as liners. A container having excellent resistance to water, chemicals, freezing or melting, whether impact shock, etc. can be obtained, thereby enabling retrieval storage for radioactive wastes at the optimum low level. (Takahashi, M.)

  13. Experiences of a High-Risk Population with Prenatal Hemoglobinopathy Carrier Screening in a Primary Care Setting: a Qualitative Study

    NARCIS (Netherlands)

    Holtkamp, Kim C. A.; Lakeman, Phillis; Hader, Hind; Jans, Suze M. J. P.; Hoenderdos, Maria; Playfair, Henna A. M.; Cornel, Martina C.; Peters, Marjolein; Henneman, Lidewij

    2017-01-01

    Carrier screening for hemoglobinopathies (HbPs; sickle cell disease and thalassemia) aims to facilitate autonomous reproductive decision-making. In the absence of a Dutch national HbP carrier screening program, some primary care midwives offer screening on an ad hoc basis. This qualitative

  14. Radioactive waste generated from JAERI partitioning-transmutation cycle system

    Energy Technology Data Exchange (ETDEWEB)

    Shinichi, Nakayama; Yasuji, Morita; Kenji, Nishihara [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2001-07-01

    Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI processes. Long-lived radionuclides such as {sup 14}C and {sup 59}Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (author)

  15. Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

    International Nuclear Information System (INIS)

    Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

    2003-01-01

    Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

  16. Characterisation of the appearance of radioactive metabolites in monkey and human plasma from the 5-HT1A receptor radioligand, [carbonyl-11C]WAY-100635 - explanation of high signal contrast in PET and an aid to biomathematical modelling

    International Nuclear Information System (INIS)

    Osman, Safiye; Lundkvist, Camilla; Pike, Victor W.; Halldin, Christer; McCarron, Julie A.; Swahn, Carl-Gunnar; Farde, Lars; Ginovart, Nathalie; Luthra, Sajinder K.; Gunn, Roger N.; Bench, Christopher J.; Sargent, Peter A.; Grasby, Paul M.

    1998-01-01

    N-(2-(4-(2-Methoxy-phenyl)-1-piperazin-1-yl)ethyl)-N-(2-pyridyl) cyclohexanecarboxamide (WAY-100635), labelled in its amido carbonyl group with 11 C (t 1/2 = 20.4 min), is a promising radioligand for the study of brain 5-HT 1A receptors with positron emission tomography (PET). Thus, in PET experiments in six cynomolgus monkeys and seven healthy male volunteers, [carbonyl- 11 C]WAY-100635 was taken up avidly by brain. Radioactivity was retained in regions rich in 5-HT 1A receptors, such as occipital cortex, temporal cortex and raphe nuclei, but cleared rapidly from cerebellum, a region almost devoid of 5-HT 1A receptors. [Carbonyl- 11 C]WAY-100635 provides about 3- and 10-fold higher signal contrast (receptor-specific to nonspecific binding) than [O-methyl- 11 C]WAY-100635 in receptor-rich areas of monkey and human brain, respectively. To elucidate the effect of label position on radioligand behaviour and to aid in the future biomathematical interpretation of the kinetics of regional cerebral radioactivity uptake in terms of receptor-binding parameters, HPLC was used to measure [carbonyl- 11 C]WAY-100635 and its radioactive metabolites in plasma at various times after intravenous injection. Radioactivity cleared rapidly from monkey and human plasma. Parent radioligand represented 19% of the radioactivity in monkey plasma at 47 min and 8% of the radioactivity in human plasma at 40 min. [Carbonyl- 11 C]desmethyl-WAY-100635 was below detectable limits in monkey plasma and at most a very minor radioactive metabolite in human plasma. [ 11 C]Cyclohexanecarboxylic acid was identified as a significant radioactive metabolite. In human plasma this maximally represented 21% of the radioactivity at 10 min after radioligand injection. All other major radioactive metabolites in monkey and human plasma were even more polar. No-carrier-added [carbonyl- 11 C]cyclohexanecarboxylic acid was prepared in the laboratory and after intravenous administration into cynomolgus monkey was

  17. Processing method for discharged radioactive laundry water waste

    International Nuclear Information System (INIS)

    Izumida, Tatsuo; Kitsukawa, Ryozo; Tsuchiya, Hiroyuki; Kiuchi, Yoshimasa; Hattori, Yasuo.

    1995-01-01

    In order to process discharged radioactive laundry water wastes safely and decrease radioactive wastes, bubbling of a surface active agent in a detergent which causes a problem upon its condensation is suppressed, so that the liquid condensate are continuously and easily dried into a powder. A nonionic surface active agent is used against the bubbling of the surface active agent. In addition, the bubbling in an the evaporation can is reduced, and the powderization is facilitated by adding an appropriate inorganic builder. (T.M.)

  18. Update: Tests confirm no radioactivity release to environment from IAEA Seibersdorf Lab after 3 August incident

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Independent analysis has confirmed that there was no release of radioactive material to the environment following an incident at the IAEA's Seibersdorf Laboratory on 3 August. The test results were provided by the Austrian Research Centers (ARC), from analysis of soil, plant and water samples collected from outside the IAEA's Laboratories in Seibersdorf, where the incident occurred. The radiation protection experts of the ARC confirmed the initial findings from the laboratory's automatic monitoring system which indicated that there had been no release of radioactivity to the environment. Since the incident, constant air monitoring near the laboratory, undertaken by the IAEA, has also provided no evidence of any radioactive contamination. A tiny amount of plutonium contained in an acid solution spilled from five small glass vials when one of them burst after a build up of pressure in it. The vials were stored in a secure steel safe. In total there was less than one gram of plutonium in the five vials. The material was in the laboratory for scientific reference purposes and virtually all of the contamination was confined within the steel walled safe. As previously reported, the automatic alarm was triggered when highly sensitive detectors of the continuous air monitoring system identified minor amounts of radioactive aerosols in the storage room containing the safe. The air contamination was trapped entirely in the filters of the ventilation system. No one was working in the laboratory at the time of the accident, which occurred at 02:31. The IAEA emergency response team promptly secured and sealed off the windowless storage room. An investigation into the circumstances and causes of the incident is still underway. In the meantime the first stage of the clean-up of the storage room was successfully completed on Friday, 22 August. According to the IAEA's nuclear regulator's assessment of the incident, the lab's safety systems worked properly and

  19. Update: Tests confirm no radioactivity release to environment from IAEA Seibersdorf Lab after 3 August incident

    International Nuclear Information System (INIS)

    2008-01-01

    Full text: Independent analysis has confirmed that there was no release of radioactive material to the environment following an incident at the IAEA's Seibersdorf Laboratory on 3 August. The test results were provided by the Austrian Research Centers (ARC), from analysis of soil, plant and water samples collected from outside the IAEA's Laboratories in Seibersdorf, where the incident occurred. The radiation protection experts of the ARC confirmed the initial findings from the laboratory's automatic monitoring system which indicated that there had been no release of radioactivity to the environment. Since the incident, constant air monitoring near the laboratory, undertaken by the IAEA, has also provided no evidence of any radioactive contamination. A tiny amount of plutonium contained in an acid solution spilled from five small glass vials when one of them burst after a build up of pressure in it. The vials were stored in a secure steel safe. In total there was less than one gram of plutonium in the five vials. The material was in the laboratory for scientific reference purposes and virtually all of the contamination was confined within the steel walled safe. As previously reported, the automatic alarm was triggered when highly sensitive detectors of the continuous air monitoring system identified minor amounts of radioactive aerosols in the storage room containing the safe. The air contamination was trapped entirely in the filters of the ventilation system. No one was working in the laboratory at the time of the accident, which occurred at 02:31. The IAEA emergency response team promptly secured and sealed off the windowless storage room. An investigation into the circumstances and causes of the incident is still underway. In the meantime the first stage of the clean-up of the storage room was successfully completed on Friday, 22 August. According to the IAEA's nuclear regulator's assessment of the incident, the lab's safety systems worked properly and

  20. Radioactive particles after different nuclear events in the USSR (overview and modern data)

    Energy Technology Data Exchange (ETDEWEB)

    Gordeev, S.K.; Stukin, E.D.; Kvasnikova, E.V. [Institute of Global Climate and Ecology, Moscow (Russian Federation)

    2004-07-01

    Institute of Global Climate and Ecology participated in all stages of investigations concerning spreading of the radioactive particles formed after nuclear explosions. Since 1963 the radioactive particles from the surface nuclear explosions on the Semipalatinsk Test Site were investigated. Since 1964 the study of the environmental contamination from the underground nuclear explosions (including the cratering nuclear explosions) was carried out. Simultaneously the secondary radioactive aerosols released into the atmosphere from ventilated underground explosions were investigated. Since 1986 the forming and spreading of the radioactive aerosols from Chernobyl accident was studied. An overview of retrospective data will be presented. For example, the fragmentation radionuclides {sup 90}Sr, {sup 137}Cs and {sup 155}Eu, radionuclides induced by neutrons {sup 60}Co, {sup 152}Eu, {sup 154}Eu and transuranium radionuclides {sup 238}Pu, {sup 239+240}Pu and {sup 241}Am were estimated in 15 particles of August, 29, 1949 explosion using the semiconductor spectrometry and radiochemical analysis. Data collection include the samples taken on local traces of ground and underground excavation nuclear explosions, this information will be added by the modern data from soil samples near '1004' explosion (lake Chagan), October 2003. The results of comparison of radionuclide fractionation in the radioactive particles in slag from cratering nuclear explosions and in melt samples will be presented. Main results obtained under the IAEA Research Contract no. 11468. (author)

  1. Studies to compare radioactivity of bone cements and their ingredient X-ray contrast media

    International Nuclear Information System (INIS)

    Hopf, C.; Gloebel, B.; Hopf, T.; Universitaet des Saarlandes, Homburg/Saar; Universitaet des Saarlandes, Homburg/Saar

    1990-01-01

    Various PMMA bone cements/containing zirconium oxide (ZrO 2 ) as an X-ray contrast medium and zirconium oxides of several manufacturers were tested for their radioactivity by means of a gamma spectrometer. All the bone cements tested (Implast, Palacos R, and Sulfix-6) showed a certain degree of radioactivity. The radiation source in the bone cement is the added zirconium oxide, which is polluted by radioactive elements. The examination of various zirconium oxides showed some high radioactive emissions. (orig./GDG) [de

  2. NoSQL databáze pro data senzorů s podporou časových řad

    OpenAIRE

    Vizina, Petr

    2017-01-01

    Tato diplomová práce se zabývá tématem NoSQL databází, jež lze využít pro efektivní ukládání senzorových dat s charakterem časových řad. Cílem je navrhnout a implementovat vlastní řešení databáze určené pro ukládání dat časových řad s využitím právě principu NoSQL. This thesis deals with NoSQL databases, which can be used for effective storage of sensors data with character of time series. The aim is to design and implement own solution for database designed to store time series data, with...

  3. Final storage of radioactive waste in Germany - a 'no-development report'?

    International Nuclear Information System (INIS)

    Roesel, H.

    1994-01-01

    The Federal Government is obliged by law to install facilities for safekeeping and ultimate storage of radioactive waste, and it fulfills this duty purposefully, assigning top priority to safety. This is demonstrated by the large number of court cases in which the Federal Government firmly seeks its right vis-a-vis a State Government bent on opting out of nuclear power. Against the backdrop of the failed energy consensus talks there is no need to discontinue the speedy exploration of the Gorleben salt dome to determine its suitability as a repository, about which there can be no doubt. Comment: The Lueneburg Court of Administration recently has set aside the decision of the Ministry of the Environment of the Land Lower Saxony, to stop the exploration at the Gorleben site. The public hearing about the Konrad site has been successfully terminated after a period of 75 days. The Magdeburg Court of Administration confirmed the lawfulness of the operating permit issued for the Morsleben site, which now is allowed to receive radwaste, also from installations in the western part of Germany. (orig./HP) [de

  4. Scandium doping brings speed improvement in Sb2Te alloy for phase change random access memory application.

    Science.gov (United States)

    Chen, Xin; Zheng, Yonghui; Zhu, Min; Ren, Kun; Wang, Yong; Li, Tao; Liu, Guangyu; Guo, Tianqi; Wu, Lei; Liu, Xianqiang; Cheng, Yan; Song, Zhitang

    2018-05-01

    Phase change random access memory (PCRAM) has gained much attention as a candidate for nonvolatile memory application. To develop PCRAM materials with better properties, especially to draw closer to dynamic random access memory (DRAM), the key challenge is to research new high-speed phase change materials. Here, Scandium (Sc) has been found it is helpful to get high-speed and good stability after doping in Sb 2 Te alloy. Sc 0.1 Sb 2 Te based PCRAM cell can achieve reversible switching by applying even 6 ns voltage pulse experimentally. And, Sc doping not only promotes amorphous stability but also improves the endurance ability comparing with pure Sb 2 Te alloy. Moreover, according to DFT calculations, strong Sc-Te bonds lead to the rigidity of Sc centered octahedrons, which may act as crystallization precursors in recrystallization process to boost the set speed.

