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Sample records for curium 243

  1. Biological transport of curium-243 in dairy animals

    International Nuclear Information System (INIS)

    Sutton, W.W.; Patzer, R.G.; Hahn, P.B.; Potter, G.D.

    1979-04-01

    Lactating cows and goats were used to examine the biological transport of curium-243 in dairy animals. After either single oral or intravenous nuclide doses were administered, samples of milk, urine, blood, and feces were taken over a 144-hr priod, and the curium concentrations were determined by gamma counting. Gastrointestinal uptake of curium was estimated to be 0.02 and 0.006% of the oral dose for cows and goats, respectively. The cumulative percentage of oral dose transported to milk and urine was 4.6 x 10 -4 and 1.9 x 10 -3 , respectively, for a cow and 2.7 x 10 -4 and 1.6 x 10 -4 , respectively, for goats. Plasma concentrations of curium decreased rapidly following all intravenous injections. The average percentage of injected curium transferred to milk, urine, and feces was 2, 8, and 1, respectively, for a cow and 2, 5, and 5, respectively, for goats. All animals were sacrificed one week after dosing. Bovine bone retained the greatest fraction of the administered dose and the next highest was the liver. However, in all three intravenously dosed goats the liver contained the greatest amount of curium. Nuclide deposition in bone and liver was essentially equal for two of the three orally dosed goats while the skeleton contained the most curium in the other animal. Comparisons are presented between curium-243 and americium-241 transport in dairy cows

  2. Fission-product yields for thermal-neutron fission of curium-243

    International Nuclear Information System (INIS)

    Breederland, D.G.

    1982-01-01

    Cumulative fission yields for 25 gamma rays emitted during the decay of 23 fission products produced by thermal-neutron fission of 243 Cm have been determined. Using Ge(Li) spectroscopy, 33 successive pulse-height spectra of gamma rays emitted from a 77-ng sample of 243 Cm over a period of approximately two and one-half months were analyzed. Reduction of these spectra resulted in the identification and matching of gamma-ray energies and half-lives to specific radionuclides. Using these results, 23 cumulative fission-product yields were calculated. Only those radionuclides having half-lives between 6 hours and 65 days were observed. Prior to this experiment, no fission-product yields had been recorded for 243 Cm

  3. Critical and subcritical mass calculations of curium-243 to -247 based on JENDL-3.2 for revision of ANSI/ANS-8.15

    International Nuclear Information System (INIS)

    Okuno, Hiroshi

    2002-01-01

    Critical and subcritical masses were calculated for a sphere of five curium isotopes from 243 Cm to 247 Cm in metal and in metal-water mixtures considering three reflector conditions: bare, with a water reflector or a stainless steel reflector. The calculation were made mainly with a combination of a continuous energy Monte Carlo neutron transport calculation code, MCNP, and the Japanese Evaluated Nuclear Data Library, JENDL-3.2. Other evaluated nuclear data files, ENDF/B-VI and JEF-2.2, were also applied to find differences in calculation results of the neutron multiplication factor originated from different nuclear data files. A large dependence on the evaluated nuclear data files was found in the calculation results: more than 10%Δk/k relative differences in the neutron multiplication factor for a homogeneous mixture of 243 Cm metal and water when JENDL-3.2 was replaced with ENDF/B-VI and JEF-2.2, respectively; and a 44% reduction in the critical mass by changing from JENDL-3.2 to ENDF/B-VI for 246 Cm metal. The present study supplied basic information to the ANSI/ANS-8.15 Working Group for revision of the standard for nuclear criticality control of special actinide elements. The new or revised values of the subcritical mass limits for curium isotopes accepted by the ANSI/ANS-8.15 Working Group were finally summarized. (author)

  4. Critical and subcritical mass calculations of curium-243 to -247 based on JENDL-3.2 for revision of ANSI/ANS-8.15

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kawasaki, Hiromitsu [CRC Solutions Corporation, Hitachinaka, Ibaraki (Japan)

    2002-10-01

    Critical and subcritical masses were calculated for a sphere of five curium isotopes from {sup 243}Cm to {sup 247}Cm in metal and in metal-water mixtures considering three reflector conditions: bare, with a water reflector or a stainless steel reflector. The calculation were made mainly with a combination of a continuous energy Monte Carlo neutron transport calculation code, MCNP, and the Japanese Evaluated Nuclear Data Library, JENDL-3.2. Other evaluated nuclear data files, ENDF/B-VI and JEF-2.2, were also applied to find differences in calculation results of the neutron multiplication factor originated from different nuclear data files. A large dependence on the evaluated nuclear data files was found in the calculation results: more than 10%{delta}k/k relative differences in the neutron multiplication factor for a homogeneous mixture of {sup 243}Cm metal and water when JENDL-3.2 was replaced with ENDF/B-VI and JEF-2.2, respectively; and a 44% reduction in the critical mass by changing from JENDL-3.2 to ENDF/B-VI for {sup 246}Cm metal. The present study supplied basic information to the ANSI/ANS-8.15 Working Group for revision of the standard for nuclear criticality control of special actinide elements. The new or revised values of the subcritical mass limits for curium isotopes accepted by the ANSI/ANS-8.15 Working Group were finally summarized. (author)

  5. Determination of Neptunium, Americium and Curium in Spent Nuclear Fuel Samples by Alpha Spectrometry Using 239Np and 243Am as a Spike and a Tracer

    International Nuclear Information System (INIS)

    Jeo, Kih-Soo; Song, Byung-Chul; Kim, Young-Bok; Han, Sun-Ho; Jeon, Young-Shin; Jung, Euo-Chang; Jee, Kwang-Yong

    2007-01-01

    Determination of actinide elements and fission products in spent nuclear fuels is of importance for a burnup determination and source term evaluation. Especially, the amounts of uranium and plutonium isotopes are used for the evaluation of a burnup credit in spent nuclear fuels. Additionally, other actinides such as Np, Am and Cm in spent nuclear fuel samples is also required for the purposes mentioned above. In this study, 237 Np, 241 Am and 244 Cm were determined by an alpha spectrometry for the source term data for high burnup spent nuclear fuels ranging from 37 to 62.9 GWD/MtU as a burnup. Generally, mass spectrometry has been known as the most powerful method for isotope determinations such as high concentrations of uranium and plutonium. However, in the case of minor actinides such as Np, Am and Cm, alpha spectrometry would be recommended instead. Determination of the transuranic elements in spent nuclear fuel samples is different from that for environmental samples because the amount of each nuclide in the spent fuel samples is higher and the relative ratios between each nuclide are also different from those for environmental samples. So, it is important to select an appropriate tracer and an optimum sample size depending on the nuclides and analytical method. In this study 237 Np was determined by an isotope dilution alpha(gamma) spectrometry using 239 Np as a spike, and 241 Am and curium isotopes were determined by alpha spectrometry using 243 Am as a tracer. The content of each nuclide was compared with that by the Origen-2 code

  6. Measurement of curium in marine samples

    Science.gov (United States)

    Schneider, D. L.; Livingston, H. D.

    1984-06-01

    Measurement of environmentally small but detectable amounts of curium requires reliable, accureate, and sensitive analytical methods. The radiochemical separation developed at Woods Hole is briefly reviewed with specific reference to radiochemical interferences in the alpha spectrometric measurement of curium nuclides and to the relative amounts of interferences expected in different oceanic regimes and sample types. Detection limits for 242 Cm and 244 Cm are ultimately limited by their presence in the 243Am used as curium yield monitor. Environmental standard reference materials are evaluated with regard to curium. The marine literature is reviewed and curium measurements are discussed in relation to their source of introduction to the environment. Sources include ocean dumping of low-level radioactive wastes and discharges from nuclear fuel reporcessing activities, In particular, the question of a detectable presence of 244Cm in global fallout from nuclear weapons testing is addressed and shown to be essentially negligible. Analyses of Scottish coastal sedimantes show traces of 242Cm and 244Cm activity which are believed to originate from transport from sources in the Irish Sea.

  7. Infrared spectrum of curium-244

    International Nuclear Information System (INIS)

    Conway, J.G.; Blaise, J.; Verges, J.

    1974-09-01

    The spectrum of curium-244 has been observed on the high resolution Fourier-transform spectrometer at Laboratoire Aime Cotton. An electrodeless lamp containing 50 μg of CmI 3 was run for 12 hours and 800,000 points were taken. A total of 1743 lines have been ascribed to curium and 87 percent of the lines have been assigned to transitions between known energy levels

  8. Subcellular distribution of curium in beagle liver

    International Nuclear Information System (INIS)

    Bruenger, F.W.; Grube, B.J.; Atherton, D.R.; Taylor, G.N.; Stevens, W.

    1976-01-01

    The subcellular distribution of curium ( 243 244 Cm) was studied in canine liver from 2 hr to 47 days after injection of 3 μCi 243 244 Cm/kg of body weight. The pattern of distribution for Cm was similar to other trivalent actinide elements studied previously (Am, Cf). Initially (2 hr), most of the nuclide was found in the cytosol and at least 90 percent was protein bound. About 70 percent of the Cm was bound to ferritin, approximately 5 percent was associated with a protein of MW approximately 200,000, and approximately 25 percent was found in the low-molecular-weight region (approximately 5000). The decrease in the Cm content of cytosol, nuclei, and microsomes coincided with an increase in the amount associated with mitochondria and lysosomes. The concentration of the Cm in the mitochondrial fraction was higher than it was in the lysosomal fraction at each time studied. In the mitochondrial fraction approximately 30 percent of the Cm was bound to membranous or granular material, and 70 percent was found in the soluble fraction. The Cm concentration initially associated with cell nuclei was high but had diminished to 20 percent of the 2 hr concentration by 20 days post injection (PI). The subcellular distribution of Cm in the liver of a dog which had received the same dose and was terminated because of severe liver damage was studied at 384 days PI. The liver weighed 130 g and contained approximately 30 percent of the injected Cm. In contrast, a normal liver weighs 280 g and at 2 hr PI contains approximately 40 percent of the injected dose. The subcellular distribution of Cm in this severely damaged liver differed from the pattern observed at earlier times after injection. The relative concentration of Cm in the cytosol was doubled; it was higher in the nuclei-debris fraction; and it was lower in the mitochondrial and lysosomal fractions when compared to earlier times

  9. Americium/curium bushing melter drain tests

    International Nuclear Information System (INIS)

    Smith, M.E.; Hardy, B.J.; Smith, M.E.

    1997-01-01

    Americium and curium were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. They have been stored in a nitric acid solution in an SRS reprocessing facility for a number of years. Vitrification of the americium/curium (Am/Cm) solution will allow the material to be safely stored or transported to the DOE Oak Ridge Reservation. Oak Ridge is responsible for marketing radionuclides for research and medical applications. The bushing melter technology being used in the Am/Cm vitrification research work is also under consideration for the stabilization of other actinides such as neptunium and plutonium. A series of melter drain tests were conducted at the Savannah River Technology Center to determine the relationship between the drain tube assembly operating variables and the resulting pour initiation times, glass flowrates, drain tube temperatures, and stop pour times. Performance criteria such as ability to start and stop pours in a controlled manner were also evaluated. The tests were also intended to provide support of oil modeling of drain tube performance predictions and thermal modeling of the drain tube and drain tube heater assembly. These drain tests were instrumental in the design of subsequent melter drain tube and drain tube heaters for the Am/Cm bushing melter, and therefore in the success of the Am/Cm vitrification and plutonium immobilization programs

  10. PROCESS FOR SEPARATING AMERICIUM AND CURIUM FROM RARE EARTH ELEMENTS

    Science.gov (United States)

    Baybarz, R.D.; Lloyd, M.H.

    1963-02-26

    This invention relates to methods of separating americium and curium values from rare earth values. In accordance with the invention americium, curium, and rare earth values are sorbed on an anion exchange resin. A major portion of the rare earth values are selectively stripped from the resin with a concentrated aqueous solution of lithium chloride, and americium, curium, and a minor portion of rare earth values are then stripped from the resin with a dilute aqueous solution of lithium chloride. The americium and curium values are further purified by increasing the concentration of lithium chloride in the solution to at least 8 molar and selectively extracting rare earth values from the resulting solution with a monoalkylphosphoric acid. (AEC)

  11. Americium/Curium Disposition Life Cycle Planning Study

    International Nuclear Information System (INIS)

    Jackson, W.N.; Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

    1998-01-01

    At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS)

  12. Americium-curium vitrification process development

    International Nuclear Information System (INIS)

    Fellinger, A.P.; Baich, M.A.; Hardy, B.J

    1999-01-01

    The successful demonstration of sequentially drying, calcining and vitrifying an oxalate slurry in the Drain Tube Test Stand (DTTS) vessel provided the process basis for testing on a larger scale in a cylindrical induction heated melter. A single processing issue, that of batch volume expansion, was encountered during the initial stage of testing. The increase in batch volume centered on a sintered frit cap and high temperature bubble formation. The formation of a sintered frit cap expansion was eliminated with the use of cullet. Volume expansions due to high temperature bubble formation (oxygen liberation from cerium reduction) were mitigated in the DTTS melter vessel through a vessel temperature profile that effectively separated the softening point of the glass cullet and the evolving oxygen from cerium reduction. An increased processing temperature of 1,470 C and a two hour hold time to find any remaining bubbles successfully reduced bubbles in the poured glass to an acceptable level. The success of the preliminary process demonstrations provided a workable process basis that was directly applicable to the newly installed Cylindrical Induction Melter (CIM) system, making the batch flowsheet the preferred option for vitrification of the americium-curium surrogate feed stream

  13. Sorption of curium by silica colloids: Effect of humic acid

    International Nuclear Information System (INIS)

    Kar, Aishwarya Soumitra; Kumar, Sumit; Tomar, B.S.; Manchanda, V.K.

    2011-01-01

    Sorption of curium by silica colloids has been studied as a function of pH and ionic strength using 244 Cm as a tracer. The sorption was found to increase with increasing pH and reach a saturation value of ∼95% at pH beyond 5.3. The effect of humic acid on the sorption of 244 Cm onto silica was studied by changing the order of addition of the metal ion and humic acid. In general, in the presence of humic acid (2 mg/L), the sorption increased at lower pH (<5) while it decreased in the pH range 6.5-8 and above pH 8, the sorption was found to increase again. As curium forms strong complex with humic acid, its presence results in the enhancement of curium sorption at lower pH. At higher pH the humic acid present in the solution competes with the surface sites for curium thus decreasing the sorption. The decrease in the Cm sorption in presence of humic acid was found to be less when humic acid was added after the addition of curium. Linear additive model qualitatively reproduced the profile of the Cm(III) sorption by silica in presence of humic acid at least in the lower pH region, however it failed to yield quantitative agreement with the experimental results. The results of the present study evidenced the incorporation of Cm into the silica matrix.

  14. A contribution to preparative micro-chemistry and structural chemistry of element 96, curium

    International Nuclear Information System (INIS)

    Kohl, R.

    1984-01-01

    Ternary oxides of curium are analyzed by preparing a spectrum of different phases and characterizing it by radiography. Physical and thermodynamic data are established on curium trihalogenides. Particular interest is taken in experiments for preparing curium of the higher valency stages IV, V, and VI. (orig./PW) [de

  15. Process for the recovery of curium-244 from nuclear waste

    International Nuclear Information System (INIS)

    Posey, J.C.

    1980-10-01

    A process has been designed for the recovery of curium from purex waste. Curium and americium are separated from the lanthanides by a TALSPEAK extraction process using differential extraction. Equations were derived for the estimation of the economically optimum conditions for the extraction using laboratory batch extraction data. The preparation of feed for the extraction involves the removal of nitric acid from the Purex waste by vaporization under reduced pressure, the leaching of soluble nitrates from the resulting cake, and the oxalate precipitation of a pure lanthanide-actinide fraction. Final separation of the curium from americium is done by ion-exchange. The steps of the process, except ion-exchange, were tested on a laboratory scale and workable conditions were determined

  16. The biokinetics and radiotoxicology of curium: A comparison with americium

    Energy Technology Data Exchange (ETDEWEB)

    Menetrier, F. [CEA, Fontenay-aux-Roses (France); Taylor, D.M. [School of Chemistry, Cardiff University, Cardiff CF10 3AT (United Kingdom)], E-mail: davtay@btinternet.com; Comte, A. [CEA, Fontenay-aux-Roses (France)

    2008-05-15

    The human and animal data on the biokinetics of {sup 242}Cm and {sup 244}Cm are reviewed and shown to be very similar to those for {sup 241}Am. Liver and skeleton are the main organs of deposition and the retention of curium in the skeleton is very prolonged in all the species examined. Retention of both curium and americium in the liver appears to be species-dependent, being relatively rapidly removed from the liver of rats, and probably humans, but being tenaciously retained in dogs and some other species. The radiotoxicity of curium is also reviewed and it is shown that, as with {sup 241}Am, lung and bone tumour induction are the major hazards from inhaled and systemically deposited {sup 244}Cm. The use of chelating agents for the treatment of accidental contamination of the human body with {sup 242,244}Cm is also discussed.

  17. Modelling of curium and americium behaviour during separation with displacing complexing chromatography

    International Nuclear Information System (INIS)

    Chuveleva, Eh.A.; Kharitonov, O.V.; Firsova, L.A.

    1994-01-01

    Certain heavy rare earths, curium and americium were separated by the method of displacement complexing chromatography using DTPA solutions and solutions containing DTPA and citric acid as eluents. Separation factors of rare earths and curium (americium) were calculated. Imitators for curium and americium separation were suggested: thulium for curium elution using 0.025 mol/l DTPA, holmium-for curium elution using 0.025 mol/l DTPA in the presence of 0.025 mol/l citric acid; terbium can serve as the imitator in both cases. 5 refs., 5 figs

  18. Calculation of prompt neutron spectra for curium isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Ohsawa, Takaaki [Kinki Univ., Higashi-Osaka, Osaka (Japan). Atomic Energy Research Inst.

    1997-03-01

    With the aim of checking the existing evaluations contained in JENDL-3.2 and providing new evaluations based on a methodology proposed by the author, a series of calculations of prompt neutron spectra have been undertaken for curium isotopes. Some of the evaluations in JENDL-3.2 was found to be unphysically hard and should be revised. (author)

  19. Determination of plutonium, americium and curium in the marine environment

    International Nuclear Information System (INIS)

    Grenaut, CLaude; Germain, Pierre; Miramand, Pierre.

    1982-01-01

    The method used in the Laboratory for plutonium, americium and curium determination in marine samples (water, sediments, animals, plants) is presented. It is a modification of a procedure based on adsorption on ion exchange resins developed by other authors. The preliminary preparation of the samples, the radiochemical procedures and electrodeposition are described so as to be used as a practical handbook [fr

  20. Thermodynamic systematics of oxides of americium, curium, and neighboring elements

    International Nuclear Information System (INIS)

    Morss, L.R.

    1984-01-01

    Recently-obtained calorimetric data on the sesquioxides and dioxides of americium and curium are summarized. These data are combined with other properties of the actinide elements to elucidate the stability relationships among these oxides and to predict the behavior of neighboring actinide oxides. 45 references, 4 figures, 5 tables

  1. The curium tagging approach for enhanced safeguards for spent fuel handling and reprocessing

    International Nuclear Information System (INIS)

    Menlove, H.O.; Beddingfield, D.H.; Rinard, P.M.; Wenz, T.R.

    1999-01-01

    Because of the intense neutron emission rate from curium, it can be a useful signature to measure and track special nuclear material in spent fuel and waste. By measuring the concentration of curium as well as plutonium and uranium in spent fuel streams, the ratio of curium to plutonium, uranium or other actinides can be used for waste assay. The quantity of special nuclear material in the waste streams such as the leached hulls and vitrified high-level waste can be calculated from the ratio of the curium to the plutonium, etc. The quantity of curium can be measured from the neutron emission rate from the various waste streams in the presence of the high-level gamma-ray backgrounds from fission products. Examples of using the curium ratio technique for measuring plutonium in leached hulls and vitrified waste canisters are presented in this paper. (author)

  2. Extraction separation of americium and curium. A review

    International Nuclear Information System (INIS)

    Petrzilova, H.

    1976-11-01

    A survey is given of extraction systems suitable for transplutonium element separation and preparation as well as for the practical application of their nuclear properties. Methods are discussed in detail of separating the actinide and the lanthanide fractions from fission and corrosion products and of separating americium from curium. The description is completed with flowsheets showing the separation of transplutonium elements from irradiated targets and waste solutions after spent fuel reprocessing. (L.K.)

  3. Gut uptake factors for plutonium, americium and curium

    International Nuclear Information System (INIS)

    Harrison, J.D.

    1982-01-01

    Data on estimates of the absorption of plutonium, americium and curium from the human gut based on measurements of uptake in other mammalian species are reviewed. It is proposed that for all adult members of the public ingesting low concentrations of plutonium in food and water, 0.05% would be an appropriate value of absorption except when the conditions of exposure are known and a lower value can be justified. For dietary intakes of americium and curium, the available data do not warrant a change from the ICRP value of 0.05%. For newborn children ingesting americium, curium and soluble forms of plutonium, a value of 1% absorption is proposed for the first 3 months of life during which the infant is maintained on a milk diet. It is proposed that a value of 0.5% should be used for the first year of life to take account of the gradual maturation of the gut. In considering the ingestion of insoluble oxides of plutonium by infants, it is proposed that absorption is taken as 0.1% for the first 3 months and 0.05% for the first year. (author)

  4. Plant uptake of americium, curium, and the chemical analog neodymium

    International Nuclear Information System (INIS)

    Weimer, W.C.; Laul, J.C.; Kutt, J.C.; Bondietti, E.A.

    1977-01-01

    The plant uptake from several bulk soils has been determined for neodymium, a chemical analog to the transuranium elements americium and curium, and several other native rare earth elements as well. These investigations have demonstrated that neodymium, which has very similar chemical properties to amercium and curium and should have a similar environmental behavior, does behave indistinguishably under both laboratory and field conditions. The uptake of the weathered or mobile forms of these elements from soils is expected to be governed primarily by their identical oxidation states and nearly identical ionic radii. This hypothesis is strongly supported by the chondritic (primordial) normalized rare earth element patterns in several plants. In these samples, the entire series of rare earth elements behaves as a smooth function of the REE ionic radii, as is also seen in the contiguous soils. This behavior suggests that the plant uptake of other ions with similar chemical properties (i.e., americium and curium) would also be governed by ionic size and charge

  5. Gclust Server: 243 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available 243 CEL_K07E3.3_17568735 Cluster Sequences Related Sequences(40) 303 dao-3: Dauer or Aging... sequences Related Sequences(40) Sequence length 303 Representative annotation dao-3: Dauer or Aging

  6. 243Cm half-life determinaton

    International Nuclear Information System (INIS)

    Timofeev, G.A.; Kalygin, V.V.; Privalova, P.A.

    1986-01-01

    By molar ratios of 243 Cm mixture with 244 Cm and Pu nuclides formed as a result of Cm nuclides α-decay the 243 Cm half-life T α243 is determined. The 244 Cm half-life is measured earlier with high accuracy. The 243 Cm/ 244 Cm ratio measured by means of a mass spectrometer equals 0.989+-0.004. The obtained value T α243 =29.20+-0.14 years

  7. Analytical separation of americium and curium, using high performance liquid chromatography

    International Nuclear Information System (INIS)

    Billon, A.

    1978-01-01

    Americium and curium are separated on a column of cation exchange resin (Aminex) using hydroxyisobutyric acid (α HIBA) as eluent, at a temperature of 80 0 C. Americium and curium were detected in line using their α emission: the separation was performed in a shielded glove box whose setting-up is given. Finally, the time necessary for a separation is comprised between 30 min and 1 hr. The purity of separated fractions was assayed by mass-spectrometry. An application in the determination of isotopic composition of americium and curium in fuels is described

  8. Determination of C0-60 in Cobalt Slugs and Slabs and Radionuclides in Curium Sampler Slugs L-Reactor Disassembly Basin

    International Nuclear Information System (INIS)

    Casella, V.R.

    2004-01-01

    Co-60 was historically produced in the SRS reactors. Cobalt slugs were irradiated in the early 1970s. Post-production, remaining cobalt slugs (including slab form) were consolidated for storage. There are approximately nine hundred cobalt slugs currently stored awaiting final disposition. These slugs had historically incomplete documentation for activity rates; therefore, assaying was required in order to determine their activity levels. Since the gamma dose rate from these slugs is extremely high, the most cost effective way to shield a source of this magnitude from personnel and the radiation detector was to use the basin water in which the slugs are stored as the shield. A sodium iodide gamma detector was placed above a specially designed air collimator assembly, so that slug was at least eight feet from the detector and was shielded by the basin water. Using a sodium iodide detector and multichannel analyzer system and an underwater collimator assembly, Co-60 concentrations we re determined for Disassembly Basin cobalt slugs and slabs and 18 curium sampler slugs. The total activity of all of the assayed slugs summed to 31,783 curies. From the Co-60 concentrations of the curium sampler slugs, the irradiation flux was determined for the known irradiation time. The amounts of Pu-238, 239, 240, 241, 242; Am-241, 243; and Cm-242, 244 produced were then obtained based on the original amount of Pu-239 irradiated

  9. Americium/Curium Vitrification Pilot Tests - Part II

    International Nuclear Information System (INIS)

    Marra, J.E.; Baich, M.A.; Fellinger, A.P.; Hardy, B.J.; Herman, D.T.; Jones, T.M.; Miller, C.B.; Miller, D.H.; Snyder, T. K.; Stone, M.E.

    1998-05-01

    Isotopes of americium (Am) and curium (Cm) were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. These highly radioactive and valuable isotopes have been stored in an SRS reprocessing facility for a number of years. Vitrification of this solution will allow the material to be more safely stored until it is transported to the DOE Oak Ridge Reservation for use in research and medical applications. A previous paper described operation results from the Am-Cm Melter 2A pilot system, a full-scale non-radioactive pilot facility. This paper presents the results from continued testing in the Pilot Facility and also describes efforts taken to look at alternative vitrification process operations and flowsheets designed to address the problems observed during melter 2A pilot testing

  10. Pretreatment of americium/curium solutions for vitrification

    International Nuclear Information System (INIS)

    Rudisill, T.S.

    1996-01-01

    Vitrification will be used to stabilize an americium/curium (Am/Cm) solution presently stored in F-Canyon for eventual transport to the heavy isotope programs at Oak Ridge National Laboratory. Prior to vitrification, an in-tank oxalate precipitation and a series of oxalic/nitric acid washes will be used to separate these elements and lanthanide fission products from the bulk of the uranium and metal impurities present in the solution. Pretreatment development experiments were performed to understand the behavior of the lanthanides and the metal impurities during the oxalate precipitation and properties of the precipitate slurry. The results of these experiments will be used to refine the target glass composition allowing optimization of the primary processing parameters and design of the solution transfer equipment

  11. Remote micro-encapsulation of curium-gold cermets

    International Nuclear Information System (INIS)

    Coops, M.S.; Voegele, A.L.; Hayes, W.N.; Sisson, D.H.

    1980-01-01

    A technique is described for fabricating minature, high-density capsules of curium-244 oxide contained in three concentric jackets of metallic gold (or silver), with the outer surface being free of alpha contamination. The completed capsules are right circular cylinders 0.2500-inch diameter and 0.125-inch tall, with each level of containment soldered (or brazed) closed. A typical capsule would contain approx. 70 mg of 244 Cm (5.7 Ci) mixed with 120 mg of gold powder in the form of a cermet wafer clad in three concentric, 0.010-inch thick, liquid tight jackets. This method of fabrication eliminates voids between the jackets and produces a minimum size, maximum density capsule. Cermet densities of 11.5 g/cc were obtained, with an overall density of 17.3 g/cc for the finished capsule

  12. 49 CFR 192.243 - Nondestructive testing.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 3 2010-10-01 2010-10-01 false Nondestructive testing. 192.243 Section 192.243... BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.243 Nondestructive testing. (a) Nondestructive testing of welds must be performed by any process, other than trepanning, that...

  13. 40 CFR 243.201 - Safety.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Safety. 243.201 Section 243.201 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES FOR THE STORAGE... Procedures § 243.201 Safety. ...

  14. 48 CFR 243.204 - Administration.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Administration. 243.204... OF DEFENSE CONTRACT MANAGEMENT CONTRACT MODIFICATIONS Change Orders 243.204 Administration. Follow the procedures at PGI 243.204 for administration of change orders. [75 FR 48277, Aug. 10, 2010] ...

  15. 7 CFR 58.243 - Checking quality.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 3 2010-01-01 2010-01-01 false Checking quality. 58.243 Section 58.243 Agriculture... Procedures § 58.243 Checking quality. All milk, milk products and dry milk products shall be subject to inspection and analysis by the dairy plant for quality and condition throughout each processing operation...

  16. 40 CFR 243.204 - Collection management.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Collection management. 243.204 Section 243.204 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES GUIDELINES... and Recommended Procedures § 243.204 Collection management. ...

  17. Density of simulated americium/curium melter feed solution

    International Nuclear Information System (INIS)

    Rudisill, T.S.

    1997-01-01

    Vitrification will be used to stabilize an americium/curium (Am/Cm) solution presently stored in F-Canyon for eventual transport to Oak Ridge National Laboratory and use in heavy isotope production programs. Prior to vitrification, a series of in-tank oxalate precipitation and nitric/oxalic acid washes will be used to separate these elements and lanthanide fission products from the bulk of the uranium and metal impurities present in the solution. Following nitric acid dissolution and oxalate destruction, the solution will be denitrated and evaporated to a dissolved solids concentration of approximately 100 g/l (on an oxide basis). During the Am/Cm vitrification, an airlift will be used to supply the concentrated feed solution to a constant head tank which drains through a filter and an in-line orifice to the melter. Since the delivery system is sensitive to the physical properties of the feed, a simulated solution was prepared and used to measure the density as a function of temperature between 20 to 70 degrees C. The measured density decreased linearly at a rate of 0.0007 g/cm3/degree C from an average value of 1.2326 g/cm 3 at 20 degrees C to an average value of 1.1973g/cm 3 at 70 degrees C

  18. Americium/Curium Melter 2A Pilot Tests

    International Nuclear Information System (INIS)

    Smith, M.E.; Fellinger, A.P.; Jones, T.M.; Miller, C.B.; Miller, D.H.; Snyder, T.K.; Stone, M.E.; Witt, D.C.

    1998-05-01

    Isotopes of americium (Am) and curium (Cm) were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. These highly radioactive and valuable isotopes have been stored in an SRS reprocessing facility for a number of years. Vitrification of this solution will allow the material to be more safely stored until it is transported to the DOE Oak Ridge Reservation for use in research and medical applications. To this end, the Am/Cm Melter 2A pilot system, a full-scale non- radioactive pilot plant of the system to be installed at the reprocessing facility, was designed, constructed and tested. The full- scale pilot system has a frit and aqueous feed delivery system, a dual zone bushing melter, and an off-gas treatment system. The main items which were tested included the dual zone bushing melter, the drain tube with dual heating and cooling zones, glass compositions, and the off-gas system which used for the first time a film cooler/lower melter plenum. Most of the process and equipment were proven to function properly, but several problems were found which will need further work. A system description and a discussion of test results will be given

  19. Density of simulated americium/curium melter feed solution

    Energy Technology Data Exchange (ETDEWEB)

    Rudisill, T.S.

    1997-09-22

    Vitrification will be used to stabilize an americium/curium (Am/Cm) solution presently stored in F-Canyon for eventual transport to Oak Ridge National Laboratory and use in heavy isotope production programs. Prior to vitrification, a series of in-tank oxalate precipitation and nitric/oxalic acid washes will be used to separate these elements and lanthanide fission products from the bulk of the uranium and metal impurities present in the solution. Following nitric acid dissolution and oxalate destruction, the solution will be denitrated and evaporated to a dissolved solids concentration of approximately 100 g/l (on an oxide basis). During the Am/Cm vitrification, an airlift will be used to supply the concentrated feed solution to a constant head tank which drains through a filter and an in-line orifice to the melter. Since the delivery system is sensitive to the physical properties of the feed, a simulated solution was prepared and used to measure the density as a function of temperature between 20 to 70{degrees} C. The measured density decreased linearly at a rate of 0.0007 g/cm3/{degree} C from an average value of 1.2326 g/cm{sup 3} at 20{degrees} C to an average value of 1.1973g/cm{sup 3} at 70{degrees} C.

  20. Study of Reaction of Curium Oxy-Compound Formation in Molten Chlorides

    Energy Technology Data Exchange (ETDEWEB)

    Osipenko, A.G.; Mayorshin, A.A.; Bychkov, A.V. [Dimitrovgrad-10, Ulyanovsk region, 433510 (Russian Federation)

    2008-07-01

    The method of potentiometric titration using oxygen sensors with solid electrolyte membrane was applied for the study of the interaction of curium cations with oxygen anions in the molten alkali metal chlorides in the temperature range of 450-850 C degrees depending on oxy-acidity of the environment. Assumptions were made concerning ion and phase composition of the obtained high-temperature compounds and chemical reactions taking place in the melts. This scheme assumes that as the basicity of the melt increases, initially the formation of soluble curium oxychlorides takes place in the melt (presumably CmO{sup -}) that is followed by formation of solid CmOCl and finally sesquioxide Cm{sub 2}O{sub 3}. Basic thermodynamic values were calculated for the resultant curium oxy-compounds.

  1. The rapid determination of americium curium, and uranium in urine by ultrafiltration

    International Nuclear Information System (INIS)

    Stradling, G.N.; Popplewell, D.S.; Ham, G.J.; Griffin, R.

    1975-01-01

    The rapid ultrafiltration method developed for the assay of plutonium has been extended to the determination of americium, curium and uranium in urine. The limits of detection for americium and curium, and uranium are 0.09 and 0.12 dm -1 l -1 respectively, and the analysis time excluding counting less than 2 hours. The method can therefor be effectively used as a rapid screening procedure. When the reference level for plutonium is exceeded, the α activity may require to be characterised. The single ultrafiltration technique must be modified for turbid urine samples. The method is inappropriate, except for uranium, when the urine contains DTPA. (author)

  2. 27 CFR 24.243 - Filtering aids.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Filtering aids. 24.243... OF THE TREASURY LIQUORS WINE Storage, Treatment and Finishing of Wine § 24.243 Filtering aids. Inert fibers, pulps, earths, or similar materials, may be used as filtering aids in the cellar treatment and...

  3. 7 CFR 1220.243 - Confidential treatment.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 10 2010-01-01 2010-01-01 false Confidential treatment. 1220.243 Section 1220.243 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (MARKETING... Confidential treatment. Except as otherwise provided in the Act, financial or commercial information that is...

  4. 40 CFR 86.243-94 - [Reserved

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false [Reserved] 86.243-94 Section 86.243-94 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF... Year Gasoline-Fueled New Light-Duty Vehicles, New Light-Duty Trucks and New Medium-Duty Passenger...

  5. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ( 242 Cm). This report also includes discussions about waste types and forms in which 242 Cm can be found and 242 Cm behavior in the environment and in the human body

  6. Final report on the decontamination of the Curium Source Fabrication Facility

    International Nuclear Information System (INIS)

    Schaich, R.W.