  5. Where are the radioactive wastes in France? Brochure no 1; Ou sont les dechets radioactifs en France? Brochure no 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 1 concerns the Ile-de-France region (Paris region). (J.S.)

  6. Where are the radioactive wastes in France? Brochure no 3; Ou sont les dechets radioactifs en France? Brochure no 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 3 concerns the Nord-Pas-de-Calais, Picardie, Champagne-Ardenne, Bourgogne, Alsace, Lorraine, Franche-Comte regions. (J.S.)

  7. Where are the radioactive wastes in France? Brochure no 2; Ou sont les dechets radioactifs en France? Brochure no 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 2 concerns the Bretagne (Brittany), Pays de la Loire, Haute-Normandie, Basse-Normandie and Centre regions. (J.S.)

  8. Where are the radioactive wastes in France? Brochure no 6; Ou sont les dechets radioactifs en France? Brochure no 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 6 concerns the Aquitaine, Limousin, Midi-Pyrenees and Poitou-Charentes regions. (J.S.)

  9. Brain uptake of a non-radioactive pseudo-carrier and its effect on the biodistribution of [18 F]AV-133 in mouse brain

    International Nuclear Information System (INIS)

    Wu, Xianying; Zhou, Xue; Zhang, Shuxian; Zhang, Yan; Deng, Aifang; Han, Jie; Zhu, Lin; Kung, Hank F.; Qiao, Jinping

    2015-01-01

    Introduction: 9-[ 18 F]Fluoropropyl-(+)-dihydrotetrabenazine ([ 18 F]AV-133) is a new PET imaging agent targeting vesicular monoamine transporter type II (VMAT2). To shorten the preparation of [ 18 F]AV-133 and to make it more widely available, a simple and rapid purification method using solid-phase extraction (SPE) instead of high-pressure liquid chromatography (HPLC) was developed. The SPE method produced doses containing the non-radioactive pseudo-carrier 9-hydroxypropyl-(+)-dihydrotetrabenazine (AV-149). The objectives of this study were to evaluate the brain uptake of AV-149 by UPLC-MS/MS and its effect on the biodistribution of [ 18 F]AV-133 in the brains of mice. Methods: The mice were injected with a bolus including [ 18 F]AV-133 and different doses of AV-149. Brain tissue and blood samples were harvested. The effect of different amounts of AV-149 on [ 18 F]AV-133 was evaluated by quantifying the brain distribution of radiolabelled tracer [ 18 F]AV-133. The concentrations of AV-149 in the brain and plasma were analyzed using a UPLC-MS/MS method. Results: The concentrations of AV-149 in the brain and plasma exhibited a good linear relationship with the doses. The receptor occupancy curve was fit, and the calculated ED 50 value was 8.165 mg/kg. The brain biodistribution and regional selectivity of [ 18 F]AV-133 had no obvious differences at AV-149 doses lower than 0.1 mg/kg. With increasing doses of AV-149, the brain biodistribution of [ 18 F]AV-133 changed significantly. Conclusion: The results are important to further support that the improved radiolabelling procedure of [ 18 F]AV-133 using an SPE method may be suitable for routine clinical application

  10. Denials and Delays of Radioactive Material Shipments

    International Nuclear Information System (INIS)

    El-Shinawy, R.M.K.

    2011-01-01

    delays of shipments of radioactive materials forms an important issue today. Radioactive materials need to be transported using all modes of transport for use in different applications such as public health, industry, research and production of nuclear power. The transport of radioactive materials is governed by national and international regulations, which are based on the International Atomic Energy Agency (IAEA) regulations for safe transport of radioactive materials (TS-R-1). These regulations ensure high standards of safety. Recently there were increasing numbers of instances of denials and delays of shipments of radioactive materials even when complying with the regulations. The denials and delays can result in difficulties to patients and others who rely on products sterilized by radiation. Therefore there is an urgent need for a universally accepted approach to solve this problem. In response, the IAEA has formed an International Steering Committee (ISC) on denials and delays of radioactive materials. Also, it designate the National Focal Points (NFP) representative to help the ISC members and the IAEA by informing about denial operations and how they can help. The Steering Committee developed and adopted an action plan which includes the action to be taken. This plan is based on: Awareness, Training, Communication, Lobbying for marketing, Economic and Harmonization among member states. It is important to work within the mandate of the ISC and in the line of action plan on denials and delays. It identified the following network members such as: National Focal Points, Regional Coordinators, National Committee, National Representative for different modes of transport and similar bodies, Carriers, Producers and Suppliers, Different civil societies, NGO's, Ministry of transport and others.

  11. Regulations for the Safe Transport of Radioactive Material, 2009 ed. Safety Requirements

    International Nuclear Information System (INIS)

    2009-01-01

    This publication establishes the regulations that are applied to the transport of radioactive material by all modes of transport on land, water or in the air, including transport that is incidental to the use of the radioactive material. The objective and scope of the regulations are described in detail as well as the range of their application. The publication provides requirements useful to governments, regulators, operators of nuclear and radiation facilities, carriers, users of radiation sources and cargo handling personnel. Contents: 1. Introduction; 2. Definitions; 3. General provisions; 4. Activity limits and classification; 5. Requirements and controls for transport; 6. Requirements for radioactive materials and for packagings and packages; 7. Test procedures; 8. Approval and administrative requirements; Annex I: Summary of approval and prior notification requirements; Annex II: Conversion factors and prefixes.

  12. Bibliography in environmental radioactivity in foods. No. 34

    International Nuclear Information System (INIS)

    Fischer, E.; Kalus, W.; Mueller, H.; Schelenz, R.

    1981-10-01

    This is the most recent bibliographic volume; it lists 226 citations, most of them of the last two years. The citations are grouped according to the main subjects of general aspects, environmental radioactivity, radioecology, and radionuclides in foodstuffs. The publication contains a conference index, an author index, a report number index, a subject index, a corporation index, and a journal index. (MG) [de

  13. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Tomita, Toshihide; Minami, Yuji; Matsuura, Hiroyuki

    1984-01-01

    Purpose: To enable complete curing even when radioactive wastes contain those materials hindering the curing reaction, for example, copper hydroxide. Method: After admixing an alkaline substance to radioactive concentrated liquid wastes containing copper hydroxide or other amphoteric substances, they are dried, powderized and then cured with thermosetting resins. The thermosetting resins usable herein include, for example, those prepared by mixing an unsaturated polyester with a monomer such as styrene. When a polymerization initiator such as methyl ethyl ketone peroxide and a polymerization promotor are added to the mixture, it takes places curing reaction at normal temperature. Suitable alkaline substances usable herein are those which are insoluble to the liquid wastes and do not change the chemical form under heating and drying. (Yoshihara, H.)

  14. Studies on methods of measurement of radioactivities of 36Cl and 3H in dual labelled samples

    International Nuclear Information System (INIS)

    Hirano, Shusuke; Asou, Hiroaki; Oishi, Katsuhiko; Hirano, Kiyoshi; Sato, Isamu

    1985-01-01

    In order to clarify how chloride molecules are transported into nervous tissue cells, we simultaneously used [ 36 Cl] -NaCl and [ 3 H] -inulin, and added AgNO 3 to the extract from the nervous tissue, obtaining 36 Cl-samples from the AgCl-precipitate and 3 H-samples from the supernatant. As for radioactivity of 36 Cl or 3 H in the dual-labelled samples, the recovery rates by our separation method were about 100%. Using cultured astrocytoma cells, 36 Cl-uptake into the cells, which was calculated by inulin assumption, was investigated. Intracellular 36 Cl-radioactivity changed vis-a-vis with that in the extracellular space. The volume of intracellular water, which was calculated by 3 H-inulin assumption, remained unchanged, even though a few variations in 36 Cl-radioactivity in cells were determined by both our separation method and spill-over method. (author)

  15. Method of solidifying liquid radioactive wastes

    International Nuclear Information System (INIS)

    Pekar, A.; Petrovic, J.; Timulak, J.

    1987-01-01

    Liquid radioactive waste containing boric acid salts is mixed with zeolite tuff and neutralized by lime. Power plant fly ash containing single-component or mixed Portland cement is then added to the mixture. Prior to packaging, anion-active bitumen emulsion or an aqueous emulsion of fatty acid salts and of free fatty acids insoluble in water can be added. Examples are given listing accurate proportions of the individual components. The advantage of the said solidification method is the use of easily available raw materials and improved values of extractability of the resulting product radionuclides. (E.S.)

  16. Organisation of the disposal of radioactive sources from Scottish hospitals

    International Nuclear Information System (INIS)

    Corrigall, R S; Martin, C J; Watson, I

    2004-01-01

    An amnesty for disposal of sealed radioactive sources from Scottish hospitals has been funded by the Scottish Executive to address problems arising from accumulation of sources. The contract was awarded to a company involved in radioactive source recycling. Coordination of uplifts from several hospitals allowed considerable financial savings to be made, so source amnesties could offer monetary advantages to Health and Education Departments elsewhere in the UK, as well as alleviating the problem from security and storage of sources that are no longer required. The sources originated in 14 hospitals, but were uplifted from five pick-up points. There were a total of 246 sources with 167 of these being caesium-137. The total activity was 16.2 TBq with one large 16.1 TBq blood irradiator source and the activities of all the other sources adding up to 167 GBq. This paper describes organisation of the collection. Options for achieving compliance with the Radioactive Substances Act 1993 are discussed, although in the event, special authorisations were obtained for each hospital. Arrangements for transport of the sources and source security were drawn up including emergency procedures for dealing with foreseeable incidents. The police provided secure overnight storage for the loaded truck and assistance in directing and monitoring progress of the load

  17. Radioactive cesium-134 and cesium-137 measured by ChIbaraki-Kizuna No.1 in the Paleo-Kantoh great depth submarine basin

    International Nuclear Information System (INIS)

    Kimura, Kazuya; Nirei, Hisashi; Yoshida, Takeshi

    2012-01-01

    The 2011 Earthquake off the Pacific Coast of Tohoku caused serious geological disasters, on March 11th. Especially radioactive pollution by the nuclear accident at the Fukushima No. 1 nuclear power plant has the medical environmental problem. We have been researching the actual condition of that in Higashi-Kanto area by use of RT-30 (made by GEORADIS). In the result, it becomes clear that almost radiogen which diffused at a Higashi-Kantou is cesium-134 and cesium-137, and radioactive pollution is also a kind of geo-pollution. In fact, radioactive ingredients move according to mass transfer and deposition rule. For example, we verified that radiogen move and deposit on a water catchment area at a side road of Higashi-kanto Expressway in the northern Chiba prefecture. So, we must make out a unit of geological layer and characteristic features of radioactive materials when investigate and decontamination. If we do that without knowledge of geological unit and radiogen's attribution, radioactive pollution would become diffuse. Just for the record, this was written in the Katori-Narita-Itako International Declaration (IUGS-GEM). (author)

  18. Emergency response planning and preparedness for transport accidents involving radioactive material

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of this Guide is to provide assistance to public authorities and others (including consignors and carriers of radioactive materials) who are responsible for ensuring safety in establishing and developing emergency response arrangements for responding effectively to transport accidents involving radioactive materials. This Guide is concerned mainly with the preparation of emergency response plans. It provides information which will assist those countries whose involvement with radioactive materials is just beginning and those which have already developed their industries involving radioactive materials and attendant emergency plans, but may need to review and improve these plans. The need for emergency response plans and the ways in which they are implemented vary from country to country. In each country, the responsible authorities must decide how best to apply this Guide, taking into account the actual shipments and associated hazards. In this Guide the emergency response planning and response philosophy are outlined, including identification of emergency response organizations and emergency services that would be required during a transport accident. General consequences which could prevail during an accident are described taking into account the IAEA Regulations for the Safe Transport of Radioactive Material. 43 refs, figs and tabs

  19. Proposal of threshold levels for the definition of non-radioactive wastes

    International Nuclear Information System (INIS)

    Yoshida, Yoshikazu

    1979-01-01

    With increasing amounts of radioactive wastes along with the advances of nuclear power generation and radioactive material utilizations, the needs for management cost reduction and resource saving have arisen. Under the situation, the threshold levels for the definition of non-radioactive solid wastes are required. The problem has been studied by an ad hoc committee in Nuclear Safety Research Association, by the request of the Science and Technology Agency. The matters described are the procedures of deriving the threshold levels, the feasibility studies of the management of waste threshold-level with several enterprises, and future subjects of study. The threshold levels are grouped in two, i.e. the unconditional level and the conditional level. According to the unconditional threshold level, solid wastes are separated definitely into radioactive and non-radioactive ones. According to the conditional threshold level, under certain conditions, some radioactive solid wastes according to the unconditional level are regarded as non-radioactive ones. (J.P.N.)