    1983-12-01

    The Curium Source Fabrication Facility (CSFF) at Oak Ridge National Laboratory (ORNL) was decontaminated to acceptable contamination levels for maintenance activities, using standard decontamination techniques. Solid and liquid waste volumes were controlled to minimize discharges to the ORNL waste systems. This program required two years of decontamination effort at a total cost of approximately $700K. 5 references, 7 figures, 2 tables

  7. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    Energy Technology Data Exchange (ETDEWEB)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

  8. Safety analysis report for packaging (SARP) of the Oak Ridge National Laboratory. TRU curium shipping container

    International Nuclear Information System (INIS)

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

    1980-06-01

    An analytical evaluation of the Oak Ridge National Laboratory Transuranium (TRU) Curium Shipping Container was made to demonstrate its compliance with the regulations governing offsite shipment of packages containing radioactive material. 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 container complies with the applicable regulations

  9. Solubility of Plutonium (IV) Oxalate During Americium/Curium Pretreatment

    International Nuclear Information System (INIS)

    Rudisill, T.S.

    1999-01-01

    Approximately 15,000 L of solution containing isotopes of americium and curium (Am/Cm) will undergo stabilization by vitrification at the Savannah River Site (SRS). Prior to vitrification, an in-tank pretreatment will be used to remove metal impurities from the solution using an oxalate precipitation process. Material balance calculations for this process, based on solubility data in pure nitric acid, predict approximately 80 percent of the plutonium in the solution will be lost to waste. Due to the uncertainty associated with the plutonium losses during processing, solubility experiments were performed to measure the recovery of plutonium during pretreatment and a subsequent precipitation process to prepare a slurry feed for a batch melter. A good estimate of the plutonium content of the glass is required for planning the shipment of the vitrified Am/Cm product to Oak Ridge National Laboratory (ORNL).The plutonium solubility in the oxalate precipitation supernate during pretreatment was 10 mg/mL at 35 degrees C. In two subsequent washes with a 0.25M oxalic acid/0.5M nitric acid solution, the solubility dropped to less than 5 mg/mL. During the precipitation and washing steps, lanthanide fission products in the solution were mostly insoluble. Uranium, and alkali, alkaline earth, and transition metal impurities were soluble as expected. An elemental material balance for plutonium showed that greater than 94 percent of the plutonium was recovered in the dissolved precipitate. The recovery of the lanthanide elements was generally 94 percent or higher except for the more soluble lanthanum. The recovery of soluble metal impurities from the precipitate slurry ranged from 15 to 22 percent. Theoretically, 16 percent of the soluble oxalates should have been present in the dissolved slurry based on the dilution effects and volumes of supernate and wash solutions removed. A trace level material balance showed greater than 97 percent recovery of americium-241 (from the beta dec

  10. Dicty_cDB: SLH243 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SL (Link to library) SLH243 (Link to dictyBase) - - - Contig-U15469-1 SLH243P (Link to Original site) SLH2...43F 436 SLH243Z 369 SLH243P 805 - - Show SLH243 Library SL (Link to library) Clone ID SLH2... URL http://dictycdb.biol.tsukuba.ac.jp/CSM/SL/SLH2-B/SLH243Q.Seq.d/ Representative seq. ID SLH2...43P (Link to Original site) Representative DNA sequence >SLH243 (SLH243Q) /CSM/SL/SLH2-B/SLH2...SA605. 785 0.0 1 ( AU062023 ) Dictyostelium discoideum slug cDNA, clone SLH243. 785 0.0 1 ( BJ416791 ) Dicty

  11. Separation and activity determination of 239+240Pu, 241Am and Curium (242and244Cm) in evaporator concentrate by Alpha Spectrometry

    International Nuclear Information System (INIS)

    Reis Junior, Aluisio S.; Temba, Eliane S.C.; Kastner, Geraldo F.; Monteiro, Roberto P.G.

    2013-01-01

    Alpha spectrometry analysis was used for activity determinations of Pu, Am and Cm isotopes in evaporator concentrate samples from nuclear power plants. Using a sequential procedure the first step was Pu isolation by an anion exchange column followed by an Am and Cm separation of U and Fe by a co-precipitation with oxalic acid. The precipitate was used for americium and curium separation of strontium by using a TRU resin extraction chromatography column. Due to their chemical similarities and energy difference it was seen that the simultaneous determination of 241 Am, 242 Cm and 24 3 ,244 Cm isotopes is possible using the 243 Am as tracer, once they have peaks in different region of interest (ROI) in the alpha spectrum. In this work it was used tracers, 238 Pu, 243 Am, 244 Cm and 232 U, for determination and quantification of theirs isotopes, respectively. The standard deviations for replicate analysis were calculated and for 241 Am it was (1,040 ± 160 mBqKg -1 ), relative standard deviation 15.38%, and for 239+240 Pu it was (551 +- 44 mBqKg -1 ), relative standard deviation 7.98%. In addition, for the 242 Cm isotope the standard deviation for determinations was(75 ± 23 mBqKg -1 ), with the relative standard deviation 30.67% higher than for 241 Am and 239+240 Pu. The radiometric yields ranged from 90% to 105% and the lower limit of detection was estimated as being 2.05 mBqKg -1 . (author)

  12. Quantitative determination of americium and curium in solutions using potassium tungstophosphate

    International Nuclear Information System (INIS)

    Chistyakov, V.M.; Baranov, A.A.; Erin, E.A.; Timoaeev, G.A.

    1990-01-01

    Two methods of americium (4) and curium (4) titration-replacement and redox ones - have been considered. According to the replacement method thorium nitrate solution was used as a titrant and the final point of titration was determined spectophotometrically. Using the method developed, on the basis of experimental data, the composition of thorium (4) complex with potassium tungstophosphate was determined. In case of the redox titration sodium nitrite was used, and the final titration point was indicated either spectrophotometrically or potentiometrically

  13. In vitro dissolution of curium oxide using a phagolysosomal simulant solvent system

    International Nuclear Information System (INIS)

    Helfinstine, S.Y.; Guilmette, R.A.; Schlapper, G.A.

    1992-01-01

    Detailed study of actinide oxide behavior in alveolar macrophages (AM) in vitro is limited because of the short life span of these cells in culture. We created an in vitro dissolution system that could mimic the acidic phagolysosomal environment for the actinide and be maintained for an indefinite period so that dissolution of more insoluble materials could be measured. The dissolution system for this investigation, consisting of nine different solutions of HCl and the chelating agent diethylenetriamine pentaacetate (DTPA) in distilled water, is called the phagolysosomal simulant solvent (PSS). In this system, both the pH and the amount of DTPA were varied. We could observe the effect of altering pH within a range of 4.0-6.0 (similar to that of the phagolysosome) and the effect of the molar ratio of DTPA to curium at 1000: 1, 100;1, or 10:1. We chose curium sesquioxide ( 244 Cm 2 O 3 ) to validate the PSS for actinide dissolution versus that occurring in AM in vitro because it dissolves significantly in less than 1 week. The polydisperse 244 Cm 2 O 3 aerosol was generated, collected on filters, resuspended, and added to the PSS solutions and to cultured canine AM. By comparing dissolution in the two systems directly, we hoped to arrive at an optimum PSS for future dissolution studies. PSS and cell culture samples were taken daily for 7 days after exposure and tested for the solubilized curium. The amount of soluble material was determined by ultracentrifugation to separate the insoluble CM 2 O 3 from the soluble curium in the PSS solutions and filtration for the cell-containing material. After separating the soluble and insoluble fractions, the samples were analyzed using alpha liquid scintillation counting. Time-dependent dissolution measurements from the PSS/AM showed that the CM 2 O 3 dissolution was similar for both the PSS solutions and the cultured AM. 13 refs., 4 tabs

  14. Spectroscopic and redox properties of curium and californium ions in concentrated aqueous carbonate-bicarbonate media

    International Nuclear Information System (INIS)

    Hobart, D.E.; Varlashkin, P.G.; Samhoun, K.; Haire, R.G.; Peterson, J.R.

    1983-01-01

    Multimilligram quantities of trivalent curium-248 and californium-249 were investigated by absorption spectroscopy, cyclic voltammetry, and bulk solution electrolysis in concentrated aqueous carbonate-bicarbonate solution. Actinide concentrations between 10 -4 and 10 -2 M were studied in 2 M sodium carbonate and 5.5 M potassium carbonate solutions at pH values from 8 to 14. The solution absorption spectra of Cm(III) and Cf(III) in carbonate media are presented for the first time and compared to literature spectra of these species in noncomplexing aqueous solution. It was anticipated that carbonate complexation of the actinide ions could provide a sufficient negative shift in the formal potentials of the M(IV)/M(III) couples of Cm and Cf to permit the generation and stabilization of their tetravalent states in aqueous carbonate-bicarbonate medium. No conclusive evidence was found in the present work to indicate the existence of any higher oxidation states of curium or californium in carbonate solution. Some possible reasons for our inability to generate and detect oxidized species of curium and californium in this medium are discussed

  15. Development of analytical methods for the separation of plutonium, americium, curium and neptunium from environmental samples

    Energy Technology Data Exchange (ETDEWEB)

    Salminen, S.

    2009-07-01

    In this work, separation methods have been developed for the analysis of anthropogenic transuranium elements plutonium, americium, curium and neptunium from environmental samples contaminated by global nuclear weapons testing and the Chernobyl accident. The analytical methods utilized in this study are based on extraction chromatography. Highly varying atmospheric plutonium isotope concentrations and activity ratios were found at both Kurchatov (Kazakhstan), near the former Semipalatinsk test site, and Sodankylae (Finland). The origin of plutonium is almost impossible to identify at Kurchatov, since hundreds of nuclear tests were performed at the Semipalatinsk test site. In Sodankylae, plutonium in the surface air originated from nuclear weapons testing, conducted mostly by USSR and USA before the sampling year 1963. The variation in americium, curium and neptunium concentrations was great as well in peat samples collected in southern and central Finland in 1986 immediately after the Chernobyl accident. The main source of transuranium contamination in peats was from global nuclear test fallout, although there are wide regional differences in the fraction of Chernobyl-originated activity (of the total activity) for americium, curium and neptunium. The separation methods developed in this study yielded good chemical recovery for the elements investigated and adequately pure fractions for radiometric activity determination. The extraction chromatographic methods were faster compared to older methods based on ion exchange chromatography. In addition, extraction chromatography is a more environmentally friendly separation method than ion exchange, because less acidic waste solutions are produced during the analytical procedures. (orig.)

  16. 39 CFR 243.2 - Quarters.

    Science.gov (United States)

    2010-07-01

    ... UNITED STATES POSTAL SERVICE ORGANIZATION AND ADMINISTRATION CONDUCT OF OFFICES § 243.2 Quarters. (a.... Postal Service, General Accounting Office Building, Washington, DC 20260, with a memorandum of... depositing mail in front of or next to the post office. Show collection time schedules on letterboxes. At...

  17. Käibemaksu maksmine maksab 243 miljonit

    Index Scriptorium Estoniae

    2005-01-01

    Poliitikauuringute keskuse PRAXIS uurimus näitas, et Eesti ettevõtetel kulub käibemaksu administreerimisele ja seadustega kursis hoidmisele aastas kokku 243 miljonit krooni, mis võrdub 0,25% SKP-st. Tabel: Suurim kulu ettevõtetele on enda kursishoidmine käibemaksuküsimustes. Vt. samas: Kuidas PRAXIS halduskoormust hindas

  18. Curium Management Studies in France, Japan and USA. A Report by the WPFC Expert Group on Chemical Partitioning of the NEA Nuclear Science Committee - April 2011

    International Nuclear Information System (INIS)

    Yamagishi, Isao; Choi, Yong-Joon; Glatz, Jean-Paul; Hyland, Bronwyn; Uhlir, Jan; Baron, Pascal; Warin, Dominique; DE ANGELIS, Giorgio; LUCE, Alfredo; Inoue, Tadashi; Morita, Yasuji; Minato, Kazuo; Lee, Han Soo; Ignatiev, Victor V.; Kormilitsyn, Mikhail V.; Caravaca, Concepcion; Lewin, Robert g.; Taylor, Robin J.; Collins, Emory D.; Laidler, James J.

    2012-01-01

    Curium is closely associated with americium in irradiated fuels because of their chemical similarity with regard to potential separation requirements, and because americium also requires special shielding and handling requirements due to its gamma radiation emission. Americium is produced in greater mass than curium in irradiated nuclear fuels and the mass ratio can grow exponentially with decay time because of the simultaneous decay of 244 Cm and in-growth of 241 Am from decay of 241 Pu (half-life = 14.4 years). For these reasons, curium management is challenging. Countries that are now engaged in or planning future fuel recycle operations, are considering methods to manage the curium produced and minimise the shielding and handling requirements, as well as the reprocessing requirements for separation of curium from americium France, Japan, and the USA have begun curium management studies. Curium management methods under consideration include (1) separation of curium from americium and storage of curium for several decades to allow 244 Cm to decay substantially to 240 Pu, while moving ahead to recycle americium; (2) recycling of americium and curium without separation; and (3) waiting several decades to reprocess used nuclear fuels, allowing decay minimisation of curium emissions and the requirement for separation of curium from americium, and allowing an alteration of the subsequent transmutation path to reduce the production of curium in recycled used fuels. In this report, recent curium management studies in France, Japan, and the USA have been described. The French studies included scenarios that compared the recycle of ail minor actinides (neptunium, americium, and curium) with the recycle of only neptunium and americium in radial blankets of sodium-cooled fast reactors (SFR). In the latter scenario, curium is separated from americium during used fuel reprocessing and stored for 5000 years to allow 244 Cm to decay to 240 Pu which is then recycled. Even though

  19. Type B investigation report of curium-244 exposure at the ORNL TRU Facility, January 15, 1986

    International Nuclear Information System (INIS)

    Love, G.L.; Butler, H.M.; Duncan, D.T.; Oakes, T.W.

    1986-04-01

    This Type B Investigative Report provides an evaluation of relevant events and activities that led to, were a part of, or resulted from the release of curium-244 in the Building 7920 facility at ORNL in January 1986. Impacts have been evaluated with respect to employee exposures and the costs and loss of productivity resulting from increased bioassay analyses and activities of investigative committees. Management systems evaluated include (1) training of employees performing lab analyses, (2) adherence to procedures, and (3) response to unusual circumstances

  20. 49 CFR 372.243 - Controlling distances and population data.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 5 2010-10-01 2010-10-01 false Controlling distances and population data. 372.243 Section 372.243 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR... EXEMPTIONS, COMMERCIAL ZONES, AND TERMINAL AREAS Commercial Zones § 372.243 Controlling distances and...

  1. 20 CFR 243.4 - Taxation of benefits.

    Science.gov (United States)

    2010-04-01

    ... 20 Employees' Benefits 1 2010-04-01 2010-04-01 false Taxation of benefits. 243.4 Section 243.4 Employees' Benefits RAILROAD RETIREMENT BOARD REGULATIONS UNDER THE RAILROAD RETIREMENT ACT TRANSFER, ASSIGNMENT, OR WAIVER OF PAYMENTS § 243.4 Taxation of benefits. (a) Annuities paid by the Board are subject...

  2. 43 CFR 24.3 - General jurisdictional principles.

    Science.gov (United States)

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false General jurisdictional principles. 24.3 Section 24.3 Public Lands: Interior Office of the Secretary of the Interior DEPARTMENT OF THE INTERIOR FISH AND WILDLIFE POLICY: STATE-FEDERAL RELATIONSHIPS § 24.3 General jurisdictional principles. (a) In...

  3. 12 CFR 24.3 - Public welfare investments.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Public welfare investments. 24.3 Section 24.3... DEVELOPMENT ENTITIES, COMMUNITY DEVELOPMENT PROJECTS, AND OTHER PUBLIC WELFARE INVESTMENTS § 24.3 Public welfare investments. A national bank or national bank subsidiary may make an investment directly or...

  4. Cleanex process: a versatile solvent extraction process for recovery and purification of lanthanides, americium, and curium

    International Nuclear Information System (INIS)

    Bigelow, J.E.; Collins, E.D.; King, L.J.

    1979-01-01

    At a concentration of 1 M in straight-chain hydrocarbon diluent, HDEHP will extract americium, curium, and other trivalent actinide and lanthanide elements from dilute acid or salt solutions. The solute is back-extracted with more concentrated acid, either nitric or hydrochloric. The process has been used in the continuous, countercurrent mode, but its greatest advantage arises in batch extractions where the excess acid can be titrated with NaOH to produce a final acidity of about 0.03 M. Under these conditions, 99% recovery can be achieved, usually in one stage. Cleanex was used on the 50-liter scale at the Transuranium Processing Plant at Oak Ridge for 12 years to provide a broad spectrum cleanup to transuranium elements before applying more sophisticated techniques for separating individual products. The process is also used routinely to recover excessive losses of curium and/or californium from plant waste streams. The solvent system is relatively resistant to radiation damage, being usable up to 200 W-h/liter

  5. Vitrification of F-area americium/curium: feasibility study and preliminary process recommendation

    International Nuclear Information System (INIS)

    Ramsey, W.G.; Miller, D.; Minichan, R.; Coleman, L.; Schumacher, R.; Hardy, B.; Jones, R.

    1994-01-01

    Work was performed to identify a process to vitrify the contents of F- canyon Tank 17.1. Tank 17.1 contains the majority of americium (Am) and curium (Cm) contained in the DOE Complex. Oak Ridge National Laboratory (ORNL) has made a formal request for this material as fuel for production of Cf252 and other transplutonium actinides. The Am and Cm (and associated lanthanide fission products) are currently in nitric acid solution. Transportation of the intensely radioactive Am/Cm in liquid form is not considered possible. As a result, the material will either be solidified and shipped to ORNL or discarded to the Tank Farm. Nuclear Materials Processing Technology (NMPT), therefore, requested Defense Waste Processing Technology (DWPT) to determine if the Tank 17.1 material could be vitrified, and if it was vitrified could the americium and curium be successfully recovered. Research was performed to determine if the Tank 17.1 contents could indeed be mixed with glass formers and vitrified. Additional studies identified critical process parameters such as heat loading, melter requirements, off-gas evolution, etc. Discussions with NMPT personnel were initiated to determine existing facilities where this work could be accomplished safely. A process has been identified which will convert the Am/Cm material into approximately 300kg of glass

  6. Safe handling of kilogram amounts of fuel-grade plutonium and of gram amounts of plutonium-238, americium-241 and curium-244

    International Nuclear Information System (INIS)

    Louwrier, K.P.; Richter, K.

    1976-01-01

    During the past 10 years about 600 glove-boxes have been installed at the Institute for Transuranium Elements at Karlsruhe. About 80% of these glove-boxes have been designed and equipped for handling 100-g to 1-kg amounts of 239 Pu containing 8-12% 240 Pu (low-exposure plutonium). A small proportion of the glove-boxes is equipped with additional shielding in the form of lead sheet or lead glass for work with recycled plutonium. In these glove-boxes gram-amounts of 241 Am have also been handled for preparation of Al-Am targets using tongs and additional shielding inside the glove-boxes themselves. Water- and lead-shielded glove-boxes equipped with telemanipulators have been installed for routine work with gram-amounts of 241 Am, 243 Am and 244 Cm. A prediction of the expected radiation dose for the personnel is difficult and only valid for a preparation procedure with well-defined preparation steps, owing to the fact that gamma dose-rates depend strongly upon proximity and source seize. Gamma radiation dose measurements during non-routine work for 241 Am target preparation showed that handling of gram amounts leads to a rather high irradiation dose for the personnel, despite lead or steel glove-box shielding and shielding within the glove-boxes. A direct glove-hand to americium contact must be avoided. For all glove-handling of materials with gamma radiation an irradiation control of the forearms of the personnel by, for example, thermoluminescence dosimeters is necessary. Routine handling of americium and curium should be executed with master-slave equipment behind neutron and gamma shielding. (author)

  7. Neutron capture cross section of ^243Am

    Science.gov (United States)

    Jandel, M.

    2009-10-01

    The Detector for Advanced Neutron Capture Experiments (DANCE) at Los Alamos National Laboratory (LANL) was used for neutron capture cross section measurement on ^243Am. The high granularity of DANCE (160 BaF2 detectors in a 4π geometry) enables the efficient detection of prompt gamma-rays following neutron capture. DANCE is located on the 20.26 m neutron flight path 14 (FP14) at the Manuel Lujan Jr. Neutron Scattering Center at the Los Alamos Neutron Science Center (LANSCE). The methods and techniques established in [1] were used for the determination of the ^243Am neutron capture cross section. The cross sections were obtained in the range of neutron energies from 0.02 eV to 400 keV. The resonance region was analyzed using SAMMY7 and resonance parameters were extracted. The results will be compared to existing evaluations and calculations. Work was performed under the auspices of the U.S. Department of Energy at Los Alamos National Laboratory by the Los Alamos National Security, LLC under Contract No. DE-AC52-06NA25396 and at Lawrence Livermore National Laboratory by the Lawrence Livermore National Security, LLC under Contract No. DE-AC52-07NA27344. [4pt] [1] M. Jandel et al., Phys. Rev. C78, 034609 (2008)

  8. Total and spontaneous fission half-lives of the americium and curium nuclides

    International Nuclear Information System (INIS)

    Holden, N.E.

    1984-01-01

    The total half-life and the half-life for spontaneous fission are evaluated for the various long-lived nuclides of interest. Recommended values are presented for 241 Am, /sup 242m/Am, 243 Am, 242 Cm, 243 Cm, 244 Cm, 245 Cm, 246 Cm, 247 Cm, 248 Cm, and 250 Cm. The uncertainties are provided at the 95% confidence limit for each of the recommended values

  9. The use of curium neutrons to verify plutonium in spent fuel and reprocessing wastes

    International Nuclear Information System (INIS)

    Miura, N.

    1994-05-01

    For safeguards verification of spent fuel, leached hulls, and reprocessing wastes, it is necessary to determine the plutonium content in these items. We have evaluated the use of passive neutron multiplicity counting to determine the plutonium content directly and also to measure the 240 Pu/ 244 Cm ratio for the indirect verification of the plutonium. Neutron multiplicity counting of the singles, doubles, and triples neutrons has been evaluated for measuring 240 Pu, 244 Cm, and 252 Cf. We have proposed a method to establish the plutonium to curium ratio using the hybrid k-edge densitometer x-ray fluorescence instrument plus a neutron coincidence counter for the reprocessing dissolver solution. This report presents the concepts, experimental results, and error estimates for typical spent fuel applications

  10. Transmutation of americium and curium incorporated in zirconia-based host materials

    International Nuclear Information System (INIS)

    Raison, P.E.

    2001-01-01

    Presented are studies involving the incorporation of americium and curium in zirconia-based materials. First explored was the pseudo ternary system AmO 2 -ZrO 2 -Y 2 O 3 . It was determined that selected Y-CSZ materials can incorporate significant quantities of americium oxide and remain cubic single-phase. The cell parameters of these fluorite-type products were established to be linear with the AmO 2 content. The Cm 2 O 3 -ZrO 2 system was also investigated. It was found that at 25 mol% of CmO 1.5 , the Cm(III) stabilized zirconia in its cubic form (a = 5.21 ±0.01 Angstrom). At higher and lower concentrations, diphasic materials were encountered. At 50 mol% of CmO 1.5 , a pyrochlore oxide - Cm 2 Zr 2 O 7 - is formed (a = 10.63 ±0.02 Angstrom). (author)

  11. Dicty_cDB: VHP243 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available VH (Link to library) VHP243 (Link to dictyBase) - - - Contig-U16236-1 - (Link to Or...iginal site) VHP243F 134 - - - - - - Show VHP243 Library VH (Link to library) Clone ID VHP243 (Link to dicty...Base) Atlas ID - NBRP ID - dictyBase ID - Link to Contig Contig-U16236-1 Original site URL http://dictycdb.b...AXXXXXXXXXX sequence update 2002.10.25 Translated Amino Acid sequence CWPTGIXKTTICT...kilsif*ynfkyyqqpkkk--- Frame B: llaywyxqnnnlyqyyyyfyl*kyflsfniilniinnpkk--- Frame C: CWPTGIXKTTICTNTTIISICKN

  12. Application of curium measurements for safeguarding at reprocessing plants. Study 1: High-level liquid waste and Study 2: Spent fuel assemblies and leached hulls

    International Nuclear Information System (INIS)

    Rinard, P.M.; Menlove, H.O.

    1996-03-01

    In large-scale reprocessing plants for spent fuel assemblies, the quantity of plutonium in the waste streams each year is large enough to be important for nuclear safeguards. The wastes are drums of leached hulls and cylinders of vitrified high-level liquid waste. The plutonium amounts in these wastes cannot be measured directly by a nondestructive assay (NDA) technique because the gamma rays emitted by plutonium are obscured by gamma rays from fission products, and the neutrons from spontaneous fissions are obscured by those from curium. The most practical NDA signal from the waste is the neutron emission from curium. A diversion of waste for its plutonium would also take a detectable amount of curium, so if the amount of curium in a waste stream is reduced, it can be inferred that there is also a reduced amount of plutonium. This report studies the feasibility of tracking the curium through a reprocessing plant with neutron measurements at key locations: spent fuel assemblies prior to shearing, the accountability tank after dissolution, drums of leached hulls after dissolution, and canisters of vitrified high-level waste after separation. Existing pertinent measurement techniques are reviewed, improvements are suggested, and new measurements are proposed. The authors integrate these curium measurements into a safeguards system

  13. 12 CFR 19.243 - Removal, suspension, or debarment.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Removal, suspension, or debarment. 19.243 Section 19.243 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY RULES OF PRACTICE AND PROCEDURE Removal, Suspension, and Debarment of Accountants From Performing Audit Services § 19...

  14. 14 CFR 243.15 - Conflict with foreign laws.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Conflict with foreign laws. 243.15 Section... PROCEEDINGS) ECONOMIC REGULATIONS PASSENGER MANIFEST INFORMATION § 243.15 Conflict with foreign laws. (a) If a... portion of this part is not required because of a conflict with applicable foreign law. [Doc. No. OST-95...

  15. 48 CFR 243.204-70-2 - Price ceiling.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Price ceiling. 243.204-70..., DEPARTMENT OF DEFENSE CONTRACT MANAGEMENT CONTRACT MODIFICATIONS Change Orders 243.204-70-2 Price ceiling. Unpriced change orders shall include a not-to-exceed price. [75 FR 48277, Aug. 10, 2010] ...

  16. A time-resolved laser fluorescence spectroscopy (TRLFS) study of the interaction of trivalent actinides (curium(III)) with calcite

    International Nuclear Information System (INIS)

    Stumpf, Th.; Fanghaenel, Th.

    2002-01-01

    Cm(III) interaction with calcite was investigated in the trace concentration range. Two different Cm(III)/calcite sorption species were found. The first Cm(III) sorption species consists of a curium ion that is bonded onto the calcite surface. The second Cm(III) sorption species has lost its complete hydration sphere and is incorporated into the calcite bulk structure /1/. (orig.)

  17. Gas-Phase Energetics of Actinide Oxides: An Assessment of Neutral and Cationic Monoxides and Dioxides from Thorium to Curium

    Science.gov (United States)

    Marçalo, Joaquim; Gibson, John K.

    2009-09-01

    An assessment of the gas-phase energetics of neutral and singly and doubly charged cationic actinide monoxides and dioxides of thorium, protactinium, uranium, neptunium, plutonium, americium, and curium is presented. A consistent set of metal-oxygen bond dissociation enthalpies, ionization energies, and enthalpies of formation, including new or revised values, is proposed, mainly based on recent experimental data and on correlations with the electronic energetics of the atoms or cations and with condensed-phase thermochemistry.

  18. Interactions of Microbes found at Aespoe Underground Lab with Actinides such as Curium, Plutonium and Uranium

    Energy Technology Data Exchange (ETDEWEB)

    Moll, H.; Merroun, M.; Geipel, G.; Rossberg, A.; Hennig, C.; Selenska-Pobell , S.; Bernhard, G. [Forschungszentrum Dresden-Rossendorf e.V., Inst. fuer Radioc hemie, 01314 Dresden (Germany)]. e-mail: h.moll@fzd.de; Stumpf, Th. [Forschungszentru m Karlsruhe, Inst. fuer Nukleare Entsorgung, 76021 Karlsruhe (Germany)

    2007-06-15

    Sulfate-reducing bacteria (SRB) frequently occur in the deep granitic rock aquifers at the Aespoe Hard Rock Laboratory (Aespoe HRL), Sweden. The new SRB strain Desulfovibrio aespoeensis could be isolated. Results describing the basic interaction mechanisms of uranium, curium, and plutonium with cells of D. aespoeensis DSM 10631T will be presented. The interaction experiments with the actinides showed that the cells are able to remove all three actinides from the surrounding solution. The amount of removed actinide and the interaction mechanism varied among the different actinides. The main U(VI) removal occurred after the first 24 h. The contact time, pH and [U(VI)]initial influence the U removal efficiency. The presence of uranium caused a damaging of the cell membranes. TEM revealed an accumulation of U inside the bacterial cell. D. aespoeensis are able to form U(IV). A complex interaction mechanism takes place consisting of biosorption, bioreduction and bioaccumulation. In the case of {sup 242}Pu, solvent extractions, UV-vis- and XANES spectroscopy were used to determine the speciation of the Pu oxidation states. In the first step, the Pu(VI) and Pu(IV)-polymers are bound to the biomass. Solvent extractions showed that 97 % of the initially present Pu(VI) is reduced to Pu(V) due to the activity of the cells within the first 24 h. Most of the formed Pu(V) dissolves from the cell envelope back to the aqueous solution due to the weak complexing properties of this plutonium oxidation state. In the case of curium at a much lower metal concentration of 3x10{sup -7} M, a pure biosorption of Cm(III) on the cell envelope forming an inner-sphere surface complex most likely with organic phosphate groups was detected. To summarize, the strength of the interaction of D. aespoeensis with the selected actinides at pH 5 and actinide concentrations = 10 mg/L ([Cm] 0.07 mg/L) follows the pattern: Cm > U > Pu >> Np.

  19. Preparation of curium-americium oxide microspheres by resin-bead loading

    International Nuclear Information System (INIS)

    Chattin, F.R.; Benker, D.E.; Lloyd, M.H.; Orr, P.B.; Ross, R.G.; Wiggins, J.T.

    1980-01-01

    Resin-bead loading and calcination techniques have been used to produce all curium and americium oxide feed material (about 2.2 kg) for HFIR targets since 1971. The process based on Dowex 50W resin has progressed from a series of test runs, through special production runs, into routine production in permanent equipment beginning in 1975. Key attributes of this process are its reliability, high yields, and ease of operation. The process is suited for remote operation in hot cells. Yields approaching 95% are routinely obtained and only one unacceptable product has been generated during routine production operations. There have been no problems in fabricating targets from this oxide or in the subsequent irradiation of these targets. The present scale of production of 150 to 250 g/y supplies the present need and is comparable with the level of other chemical process operations at TRU. Since the annual production is accomplished in two 8 to 12 day periods, there has been no reason to consider further scale-up. However, the rate of production could easily be doubled by simply adding a second set of calcination equipment

  20. Transmutation of americium and curium incorporated in zirconia-based host materials

    Energy Technology Data Exchange (ETDEWEB)

    Raison, P.E. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Combustibles; Haire, R.G. [Oak Ridge National Lab., TN (United States)

    2001-07-01

    Presented are studies involving the incorporation of americium and curium in zirconia-based materials. First explored was the pseudo ternary system AmO{sub 2}-ZrO{sub 2}-Y{sub 2}O{sub 3}. It was determined that selected Y-CSZ materials can incorporate significant quantities of americium oxide and remain cubic single-phase. The cell parameters of these fluorite-type products were established to be linear with the AmO{sub 2} content. The Cm{sub 2}O{sub 3}-ZrO{sub 2} system was also investigated. It was found that at 25 mol% of CmO{sub 1.5}, the Cm(III) stabilized zirconia in its cubic form (a = 5.21 {+-}0.01 Angstrom). At higher and lower concentrations, diphasic materials were encountered. At 50 mol% of CmO{sub 1.5}, a pyrochlore oxide - Cm{sub 2}Zr{sub 2}O{sub 7} - is formed (a = 10.63 {+-}0.02 Angstrom). (author)

  1. Transport of plutonium, americium, and curium from soils into plants by roots

    International Nuclear Information System (INIS)

    Pimpl, M.; Schuettelkopf, H.

    1979-12-01

    For assessing the dose from radionuclides in agricultural products by ingestion it is necessary to know the soil to plant transfer factors. The literature was entirely investigated, in order to judge the size of the soil to plant transfer factors. In total, 92 publications - from 1948 to 1978 -have been evaluated. As result, transfer factors from 10 -9 to 10 -3 have been found for Plutonium, and from 10 -6 to 1 for Americium. For Curium only few data are available in literature. The considerable variation of the measured transfer factors is based on the dependence of these transfer factors from the ion exchange capacity of soils, from the amount of organic materials, from the pH-value, and from the mode of contamination. There are, in any case, contradictory data, although there has been detected a dependence of the transfer factors from these parameters. Chelating agenst increase the transfer factors to approximately 1300. As well, fertilizers have an influence on the size of the transfer factors - however, the relationships have been scarcely investigated. The distribution of actinides within the individual parts of plants has been investigated. The highest concentrations are in the roots; in the plant parts above ground the concentration of actinides decreases considerably. The most inferior transfer factors were measured for the respective seed or fruits. The soil to plant transfer factors of actinides are more dependend on the age of the plants within one growing period. At the beginning of the period, the transfer factor is considerably higher than at the end of this period. With respect to plants with a growing period of several years, correlations are unknown. (orig.) [de

  2. Sorption behavior of europium(III) and curium(III) on the cell surfaces of microorganisms

    International Nuclear Information System (INIS)

    Ozaki, T.; Kimura, T.; Ohnuki, T.; Yoshida, Z.; Gillow, J.B.; Francis, A.J.

    2004-01-01

    We investigated the association of europium(III) and curium(III) with the microorganisms Chlorella vulgaris, Bacillus subtilis, Pseudomonas fluorescens, Halomonas sp., Halobacterium salinarum, and Halobacterium halobium. We determined the kinetics and distribution coefficients (K d ) for Eu(III) and Cm(III) sorption at pH 3-5 by batch experiments, and evaluated the number of water molecules in the inner-sphere (N H 2 O ) and the degree of strength of ligand field (R E/M ) for Eu(III) by time-resolved laser-induced fluorescence spectroscopy (TRLFS). Exudates from C. vulgaris, Halomonas sp., and H. halobium had an affinity for Eu(III) and Cm(III). The log K d of Eu(III) and Cm(III) showed that their sorption was not fully due to the exchange with three protons on the functional groups on cell surfaces. The halophilic microorganisms (Halomonas sp., Halobacterium salinarum, H. halobium) showed almost no pH dependence in log K d , indicating that an exchange with Na + on the functional groups was involved in their sorption. The ΔN H 2 O (= 9 - N H 2 O ) for Eu(III) on C. vulgaris was 1-3, while that for the other microorganisms was over 3, demonstrating that the coordination of Eu(III) with C. vulgaris was predominantly an outer-spherical process. The R E/M for Eu(III) on halophilic microorganisms was 2.5-5, while that for non-halophilic ones was 1-2.5. This finding suggests that the coordination environment of Eu(III) on the halophilic microorganisms is more complicated than that on the other three non-halophilic ones. (orig.)