  20. Radioactivity and wildlife

    International Nuclear Information System (INIS)

    Kennedy, V.H.; Horrill, A.D.; Livens, F.R.

    1990-01-01

    The official assumption is that if levels of radioactivity are safe for humans, they are safe for wildlife too. NCC sponsored a research project by the Institute of Terrestrial Ecology to find out what was known in this field. It appears that the assumption is justified to a certain extent in that mammals are identified as the organisms most vulnerable to the damaging effects of radioactivity. Other general principles are put forward: where there are radioactive discharges to the marine environment, coastal muds and saltmarshes can be particularly contaminated; upland habitats, with low nutrient status and subject to high rainfall, are likely to accumulate radioactivity from atmospheric discharges (e.g. Chernobyl, the wildlife effects of which are reported here). The document concludes that no deleterious effects of radioactivity on wild plants and animals have been detected in the UK, but acknowledges that there are still many gaps in our knowledge of the behaviour of radioisotopes in the natural environment. (UK)

  1. Chapter No.6. Radioactive waste (RAW)

    International Nuclear Information System (INIS)

    2002-01-01

    during the commissioning of this nuclear facility after UJD issued permission in 1999. Operational permission was issued by UJD after assessment of repository commissioning report in September 2001. At the end of 2001 totally 122 containers were disposed of. It is assumed that during design operational lifetime the installed NPPs will produce 2500 t of spent nuclear fuel and 3700 t of radwaste unacceptable for Mochovce repository (including radwaste generated at NPP A1) and their deep geological disposal will be necessary. Development of deep geological disposal facility in Slovakia started in 1996. On the basis of preliminary evaluation of existing geological data 15 sites potentially appropriate for underground repository were identified. Further investigation has led to reduction of this number to 4 sites in two possible host rocks which have been proposed for more detailed research. During 2001 approximately 365,5 t of solid radwaste and 474 m3 of liquid radwaste was shipped to the individual radwaste treatment technologies. 115 filled FRC containers e.g. 356,5 m3 of solid and solidified radwaste were shipped to the repository. The assessment activities were focused on reviewing of the safety documentation of activities, which were described before, on approving of technical specifications for operation safety and on an approving of quality assurance programmes. No event either at the facilities for radioactive was or during RAW transport that might have resulted in some incident or accident occurred during 2001. The inspection activity of UJD at BSC RAW was oriented on composition and inventory declaration and on the improvement of package quality from the integrity point of view. The inspection activity at RU RAW was mainly focused on commissioning process. The minimisation of RAW generation and the record keeping for the whole radioactive waste management system were the main goals of inspection activities at all nuclear installations

  2. Effective dose evaluation of NORM-added consumer products using Monte Carlo simulations and the ICRP computational human phantoms.

    Science.gov (United States)

    Lee, Hyun Cheol; Yoo, Do Hyeon; Testa, Mauro; Shin, Wook-Geun; Choi, Hyun Joon; Ha, Wi-Ho; Yoo, Jaeryong; Yoon, Seokwon; Min, Chul Hee

    2016-04-01

    The aim of this study is to evaluate the potential hazard of naturally occurring radioactive material (NORM) added consumer products. Using the Monte Carlo method, the radioactive products were simulated with ICRP reference phantom and the organ doses were calculated with the usage scenario. Finally, the annual effective doses were evaluated as lower than the public dose limit of 1mSv y(-1) for 44 products. It was demonstrated that NORM-added consumer products could be quantitatively assessed for the safety regulation. Copyright © 2016 Elsevier Ltd. All rights reserved.

  3. Methodology study for fixation of radioactive iodine in polymeric substrate for brachytherapy sources

    International Nuclear Information System (INIS)

    Rodrigues, Bruna T.; Rostelato, Maria Elisa C.M.; Souza, Carla D.; Tiezzi, Rodrigo; Souza, Daiane B. de; Benega, Marcos A.G.; Souza, Anderson S. de; Peleias Junior, Fernando S.; Zeituni, Calos A.; Fernandes, Vagner; Melo, Emerson Ronaldo de; Camargo, Anderson Rogerio de

    2015-01-01

    Cancer is now the second leading cause of death by disease in several countries, including Brazil. Prostate cancer is the most common among men. Brachytherapy is a modality of radiotherapy in which radioactive seeds are placed inside or in contact with the organ to be treated. The most widely used radioisotope in prostate brachytherapy is Iodine-125 which is presented fixated on a silver substrate that is subsequently placed inside a titanium capsule. A large dose of radiation is released only in the targeted tumor protecting healthy surrounding tissues. The technique requires the application of 80 - 120 seeds per patient. The implants of seeds have low impact and non-surgical procedures. Most patients can return to normal life within three days with little or no pain. This work proposes an alternative to the seeds that have already been developed, in order to reduce the cost by obtaining a better efficiency on fixing the radioactive iodine onto the epoxy resin. Methods have been developed to perform the fixation of Iodine-125 onto polymeric substrates. The parameters analyzed were the immersion time, type of static or dynamic reaction, concentration of the adsorption solution, the specific activity of the radioactive source, the need for carrier and chemical form of the radioactive Iodine. These experiments defined the most effective method to fixate the Iodine onto the polymeric material (epoxy resin), the Iodine activity in the polymeric substrate, the activity of the distribution of variation in a plot of polymeric cores and the efficiency of the epoxy resin to seal the seed. (author)

  4. A guide for controlling consumer products containing radioactive substances

    International Nuclear Information System (INIS)

    1985-01-01

    Consumer products are considered regardless of the purpose for which the radionuclide is added. For example, the purpose may be to make use of the ionising radiation emitted by the substance in the product itself (e.g. radioluminescent devices antistatic devices and ionisation chamber smoke detectors), or to make use of some other property of the material where the presence of radiation in the final product is merely adventitious (e.g. thorium gas mantles, ceramics with uranium glazes, and products containing radioactive tracers added to facilitate manufacturing and inspection processes). The Guide does not cover some products containing natural radioactive substances which have not been intentionally added, such as building materials. The Guide does not cover medicinal products and pharmaceuticals, nuclear powered cardiac pacemakers, or electronic equipment, such as television receivers, that emit X-rays. Unlike the 1970 Guide, this Guide does not consider those products, such as EXIT signs, containing gaseous tritium light sources, that would not be supplied directly to members of the public. The Guide is concerned mainly with the exposure arising from consumer products of those persons who are not subject to any regulatory controls for purposes of radiation protection in normal circumstances. Members of the public come under this heading, but not workers involved in the manufacture of consumer products. These workers will normally be subject to separate control. Radiological protection concepts and policy for the control of radioactive consumer products and licensing and post-licensing surveillance are developed

  5. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 3

    International Nuclear Information System (INIS)

    2003-08-01

    The purpose of this report is to compile and disseminate information about the status of and trends in radioactive waste management in Agency Member States in a timely manner. The report is suitable for radioactive waste managers and regulators, decision making organizations in both governmental and private sectors, and for Agency Departments, in both the regular and Technical Co-operation programmes. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. The plan is to have the document evolve to serve a broader audience using easy-to-understand graphical and tabular data. For this, the third report in the series, contributions on a variety of topics in radioactive waste management were solicited from persons and organizations external to the Agency. Throughout the report, submissions received from external contributors are denoted. The preparation of this annual report involves (a) a meeting with a team of consultants from a variety of government and industrial organizations to compile a first draft, (b) the optional issuance of special service contracts to polish and supplement the first draft, (c) review by Agency staff and external contributors to the report and (d) final review and approval by the Director of the Nuclear Energy and Waste Technology Division, Nuclear Energy Department, in the Agency

  6. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-08-01

    The purpose of this report is to compile and disseminate information about the status of and trends in radioactive waste management in Agency Member States in a timely manner. The report is suitable for radioactive waste managers and regulators, decision making organizations in both governmental and private sectors, and for Agency Departments, in both the regular and Technical Co-operation programmes. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. The plan is to have the document evolve to serve a broader audience using easy-to-understand graphical and tabular data. For this, the third report in the series, contributions on a variety of topics in radioactive waste management were solicited from persons and organizations external to the Agency. Throughout the report, submissions received from external contributors are denoted. The preparation of this annual report involves (a) a meeting with a team of consultants from a variety of government and industrial organizations to compile a first draft, (b) the optional issuance of special service contracts to polish and supplement the first draft, (c) review by Agency staff and external contributors to the report and (d) final review and approval by the Director of the Nuclear Energy and Waste Technology Division, Nuclear Energy Department, in the Agency.

  7. Import/export Service of Radioactive Material

    CERN Multimedia

    2004-01-01

    Please note that the Import/Export service of radioactive material (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Web site: http://cern.ch/service-rp-shipping/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch Radioactive Sources Service Please note that the radioactive sources service (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Moreover, the service being reduced transports between Swiss and French sites (and vice versa) will now be achieved by internal transport. Web site : http://cern.ch/service-radioactive-sources/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch

  8. New method for the radioactive determination of vitamin B12

    International Nuclear Information System (INIS)

    Lewin, Nathan; Fries, J.E.; Richards, C.S.

    1975-01-01

    A description is given of a method for the radioactive determination of vitamin B12 in a sample solution of serum in which a radioactive tracer of vitamin B12 and the vitamin B12 of the serum compete with respect to an intrinsic factor of limited linking capacity. The free radioactive vitamin B12 and the free vitamin B12 of the serum are separated from the intrinsic factor and from the radioactive vitamin B12 and from the serum vitamin B12 linked to this factor, before the radioactivity is measured against standard values. The method consists in separating the free radioactive vitamin B12 and the free serum vitamin B12 of the intrinsic factor and portions of radioactive and serum vitamin B12 linked to this factor, by adding an adequate quantity of bentonite to adsorb the free radioactive vitamin B12 and free serum vitamin B12 so that the intrinsic factor surface floating solution in association with the linked radioactive vitamin B12 and the linked serum vitamin B12 may be physically isolated from the solid bentonite that has adsorbed the free radioactive vitamin B12 and the free serum vitamin B12 [fr

  9. Channel-mediated and carrier-mediated uptake of K+ into cultured ovine oligodendrocytes

    Energy Technology Data Exchange (ETDEWEB)

    Hertz, L.; Soliven, B.; Hertz, E.; Szuchet, S.; Nelson, D.J. (Univ. of Saskatchewan, Saskatoon (Canada))

    1990-01-01

    Uptake of radioactive K+ by mature ovine oligodendrocytes (OLGs) maintained in primary culture was measured under steady-state conditions, i.e., in cells maintained in a normal tissue culture medium (5.4 mM K+), and in cells after depletion of intracellular K+ to less than 15% of its normal value by pre-incubation in K(+)-free medium. The latter value is dominated by an active, carrier-mediated uptake (although it may include some diffusional uptake), whereas the former, in addition to active uptake, also reflects passive K+ diffusion through ion selective channels and possible self-exchange between extracellular and intracellular K+, which may be carrier-mediated. The total uptake rate was 144 +/- 10 nmol/min/mg protein, and the uptake after K+ depletion was 60 +/- 2 nmol/min/mg protein, much lower rates than previously observed in astrocytes. The uptake into K(+)-depleted cells was inhibited by about 80% in the presence of ouabain (1 mM) and about 30% in the presence of furosemide (2 mM). Activators of protein kinase C (phorbol esters) and cAMP-dependent protein kinase (forskolin) have been shown to alter the myelinogenic metabolism as well as outward K+ current in cultured OLGs. The present study demonstrates that K+ homeostasis in OLGs is modulated through similar second messenger pathways. Active uptake was inhibited by about 60% in the presence of active phorbol esters (100 nM) but was not affected by forskolin (100 nM). Forskolin likewise had no effect on total uptake, whereas phorbol esters caused a much larger inhibition than expected from their effect on carrier-mediated uptake alone, suggesting that channel-mediated uptake was also reduced.