  3. Sorption behavior of europium(III) and curium(III) on the cell surfaces of microorganisms

    Energy Technology Data Exchange (ETDEWEB)

    Ozaki, T.; Kimura, T.; Ohnuki, T.; Yoshida, Z. [Advanced Science Research Center, Japan Atomic Energy Research Inst., Ibaraki (Japan); Gillow, J.B.; Francis, A.J. [Environmental Sciences Dept., Brookhaven National Lab., Upton, NY (United States)

    2004-07-01

    We investigated the association of europium(III) and curium(III) with the microorganisms Chlorella vulgaris, Bacillus subtilis, Pseudomonas fluorescens, Halomonas sp., Halobacterium salinarum, and Halobacterium halobium. We determined the kinetics and distribution coefficients (K{sub d}) for Eu(III) and Cm(III) sorption at pH 3-5 by batch experiments, and evaluated the number of water molecules in the inner-sphere (N{sub H{sub 2}O}) and the degree of strength of ligand field (R{sub E/M}) for Eu(III) by time-resolved laser-induced fluorescence spectroscopy (TRLFS). Exudates from C. vulgaris, Halomonas sp., and H. halobium had an affinity for Eu(III) and Cm(III). The log K{sub d} of Eu(III) and Cm(III) showed that their sorption was not fully due to the exchange with three protons on the functional groups on cell surfaces. The halophilic microorganisms (Halomonas sp., Halobacterium salinarum, H. halobium) showed almost no pH dependence in log K{sub d}, indicating that an exchange with Na{sup +} on the functional groups was involved in their sorption. The {delta}N{sub H{sub 2}O} (= 9 - N{sub H{sub 2}O}) for Eu(III) on C. vulgaris was 1-3, while that for the other microorganisms was over 3, demonstrating that the coordination of Eu(III) with C. vulgaris was predominantly an outer-spherical process. The R{sub E/M} for Eu(III) on halophilic microorganisms was 2.5-5, while that for non-halophilic ones was 1-2.5. This finding suggests that the coordination environment of Eu(III) on the halophilic microorganisms is more complicated than that on the other three non-halophilic ones. (orig.)

  4. Behavior of americium, curium, and certain fission products in fluoride melts in the presence of s olid extraction agents

    International Nuclear Information System (INIS)

    Alekseev, V.A.; Klokman, V.R.; Morozova, Z.E.; Ziv, V.S.

    1986-01-01

    The authors consider the behavior of americium, curium, and certain fission products (europium, cerium, yttrium, and strontium) in fluoride and chlode-fluoride melts in the presence of nonisomorphous solid phases: calcium fluoride and lanthanum and zirconium oxides. It is shown that the trace components enter the solid calcium fluoride in a regular fashion only in the presence of an adequate amount of oxygen in the melt. The effect of oxygen on the coprecipitation with calcium fluoride occurs because oxygen compounds of the elements must be formed in the melt, and these are then coprecipitated with the calcium fluoride

  5. The effect of temperature on the sorption of technetium, uranium, neptunium and curium on bentonite, tuff and granodiorite

    International Nuclear Information System (INIS)

    Baston, G.M.N.; Berry, J.A.; Brownsword, M.; Heath, T.G.; Ilett, D.J.; Tweed, C.J.; Yui, M.

    1997-01-01

    A study of the sorption of the radioelements technetium; uranium; neptunium; and curium onto geological materials has been carried out as part of the PNC program to increase confidence in the performance assessment for a high-level radioactive waste repository in Japan. Batch sorption experiments have been performed in order to study the sorption of the radioelements onto bentonite, tuff and granodiorite from equilibrated de-ionized water under strongly-reducing conditions at both room temperature and at 60 C. Mathematical modelling using the geochemical speciation program HARPHRQ in conjunction with the HATCHES database has been undertaken in order to interpret the experimental results

  6. Determination of americium and curium using ion-exchange in the nitric-acid-methanol medium for environmental analysis

    International Nuclear Information System (INIS)

    Holm, E.; Fukai, R.

    1976-01-01

    While transplutonic elements are only slightly sorbed to anion exchangers from hydrochloric or nitric acid media, the presence of alcohol enhances the anionic exchange of these elements, especially in nitric and sulfuric solutions. In the present work a method has been developed for determining americium and curium in environmental samples, on the basis of the difference between the sorption characteristics to anion exchangers in the acid-methanol system of these transplutonic elements and those of plutonium, polonium and thorium. The method also permits us to perform sequential determination of plutonium, when necessary

  7. Electrochemistry of oxygen-free curium compounds in fused NaCl-2CsCl eutectic

    International Nuclear Information System (INIS)

    Osipenko, A.; Maershin, A.; Smolenski, V.; Novoselova, A.; Kormilitsyn, M.; Bychkov, A.

    2010-01-01

    This work presents the electrochemical study of Cm(III) in fused NaCl-2CsCl eutectic in the temperature range 823-1023 K. Transient electrochemical techniques such as cyclic, differential pulse and square wave voltammetry, and chronopotentiometry have been used in order to investigate the reduction mechanism of curium ions up to the metal. The results obtained show that the reduction reaction takes place in a single step Cm(III)+3e-bar →Cm(0). The diffusion coefficient of [CmCl 6 ] 3- complex ions was determined by cyclic voltammetry at different temperatures by applying the Berzins-Delahay equation. The validity of the Arrhenius law was also verified and the activation energy for diffusion was found to be 44.46 kJ/mol. The apparent standard electrode potential of the redox couple Cm(III)/Cm(0) was found by chronopotentiometry at several temperatures. The thermodynamic properties of curium trichloride have also been calculated.

  8. 48 CFR 52.243-6 - Change Order Accounting.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Change Order Accounting....243-6 Change Order Accounting. As prescribed in 43.205(f), the contracting officer may insert a clause, substantially the same as follows: Change Order Accounting (APR 1984) The Contracting Officer may require change...

  9. 27 CFR 46.243 - Articles at multiple locations.

    Science.gov (United States)

    2010-04-01

    ... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Articles at multiple... Cigarette Tubes Held for Sale on April 1, 2009 Records § 46.243 Articles at multiple locations. The dealer must maintain a list of all places where the dealer holds articles subject to the floor stocks tax...

  10. 5 CFR 531.243 - Promotion of a GM employee.

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false Promotion of a GM employee. 531.243... Promotion of a GM employee. (a) Upon promotion, an employee's status as a GM employee ends, as provided in § 531.241(b). (b) When an employee loses status as a GM employee because of a temporary promotion and is...

  11. 48 CFR 52.243-1 - Changes-Fixed-Price.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Changes-Fixed-Price. 52....243-1 Changes—Fixed-Price. As prescribed in 43.205(e), insert the following clause: Changes—Fixed-Price (AUG 1987) (a) The Contracting Officer may at any time, by written order, and without notice to...

  12. 40 CFR 98.243 - Calculating GHG emissions.

    Science.gov (United States)

    2010-07-01

    ... feedstock). (MWf)i = Molecular weight of gaseous feedstock i (kg/kg-mole). MVC = Molar volume conversion... (CONTINUED) MANDATORY GREENHOUSE GAS REPORTING Petrochemical Production § 98.243 Calculating GHG emissions. (a) If you route all process vent emissions and emissions from combustion of process off-gas to one...

  13. 48 CFR 52.243-2 - Changes-Cost-Reimbursement.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 2 2010-10-01 2010-10-01 false Changes-Cost-Reimbursement....243-2 Changes—Cost-Reimbursement. As prescribed in 43.205(b)(1), insert the following clause. The 30-day period may be varied according to agency procedures. Changes—Cost-Reimbursement (AUG 1987) (a) The...

  14. Experimental and in situ investigations on americium, curium and plutonium behaviour in marine benthic species: transfer from water or sediments

    International Nuclear Information System (INIS)

    Miramand, P.

    1984-06-01

    The tranfer of transuranic elements -americium, curium and plutonium- from the sediments containing them to some marine benthic species (endofauna and epifauna) was studied with a twofold approach - laboratory and in-situ investigation. The experimental investigations, divided into three parts, made it possible to specify concentration factors (F.C.), transfer factors (F.T.) and to understand the process involved for 5 benthic species. The result were refined by an in-situ study that brought new data on the marine distribution of the transuranic elements released by the La Hague plant. Finally, the localization of americium and plutonium in the tissues and cells of these species was determined by autoradiography [fr

  15. Photodissociation of the OD radical at 226 and 243 nm

    International Nuclear Information System (INIS)

    Radenovic, Dragana C.; Roij, Andre J.A. van; Chestakov, Dmitri A.; Eppink, Andre T.J.B.; Meulen, J.J. ter; Parker, David H.; Loo, Mark P.J. van der; Groenenboom, Gerrit C.; Greenslade, Margaret E.; Lester, Marsha I.

    2003-01-01

    The photodissociation dynamics of state selected OD radicals has been examined at 243 and 226 nm using velocity map imaging to probe the angle-speed distributions of the D( 2 S) and O( 3 P 2 ) products. Both experiment and complementary first principle calculations demonstrate that photodissociation occurs by promotion of OD from high vibrational levels of the ground X 2 Π state to the repulsive 1 2 Σ - state

  16. 5 CFR 591.243 - How many members are on each COLA Advisory Committee?

    Science.gov (United States)

    2010-01-01

    ... 5 Administrative Personnel 1 2010-01-01 2010-01-01 false How many members are on each COLA Advisory Committee? 591.243 Section 591.243 Administrative Personnel OFFICE OF PERSONNEL MANAGEMENT CIVIL... Areas Program Administration § 591.243 How many members are on each COLA Advisory Committee? A COLA...

  17. 30 CFR 243.201 - How will MMS determine if I am financially solvent?

    Science.gov (United States)

    2010-07-01

    ... Section by one of the methods in § 243.200(a): (1) A written request asking us to consult a business... active appeals. (d) If you request that we consult a business-information or credit-reporting service or... solvent? 243.201 Section 243.201 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR...

  18. 30 CFR 243.202 - When will MMS monitor my financial solvency?

    Science.gov (United States)

    2010-07-01

    ... you ask us to consult a business-information or credit-reporting service or program under § 243.201(c...? 243.202 Section 243.202 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR MINERALS REVENUE MANAGEMENT SUSPENSIONS PENDING APPEAL AND BONDING-MINERALS REVENUE MANAGEMENT Financial...

  19. 42 CFR 456.243 - Content of medical care evaluation studies.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 4 2010-10-01 2010-10-01 false Content of medical care evaluation studies. 456.243 Section 456.243 Public Health CENTERS FOR MEDICARE & MEDICAID SERVICES, DEPARTMENT OF HEALTH AND HUMAN... Ur Plan: Medical Care Evaluation Studies § 456.243 Content of medical care evaluation studies. Each...

  20. Review of fission product yields and delayed neutron data for the actinides NP-237, PU-242, AM-242M, AM-243, CM-243 and CM-245

    International Nuclear Information System (INIS)

    Mills, R.W.

    1990-07-01

    A review of fission product yields and delayed neutron data for Np-237, Pu-242, Am-242m, Am-243, Cm-243 and Cm-245 has been undertaken. Gaps in understanding and inconsistencies in existing data were identified and priority areas for further experimental, theoretical and evaluation investigation detailed

  1. Americium-241 and -243 as an ion-engine propellant

    International Nuclear Information System (INIS)

    Schachter, M.M.

    1994-01-01

    Commercially available americium-241 and -243 can be obtained as the mixture of the two isotopes in 100-gram quantities--a product of reprocessing spent nuclear powerplant fuel elements along with plutonium. The half-lives of the isotopes are 450 years for the -241 and 8,000 years for the -243 (the plutonium half-life isotope so obtained is 24,000 years). Americium rolled out in thin foil sheets emits alpha-rays (helium-4 ions) and beta-rays--2 valence electrons for each helium ion. Electrons are also considered as ions. As a foil, the americium radiates only a minimal amount of gamma-rays via the Curie effect. With appropriately designed permanent magnet rings insulated with Wood's alloy, the + and - ions can be accelerated from their already 5.5 million electron-Volts to billion and even trillions of electron-Volts by electronic control grids powered by the magnetohydrodynamic effect of electrons and helium ions streaming at the post-rocket nozzle of the ion engine. Protocol for the estimated thrust of this ion rocket engine is more than ten kilograms continuously sustainable for several thousand years

  2. Radiation-chemical behaviour of neptunium ions in nitric acid solutions in the presence of curium-244

    International Nuclear Information System (INIS)

    Frolova, L.M.; Frolov, A.A.; Vasil'ev, V.Ya.

    1984-01-01

    Radiation-chemical behaviour of neptunium ions in nitric acid solutions is studied under the action of intensive internal alpha-irradiation conditioned by curium nuclides. In 0.3-1.1 mol/l solutions of nitric acid radiation-chemical oxidation of neptunium (4) and reduction of neptunium (6) is obeyed to the first order law of reaction rate in respect to neptunium concentration. Effective constants of neptunium (4) oxidation rates and neptuniumi(6) reduction rates are not dependent on neptunium ion in1tial concentration and increase with a growth of a dose rate of alpha-irradiation of solution. In equilibrium only neptunium (5) and neptunium (6) are present in solutions with HNO 3 concentration less than 1 mol/l. In more concentrated solutions equilibrium between sexa-, penta- and tetravalent neptunium forms is established. Equilibrium concentrations of neptunium valent forms are not dependent on neptunium initial oxidation state under the same initial conditions (dose rate, neptunium concentration and acidity. It is shown form experimental data that under the action of alpha-irradiation neptunium (5) both is oxidated to neptunium (6) and is reduced to neptunium (4)

  3. Use of radioanalytical methods for determination of uranium, neptunium, plutonium, americium and curium isotopes in radioactive wastes

    International Nuclear Information System (INIS)

    Geraldo, Bianca

    2012-01-01

    Activated charcoal is a common type of radioactive waste that contains high concentrations of fission and activation products. The management of this waste includes its characterization aiming the determination and quantification of the specific radionuclides including those known as Difficult-to-Measure Radionuclides (RDM). The analysis of the RDM's generally involves complex radiochemical analysis for purification and separation of the radionuclides, which are expensive and time-consuming. The objective of this work was to define a methodology for sequential analysis of the isotopes of uranium, neptunium, plutonium, americium and curium present in a type of radioactive waste, evaluating chemical yield, analysis of time spent, amount of secondary waste generated and cost. Three methodologies were compared and validated that employ ion exchange (TI + EC), extraction chromatography (EC) and extraction with polymers (ECP). The waste chosen was the activated charcoal from the purification system of primary circuit water cooling the reactor IEA-R1. The charcoal samples were dissolved by acid digestion followed by purification and separation of isotopes with ion exchange resins, extraction and chromatographic extraction polymers. Isotopes were analyzed on an alpha spectrometer, equipped with surface barrier detectors. The chemical yields were satisfactory for the methods TI + EC and EC. ECP method was comparable with those methods only for uranium. Statistical analysis as well the analysis of time spent, amount of secondary waste generated and cost revealed that EC method is the most effective for identifying and quantifying U, Np, Pu, Am and Cm present in charcoal. (author)

  4. Evaluation of neutron nuclear data for 243Am

    International Nuclear Information System (INIS)

    Igarasi, Sin-iti; Nakagawa, Tsuneo

    1977-06-01

    Evaluation of neutron nuclear data for 243 Am was performed below 16 MeV. The energy region above 250 eV was separated from the lower region where the resonance parameters were given. Evaluation was made to select suitable resonance parameters, and thermal values of the capture and fission cross sections were obtained with the adopted resonance parameters. An average fission width was assumed to bridge the cross sections at 0.0253 eV and above 250 eV. Using a semi-empirical formula, the fission cross section was reproduced above 250 eV. Optical and statistical model calculations were made in order to obtain the total, capture, inelastic and elastic scattering, and (n,2n) reaction cross sections. (auth.)

  5. Functional annotation of the genome unravels probiotic potential of Bacillus coagulans HS243.

    Science.gov (United States)

    Kapse, N G; Engineer, A S; Gowdaman, V; Wagh, S; Dhakephalkar, P K

    2018-05-30

    Spore forming Bacillus species are widely used as probiotics for human dietary supplements and in animal feeds. However, information on genetic basis of their probiotic action is obscure. Therefore, the present investigation was undertaken to elucidate probiotic traits of B. coagulans HS243 through its genome analysis. Genome mining revealed the presence of an arsenal of marker genes attributed to genuine probiotic traits. In silico analysis of HS243 genome revealed the presence of multi subunit ATPases, ADI pathway genes, chologlycine hydrolase, adhesion proteins for surviving and colonizing harsh gastric transit. HS243 genome harbored vitamin and essential amino acid biosynthetic genes, suggesting the use of HS243 as a nutrient supplement. Bacteriocin producing genes highlighted the disease preventing potential of HS243. Thus, this work established that HS243 possessed the genetic repertoire required for surviving harsh gastric transit and conferring health benefits to the host which were further validated by wet lab evidences. Copyright © 2018. Published by Elsevier Inc.

  6. Motion of the moonlet in the binary system 243 Ida

    Science.gov (United States)

    Lan, L.; Ni, Y.; Jiang, Y.; Li, J.

    2018-02-01

    The motion of the moonlet Dactyl in the binary system 243 Ida is investigated in this paper. First, periodic orbits in the vicinity of the primary are calculated, including the orbits around the equilibrium points and large-scale orbits. The Floquet multipliers' topological cases of periodic orbits are calculated to study the orbits' stabilities. During the continuation of the retrograde near-circular orbits near the equatorial plane, two period-doubling bifurcations and one Neimark-Sacker bifurcation occur one by one, leading to two stable regions and two unstable regions. Bifurcations occur at the boundaries of these regions. Periodic orbits in the stable regions are all stable, but in the unstable regions are all unstable. Moreover, many quasi-periodic orbits exist near the equatorial plane. Long-term integration indicates that a particle in a quasi-periodic orbit runs in a space like a tire. Quasi-periodic orbits in different regions have different styles of motion indicated by the Poincare sections. There is the possibility that moonlet Dactyl is in a quasi-periodic orbit near the stable region I, which is enlightening for the stability of the binary system.

  7. 19 CFR 24.3a - CBP bills; interest assessment; delinquency; notice to principal and surety.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 1 2010-04-01 2010-04-01 false CBP bills; interest assessment; delinquency; notice to principal and surety. 24.3a Section 24.3a Customs Duties U.S. CUSTOMS AND BORDER PROTECTION....3a CBP bills; interest assessment; delinquency; notice to principal and surety. (a) Due date of CBP...

  8. Co-ordination properties of diglycol-amide (DGA) to trivalent curium and lanthanides studied by XAS, XRD and XPS methods

    International Nuclear Information System (INIS)

    Yaita, T.; Hirata, M.; Narita, H.; Tachimori, S.; Yamamoto, H.; Edelstein, N.M.; Bucher, J.J.; Shuh, D.K.; Rao, L.

    2001-01-01

    Co-ordination properties of diglycol-amide (DGA) to trivalent curium and to the trivalent lanthanides were studied by the EXAFS, the XRD and the XPS methods. The structural determinations by both the crystal XRD and the solution EXAFS methods showed that the DGA co-ordinated to the trivalent lanthanide ion in a tridentate fashion: co-ordination of three oxygen atoms of each ligand to the metal ion. The bond distances of Er-O (carbonyl) and Er-O (ether) in the Er-DGA complex were 2.35 Angstrom, and 2.46 Angstrom, respectively, while the atom distances of Cm-O (carbonyl) and Cm-O (ether) in the Cm-DGA complex were 2.42 Angstrom and 3.94 Angstrom, respectively from the EXAFS data for the Cm-DGA complex. Accordingly, the DGA would behave only as a semi-tridentate in the co-ordination to trivalent curium in solution. We determined the valence band structures of the Er-DGA complex by the XPS in order to clarify the bond properties of the complex, and assigned the XPS spectrum by using the DV-DS molecular orbital calculation method. (authors)

  9. 40 CFR 61.243-2 - Alternative standards for valves in VHAP service-skip period leak detection and repair.

    Science.gov (United States)

    2010-07-01

    ... VHAP service-skip period leak detection and repair. 61.243-2 Section 61.243-2 Protection of Environment... AIR POLLUTANTS National Emission Standard for Equipment Leaks (Fugitive Emission Sources) § 61.243-2 Alternative standards for valves in VHAP service—skip period leak detection and repair. (a)(1) An owner or...

  10. 76 FR 13075 - Airworthiness Directives; Airbus Model A330-243F Airplanes

    Science.gov (United States)

    2011-03-10

    ... Airworthiness Directives; Airbus Model A330-243F Airplanes AGENCY: Federal Aviation Administration (FAA... recent in-service event the flight crew of a Trent 700 powered A330 aircraft [[Page 13076

  11. Thermodynamics of curium(III) in concentrated electrolyte solutions: formation of sulfate complexes in NaCl/Na2SO4 solutions

    International Nuclear Information System (INIS)

    Paviet, P.; Fanghaenel, T.; Klenze, R.; Kim, J.I.

    1996-01-01

    The formation of sulfate complexes of Curium in aqueous solutions is studied by time resolved laser fluorescence spectroscopy (TRLFS) at 25 C. The species Cm 3+ , Cm(SO 4 ) - , Cm(SO 4 ) - 2 and Cm(SO 4 ) 3- 3 are quantified spectroscopically in the trace concentration range by peak deconvolution of fluorescence emission spectra. The complex formation equilibria are measured in NaCl/ Na 2 SO 4 solutions of constant ionic strength (3 molal) as a function of the sulfate concentration. The stability constants of Cm(SO 4 ) + and Cm(SO 4 ) - 2 are determined to be log β 1 = 0.93±0.08 and log β 2 = 0.61±0.08, respectively. The complex Cm(SO 4 ) 3- 3 is found to be stable only at very high sulfate concentrations (above 1 molal) and therefore not considered for further evaluation. (orig.)

  12. Erosion and Ejecta Reaccretion on 243 Ida and Its Moon

    Science.gov (United States)

    Geissler, Paul; Petit, Jean-Marc; Durda, Daniel D.; Greenberg, Richard; Bottke, William; Nolan, Michael; Moore, Jeffrey

    1996-03-01

    Galileo images of Asteroid 243 Ida and its satellite Dactyl show surfaces which are dominantly shaped by impact cratering. A number of observations suggest that ejecta from hypervelocity impacts on Ida can be distributed far and wide across the Ida system, following trajectories substantially affected by the low gravity, nonspherical shape, and rapid rotation of the asteroid. We explore the processes of reaccretion and escape of ejecta on Ida and Dactyl using three-dimensional numerical simulations which allow us to compare the theoretical effects of orbital dynamics with observations of surface morphology. The effects of rotation, launch location, and initial launch speed are first examined for the case of an ideal triaxial ellipsoid with Ida's approximate shape and density. Ejecta launched at low speeds (V≪Vesc) reimpact near the source craters, forming well-defined ejecta blankets which are asymmetric in morphology between leading and trailing rotational surfaces. The net effect of cratering at low ejecta launch velocities is to produce a thick regolith which is evenly distributed across the surface of the asteroid. In contrast, no clearly defined ejecta blankets are formed when ejecta is launched at higher initial velocities (V∼Vesc). Most of the ejecta escapes, while that which is retained is preferentially derived from the rotational trailing surfaces. These particles spend a significant time in temporary orbit around the asteroid, in comparison to the asteroid's rotation period, and tend to be swept up onto rotational leading surfaces upon reimpact. The net effect of impact cratering with high ejecta launch velocities is to produce a thinner and less uniform soil cover, with concentrations on the asteroids' rotational leading surfaces. Using a realistic model for the shape of Ida (P. Thomas, J. Veverka, B. Carcich, M. J. S. Belton, R. Sullivan, and M. Davies 1996,Icarus120, 000-000), we find that an extensive color/albedo unit which dominates the

  13. Spectroscopic and thermodynamic studies on the complexation of trivalent curium with inorganic ligands at increased temperatures; Spektroskopische und thermodynamische Untersuchungen zur Komplexierung von trivalentem Curium mit anorganischen Liganden bei erhoehten Temperaturen

    Energy Technology Data Exchange (ETDEWEB)

    Skerencak, Andrej

    2010-05-11

    The subject of the present investigation is the complexation of trivalent actinides at elevated temperatures. The objective of this work is to broaden the comprehension of the geochemical processes relevant for the migration of radionuclides in the near-field of a nuclear waste repository. Depending on the disposed nuclear waste, the temperature in the direct vicinity of a nuclear waste repository may reach up to 200 C. The result is a distinct change of the geochemistry of the actinides. Many of these processes have already been studied in detail at room temperature. Yet, data at elevated temperature are rare. However, a comprehensive long term safety analysis of a nuclear waste repository requires the precise thermodynamic description of the relevant geochemical processes at room as well as at elevated temperatures. The present work is focused on the investigation of the complexation of trivalent curium (Cm(III)) with different inorganic ligands at elevated temperatures. Due to its outstanding spectroscopic properties, Cm(III) is chosen as a representative for trivalent actinides. The studied ligand systems are nitrate (NO{sub 3}{sup -}), fluoride (F{sup -}), sulphate (SO{sub 4}{sup 2-}) and chloride (Cl{sup -}). The main analytical method employed is the ''time resolved laser fluorescence spectroscopy'' (TRLFS). The experiments with nitrate, sulphate and chloride were carried out in a custom-built high temperature cell, enabling spectroscopic studies at temperatures up to 200 C. The Cm(III)-fluoride-system was studied in a cuvette (quartz glass) in the temperature range from 20 to 90 C. Supplementary structural studies were performed using EXAFS (Extended X-Ray Absorption Fine Structure) spectroscopy and supported by quantum chemical calculations at DFT (Density Functional Theory) level. The results of the TRLFS studies show a general shift of the chemical equilibrium towards the complexed species with increasing temperature. For instance

  14. CL316,243, a β3-adrenergic receptor agonist, induces muscle hypertrophy and increased strength.

    Science.gov (United States)

    Puzzo, Daniela; Raiteri, Roberto; Castaldo, Clotilde; Capasso, Raffaele; Pagano, Ester; Tedesco, Mariateresa; Gulisano, Walter; Drozd, Lisaveta; Lippiello, Pellegrino; Palmeri, Agostino; Scotto, Pietro; Miniaci, Maria Concetta

    2016-11-22

    Studies in vitro have demonstrated that β3-adrenergic receptors (β3-ARs) regulate protein metabolism in skeletal muscle by promoting protein synthesis and inhibiting protein degradation. In this study, we evaluated whether activation of β3-ARs by the selective agonist CL316,243 modifies the functional and structural properties of skeletal muscles of healthy mice. Daily injections of CL316,243 for 15 days resulted in a significant improvement in muscle force production, assessed by grip strength and weight tests, and an increased myofiber cross-sectional area, indicative of muscle hypertrophy. In addition, atomic force microscopy revealed a significant effect of CL316,243 on the transversal stiffness of isolated muscle fibers. Interestingly, the expression level of mammalian target of rapamycin (mTOR) downstream targets and neuronal nitric oxide synthase (NOS) was also found to be enhanced in tibialis anterior and soleus muscles of CL316,243 treated mice, in accordance with previous data linking β3-ARs to mTOR and NOS signaling pathways. In conclusion, our data suggest that CL316,243 systemic administration might be a novel therapeutic strategy worthy of further investigations in conditions of muscle wasting and weakness associated with aging and muscular diseases.

  15. Measurement of 24.3 keV activation cross sections with the iron filter technique

    International Nuclear Information System (INIS)

    Rimawi, K.; Chrien, R.E.

    1975-01-01

    By using high-resolution detection techniques, intensities of specific activation lines from 197 Au(n,gamma), 238 U(n,gamma), 127 I(n,gamma), and 115 In(n,gamma) [54 min + 2.2 sec] were recorded, by using the BNL HFBR iron-filtered neutron beam. From a com- parison with the reaction 10 B(n,αgamma), cross sections at 24.3 keV were determined. (24.3 keV neutron activation cross sections, relative 10 B standard). (4 figures) (U.S.)

  16. Pesticides: Benefaction or Pandora's Box? A synopsis of the environmental aspects of 243 pesticides

    NARCIS (Netherlands)

    Linders JBHJ; Jansma JW; Mensink BJWG; Otermann K; ACT

    1994-01-01

    The report provides an overview of physical, chemical and environmental data of 243 pesticides. The data mentioned are based on confidential information supplied by the manufacturers of the pesticides. For all pesticides mentioned a Final Environmental File, which is public, is derived. Tables with

  17. The recycling of the actinides neptunium, americium and curium in a fast power reactor to reduce the long term activity in a final store

    International Nuclear Information System (INIS)

    Beims, H.D.

    1986-01-01

    The starting point for the considerations and calculations given in this dissertation is the inevitable production of radioactive materials in the use of nuclear energy, which creates a considerable potential danger in a final store for a very long period. As one possibility of alleviating this problem, a concept for recycling the waste actinides neptunium, americium and curium was proposed. The waste actinides are separated in the reprocessing of burnt-up fuel elements and reach a further irradiation circuit. There they pass through the stages 'manufacture of irradiation elements', 'use in a fast power reactor' and reprocessing of irradiation elements' several times. In each irradiation and subsequent storage, about 17% of the waste actinides are removed by fission or by conversion into nuclides which can be reused as fuel, so that during the life of 40 years of the fast recycling reacor, the waste actinides can be reduced in mass by one half. In order to determine this mass reduction effect, a model calculation was developed, which includes the representation of the neutron physics and thermal properties of the reactor core and the storage and reprocessing of the irradiation elements. (orig./RB) [de

  18. Type B accident investigation board report of the July 2, 1997 curium intake by shredder operator at Building 513 Lawrence Livermore National Laboratory, Livermore, California. Final report

    International Nuclear Information System (INIS)

    1997-08-01

    On July 2, 1997 at approximately 6:00 A.M., two operators (Workers 1 and 2), wearing approved personal protective equipment (PPE), began a shredding operation of HEPA filters for volume reduction in Building 513 (B-513) at Lawrence Livermore National Laboratory (LLNL). The waste requisitions indicated they were shredding filters containing ≤ 1 μCi of americium-241 (Am-241). A third operator (Worker 3) provided support to the shredder operators in the shredding area (hot area) from a room that was adjacent to the shredding area (cold area). At Approximately 8:00 A.M., a fourth operator (Worker 4) relieved Worker 2 in the shredding operation. Sometime between 8:30 A.M. and 9:00 A.M., Worker 3 left the cold area to make a phone call and set off a hand and foot counter in Building 514. Upon discovering the contamination, the shredding operation was stopped and surveys were conducted in the shredder area. Surveys conducted on the workers found significant levels of contamination on their PPE and the exterior of their respirator cartridges. An exit survey of Worker 1 was conducted at approximately 10:05 A.M., and found contamination on his PPE, as well as on the exterior and interior of his respirator. Contamination was also found on his face, chest, back of neck, hair, knees, and mustache. A nose blow indicated significant contamination, which was later determined to be curium-244

  19. Fast radiochemical procedure to measure neptunium, plutonium, americium and curium in environmental samples for application in environmental monitoring and in radioecology research

    International Nuclear Information System (INIS)

    Pimpel, M.; Schuettelkopf, H.

    1984-01-01

    A radiochemical method is described by which Np, Pu, Am and Cm in environmental samples can be determined. The transuranium elements are dissolved with acids out of the ashed material. Np/Pu is separated from Am/Cm by sequential extraction using TOPO/cyclohexane. The two fractions are radiochemically purified. Np-237, Pu-239+240, Pu-238 and Pu-236 as well as Am-243, Am-241, Cm-244 and Cm-242 are measured by alpha spectrometery. Pu-236, Am-243 and Np-239 are used to determine the respective yields. A fast method of Np-239 preparation is described. The chemical yields range from 60 to 90%. The detection limit attained per nuclide is 10 fCi/sample. 20 reference, 1 table

  20. Critical mass calculations for 241Am, 242mAm and 243Am

    International Nuclear Information System (INIS)

    Dias, Hemanth; Tancock, Nigel; Clayton, Angela

    2003-01-01

    Criticality mass calculations are reported for 241 Am, 242m Am and 243 Am using the MONK and MCNP computer codes with the UKNDL, JEF-2.2, ENDF/B-VI and JENDL-3.2 nuclear data libraries. Results are reported for spheres of americium metal and dioxide in bare, water reflected and steel reflected systems. Comparison of results led to the identification of a serious inconsistency in the 241 Am ENDF/B-VI DICE library used by MONK - this demonstrates the importance of using different codes to verify critical mass calculations. The 241 Am critical mass estimates obtained using UKNDL and ENDF/B-VI show good agreement with experimentally inferred data, whilst both JEF-2.2 and JENDL-3.2 produce higher estimates of critical mass. The computed critical mass estimates for 242m Am obtained using ENDF/B-VI are lower than the results produced using the other nuclear data libraries - the ENDF/B-VI fission cross-section for 242m Am is significantly higher than the other evaluations in the fast region and is not supported by recent experimental data. There is wide variation in the computed 243 Am critical mass estimates suggesting that there is still considerable uncertainty in the 243 Am nuclear data. (author)

  1. Electric resistivity of 241-americium and 244-curium metals. Creation of defects and isochronous annealing of 241-americium metal after self-irradiation

    International Nuclear Information System (INIS)

    Schenkel, R.

    1977-03-01

    The temperature dependence of the electrical resistivity of thin films of bulk 241 Am metal were measured between 300 and 4.5 K. The room temperature resistivity was found to be 68.90μΩcm. At room temperature the electrical resistivity of americium increases with pressure (3% up to 13 kbar). The application of 13 kbar pressure did not change the low temperature power law in the electrical resistivity. The resistivity vs temperature curve can be explained by assuming s-d scattering of conduction electrons. The localized 5f electrons are considered to be about 5eV below the Fermi level. Americium therefore should be the first lanthanide-like element in the actinide series. The defect production due to self-irradiation damage was studied by measuring the increase of the resistivity at 4.2 K over a period of 738 h. A saturation resistivity of 16.036 μΩcm was found corresponding to a defect concentration of about 0.22 a/o. After isochronal annealing two recovery stages were observed at about 65 and 145 K. The two stages shift with increasing initial defect concentration to lower temperatures. Estimates of the activation energies and the reaction order were made and possible defect reactions suggested. The magnetic contribution to the electrical resistivity of curium, which shows an antiferromagnetic transition at 52.5 k, was obtained by subtracting the resistivity of americium (to be considered as phonon part). Comparison with theoretical models were made. At low temperatures the measurements are strongly affected by self-irradiation damage [drho/dt(t=0)=9.8μΩcm/h

  2. Hydration Experiments and Physical Observations at 193 K and 243 K for Mg-Sulfates Relevant to Mars

    Science.gov (United States)

    Vaniman, D. T.; Chipera, S. J.; Carey, J. W.

    2006-03-01

    Hydration of kieserite and amorphous Mg-sulfate at 243 K progresses along simple pathways involving only hexahydrite and kieserite. Kieserite forms a duricrust-like cement, but the anhydrous precursor does not.