  10. Process for cleaning radioactively contaminated metal surfaces

    International Nuclear Information System (INIS)

    Mihram, R.G.; Snyder, G.A.

    1975-01-01

    A process is described for removing radioactive scale from a ferrous metal surface, including the steps of initially preconditioning the surface by contacting it with an oxidizing solution (such as an aqueous solution of an alkali metal permanganate or hydrogen peroxide), then, after removal or decomposition of the oxidizing solution, the metallic surface is contacted with a cleaning solution which is a mixture of a mineral acid and a complexing agent (such as sulfuric acid and oxalic acid), and which preferably contains a corrosion inhibitor. A final step in the process is the treatment of the spent cleaning solution containing radioactive waste materials in solution by adding a reagent selected from the group consisting of calcium hydroxide or potassium permanganate and an alkali metal hydroxide to thereby form easily recovered metallic compounds containing substantially all of the dissolved metals and radioactivity. (auth)

  11. Rapid Pneumatic Transport of Radioactive Samples - RaPToRS

    Science.gov (United States)

    Padalino, S.; Barrios, M.; Sangster, C.

    2005-10-01

    Some ICF neutron activation diagnostics require quick retrieval of the activated sample. Minimizing retrieval times is particularly important when the half-life of the activated material is on the order of the transport time or the degree of radioactivity is close to the background counting level. These restrictions exist in current experiments performed at the Laboratory for Laser Energetics, thus motivating the development of the RaPToRS system. The system has been designed to minimize transportation time while requiring no human intervention during transport or counting. These factors will be important if the system is to be used at the NIF where radiological hazards will be present during post activation. The sample carrier is pneumatically transported via a 4 inch ID PVC pipe to a remote location in excess of 100 meters from the activation site at a speed of approximately 7 m/s. It arrives at an end station where it is dismounted robotically from the carrier and removed from its hermetic package. The sample is then placed by the robot in a counting station. This system is currently being developed to measure back-to-back gamma rays produced by positron annihilation which were emitted by activated graphite. Funded in part by the U.S. DOE under sub contract with LLE at the University of Rochester.

  12. Duchenne muscular dystrophy carriers

    International Nuclear Information System (INIS)

    Matsumura, K.; Nakano, I.

    1989-01-01

    By means of magnetic resonance imaging (MRI), the proton spin-lattice relaxation times (T1 values) of the skeletal muscles were measured in Duchenne muscular dystrophy (DMD) carriers and normal controls. The bound water fraction (BWF) was calculated from the T1 values obtained, according to the fast proton diffusion model. In the DMD carriers, T1 values of the gluteus maximus and quadriceps femoris muscles were significantly higher, and BWFs of these muscles were significantly lower than in normal control. Degenerative muscular changes accompanied by interstitial edema were presumed responsible for this abnormality. No correlation was observed between the muscle T1 and serum creatine kinase values. The present study showed that MRI could be a useful method for studying the dynamic state of water in both normal and pathological skeletal muscles. Its possible utility for DMD carrier detection was discussed briefly. (orig.)

  13. Where are the radioactive wastes in France? Brochure no 5; Ou sont les dechets radioactifs en France? Brochure no 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    This document is one of the 6 regional brochures which make the geographical inventory of radioactive wastes in France. For each region, a table lists the recorded sites and a regional map localizes those having a detailed descriptive file. These files mention the most important waste owners (medical, research, nuclear and military industries), the type of waste and the type of management. The polluted sites are also mentioned, even if they are already decontaminated. The volume no 5 concerns the Languedoc-Roussillon and Provence-Alpes-Cote d'Azur regions, Corsica, and the overseas departements and territories. (J.S.)

  14. Adjusting Sensing Range to Maximize Throughput on Ad-Hoc Multi-Hop Wireless Networks

    National Research Council Canada - National Science Library

    Roberts, Christopher

    2003-01-01

    .... Such a network is referred to as a multi-hop ad-hoc network, or simply a multi-hop network. Most multi-hop network protocols use some form of carrier sensing to determine if the wireless channel is in use...

  15. Fibres as carriers for Lactobacillus rhamnosus during freeze-drying and storage in apple juice and chocolate-coated breakfast cereals.

    Science.gov (United States)

    Saarela, Maria; Virkajärvi, Ilkka; Nohynek, Liisa; Vaari, Anu; Mättö, Jaana

    2006-11-01

    The capability of different fibre preparations to protect the viability and stability of Lactobacillus rhamnosus during freeze-drying, storage in freeze-dried form and after formulation into apple juice and chocolate-coated breakfast cereals was studied. In freeze-drying trials wheat dextrin and polydextrose proved to be promising carriers for the L. rhamnosus strains: both freeze-drying survival and storage stability at 37 degrees C were comparable to the control carrier (sucrose). Using apple fibre and inulin carriers resulted in powders with fairly good initial freeze-drying survival but with poor storage stability at 37 degrees C. When fresh L. rhamnosus cells were added into apple juice (pH 3.5) together with oat flour with 20% beta-glucan the survival of the cells was much better at 4 degrees C and at 20 degrees C than with sucrose, wheat dextrin and polydextrose, whereas with freeze-dried cells no protective effect of oat flour could be seen. The stability of freeze-dried L. rhamnosus cells at 20 degrees C was higher in chocolate-coated breakfast cereals compared to low pH apple juice. Similar to freeze-drying stability, wheat dextrin and polydextrose proved to be better carriers than oat flour in chocolate-coated breakfast cereals. Regardless of their differing capability to adhere to fibre preparations the two L. rhamnosus strains studied gave parallel results in the stability studies with different carriers.

  16. Dose absorbed in the fetus by radioactive drugs prescribed

    International Nuclear Information System (INIS)

    Rojo, A.M.; Gomez Parada, I.; Di Trano, J.L.

    1998-01-01

    This work aims to review existing guidelines on the hypothesis that must be taken into account when calculating impact from the dose on the fetus for widely employed radioactive drugs. Recent research is added giving data on placenta transference linked to pregnancy term. The most widely used diagnostic and therapeutic practices are analyzed comparing the dose impact on the fetus with limits internationally accepted. This will allow having the necessary tools to answer questions concerning radiological risks due to the administration of radioactive drugs to pregnant women

  17. Carbon 14 and tritium radioactivity of alcohols

    International Nuclear Information System (INIS)

    Guerain, J.; Tourliere, S.

    1975-01-01

    The method of measuring carbon 14 radioactivity of alcohols has been perfected in order to establish the correct determination of synthetic alcohol added to fermentation alcohol. The specific carbon and tritium activity of alcohol of different origins have been determined for 1973 and 1974. The Suess effect and nuclear fall-out are observed [fr

  18. Recovery and storage method for radioactive iodine by vacuum freeze-drying

    International Nuclear Information System (INIS)

    Otsuka, Katsuyuki; Ouchi, Hitoshi; Suzuki, Toru.

    1990-01-01

    After scrubbing off-gas formed in a re-processing process for spent nuclear fuels, scrubbing liquids after use are subjected, as they are or with addition of additives, to a precipitating treatment. Then, liquid wastes containing radioactive iodine was subjected to freeze-drying treatment by freeze-drying under vacuum to recover radioactive iodine as iodine compounds. Off-gas scrubbing is conducted by using a sodium hydroxide solution and copper or silver ions may be added as additives in the precipitating treatment. Recovered iodine compounds containing radioactive iodine are solidified, either directly or after formulating into a composition of naturally existing iodine-containing ores by means of high pressure pressing into ores. This can prevent radioactive iodine 1 29I of long half-decay time from diffusing into the circumference and store the radioactive iodine stably for a long period of time. (T.M.)

  19. Effect of Aqueous Media on the Recovery of Scandium by Selective Precipitation

    Directory of Open Access Journals (Sweden)

    Bengi Yagmurlu

    2018-05-01

    Full Text Available This research presents a novel precipitation method for scandium (Sc concentrate refining from bauxite residue leachates and the effect of aqueous media on this triple-stage successive precipitation process. The precipitation pattern and the precipitation behavior of the constituent elements was investigated using different precipitation agents in three major mineral acid media, namely, H2SO4, HNO3, and HCl in a comparative manner. Experimental investigations showed behavioral similarities between HNO3 and HCl media, while H2SO4 media was different from them because of the nature of the formed complexes. NH4OH was found to be the best precipitation agent in every leaching media to remove Fe(III with low Sc co-precipitation. To limit Sc loss from the system, Fe(III removal was divided into two steps, leading to more than 90% of Fe(III removal at the end of the process. Phosphate concentrates were produced in the final step of the precipitation process with dibasic phosphates which have a strong affinity towards Sc. Concentrates containing more than 50% of ScPO4 were produced in each case from the solutions after Fe(III removal, as described. A flow diagram of the selective precipitation process is proposed for these three mineral acid media with their characteristic parameters.

  20. The transport safety of radioactive matters

    International Nuclear Information System (INIS)

    Landier, D.; Louet, Ch.A.; Robert, Ch.; Binet, J.; Malesys, P.; Pourade, C.; Le Meur, A.; Robert, M.; Turquet de Beauregard, G.Y.; Hello, E.; Laumond, A.; Regnault, Ph.; Gourlay, M.; Bruhl, G.; Malvache, P.; Dumesnil, J.; Cohen, B.; Sert, G.; Pain, M.; Green, L.; Hartenstein, M.; Stewart, J.; Cottens, E.; Liebens, M.; Marignac, Y.

    2007-01-01

    Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

  1. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 1

    International Nuclear Information System (INIS)

    2001-09-01

    The IAEA attaches a high importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications. This status and trends report has been issued in support of the Agency's strategy. It also represents the start of a process to improve the reporting of status and trends in radioactive waste management. The objectives of the report were: to identify subject areas deemed to be of interest to Member States and the Agency; to report the status of and trends in radioactive waste management according to these subject areas; and to base this reporting, to the greatest extent practicable, on quantitative data. This issue of the status and trends report is intended for persons directly involved in radioactive waste management and regulation as well as members of the general public who are relatively familiar with the nuclear industry

  2. Incubation of curing brines for the production of ready-to-eat, uncured, no-nitrite-or-nitrate-added, ground, cooked and sliced ham.

    Science.gov (United States)

    Krause, B L; Sebranek, J G; Rust, R E; Mendonca, A

    2011-12-01

    Salt concentration, vegetable juice powder (VJP) concentration and temperature were investigated to determine necessary conditions for incubation of curing brines including VJP and a starter culture containing Staphylococcus carnosus prior to production of naturally cured, no-nitrate/nitrite-added meat products. Subsequently, incubated brines were utilized to produce no-nitrate/nitrite-added sliced ham in which quality characteristics and residual nitrite concentrations were measured to determine feasibility of brine incubation for nitrate conversion prior to injection. Two ham treatments (one with VJP and starter culture; one with pre-converted VJP) and a nitrite-added control were used. No differences (P>0.05) were found for color in the VJP treatments. Control sliced ham was redder after 42 days of storage, retaining significantly (Phams during the first week of storage. While the nitrite-added control retained greater red color and initially had more residual nitrite than the VJP treatments, the two VJP treatments did not differ from each other. Copyright © 2011 Elsevier Ltd. All rights reserved.

  3. Synthesis of a Potent Aminopyridine-Based nNOS-Inhibitor by Two Recent No-Carrier-Added $^{18}$F-Labelling Methods

    OpenAIRE

    Drerup, Christian; Ermert, Johannes; Coenen, Heinrich Hubert

    2016-01-01

    Nitric oxide (NO), an important multifunctional signaling molecule, is produced by three isoforms of NO-synthase (NOS) and has been associated with neurodegenerative disorders. Selective inhibitors of the subtypes iNOS (inducible) or nNOS (neuronal) are of great interest for decoding neurodestructive key factors, and 18F-labelled analogues would allow investigating the NOS-function by molecular imaging with positron emission tomography. Especially, the highly selective nNOS inhibitor 6-((3-((...

  4. Foodstuffs (radioactive contamination)

    International Nuclear Information System (INIS)

    Thompson, Donald; Taylor, Teddy; Campbell-Savours, D.N.