  3. Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction

    Energy Technology Data Exchange (ETDEWEB)

    Hatsukawa, Yuichi; Shinohara, Nobuo; Hata, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    The effective thermal neutron cross section of {sup 243}Am(n,{gamma}){sup 244}Am reaction was measured by the activation method. Highly-purified {sup 243}Am target was irradiated in an aluminum capsule by using a research reactor JRR-3M. The tentative effective thermal neutron cross sections are 3.92 b, and 84.44 b for the production of {sup 244g}Am and {sup 244m}Am, respectively. (author)

  4. Measurement of fission cross section with pure Am-243 sample using lead slowing-down spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Katsuhei; Yamamoto, Shuji; Kai, T.; Fujita, Yoshiaki; Yamamoto, Hideki; Kimura, Itsuro [Kyoto Univ. (Japan); Shinohara, Nobuo

    1997-03-01

    By making use of back-to-back type double fission chambers and a lead slowing-down spectrometer coupled to an electron linear accelerator, the fission cross section for the {sup 243}Am(n,f) reaction has been measured relative to that for the {sup 235}U(n,f) reaction in the energy range from 0.1 eV to 10 keV. The measured result was compared with the evaluated nuclear data appeared in ENDF/B-VI and JENDL-3.2, whose evaluated data were broadened by the energy resolution function of the spectrometer. General agreement was seen between the evaluated data and the measurement except that the ENDF/B-VI data were lower in the range from 15 to 60 eV and that the JENDL-3.2 data seemed to be lower above 100 eV. (author)

  5. Evaluation of neutron nuclear data for 241Am and 243Am

    International Nuclear Information System (INIS)

    Kikuchi, Yasuyuki

    1982-08-01

    Neutron nuclear data of 241 Am and 243 Am were evaluated for JENDL-2. Evaluated quantities are the total, elastic and inelastic scattering, fission, capture, (n,2n), (n,3n) and (n,4n) reaction cross sections, the resolved and unresolved resonance parameters, the angular or energy distribution of the emitted neutrons, and the average number of neutrons emitted per fission. The fission cross section was evaluated on the basis of newly measured data, and lower values than JENDL-1 were given in the subthreshold energy region. The reliability of the calculation parameters are also much improved, because experimental data became available for the total and capture cross sections of 241 Am in the high energy region. (author)

  6. Cluster decay channel in 238U + 40Ar (243 MeV)

    International Nuclear Information System (INIS)

    Pyatkov, Yu.V.; Penionzhkevich, Yu.Eh.; Osetrov, O.I.

    1999-01-01

    The reaction 238 U + 40 Ar (E lab = 243 MeV) was studied. For the first time a pronounced fine structure (FS) in the form of distinct peaks has been observed in the mass yields of the fragments of the 278 110 nuclear system decay at the initial excitation of about 60 MeV. The FS peaks are located in the vicinity of the mass numbers A ∼ 70, 100, 130, which are specific for magic nuclei (clusters) of Ni, Ge, Zr, Sn, Sr. The FS peaks contain only low-energy events linked with the very elongated prescission configurations of the system. Some events are observed which can be treated as an indication of ternary fission via such configurations with the appearance of two equal clusters. Hence presumably the collinear cluster tripartition channel is realized observed earlier in the spontaneous fission of 248 Cm and 252 Cf nuclei

  7. Tat protein vaccination of cynomolgus macaques influences SHIV-89.6P cy243 epitope variability.

    Science.gov (United States)

    Ridolfi, Barbara; Genovese, Domenico; Argentini, Claudio; Maggiorella, Maria Teresa; Sernicola, Leonardo; Buttò, Stefano; Titti, Fausto; Borsetti, Alessandra; Ensoli, Barbara

    2008-02-01

    In a previous study we showed that vaccination with the native Tat protein controlled virus replication in five out of seven monkeys against challenge with the simian human immunodeficiency virus (SHIV)-89.6P cy243 and that this protection correlated with T helper (Th)-1 response and cytotoxic T lymphocyte (CTL) activity. To address the evolution of the SHIV-89.6P cy243 both in control and vaccinated infected monkeys, the sequence of the human immunodeficiency virus (HIV)-1 Tat protein and the C2-V3 Env region of the proviral-DNA-derived clones were analyzed in both control and vaccinated but unprotected animals. We also performed analysis of the T cell epitope using a predictive epitope model taking into consideration the phylogeny of the variants. Our results suggest that even though the viral evolution observed in both groups of monkeys was directed toward variations in the major histocompatibility complex (MHC)-I epitopes, in the control animals it was associated with mutational escape of such epitopes. On the contrary, it is possible that viral evolution in the vaccinated monkeys was linked to mutations that arose to keep high the viral fitness. In the vaccinated animals the reduction of epitope variability, obtained prompting the immune system by vaccination and inducing a specific immunological response against virus, was able to reduce the emergence of escape mutants. Thus the intervention of host's selective forces in driving CTL escape mutants and in modulating viral fitness appeared to be different in the two groups of monkeys. We concluded that in the vaccinated unprotected animals, vaccination with the Tat protein induced a broad antiviral response, as demonstrated by the reduced ability to develop escape mutants, which is known to help in the control of viral replication.

  8. Neutron-Induced Fission Cross Section of Uranium, Americium and Curium Isotopes. Progress report - Research Contract 14485, Coordinated Research Project on Minor Actinide Neutron Reaction Data (MANREAD)

    International Nuclear Information System (INIS)

    Alekseev, A.A.; Bergman, A.A.; Berlev, A.I.; Koptelov, E.A.; Samylin, B.F.; Trufanov, A.M.; Fursov, B.I.; Shorin, V.S.

    2009-12-01

    This report contains brief description of the Lead Slowing Down Spectrometer and results of measurements of neutron-induced fission cross sections for 236 U, 242m Am, 243 Cm, 244 Cm, 245 Cm and 246 Cm done at this spectrometer. The work was partially supported through the IAEA research contract RC-14485-RD in the framework of the IAEA Coordinated Research Project 'Minor Actinide Neutron Reaction Data (MANREAD)'. The detailed description of the experimental set up, measurements procedure and data treatment can be found in the JIA-1182 (2007) and JIA-1212 (2009) reports from the Institute of Nuclear Research of the Russian Academy of Science published in Russian. Part 1 contains the first year report of the research contract and part 2 the second year report. (author)

  9. Magnetic susceptibility of curium pnictides

    International Nuclear Information System (INIS)

    Nave, S.E.; Huray, P.G.; Peterson, J.R.; Damien, D.A.; Haire, R.G.

    1981-09-01

    The magnetic susceptibility of microgram quantities of 248 CmP and 248 CmSb has been determined with the use of a SQUID micromagnetic susceptometer over the temperature range 4.2 to 340 K and in the applied magnetic field range of 0.45 to 1600 G. The fcc (NaCl-type) samples yield magnetic transitions at 73K and 162 K for the phosphide and antimonide, respectively. Together with published magnetic data for CmN and CmAs, these results indicate spatially extended exchange interactions between the relatively localized 5f electrons of the metallic actinide atoms

  10. 3-Amino-1,2,4-triazolium ion in [24(3at)]Cl and [24(3at)]2SnCl6·H2O. Comparative X-ray, vibrational and theoretical studies

    Science.gov (United States)

    Daszkiewicz, Marek; Marchewka, Mariusz K.

    2012-09-01

    Crystal structures of 3-amino-1,2,4-triazolium chloride and bis(3-amino-1,2,4-triazolium) hexachloridostannate monohydrate were determined by means of X-ray single crystal diffraction. The route of protonation of organic molecule and tautomer equilibrium constants for the cationic forms were calculated using B3LYP/6-31G* method. The most stable protonated species is 2,4-H2-3-amino-1,2,4-triazolium ion, 24(3at)+. Very good agreement between theoretical and experimental frequencies was achieved due to very weak interactions existing in studied compounds. Significantly weaker intermolecular interactions are found in [24(3at)]2SnCl6·H2O than in [24(3at)]Cl. The differences in strength of interactions are manifested in red and blue shifts for stretching and bending motions, respectively. PED calculations show that for 24(3at)+ ion the stretching type of motion of two Nringsbnd H bonds is independent, whereas bending is coupled.

  11. Measurement of fast neutron induced fission cross sections of 232Th, 238U, 237Np and 243Am

    International Nuclear Information System (INIS)

    Kanda, Kazutaka; Sato, Osamu; Yoshida, Kazuo; Imaruoka, Hiromitsu; Terayama, Hiromichi; Yoshida, Masashi; Hirakawa, Naohiro

    1984-01-01

    Neutron induced fission cross sections of 232 Th, 238 U, 237 Np and 243 Am relative to 235 U were measured in the energy range from 1.5 to 6.6 MeV. The present results are compared with experimental results of others and evaluated data in JENDL-2 and ENDF/B-IV. (author)

  12. Recoil-alpha-fission and recoil-alpha-alpha-fission events observed in the reaction Ca-48 + Am-243

    NARCIS (Netherlands)

    Forsberg, U.; Rudolph, D.; Andersson, L. -L.; Nitto, A. Di; Düllmann, Ch E.; Gates, J. M.; Golubev, P.; Gregorich, K. E.; Gross, C. J.; Herzberg, R. -D.; Hessberger, F. P.; Khuyagbaatar, J.; Kratz, J. V.; Rykaczewski, K.; Sarmiento, L. G.; Schädel, M.; Yakushev, A.; Åberg, S.; Ackermann, D.; Block, M.; Brand, H.; Carlsson, B. G.; Cox, D.; Derkx, X.; Dobaczewski, J.; Eberhardt, K.; Even, J.; Fahlander, C.; Gerl, J.; Jäger, E.; Kindler, B.; Krier, J.; Kojouharov, I.; Kurz, N.; Lommel, B.; Mistry, A.; Mokry, C.; Nazarewicz, W.; Nitsche, H.; Omtvedt, J. P.; Papadakis, P.; Ragnarsson, I.; Runke, J.; Schaffner, H.; Schausten, B.; Shi, Y.; Thörle-Pospiech, P.; Torres, T.; Traut, T.; Trautmann, N.; Türler, A.; Ward, A.; Ward, D. E.; Wiehl, N.

    2016-01-01

    Products of the fusion-evaporation reaction Ca-48 + Am-243 were studied with the TASISpec set-up at the gas-filled separator TASCA at the GSI Helmholtzzentrum f\\"ur Schwerionenforschung. Amongst the detected thirty correlated alpha-decay chains associated with the production of element Z=115, two

  13. Measurement and analysis of the $^{243}$Am neutron capture cross section at the n_TOF facility at CERN

    CERN Document Server

    Mendoza, E; Guerrero, C; Berthoumieux, E; Abbondanno, U; Aerts, G; Alvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Assimakopoulos, P; Audouin, L; Badurek, G; Balibrea, J; Baumann, P; Becvar, F; Belloni, F; Calvino, F; Calviani, M; Capote, R; Carrapico, C; Carrillo de Albornoz, A; Cennini, P; Chepel, V; Chiaveri, E; Colonna, N; Cortes, G; Couture, A; Cox, J; Dahlfors, M; David, S; Dillmann, I; Dolfini, R; Domingo-Pardo, C; Dridi, W; Duran, I; Eleftheriadis, C; Ferrant†, L; Ferrari, A; Ferreira-Marques, R; Fitzpatrick, L; Frais-Koelbl, H; Fujii, K; Furman, W; Goncalves, I; Gonz alez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A; Igashira, M; Isaev, S; Jericha, E; Kappeler, F; Kadi, Y; Karadimos, D; Karamanis, D; Ketlerov, V; Kerveno, M; Koehler, P; Konovalov, V; Kossionides, E; Krticka, M; Lampoudis, C; Leeb, H; Lindote, A; Lopes, I; Lossito, R; Lozano, M; Lukic, S; Marganiec, J; Marques, L; Marrone, S; Martınez, T; Massimi, C; Mastinu, P; Mengoni, A; Milazzo, P M; Moreau, C; Mosconi, M; Neves, F; Oberhummer, H; O’Brien, S; Oshima, M; Pancin, J; Papachristodoulou, C; Papadopoulos, C; Paradela, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perrot, L; Pigni, M T; Plag, R; Plompen, A; Plukis, A; Poch, A; Praena, J; Pretel, C; Quesada, J; Rauscher, T; Reifarth, R; Rosetti, M; Rubbia, C; Rudolf, G; Rullhusen, P; Salgado, J; Santos, C; Sarchiapone, L; Savvidis, I; Stephan, C; Tagliente, G; Tain, J L; Tassan-Got, L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A; Villamarin, D; Vicente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wendler, H; Wiescher, M; Wisshak, K

    2014-01-01

    Background:The design of new nuclear reactors and transmutation devices requires to reduce the present neutron cross section uncertainties of minor actinides. Purpose: Reduce the $^{243}$Am(n,$\\gamma$) cross section uncertainty. Method: The $^{243}$Am(n,$\\gamma$) cross section has been measured at the n_TOF facility at CERN with a BaF$_{2}$ Total Absorption Calorimeter, in the energy range between 0.7 eV and 2.5 keV. Results: The $^{243}$Am(n,$\\gamma$) cross section has been successfully measured in the mentioned energy range. The resolved resonance region has been extended from 250 eV up to 400 eV. In the unresolved resonance region our results are compatible with one of the two incompatible capture data sets available below 2.5 keV. The data available in EXFOR and in the literature has been used to perform a simple analysis above 2.5 keV. Conclusions: The results of this measurement contribute to reduce the $^{243}$Am(n,$\\gamma$) cross section uncertainty and suggest that this cross section is underestimate...

  14. Measurement of the 241Am and the 243Am Neutron Capture Cross Sections at the n_TOF Facility at CERN

    CERN Document Server

    Mendoza, E; Guerrero, C; Altstadt, S; Andrzejewski, J; Audouin, L; Barbagallo, M; Bécares, V; Bečvář, F; Belloni, F; Berthoumieux, E; Billowes, J; Boccone, V; Bosnar, D; Brugger, M; Calviani, M; Calviño, F; Carrapiço, C; Cerutti, F; Chiaveri, E; Chin, M; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Diakaki, M; Domingo-Pardo, C; Duran, I; Dressler, R; Dzysiuk, N; Eleftheriadis, C; Ferrari, A; Fraval, K; Ganesan, S; García, A R; Giubrone, G; Gómez-Hornillos, M B; Gonçalves, I F; González-Romero, E; Griesmayer, E; Gunsing, F; Gurusamy, P; Jenkins, D G; Jericha, E; Kadi, Y; Käppeler, F; Karadimos, D; Kivel, N; Koehler, P; Kokkoris, M; Korschinek, G; Krtička, M; Kroll, J; Langer, C; Lederer, C; Leeb, H; Leong, L S; Losito, R; Manousos, A; Marganiec, J; Martínez, T; Mastinu, P F; Mastromarco, M; Massimi, C; Meaze, M; Mengoni, A; Milazzo, P M; Mingrone, F; Mirea, M; Mondelaers, W; Paradela, C; Pavlik, A; Perkowski, J; Pignatari, M; Plompen, A; Praena, J; Quesada, J M; Rauscher, T; Reifarth, R; Riego, A; Roman, F; Rubbia, C; Sarmento, R; Schillebeeckx, P; Schmidt, S; Schumann, D; Tagliente, G; Tain, J L; Tarrío, D; Tassan-Got, L; Tsinganis, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Versaci, R; Vermeulen, M J; Vlachoudis, V; Vlastou, R; Wallner, A; Ware, T; Weigand, M; Weiß, C; Wright, T J; Žugec, P

    2014-01-01

    The capture cross sections of Am-241 and Am-243 were measured at the n\\_TOF facility at CERN in the epithermal energy range with a BaF2 Total Absorption Calorimeter. A preliminary analysis of the Am-241 and a complete analysis of the Am-243 measurement, including the data reduction and the resonance analysis, have been performed.

  15. Investigating SLIM Disk Solutions FOR HLX-1 IN ESO 243-49

    Science.gov (United States)

    Godet, O.; Plazolles, B.; Kawaguchi, T.; Lasota, J.-P; Barret, d.; Farrell, S. A.; Braito, V.; Servillat, M.; Webb, N.; Gehrels, N.

    2012-01-01

    The hyperluminous X-ray source HLX-1 in the galaxy ESO 243-49, currently the best intermediate-mass blackhole (BH) candidate, displays spectral transitions similar to those observed in Galactic BH binaries, but with aluminosity 100-1000 times higher. We investigated the X-ray properties of this unique source by fitting multiepochdata collected by Swift, XMM-Newton, and Chandra with a disk model computing spectra for a wide rangeof sub- and super-Eddington accretion rates assuming a non-spinning BH and a face-on disk (i=0 deg.). Under theseassumptions we find that the BH in HLX-1 is in the intermediate-mass range (approximately 2 x 10(exp 4) solar mass) and the accretionflow is in the sub-Eddington regime. The disk radiation efficiency is eta = 0.11 plus or minus 0.03. We also show that the source does follow the LX is proportional to T(exp 4) relation for our mass estimate. At the outburst peaks, the source radiates near the Eddington limit. The accretion rate then stays constant around 4 x 10(exp 4) solar mass yr (sup -1) for several days and then decreases exponentially. Such plateaus in the accretion rate could be evidence that enhanced mass-transfer rateis the driving outburst mechanism in HLX-1. We also report on the new outburst observed in 2011 August by theSwift X-Ray Telescope. The time of this new outburst further strengthens the approximately 1 year recurrence timescale.