    1987-01-01

    The proceedings are given of the debate in the UK House of Commons on the maximum permitted radioactivity levels for foodstuffs, feeding stuffs and drinking water in the case of abnormal levels of radioactivity or of a nuclear accident. The motion takes note of European Community Document no. 7183/87 and urges the Community to assure a common standard of health protection by adopting a rational set of scientifically based intervention levels for foodstuffs. (UK)

  5. Radioactively labelled vitamin B12

    Energy Technology Data Exchange (ETDEWEB)

    Charlton, J C; Lewis, A

    1976-12-01

    A method is described for preparing radioactively labelled vitamin B 12 (cyanocobalamin) by reacting ..cap alpha..-(5,6-dimethylbenzimidazolyl) hydrogenobamide with active (sup(57,58)Co) cobaltous ion. The latter may be in the form of cobaltous chloride or sulphate in aqueous or aqueous alcoholic medium. The reaction is effected by heating the reactants in darkness at pH 4 to 8. An excess of cyanide is added to convert the hydroxocobalamin formed to cyanocobalamin.

  6. RAILWAY INFRASTRUCTURE CAPACITY MANAGEMENT FOR AD-HOC TRAINS ON THE SŽDC NETWORK

    Directory of Open Access Journals (Sweden)

    Petr Nachtigall

    2016-09-01

    Full Text Available The paper describes basic principles of ad-hoc routes assignment. Each carrier has its own interface called information system KADR with SŽDC for capacity requests management. The paper describes all steps which must be done before train departure.

  7. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

    Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

  8. The use of ceramic membranes for radioactive solutions purification

    International Nuclear Information System (INIS)

    Zakrzewska-Trznadel, G.

    2002-01-01

    Membrane permeation combined with complexation was tested for radioactive wastes processing purpose. The results of experiments with MEMBRALOX and CeRAM INSIDE filtering elements are presented in the paper. The pore size of ceramic membranes was in 1kD-100 nm range. The experiments were performed with non-active and with radioactive model solutions and original radioactive waste samples. To achieve high decontamination factors the process was enhanced by chemical complexation. Such complexants as poly(acrylic) acid and polyacrylic)acid salts of different crosslinking, polyethylenimine and cyanoferrates were tested. The experiments showed the significant increase of retention and decontamination factors while before ultrafiltration macromolecular ligands were added. The effectiveness of complexation by each ligand is strongly dependent on pH and alkali metals concentration. (author)

  9. Radiation sources and methods for producing them

    International Nuclear Information System (INIS)

    Malson, H.A.; Moyer, S.E.; Honious, H.B.; Janzow, E.F.

    1979-01-01

    The radiation sources contain a substrate with an electrically conducting, non-radioactive metal surface, a layer of a metal isotope of the scandium group as well as a percentage of non-radioactive binding metal being coated on the surface by means of an electroplating method. Besides examples for β sources ( 147 Pm), γ sources ( 241 Am), and neutron sources ( 252 Cf) there is described an α-radiation source ( 241 Am, 244 Cu, 238 Pu) for smoke detectors. There are given extensive tables and a bibliography. (DG) [de

  10. Serum sample levels of bromine, iron, scandium and zinc in preschool children of Atayal and Bunun aborigines living in central Taiwan

    International Nuclear Information System (INIS)

    Chien-Yi Chen; Ding-Bang Lin; Yuan-Yaw Wei

    2006-01-01

    This study determined bromine, iron, scandium and zinc serum levels in Taiwanese aboriginal preschool children living in remote mountainous areas to increase the understanding of the social, cultural, nutrient and ethnic background of the Taiwanese children. Seventy-three serum samples were taken from two ethnic groups of preschool children, Atayal aborigines (AAPC) and Bunun aborigines (BAPC). Sera of these children were freeze dried. Trace elements in sera were identified by instrumental neutron activation analysis (INAA). The accuracy and precision of INAA was evaluated using certified reference materials: Tomato Leaves (NIST-SRM 1570a) and Lichen (IAEA-336). Statistical analysis identified several different patterns for ethnic groups, gender and age via the two-tailed Student's t-test. Analytical results showed that the ranges of Br, Fe, Sc and Zn in sera were somewhat wide. The Zn serum levels (p < 0.05) and Br serum levels (p < 0.01) in the AAPC were significantly lower than those in the BAPC. However, there were no significant differences in Fe or Sc serum levels between the two groups. Analytical results were compared to published data for different counties. This study is the first investigating trace elements in Taiwanese aborigines and can be used to establish a much-needed serum element database. (author)

  11. Wilson lines for AdS5 black strings

    International Nuclear Information System (INIS)

    Hristov, Kiril; Katmadas, Stefanos

    2015-01-01

    We describe a simple method of extending AdS 5 black string solutions of 5d gauged supergravity in a supersymmetric way by addition of Wilson lines along a circular direction in space. When this direction is chosen along the string, and due to the specific form of 5d supergravity that features Chern-Simons terms, the existence of magnetic charges automatically generates conserved electric charges in a 5d analogue of the Witten effect. Therefore we find a rather generic, model-independent way of adding electric charges to already existing solutions with no backreaction from the geometry or breaking of any symmetry. We use this method to explicitly write down more general versions of the Benini-Bobev black strings (http://dx.doi.org/10.1103/PhysRevLett.110.061601, http://dx.doi.org/10.1007/JHEP06(2013)005) and comment on the implications for the dual field theory and the similarities with generalizations of the Cacciatori-Klemm black holes (http://dx.doi.org/10.1007/JHEP01(2010)085) in AdS 4 .

  12. Synthesis of ''no carrier added'' 1,3-bis-(2-chloroethyl)nitrosourea (BCNU)

    International Nuclear Information System (INIS)

    Diksic, M.; Farrokhzad, S.; Yamamoto, L.; Feindel, W.

    1982-01-01

    A chemotherapeutic agent, C-11-labeled BCNU, has been prepared by nitrosation of C-11-labeled BCU, which was synthesized by reacting C-11-labeled phosgene with ethylenimine. Two methods of nitrosation are outlined and the results of both are discussed. The specific activity of C-11 BCNU was about 85 Ci/mmole at the end of bombardment and 30 Ci/mmole at the time of administration. Chemical and radiochemical purity of the final material was at least 98%

  13. Methods for estimating costs of transporting spent fuel and defense high-level radioactive waste for the civilian radioactive waste management program

    International Nuclear Information System (INIS)

    Darrough, M.E.; Lilly, M.J.

    1989-01-01

    The US Department of Energy (DOE), through the Office of Civilian Radioactive Waste Management, is planning and developing a transportation program for the shipment of spent fuel and defense high-level waste from current storage locations to the site of the mined geologic repository. In addition to its responsibility for providing a safe transportation system, the DOE will assure that the transportation program will function with the other system components to create an integrated waste management system. In meeting these objectives, the DOE will use private industry to the maximum extent practicable and in a manner that is cost effective. This paper discusses various methodologies used for estimating costs for the national radioactive waste transportation system. Estimating these transportation costs is a complex effort, as the high-level radioactive waste transportation system, itself, will be complex. Spent fuel and high-level waste will be transported from more than 100 nuclear power plants and defense sites across the continental US, using multiple transport modes (truck, rail, and barge/rail) and varying sizes and types of casks. Advance notification to corridor states will be given and scheduling will need to be coordinated with utilities, carriers, state and local officials, and the DOE waste acceptance facilities. Additionally, the waste forms will vary in terms of reactor type, size, weight, age, radioactivity, and temperature

  14. Method of solidifying radioactive waste

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Mihara, Shigeru; Yamashita, Koji; Sauda, Kenzo.

    1988-01-01

    Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO 2 , they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

  15. 78 FR 5243 - Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees

    Science.gov (United States)

    2013-01-24

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Meeting of Subcommittees AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of meeting of Motor Carrier Safety...

  16. Analysis of radioactive cobalt

    International Nuclear Information System (INIS)

    1977-01-01

    This is a manual published by Science and Technology Agency, Japan, which prescribes on the analysis method for radioactive cobalt which is a typical indexing nuclide among the radioactive nuclides released from nuclear facilities. Since the released cobalt is mainly discharged to coastal region together with waste water, this manual is written for samples of sea water, sea bottom sediments and marine organisms. Radioactive cobalt includes the nuclides of 57 co, 58 Co, 60 Co, etc., the manual deals with them as a whole as 60 Co of long half life. Though 60 Co analysis has become feasible comparatively simply due to scintillation or semi-conductor spectrometry, trace 60 Co analysis is performed quantitatively by co-precipitation or collection into alumina and scintillation spectrometry. However, specific collecting operation and γ-γ coincidence measurement have been required so far. This manual employs 60 Co collection by means of ion-exchange method and measurement with low background GM counting system, to analyze quantitatively and rapidly low level 60 Co. It is primarily established as the standard analyzing method for the survey by local autonomous bodies. It is divided into 4 chapters including introduction sea water, marine organisms, and sea bottom sediments. List of required reagents is added in appendix. (Wakatsuki, Y.)

  17. Summary report of the state surveillance program on the transportation of radioactive materials

    International Nuclear Information System (INIS)

    1977-11-01

    From 1973 to 1976, a surveillance program was conducted in New Jersey, Oregon, Missouri, New York, Illinois, Texas, Louisiana, South Carolina, Minnesota, and New York City to provide training support for State radiation personnel and to determine actual radiation exposure conditions and radioactive material package handling practices through the terminals of air carriers and freight forwarders. NRC and DOT along with the participating States, developed the surveillance program. In general, the results did not indicate a public health or safety problem due to the transportation of radioactive materials. Some employees of several freight forwarders, are, however, receiving annual exposures in excess of 500 mrem. Recommendations are given

  18. Storage of solid and liquid radioactive material

    International Nuclear Information System (INIS)

    Matijasic, A.; Gacinovic, O.

    1961-01-01

    Solid radioactive waste collected during 1961 from the laboratories of the Institute amounted to 22.5 m 3 . This report contains data about activity of the waste collected from january to November 1961. About 70% of the waste are short lived radioactive material. Material was packed in metal barrels and stored in the radioactive storage in the Institute. There was no contamination of the personnel involved in these actions. Liquid radioactive wastes come from the Isotope production laboratory, laboratories using tracer techniques, reactor cooling; decontamination of the equipment. Liquid wastes from isotope production were collected in plastic bottles and stored. Waste water from the RA reactor were collected in special containers. After activity measurements this water was released into the sewage system since no activity was found. Table containing data on quantities and activity of radioactive effluents is included in this report

  19. Disposition of nonflammable low-level radioactive wastes using supercritical water with ruthenium(IV) oxide catalyst

    International Nuclear Information System (INIS)

    Sugiyama, Wataru

    2013-01-01

    This paper presents the distribution behavior of iron, cobalt, cesium, iodine and strontium attached to nonflammable organic materials, in solid, liquid and gas phases during the decomposition of these materials using supercritical water with ruthenium(IV) oxide (RuO 2 ) catalyst. The distributions of these elements under various conditions (initial amounts, with/without precipitation reagent) were determined by using their radioisotopes as simulated low-level radioactive wastes (LLW) in order to ease the detection of trace amounts of elements even in solid and gas phases. Iron and cobalt were found only in the solid phase when iron hydroxide was added as a precipitation reagent before the supercritical water reaction. Cesium, iodine and strontium were found in the liquid phase after the reaction. Therefore, by adding precipitation reagents such as sodium tetraphenylborate, and sodium carbonate (Na 2 CO 3 ) (or sodium hydrogen carbonate (NaHCO 3 )) and silver nitrate (AgNO 3 ) aqueous solutions to each resultant liquid phase containing cesium, strontium and iodine, respectively, these elements can be successfully recovered only in the solid phase. The gases produced during the decomposition of the organic material contain no radioactivity under all conditions in this study. These results indicate that all of the elements investigated in this study (iron, cobalt, cesium, iodine and strontium) can be recovered successfully by this supercritical water process using RuO 2 Consequently, this process is suggested as a predominant candidate for the treatment of nonflammable organic materials in LLW. (author)

  20. Reducing logistical barriers to radioactive soil remediation after the Fukushima No. 1 nuclear power plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Ishii, K., E-mail: keizo.ishii@qse.tohoku.ac.jp [Research Center for Remediation Engineering of Living Environments Contaminated with Radioisotopes, Department of Quantum Science and Energy Engineering, Tohoku University, 6-6 Aza-Aoba, Aramaki, Aoba-ku, Sendai 980-8579 (Japan); Terakawa, A.; Matsuyama, S.; Kikuchi, Y.; Fujishiro, F.; Ishizaki, A.; Osada, N.; Arai, H.; Sugai, H.; Takahashi, H.; Nagakubo, K.; Sakurada, T. [Research Center for Remediation Engineering of Living Environments Contaminated with Radioisotopes, Department of Quantum Science and Energy Engineering, Tohoku University, 6-6 Aza-Aoba, Aramaki, Aoba-ku, Sendai 980-8579 (Japan); Yamazaki, H.; Kim, S. [Cyclotron and Radioisotope Center, Tohoku University, 6-3 Aza-Aoba, Aramaki, Aoba-ku, Sendai 980-8578 (Japan)

    2014-01-01

    We present an updated assessment of soil contamination due to the nuclear accident at the Fukushima No. 1 nuclear power plant on 11 March 2011. A safe limit for the spatial dose rate (micro-Sv/h) of gamma rays from {sup 134,137}Cs has been established in this work. Based on this value, the highly contaminated region within Fukushima Prefecture that must be decontaminated could be defined. Moreover, a conceptual model for the chemical speciation that occurred during the accident has been delineated. The compound model Cs{sub 2}CO{sub 3} was found to be meaningful and practical (non-radioactive) to simulate contamination in our decontamination experiments. Finally, we explain the mechanism of action of our soil remediation technique, which effectively reduces the total volume of contaminated soil by isolating the highly Cs-adsorptive clay fraction. The adsorption of non-radioactive Cs atoms on clay particles with diameters <25 μm were analyzed using micro-particle-induced X-ray emission (PIXE)

  1. Radioactivity Monitoring of the Irish Environment 2007

    International Nuclear Information System (INIS)

    Fegan, M.; Dowdall, A.; Hanley, O.; Hayden, E.; Kelleher, K.; Long, S.; Smith, V.; Somerville, S.; Wong, J.; Pollard, D.

    2008-10-01

    detect the presence of the gas krypton-85. This gas is released into the environment primarity as a result of the reprocessing of nuclear fuel. During 2007, levels of radionuclides in airborne radioactivity were low and consistent with measurements in previous years. External gamma dose rates were monitored continuously at fifteen stations. No abnormal levels were observed. A major upgrade of the aerosol sampling equipment began in 2007 when three on-line low volume systems and seven upgraded off-line low volume systems were installed and commissioned. Two additional on-line sites will be added in 2008. In accordance with the RPII's drinking water monitoring protocol, a number of major water supplies from Cork, Dublin, Galway and Limerick were tested and found to be within the requirements for radioactivity set out in the relevant national standards. In addition, groundwater supplies were tested in nine countries as a pilot for a national survey of ground water scheduled for 2008 to 2010. The RPII sampled and measured levels of radioactivity in mixed diet, milk and various other foodstuffs including milk products, baby foods, beef, lamb and poultry. These measurements show that the levels of artificual radioactivity in the Irish diet continue to be low. One hundred and ninety samples of fish, shellfish, seaweed, seawater and sediment were analysed for a range of radionuclides. Along the Irish coastline the highest activity concentrations observed were in the north-east. The main pathway contributing to the exposure of the Irish public to artificial radioactivity from the marine environment is the consumption of seafood. Caesium-137 continues to be the dominant radionuclide, accounting for approximately 84% of the total dose. The dose to the Irish population from consumption of seafood landed at north-east ports has declined significantly over the last two decades corresponding to the reduction in discharges from Sellafield. The annual doses incurred by the Irish public

  2. Reduction of radioactivity produced by nuclear explosives

    Energy Technology Data Exchange (ETDEWEB)

    Lessler, Richard M [Lawrence Radiation Laboratory, University of California, Livermore, CA (United States)

    1970-05-15

    Four main sources contribute to the radioactivity produced by a nuclear explosive: 1. Fission products from the nuclear explosive, 2. Fusion products from the nuclear explosive, 3. Induced radioactivity in the nuclear explosive, 4. Induced radioactivity in the environment. This paper will summarize some of the work done at the Lawrence Radiation Laboratory at Livermore to reduce the radioactivity from these sources to levels acceptable for peaceful applications. Although it is theoretically possible to have no radioactivity produced by nuclear explosives, this goal has not been achieved.

  3. Production of and studies with secondary radioactive ion beams at Lise

    International Nuclear Information System (INIS)

    Mueller, A.C.

    1990-01-01

    The doubly achromatic spectrometer LISE, installed at GANIL has delivered secondary radioactive beams for the past 6 years. Essentially, it consists of by two dipole magnets selecting (in A/Z) and refocusing (achromatically) the projectile-like fragment-beams emitted at 0 0 . Important features of LISE and selected experimental results will be discussed. LISE was substantially upgraded, recently, by adding a Wien-filter, providing secondary radioactive beams of still increased intensity and isotopic purity. (6 figs)

  4. Radioactively labelled vitamin B12

    International Nuclear Information System (INIS)

    Charlton, J.C.; Lewis, A.

    1976-01-01

    A method is described for preparing radioactively labelled vitamin B 12 (cyanocobalamin) by reacting α-(5,6-dimethylbenzimidazolyl) hydrogenobamide with active (sup(57,58)Co) cobaltous ion. The latter may be in the form of cobaltous chloride or sulphate in aqueous or aqueous alcoholic medium. The reaction is effected by heating the reactants in darkness at pH 4 to 8. An excess of cyanide is added to convert the hydroxocobalamin formed to cyanocobalamin. (U.K.)

  5. 77 FR 60507 - Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting

    Science.gov (United States)

    2012-10-03

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2006-26367] Motor Carrier Safety Advisory Committee (MCSAC): Public Subcommittee Meeting AGENCY: Federal Motor Carrier Safety Administration (FMCSA), DOT. ACTION: Notice of Meeting of Compliance, Safety...

  6. Radioactivity and foods

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1991-01-01

    The purpose of this article is to describe and contrast two relationships between radiation and food on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods

  7. Supersymmetric AdS3, AdS2 and bubble solutions

    International Nuclear Information System (INIS)

    Gauntlett, Jerome P.; Waldram, Daniel; Kim, Nakwoo

    2007-01-01

    We present new supersymmetric AdS 3 solutions of type IIB supergravity and AdS 2 solutions of D = 11 supergravity. The former are dual to conformal field theories in two dimensions with N = (0, 2) supersymmetry while the latter are dual to conformal quantum mechanics with two supercharges. Our construction also includes AdS 2 solutions of D = 11 supergravity that have non-compact internal spaces which are dual to three-dimensional N = 2 superconformal field theories coupled to point-like defects. We also present some new bubble-type solutions, corresponding to BPS states in conformal theories, that preserve four supersymmetries

  8. Labelled radioactive adenosinphosphates for the determination of toxic action

    International Nuclear Information System (INIS)

    Tahbaz, Z.

    1983-01-01

    Normal house-flies had been fed with carrier free radiophosphate (phosphorus). Many phosphorous containing substances in the tissue of the housefly are labelled with radiophosphorus by this procedure. Radiophosphorus is also found in the nucleotides of the housefly after applying radioactive phosphate. Suitable methods for processing and separation had been selected and worked out to isolate 32 P-adenosin-triphosphate 32 P-adenosin-diphosphate, 32 P-adenosin-monophosphate and 32 P-phosphate. Working at low temperature prevents chemical changes of the nucleotides. Extraction and thin layer chromatorgraphy turned out to be effective separation procedures for preparing samples for radioactivity measurement of the nucleotides. Autoradiographic techniques, scanning and liquid scitillation counting had been used for radioactivity measurements of the radioactive zones at the chromatograms. The results of these measurements provide information concerning the normal composition of adenosin-phosphates in the tissues of the housefly. If the animals are exposed to toxic chemicals, to insecticides, the composition of the phosphate containing compounds is changing. The concentration of adenosin-triphosphate is decreasing and the concentration of phosphate is increasing. This can be very easily shown by scanning the chromatograms of the extracts of the muscles of houseflies after feeding the animals with radioactive phosphate. Using this method, it is possible to show the toxic action of insecticides upon the metabolism of adenosin-phosphates. The decrease of the radioactivity at the zone of the adenosin-triphosphate and the increase of the radioactivity at the phosphate zone corresponds to the toxic action of foreign chemicals like insecticides. By using this tracer technique, it may be possible to investigate the toxic action of several toxic chemicals, if they are applied at the same time, thus investigating synergetic actions of environmental poisons. (Author)

  9. Method of plastic solidification of radioactive wastes

    International Nuclear Information System (INIS)

    Oikawa, Yasuo; Tokimitsu, Fujio.

    1986-01-01

    Purpose: To prevent occurrence of deleterious cracks to the inside and the surface of solidification products, as well as eliminate gaps between the products and the vessel inner wall upon plastic solidification processing for powdery or granular radioactive wastes. Method: An appropriate amount of thermoplastic resins such as styrenic polymer or vinyl acetate type polymer as a low shrinking agent is added and mixed with unsaturated polyester resins to be mixed with radioactive wastes so as to reduce the shrinkage-ratio to 0 % upon curing reaction. Thus, a great shrinkage upon hardening the mixture is suppressed to prevent the occurrence of cracks to the surface and the inside of the solidification products, as well as prevent the gaps between the inner walls of a drum can vessel and the products upon forming solidification products to the inside of the drum can. The resultant solidification products have a large compression strength and can sufficiently satisfy the evaluation standards as the plastic solidification products of radioactive wastes. (Horiuchi, T.)

  10. Residual radioactivity of treated green diamonds.

    Science.gov (United States)

    Cassette, Philippe; Notari, Franck; Lépy, Marie-Christine; Caplan, Candice; Pierre, Sylvie; Hainschwang, Thomas; Fritsch, Emmanuel

    2017-08-01

    Treated green diamonds can show residual radioactivity, generally due to immersion in radium salts. We report various activity measurements on two radioactive diamonds. The activity was characterized by alpha and gamma ray spectrometry, and the radon emanation was measured by alpha counting of a frozen source. Even when no residual radium contamination can be identified, measurable alpha and high-energy beta emissions could be detected. The potential health impact of radioactive diamonds and their status with regard to the regulatory policy for radioactive products are discussed. Copyright © 2017. Published by Elsevier Ltd.

  11. Study on immobilized yeast cells with hydrophilic polymer carrier by radiation-induced copolymerization

    International Nuclear Information System (INIS)

    Li Zhengkui; Zhang Bosen

    1993-01-01

    Various kinds of monomers 2-hydroxyethyl methacrylate (HEMA), 2-hydroxyethyl acrylate (HEA), hydroxypropyl methacrylate (HPMA) and methoxy polyethylene glycol methylacrylate (M-23G) are copolymerized by radiation technique at low temperature (-78 degree C) and several kinds of copolymer carriers were obtained. Yeast cells are immobilized through adhesion and multiplication of yeast cells themselves on these carriers. The ethanol productivity of immobilized yeast cells with these carriers was related to the monomer composition and water content of copolymer carriers and the optimum monomer composition was 20%:10% in poly (HEA-M23G). In this case, the ethanol productivity of immobilized yeast cells was 26 mg/(ml · h), which was 4 times as high as that of free cells. Effect of adding crosslinking reagent (4G) in lower monomer composition of poly(HEA-M23G) on the ethanol productivity of immobilized cells was better than that in higher one in this work

  12. Properties of Natural Radiation and Radioactivity

    International Nuclear Information System (INIS)

    Strom, Daniel J.

    2009-01-01

    Ubiquitous natural sources of radiation and radioactive material (naturally occurring radioactive material, NORM) have exposed humans throughout history. To these natural sources have been added technologically-enhanced naturally occurring radioactive material (TENORM) sources and human-made (anthropogenic) sources. This chapter describes the ubiquitous radiation sources that we call background, including primordial radionuclides such as 40K, 87Rb, the 232Th series, the 238U series, and the 235U series; cosmogenic radionuclides such as 3H and 14C; anthropogenic radionuclides such as 3H, 14C, 137Cs, 90Sr, and 129I; radiation from space; and radiation from technologically-enhanced concentrations of natural radionuclides, particularly the short-lived decay products of 222Rn ('radon') and 220Rn ('thoron') in indoor air. These sources produce radiation doses to people principally via external irradiation or internal irradiation following intakes by inhalation or ingestion. The effective doses from each are given, with a total of 3.11 mSv y-1 (311 mrem y-1) to the average US resident. Over 2.5 million US residents receive over 20 mSv y-1 (2 rem y-1), primarily due to indoor radon. Exposure to radiation from NORM and TENORM produces the largest fraction of ubiquitous background exposure to US residents, on the order of 2.78 mSv (278 mrem) or about 89%. This is roughly 45% of the average annual effective dose to a US resident of 6.2 mSv y-1 (620 mrem y-1) that includes medical (48%), consumer products and air travel (2%), and occupational and industrial (0.1%). Much of this chapter is based on National Council on Radiation Protection and Measurements (NCRP) Report No. 160, 'Ionizing Radiation Exposure of the Population of the United States,' for which the author chaired the subcommittee that wrote Chapter 3 on 'Ubiquitous Background Radiation.'

  13. Transport of radioactive material in Canada

    International Nuclear Information System (INIS)

    1997-09-01

    In this report, the Advisory Committee on Nuclear Safety (ACNS) presents the results of its study on how the system of the transport of radioactive material (TRM) in Canada is regulated, how it operates, and how it performs. The report deals with the transport of packages, including Type B packages which are used to carry large quantities of radioactive material, but not with the transport of spent nuclear fuel or with the transport of low-level historical waste. The ACNS has examined the Canadian experience in the TRM area, the regulatory framework in Canada with respect to the TRM some relevant aspects of training workers and monitoring compliance with regulatory requirements, the state of the emergency preparedness of organizations involved in the TRM and the process of updating present regulations by the Atomic Energy Control Board (AECB). As a result of this study, the ACNS concludes that the current Canadian regulatory system in the TRM is sound and that the TRM is, for the most part, conducted safely. However, improvements can be made in a number of areas, such as: determining the exposures of workers who transport radioactive material; rewording the proposed Transport Regulations in plain language; training all appropriate personnel regarding the AECB and Transport Canada (TC) Regulations; enforcing compliance with the regulations; and increasing the level of cooperation between the federal agencies and provincial authorities involved in the inspection and emergency preparedness aspects of the TRM. It is also noted that Bill C-23, the Nuclear Safety and Control Act, imposes a new requirement, subject to the Regulations, for a licence for a carrier to transport some types of radioactive material

  14. Transport of radioactive material in Canada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    In this report, the Advisory Committee on Nuclear Safety (ACNS) presents the results of its study on how the system of the transport of radioactive material (TRM) in Canada is regulated, how it operates, and how it performs. The report deals with the transport of packages, including Type B packages which are used to carry large quantities of radioactive material, but not with the transport of spent nuclear fuel or with the transport of low-level historical waste. The ACNS has examined the Canadian experience in the TRM area, the regulatory framework in Canada with respect to the TRM some relevant aspects of training workers and monitoring compliance with regulatory requirements, the state of the emergency preparedness of organizations involved in the TRM and the process of updating present regulations by the Atomic Energy Control Board (AECB). As a result of this study, the ACNS concludes that the current Canadian regulatory system in the TRM is sound and that the TRM is, for the most part, conducted safely. However, improvements can be made in a number of areas, such as: determining the exposures of workers who transport radioactive material; rewording the proposed Transport Regulations in plain language; training all appropriate personnel regarding the AECB and Transport Canada (TC) Regulations; enforcing compliance with the regulations; and increasing the level of cooperation between the federal agencies and provincial authorities involved in the inspection and emergency preparedness aspects of the TRM. It is also noted that Bill C-23, the Nuclear Safety and Control Act, imposes a new requirement, subject to the Regulations, for a licence for a carrier to transport some types of radioactive material.

  15. Recycled scrap metal and soils/debris with low radioactive contents

    International Nuclear Information System (INIS)

    Carriker, A.W.

    1996-01-01

    Two types of large volume bulk shipments of materials with low radioactivity have characteristics that complicate compliance with normal transport regulations. Scrap metal for recycling sometimes contains radioactive material that was not known or identified by the shipper prior to it being offered for transport to a scrap recycle processor. If the radioactive material is not detected before the scrap is processed, radiological and economic problems may occur. If detected before processing, the scrap metal will often be returned to the shipper. Uranium mill-tailings and contaminated soils and debris have created potential public health problems that required the movement of large volumes of bulk material to isolated safe locations. Similarly, old radium processing sites have created contamination problems needing remediation. The US Department of Transportation has issued exemptions to shippers and carriers for returning rejected scrap metal to original shippers. Other exemptions simplify transport of mill-tailings and debris from sites being remediated. These exemptions provide relief from detailed radioassay of the radioactive content in each conveyance as well as relief from the normal requirements for packaging, shipping documents, marking, labelling, and placarding which would be required for some of the shipments if the exemptions were not issued. (Author)

  16. Radioactive waste solidification material

    International Nuclear Information System (INIS)

    Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

    1992-01-01

    The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

  17. Reconstruction and modernization of Novi Han radioactive waste repository

    International Nuclear Information System (INIS)

    Kolev, I.

    2001-01-01

    The paper is an overview of the Feasibility Study for Reconstruction and Modernisation of Novi Han Radioactive Waste Repository (NHRWR), performed by EQE Bulgaria AD in 2000 for the Institute for Nuclear Research and Nuclear Energy of the Bulgarian Academy of Sciences. The Study develops a concept for overall reconstruction and modernisation of NHRWR, including rehabilitation and partial reconstruction of existing facilities and planning of new facilities for conditioning and storage of various radioactive wastes and spent sealed sources. The paper presents the general modernisation concept and outlines the proposed principle technical solutions for the existing and new facilities. (author)

  18. Environmental radioactivity surveillance programme 1994-1996

    International Nuclear Information System (INIS)

    Pollard, D.; Smith, V.; Howett, D.; Hayden, E.; Fegan, M.; O'Colmain, M.; Cunningham, J.D.

    1997-12-01

    This report presents the results of the terrestrial monitoring programme implemented by the Radiological Protection Institute of Ireland during the period 1994 to 1996. This monitoring programme includes the routine sampling and testing for radioactivity of samples of air, rainwater, drinking water and milk. Atmospheric concentrations of krypton-85 continued to rise over the period. No abnormal readings were observed for gamma dose rate, radioactivity in airborne particulates or radioactivity in rainwater. Significant variation in the concentrations of natural radioactivity was observed between drinking water supplies.The levels of anthropogenic radioactivity recorded during this reporting period in air, rainwater, drinking water and milk continue to be insignificant from a radiological safety point of view

  19. Bibliography in environmental radioactivity in foods. No. 33

    International Nuclear Information System (INIS)

    Fischer, E.; Kalus, W.; Mueller, H.; Schelenz, R.

    1981-01-01

    The newest issue in the line of this bibliography contains 249 quotations which are based on the original documents, primarily of the last two years. The bibliography is divided into the following chapters: general aspects (38 quotations), environmental radioactivity (70 quotations), radio ecology (114 quotations) and radio nuclide in food (27 quotations). The main emphasis is as the number of quotations shows, on the area of radio ecology and that contains: eco-systems in country and nourishment connections, eco-systems in water and nourishment connections and bibliographical effects. (MG) [de

  20. Radioactive liquid water processing method

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Noda, Tetsuya; Kobayashi, Fumio.

    1993-01-01

    Alkaline earth metals and heavy metals are added to radioactive liquid wastes containing a surface active agent comprising alkali metal salts of higher fatty acids. These metals form metal soaps with the surface active agent dissolved in the liquid wastes and crystallized. The crystallized metal soaps are introduced to a filtering column filled with a burnable polymeric fibrous filtering material. The filtering material is burnt. This can remove the surface active agent to remove COD without using an active carbon. (T.M.)

  1. Method of melt-decontaminating alumium contaminated with radioactivity

    International Nuclear Information System (INIS)

    Uda, Tatsuhiko; Iba, Hajime; Miura, Noboru; Kawasaki, Katsuo.

    1986-01-01

    Purpose: To enable optimum deontamination for radioactive-contaminated aluminum by further improving the decontaminating effect of the slag agent added to radioactive contaminated materials. Method: The slag agent is mainly composed of chloride type slags having a high reactivity for mainly incorporating uranium compounds and easily reacting near the melting point of aluminum and incorporated with fluorides for weakening the deliquescent characteristic to the chloride materials. Further, those slag agents are selected which can be treated at a low temperature in order to prevent the uranium compounds once incorporated into the slags from re-melting into the molten aluminum. Typically, a slag agent comprising 14 LiF, 76 KCl - 10 BaCl 2 is preferred. The basicity of the slag agent ranges from 0.5 to 2 and the melting point is 700 deg C. The melting decontaminating efficiency for the radioactive-contaminated aluminum can thus be improved. (Horiuchi, T.)

  2. Import/export Service of Radioactive Material

    CERN Multimedia

    2004-01-01

    Please note that the Import/Export service of radioactive material (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Web site: http://cern.ch/service-rp-shipping/ Tel.: 73171 E-mail: service-rp-shipping@cern.ch Radioactive Sources Service Please note that the radioactive sources service (24/E-024) is open from Monday to Friday, 8:00 to 11:00. No request will be treated the afternoon. Moreover, the service being reduced, transports between Swiss and French sites (and vice versa) will now be achieved by internal transport. Web site : http://cern.ch/service-rp-sources Tel.: 73171 E-mail: service-rp-sources@cern.ch

  3. Measurement of Radioactivity in Some Croatian Regions

    International Nuclear Information System (INIS)

    Orehovec, Z.; Ilijas, B.; Bokan, S.

    2001-01-01

    Full text: After Government of Canada expressed its suspicion that Canadian soldiers who were included in UNPROFOR mission in Croatia were exposed to increased radioactivity and possible some chemical influences, a large action of measuring and sampling was undertaken. Canadian and Croatian experts were working together and a very large number of samples was collected. Measurements of alpha, beta and gamma radioactivity on terrain, as well as later analysis of samples showed no increased radioactivity or any other signs of radioactive contamination. The conclusion is that any possible diseases of Canadian soldiers can not originate from radiation or radioactive contamination in Croatia. (author)

  4. Works of shifting discharge facilities in construction for adding No.3 and No.4 plants to Oi Nuclear Power Station

    International Nuclear Information System (INIS)

    Matsuoka, Gen-ichi; Yoshida, Atsumu.

    1989-01-01

    At present in Oi Power Station, No.1 and No.2 plants of 1175 MWe output each are in operation, but in order to stabilize electric power supply for a long period, Kansai Electric Power Co., Inc. earnestly advances the construction works for adding No.3 and No.4 plants of each 1180 MWe output PWR. No.3 plant is expected to begin the operation in October, 1991, and No.4 plant in August, 1992. The works for creating the site were started in July, 1985, and the flat land of about 60,000 m 2 and the reclaimed land of about 80,000 m 2 were prepared. Subsequently, the main construction works were started in May, 1987, and the rate of general progress was 21 % in No.3 plant and 2 % in No.4 plant as of the end of October, 1988. Due to the addition of No.3 and No.4 plants, the quantity of condenser cooling water discharge increases to 318 m 3 /s from 150 m 3 /s at present, therefore, the bank having discharge holes is shifted from the present position about 100 m toward sea. As to the problems, the shifting works in flowing water, the method of shifting, the examination on lifting caissons and culverts, the trial construction of chemical anchors and so on were investigated. The execution of the shifting works is reported. (K.I.)

  5. Ife Journal of Science - Vol 16, No 1 (2014)

    African Journals Online (AJOL)

    The effects of aluminum or scandium on the toughness, density and phase stability of iridium, platinum, rhodium and palladium · EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT · DOWNLOAD FULL TEXT DOWNLOAD FULL TEXT. A. I. Popoola, O. R. Bello, 99-105 ...

  6. Radioactive waste vitrification offgas analysis proposal

    International Nuclear Information System (INIS)

    Nelson, C.W.; Morrey, E.V.

    1993-11-01

    Further validation of the Hanford Waste Vitrification Plant (HWVP) feed simulants will be performed by analyzing offgases during crucible melting of actual waste glasses and simulants. The existing method of vitrifying radioactive laboratory-scale samples will be modified to allow offgas analysis during preparation of glass for product testing. The analysis equipment will include two gas chromatographs (GC) with thermal conductivity detectors (TCD) and one NO/NO x analyzer. This equipment is part of the radioactive formating offgas system. The system will provide real-time analysis of H 2 , O 2 , N 2 , NO, N 2 O, NO 2 , CO, CO 2 , H 2 O, and SO 2 . As with the prior melting method, the product glass will be compatible with durability testing, i.e., Product Consistency Test (PCT) and Material Characterization Center (MCC-1), and crystallinity analysis. Procedures have been included to ensure glass homogeneity and quenching. The radioactive glass will be adaptable to Fe +2 /ΣFe measurement procedures because the atmosphere above the melt can be controlled. The 325 A-hot cell facility is being established as the permanent location for radioactive offgas analysis during formating, and can be easily adapted to crucible melt tests. The total costs necessary to set up and perform offgas measurements on the first radioactive core sample is estimated at $115K. Costs for repeating the test on each additional core sample are estimated to be $60K. The schedule allows for performing the test on the next available core sample

  7. Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-11-01

    The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones.

  8. Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

    International Nuclear Information System (INIS)

    1985-11-01

    The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones

  9. A direct-conversion WLAN transceiver baseband with DC offset compensation and carrier leakage reduction

    Energy Technology Data Exchange (ETDEWEB)

    Yuan Fang; Yan Jun; Ma Heping; Shi Yin [Institute of Semiconductors, Chinese Academy of Sciences, Beijing 100083 (China); Foster, Dai Fa, E-mail: fyuan@sci-inc.com.c [Department of Electrical and Computer Engineering, Auburn University, Auburn, AL 36849-5201 (United States)

    2010-10-15

    A dual-band direct-conversion WLAN transceiver baseband compliant with the IEEE 802.11a/b/g standards is described. Several critical techniques for receiver DC offset compensation and transmitter carrier leakage rejection calibration are presented that enable the direct-conversion architecture to meet all WLAN specifications. The receiver baseband VGA provides 62 dB gain range with steps of 2 dB and a DC offset cancellation circuit is introduced to remove the offset from layout and self-mixing. The calibration loop achieves constant high-pass pole when gain changes; and a fast response time by programming the pole to 1 MHz during preamble and to 30 kHz during receiving data. The transmitter baseband employs an auto-calibration loop with on-chip AD and DA to suppress the carrier leakage, and AD can be powered down after calibration to save power consumption. The chip consumes 17.52 mA for RX baseband VGA and DCOC, and 8.3 mA for TX carrier leakage calibration (5.88 mA after calibration) from 2.85 V supply. Implemented in a 0.35 {mu}m SiGe technology, they occupy 0.68 mm{sup 2} and 0.18 mm{sup 2} die size respectively. (semiconductor integrated circuits)

  10. Radioactivity and foods

    International Nuclear Information System (INIS)

    Olszyna Marzys, A.E.

    1991-01-01

    The purpose of this article is to describe and contrast two relationships between radiation and food-on the one hand, beneficial preservation of food by controlled exposure to ionizing radiation; and, on the other, contamination of food by accidental incorporation of radioactive nuclides within the food itself. In food irradiation, electrons or electromagnetic radiation is used to destroy microorganisms and insects or prevent seed germination. The economic advantages and health benefits of sterilizing food in this manner are clear, and numerous studies have confirmed that under strictly controlled conditions no undesirable changes or induced radioactivity is produced in the irradiated food. An altogether different situation is presented by exposure of food animals and farming areas to radioactive materials, as occurred after the major Soviet nuclear reactor accident at Chernobyl. This article furnishes the basic information needed to understand the nature of food contamination associated with that event and describes the work of international organizations seeking to establish appropriate safe limits for levels of radioactivity in foods. 14 refs, 4 tabs

  11. Method for solidification and disposal of radioactive pellet waste

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Matsuura, Hiroyuki.

    1975-01-01

    Object: To form radioactive waste into pellet, which is impregnated with plastic monomer for polymerization, and then packed into a drum can to have gaps between composites filled with cement, mortar, and molten asphalt, thus increasing water resistance and strength. Structure: Radioactive powdery bodies discharged from a thin film scaraping drier are formed into pellets in the desired shape. The thus pelletized radioactive solid waste is impregnated with a fluid plastic monomer such as styrene monomer and methacrylacidmethyl, and a polymerization accelerator is added thereto for polymerization. As a consequence, a composite pellet of powdery solid waste and plastic may be obtained. This is packed into the drum can container, into which cement paste, cement mortar or molten asphalt are put to fill the space between the plastic pellet composites, thus obtaining a solidified body integral with the drum can. (Taniai, N.)

  12. No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes

    International Nuclear Information System (INIS)

    2006-02-01

    This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

  13. Investigation of radioactive contamination at non-radioactive drains of the Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    Koide, Hiroaki; Imanaka, Tetsuji; Ebisawa, Toru; Kawano, Shinji; Kobayashi, Keiji.

    1982-05-01

    In April, 1981, it was disclosed that a drainage area at the Tsuruga Nuclear Power Station was so much contaminated with radioactivites. Although Ministry of International Trade and Industry (MITI) officially provided an explanation of a process that resulted in the contamination, many problems remain unsolved on account of insufficient and limited investigations. The authors collected mud samples from contaminated manholes and examined radioactivities in them through the measurement of #betta#- and #betta#-spectra. Chemical separation of the samples was carried out in order to obtain precise concentration of radioactive cesium. Results are as follows: i) the concentration of radioactivities does not show monotonous decrease along the stream line but an anomalous peak at downstream manholes, ii) at the manhole specified No. 6 located rather downstream, 137 Cs concentration is significantly high and the composition of radioactive nuclides is quite different from that in the other manholes, and iii) additional radioactive contamination was observed in other manholes of non-radioactive drains which would not be influenced by the accident explained by MITI. Our present work has provided much more data than by MITI and made it clear that the overall data cnnot be consistent with the simple MITI explanation; a single radioactive release accident caused the disclosed contamination. It is concluded that non-radioactive water drains at the Tsuruga Nuclear Power Station had been under continual contamination. (author)

  14. Radioactive waste processing apparatus

    Science.gov (United States)

    Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

    1985-08-30

    Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

  15. Small black holes in global AdS spacetime

    Science.gov (United States)

    Jokela, Niko; Pönni, Arttu; Vuorinen, Aleksi

    2016-04-01

    We study the properties of two-point functions and quasinormal modes in a strongly coupled field theory holographically dual to a small black hole in global anti-de Sitter spacetime. Our results are seen to smoothly interpolate between known limits corresponding to large black holes and thermal AdS space, demonstrating that the Son-Starinets prescription works even when there is no black hole in the spacetime. Omitting issues related to the internal space, the results can be given a field theory interpretation in terms of the microcanonical ensemble, which provides access to energy densities forbidden in the canonical description.

  16. Experiences for the Safe and Secure transport of Radioactive Material in Islamic Republic of Iran

    International Nuclear Information System (INIS)

    Hajizadeh, B.; Eshraghi, A.; Deevband, M.R.; Kardan, M.R.

    2016-01-01

    The Iranian Nuclear Regulatory Authority (INRA) has been addressed the actions to be taken in respect of the safe and secure transport of radioactive material. Firstly, INRA translated TS-R-1 and approved it as national standard and imparted it to all entities that engage in transport of radioactive material. Training course was provided for the designers, consignors, carriers and consignees based on their actions in transport of radioactive material. All radioactive material carrier companies were enforced to observe all aspects of national standard and receive an authorized license of National Radiation Protection Department (NRPD). The NRPD has written procedures to regain control of the radiation sources together with the National Waste Management Department. Transport arrangements are in place for imported and exported sources. According to the Code of Conduct on safety and security, the sources category I, II and III have been registered in data bases carefully so far. All the licensees are obligated to inform the Regulatory Authority for any changes in position, application, possession, transfer or waste of radiation sources. There is a formal agreement with the National Security Council to permit the import of scrap metal at major entry points on the borders. Scrap metal importers are required to use these points of entry which are monitored by officers of the NRPD and portal gate monitors which are installed at the main entry points and be controlled from unique centre. If required, the NRPD will supply staff to other border entry points. Presently some portal gate monitors are in progress at the borderline customs also. All the major metal recycling facilities in IRAN have installed portal gate monitors to recheck their scrap metal imports. (author)

  17. Experiences for the Safe and Secure Transport of Radioactive Material in Islamic Republic of Iran

    International Nuclear Information System (INIS)

    Hajizadeh, B.; Eshraghi, A.; Deevband, M.R.; Kardan, M.R.

    2011-01-01

    The Iranian Nuclear Regulatory Authority (INRA) has been addressed the actions to be taken in respect of the safe and secure transport of radioactive material. Firstly, INRA translated TS-R-1 and approved it as national standard and imparted it to all entities that engage in transport of radioactive material. Training course was provided for the designers, consignors, carriers and consignees based on their actions in transport of radioactive material. All radioactive material carrier companies were enforced to observe all aspects of national standard and receive an authorized license of National Radiation Protection Department (NRPD). The NRPD has written procedures to regain control of the radiation sources together with the National Waste Management Department. Transport arrangements are in place for imported and exported sources. According to the Code of Conduct on safety and security, the sources category I, II and III have been registered in data bases carefully so far. All the licensees are obligated to inform the Regulatory Authority for any changes in position, application, possession, transfer or waste of radiation sources. There is a formal agreement with the National Security Council to permit the import of scrap metal at major entry points on the borders. Scrap metal importers are required to use these points of entry which are monitored by officers of the NRPD and portal gate monitors which are installed at the main entry points and be controlled from unique centre. If required, the NRPD will supply staff to other border entry points. Presently some portal gate monitors are in progress at the borderline customs also. All the major metal recycling facilities in IRAN have installed portal gate monitors to recheck their scrap metal imports. (author)

  18. Feasibility study for the assessment of the exposed dose with TENORM added in consumer products

    International Nuclear Information System (INIS)

    Yoo, Do Hyeon; Lee, Hyun Cheol; Shin, Wook-Geun; Min, Chul Hee; Ha, Wi-Ho; Yoo, Jae Ryong; Yoon, Seok-Won; Lee, Jiyon; Choi, Won-Chul

    2015-01-01

    Consumer products including naturally occurring radioactive material have been distributed widely in human life. The potential hazard of the excessively added technically enhanced naturally occurring radioactive material (TENORM) in consumer products should be assessed. The aim of this study is to evaluate the organ equivalent dose and the annual effective dose with the usage of the TENORM added in paints. The activities of gammas emitted from natural radionuclides in the five types of paints were measured with the high-purity germanium detector, and the annual effective dose was assessed with the computational human phantom and the Monte Carlo method. The results show that uranium and thorium series were mainly measured over the five paints. Based on the exposure scenario of the paints in the room, the highest effective dose was evaluated as <1 mSv y -1 of the public dose limit. (authors)

  19. No efficacy of annual gynaecological screening in BRCA1/2 mutation carriers; an observational follow-up study

    NARCIS (Netherlands)

    Hermsen, B. B. J.; Olivier, R. I.; Verheijen, R. H. M.; van Beurden, M.; de Hullu, J. A.; Massuger, L. F.; Burger, C. W.; Brekelmans, C. T.; Mourits, M. J.; de Bock, G. H.; Gaarenstroom, K. N.; van Boven, H. H.; Mooij, T. M.; Rookus, M. A.

    2007-01-01

    BRCA1/ 2 mutation carriers are offered gynaecological screening with the intention to reduce mortality by detecting ovarian cancer at an early stage. We examined compliance and efficacy of gynaecological screening in BRCA1/ 2 mutation carriers. In this multicentre, observational, follow-up study we

  20. High school Tay-Sachs disease carrier screening: 5 to 11-year follow-up.

    Science.gov (United States)

    Curd, Helen; Lewis, Sharon; Macciocca, Ivan; Sahhar, Margaret; Petrou, Vicki; Bankier, Agnes; Lieberman, Sari; Levy-Lahad, Ephrat; Delatycki, Martin B

    2014-04-01

    The Melbourne high school Tay-Sachs disease (TSD) carrier screening program began in 1997. The aim of this study was to assess the outcomes of this screening program among those who had testing more than 5 years ago, to evaluate the long-term impact of screening. A questionnaire was used for data collection and consisted of validated scales and purposively designed questions. Questionnaires were sent to all carriers and two non-carriers for each carrier who were screened in the program between 1999 and 2005. Twenty-four out of 69 (34.8 %) carriers and 30/138 (21.7 %) non-carriers completed the questionnaire. Most participants (82 %) retained good knowledge of TSD and there was no evidence of a difference in knowledge between carriers and non-carriers. Most participants (83 %) were happy with the timing and setting of screening and thought that education and screening for TSD should be offered during high school. There was no difference between carriers and non-carriers in mean scores for the State Trait Anxiety Inventory and Decision Regret Scale. This evaluation indicated that 5-11 years post high school screening, those who were screened are supportive of the program and that negative consequences are rare.