  16. The influence of impurities for cross section measurement of {sup 241,243}Am(n,f) reactions

    Energy Technology Data Exchange (ETDEWEB)

    Kai, Tetsuya; Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki; Kimura, Itsuro; Miyoshi, Mitsuharu; Yamamoto, Hideki [Kyoto Univ. (Japan); Shinohara, Nobuo

    1997-03-01

    The influence of the impurities on the fission cross section measurements for {sup 241}Am and {sup 243}Am has been investigated with the practical results. Following cases have been considered as the influence of impurities; (a) experiments with the {sup 241}Am sample that contains impurities originally, and (b) experiments with the {sup 243}Am sample that contains impurities produced by {alpha}, {beta} decays after the chemical purification. The present study has demonstrated the usefulness of pure samples by the comparison of the experiments using the sample on the market with those using the pure sample processed by the authors. Particularly on the case (b), the correction of the impurity through the periodical measurements was experimentally performed (about 18% around 0.3 eV in 4 weeks after the chemical purification). (author)

  17. Independent Yields of Kr and Xe Fragments at Photofission of Odd Nuclei ^{237}Np and ^{243}Am

    CERN Document Server

    Gangrsky, Yu P; Myshinskii, G V; Penionzhkevich, Yu E

    2004-01-01

    he independent yields of fragments Kr (A=89-93) and Xe (A=135-142) at photofission of odd nuclei 237Np and 243Am are presented. The experiments were performed using the bremsstrahlung of 25 MeV electrons on the microtron of FLNR, JINR. A technique was used that included the transportation of fragments which escaped from the target with the gas flow through a capillary and the condensation of inert gases in a cryostat at the temperature of liquid nitrogen. Kr and Xe isotopes were identified by the spectra of their daughter products. The mass number distributions of the independent yields of Kr and Xe isotopes and of the complementary fragments (Y and La at the photofission of ^{237}Np and Nb and Pr at the photofission of ^{243}Am) were obtained.

  18. Reaction mechanisms in 24.3 MeV/nucleon 238U induced reactions through a comprehensive study of fission

    International Nuclear Information System (INIS)

    Chbihi, A.; Galin; Guerreau, D.; Lewitowicz, M.; Morjean, M.; Pouthas, J.; Piasecki, E.; Kordyasz, A.; Iwanicki, J.; Jastrzebski, J.; Pienkowski, L.; Crema, E.; Gatty, B.; Jacquet, D.; Muchorowska, M.

    1994-01-01

    Nuclear reaction mechanisms for system characterized by very different asymmetries (U+C, Si, Ni, Au) have been investigated at 24.3 MeV/nucleon, using as observables both the fission products and the neutron multiplicity. It is clearly observed that the fusion process-whatever its completeness- can only occur with rather light target nuclei, indicating the persistence of potential energy effects much above the interaction barrier. (authors). 22 refs., 1 fig

  19. Implications of the delayed 2013 outburst of ESO 243-49 HLX-1

    Energy Technology Data Exchange (ETDEWEB)

    Godet, O.; Webb, N. A. [Institut de Recherche en Astrophysique and Planétologie (IRAP), Université de Toulouse, UPS, 9 Avenue du colonel Roche, F-31028 Toulouse Cedex 4 (France); Lombardi, J. C.; Vingless, J.; Thomas, M. [Department of Physics, Allegheny College, Meadville, PA 16335 (United States); Antonini, F.; Barret, D. [Canadian Institute for Theoretical Astrophysics, University of Toronto, 60 St. George Street, Toronto, Ontario M5S 3H8 (Canada)

    2014-10-01

    After showing four quasi-periodic outbursts spaced by ∼1 yr from 2009 to 2012, the hyper luminous X-ray source ESO 243-49 HLX-1, currently the best intermediate mass black hole (IMBH) candidate, showed an outburst in 2013 delayed by more than a month. In Lasota et al., we proposed that the X-ray light curve is the result of enhanced mass transfer episodes at periapsis from a donor star orbiting the IMBH in a highly eccentric orbit. In this scenario, the delay can be explained only if the orbital parameters can change suddenly from orbit to orbit. To investigate this, we ran Newtonian smooth particle hydrodynamical simulations starting with an incoming donor approaching an IMBH on a parabolic orbit. We survey a large parameter space by varying the star-to-black hole mass ratio (10{sup –5}-10{sup –3}) and the periapsis separation r{sub p} from 2.2 to 2.7r{sub t} with r{sub t} , the tidal radius. To model the donor, we choose several polytropes (Γ = 5/2, n = 3/2, Γ = 3/2, n = 2, Γ = 5/3, n = 2, and Γ = 5/3, n = 3). Once the system is formed, the orbital period decreases until reaching a minimum that may be shallow. Then, the period tends to increase over several periapsis passages due to tidal effects and increasing mass transfer, leading ultimately to the ejection of the donor. We show that the development of stochastic fluctuations inside the donor by adding or removing orbital energy from the system could lead to sudden changes in the orbital period from orbit to orbit with the appropriate order of magnitude to that which has been observed for HLX-1. We also show that given the constraints on the black hole (BH) mass (M {sub BH} > 10{sup 4} M {sub ☉}) and assuming that the HLX-1 system is currently near a minimum in period of ∼1 yr, the donor has to be a white dwarf or a stripped giant core. We predict that if HLX-1 is indeed emerging from a minimum in orbital period, then the period would generally increase with each passage, although substantial

  20. Use of radioanalytical methods for determination of uranium, neptunium, plutonium, americium and curium isotopes in radioactive wastes; Utilizacao de metodos radioanaliticos para a determinacao de isotopos de uranio, plutonio, americio e curio em rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Geraldo, Bianca

    2012-07-01

    Activated charcoal is a common type of radioactive waste that contains high concentrations of fission and activation products. The management of this waste includes its characterization aiming the determination and quantification of the specific radionuclides including those known as Difficult-to-Measure Radionuclides (RDM). The analysis of the RDM's generally involves complex radiochemical analysis for purification and separation of the radionuclides, which are expensive and time-consuming. The objective of this work was to define a methodology for sequential analysis of the isotopes of uranium, neptunium, plutonium, americium and curium present in a type of radioactive waste, evaluating chemical yield, analysis of time spent, amount of secondary waste generated and cost. Three methodologies were compared and validated that employ ion exchange (TI + EC), extraction chromatography (EC) and extraction with polymers (ECP). The waste chosen was the activated charcoal from the purification system of primary circuit water cooling the reactor IEA-R1. The charcoal samples were dissolved by acid digestion followed by purification and separation of isotopes with ion exchange resins, extraction and chromatographic extraction polymers. Isotopes were analyzed on an alpha spectrometer, equipped with surface barrier detectors. The chemical yields were satisfactory for the methods TI + EC and EC. ECP method was comparable with those methods only for uranium. Statistical analysis as well the analysis of time spent, amount of secondary waste generated and cost revealed that EC method is the most effective for identifying and quantifying U, Np, Pu, Am and Cm present in charcoal. (author)

  1. RV SONNE SO243 Cruise Report / Fahrtbericht Guayaquil, Ecuador: 05. October 2015 Antofagasta, Chile: 22. October 2015 SO243 ASTRA-OMZ: AIR SEA INTERACTION OF TRACE ELEMENTS IN OXYGEN MINIMUM ZONES

    OpenAIRE

    Marandino, Christa A.

    2016-01-01

    The ASTRA-OMZ SO243 cruise on board the R/V Sonne took place between the 5th and 22nd October 2015 from Guayaquil, Ecuador to Antofagasta, Chile. Scientists from Germany, the U.S.A, and Norway participated, spanning chemical, biological, and physical oceanography, as well as atmospheric science. The main goal of the cruise was to determine the impact of low oxygen conditions on trace element cycling and distributions, as well as to determine how air-sea exchange of trace elements is influence...

  2. LncRNA CASC2 inhibited the viability and induced the apoptosis of hepatocellular carcinoma cells through regulating miR-24-3p.

    Science.gov (United States)

    Zeng, Fei; Le, Yi-Guan; Fan, Ji-Chang; Xin, Lin

    2017-11-01

    Background Cancer susceptibility candidate 2 (CASC2), a recently discovered long non-coding RNA (lncRNA), was confirmed to play numerous roles in several human cancers. However, the involvement and concrete mechanism of CASC2 in hepatocellular carcinoma (HCC) still need to be further elucidated. Methods The relative expressions of CASC2 and miR-24-3p in HCC tissue and cell lines were determined by quantitative real-time PCR (qRT-PCR). The effects of CASC2 and miR-24-3p on HCC cells were further assessed via cell viability and apoptosis. In vivo tumorigenesis assay was performed to verify the inhibition effect of CASC2 on the tumor growth and further clarify the important role of miR-24-3p in this mechanism. Results Compared with the paired normal tissues, the relative expression of CASC2 significantly reduced in the HCC tissues, while miR-24-3p as determined by qRT-PCR obviously increased in the HCC tissues. This observation was also found in HCC cell lines. Meanwhile, the expression of CASC2 was negatively related to miR-24-3p expression in the HCC tissues (r = -0.804, p cells, but the up-regulation of miR-24-3p greatly eliminated the CASC2-induced effects. The tumorigenesis of HCC cells was restrained significantly by CASC2 overexpression as shown by decreased tumor volume and growth rate. However, miR-24-3p up-regulation rescued the inhibition of CASC2 on the tumor growth in tumor-bearing mice. Conclusion LncRNA CASC2 inhibited the viability and induced the apoptosis of HCC cells through regulating miR-24-3p. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

  3. 2.43 kW narrow linewidth linearly polarized all-fiber amplifier based on mode instability suppression

    Science.gov (United States)

    Su, Rongtao; Tao, Rumao; Wang, Xiaolin; Zhang, Hanwei; Ma, Pengfei; Zhou, Pu; Xu, Xiaojun

    2017-08-01

    We demonstrate an experimental study on scaling mode instability (MI) threshold in fiber amplifiers based on fiber coiling. The experimental results show that coiling the active fiber in the cylindrical spiral shape is superior to the coiling in the plane spiral shape. When the polarization maintained Yb-doped fiber (PM YDF: with a core/inner-cladding diameter of 20/400 µm) is coiled on an aluminous plate with a bend diameter of 9-16 cm, the MI threshold is ~1.55 kW. When such a PM YDF is coiled on an aluminous cylinder with diameter of 9 cm, no MI is observed at the output power of 2.43 kW, which is limited by the available pump power. The spectral width and polarization extinction ratio is 0.255 nm and 18.3 dB, respectively, at 2.43 kW. To the best of our knowledge, this is the highest output power from a linear polarized narrow linewidth all-fiberized amplifier. By using a theoretical model, the potential MI-free scaling capability in such an amplifier is estimated to be 3.5 kW.

  4. Chemical Identification of Dubnium as a Decay Product of Element 115 Produced in the Reaction $\\rm {^{48}Ca}+{^{243}Am}$

    CERN Document Server

    Dmitriev, S N; Utyonkov, V K; Shishkin, S V; Eremin, A V; Lobanov, Yu V; Chepigin, V I; Sokol, E A; Tsyganov, Yu S; Vostokin, G K; Aksenov, N V; Hussonnois, M; Itkis, M G; Aggeler, H W; Schumann, D; Bruchertseifer, H; Eichler, R; Shaughnessy, D A; Wilk, P A; Kenneally, J M; Stoyer, M A; Wild, J F

    2004-01-01

    The results of an experiment designed to identify $^{268}$Db as the terminal isotope in the $\\alpha $-decay chain of element 115 produced via the ${\\rm {^{243}Am}}({\\rm {^{48}Ca}},3n){\\rm {^{288}115}}$ reaction are presented. The $^{243}$Am target was bombarded with a beam dose of $3.4\\cdot 10^{18}$ $^{48}$Ca projectiles at an energy of 247 MeV at the center of the target. The reaction products were collected in the surface layer of a copper catcher block, which was removed with a lathe and then dissolved in concentrated HNO$_{3}$. The group-5 elements were separated by sorption onto Dowex $50{\\times} 8$ cation-exchange resin with subsequent desorption using 1 M HF, which forms anionic fluoride complexes of group-5 elements. The eluent was evaporated onto a 0.4 $\\mu$m thick polyethylene foil that was placed between a pair of semiconductor detectors surrounded by $^{3}$He neutron counters for measurement of $\\alpha$ particles, fission fragments, and neutrons. In the course of the experiment, we observed 15 spo...

  5. miR-24-3p/FGFR3 Signaling as a Novel Axis Is Involved in Epithelial-Mesenchymal Transition and Regulates Lung Adenocarcinoma Progression

    Directory of Open Access Journals (Sweden)

    Pengyu Jing

    2018-01-01

    Full Text Available Our previous studies showed that Fibroblast growth factor receptor 3 (FGFR3 contributed to cell growth in lung cancer. However, the correlation between FGFR3 and tumor progression, coupled with the underlying mechanisms, are not fully understood. The clinical significance of FGFR3 was determined in two cohorts of clinical samples (n=22, n=78. A panel of biochemical assays and functional experiments was utilized to elucidate the underlying mechanisms and effects of FGFR3 and miR-24-3p on lung adenocarcinoma progression. Upregulated FGFR3 expression indicated an adverse prognosis for lung adenocarcinoma individuals and promoted metastatic potential of lung adenocarcinoma cells. Owing to the direct regulation towards FGFR3, miR-24-3p could interfere with the potential of proliferation, migration, and invasion in lung adenocarcinoma, following variations of EMT-related protein expression. As a significant marker of EMT, E-cadherin was negatively correlated with FGFR3, of which ectopic overexpression could neutralize the antitumour effects of miR-24-3p and reverse its regulatory effects on EMT markers. Taken together, these findings define a novel insight into the miR-24-3p/FGFR3 signaling axis in regulating lung adenocarcinoma progression and suggest that targeting the miR-24-3p/FGFR3 axis could be an effective and efficient way to prevent tumor progression.

  6. Investigating the Role of the Post-transcriptional Gene Regulator MiR-24-3p in the Proliferation, Migration and Apoptosis of Human Arterial Smooth Muscle Cells in Arteriosclerosis Obliterans

    Directory of Open Access Journals (Sweden)

    Xiao-feng Zhu

    2015-07-01

    Full Text Available Aims: To explore the expression of miR-24-3p in human arteries with arteriosclerosis obliterans (ASO as well as the role of miR-24-3p in the pathogenesis of ASO. Methods: We used quantitative real-time PCR (qRT-PCR and in situ hybridization to monitor miR-24-3p expression in human arteries. To investigate the effect of miR-24-3p on human arterial smooth muscle cells (HASMCs, we applied cell counting and EdU assays to monitor proliferation and transwell and wound healing assays to investigate migration and flow cytometry to investigate apoptosis. Furthermore, we applied 3'-untranslated region (3'-UTR luciferase assays to investigate the role of miR-24-3p in targeting platelet-derived growth factor receptor B (PDGFRB and c-Myc. Results: MiR-24-3p was mainly located in the media of arteries and was downregulated in ASO arteries compared with normal arteries. Platelet-derived growth factor BB (PDGF-BB treatment reduced the expression of miR-24-3p in primary cultured HASMCs. MiR-24-3p mimic oligos inhibited the proliferation and migration, and promotes apoptosis of HASMCs. Our 3'-UTR luciferase assays confirmed that PDGFRB and c-Myc were targets of miR-24-3p. Conclusion: The results suggest that miR-24-3p regulates the proliferation and migration of HASMCs by targeting PDGFRB and c-Myc. The PDGF/miR-24-3p/PDGFRB and PDGF/miR-24-3p/c-Myc pathways may play critical roles in the pathogenesis of ASO. These findings highlight the potential for new therapeutic targets for ASO.

  7. Partial monosomy 8q and partial trisomy 9q due to the maternal translocation t(8;9(q24.3;q34.1)

    DEFF Research Database (Denmark)

    Tos, T; Alp, M Y; Eker, H K

    2014-01-01

    Partial trisomy 9q34-qter and partial monosomy 8q24.3-qter are very rare chromosomal abnormalities. Characteristic features of partial trisomy 9q34-qter are hypotonia, developmental delay, mild intellectual disability, dolichocephaly, distinct facial phenotype, long and thin fingers, and cardiac...

  8. Enhanced anticaries efficacy of a 0.243% sodium fluoride/10% xylitol/silica dentifrice: 3-year clinical results.

    Science.gov (United States)

    Sintes, J L; Escalante, C; Stewart, B; McCool, J J; Garcia, L; Volpe, A R; Triol, C

    1995-10-01

    To evaluate the efficacy of a sodium fluoride (NaF)/silica/xylitol dentifrice compared with that of a positive control NaF/silica dentifrice on caries increments in school children over a 3-year period in an area without an optimal level of fluoride in the drinking water (mean level schools in the San Jose, Costa Rica metropolitan area. Clinical dental examinations were performed at participating schools utilizing portable dental equipment. Caries evaluations employed conventional tactile/visual methodology consisting of artificial light, dental mirrors and single-edge #23 explorers. Children accepted into the study were stratified by age and sex into two balanced groups within each school, and randomly assigned to use either a positive control dentifrice containing 0.243% NaF/silica or a test dentifrice containing 0.234% NaF/silica/10% xylitol. Children were instructed to brush with the assigned dentifrice twice daily. Caries evaluations were conducted at baseline, 2 years, and 3 years. After 3 years, subjects using the 0.234% NaF/silica/10% xylitol dentifrice had statistically significantly reduced decayed/filled surfaces (DFS; -12.3% reduction; P < or = 0.001) and decayed/filled buccal and lingual surfaces (DFS-BL; -10.5% reduction; P < or = 0/01).

  9. Neutron capture cross section measurements of $^{238}$U, $^{241}$Am and $^{243}$Am at n_TOF

    CERN Multimedia

    Koehler, P E; Plag, R

    The increase of the world energy demand and the need of low carbon energy sources have triggered the renaissance and/or enhancement of nuclear energy in many countries. Fundamental nuclear physics can contribute in a practical way to the sustainability and safety of the nuclear energy production and the management of the nuclear waste. There exists a series of recent studies which address the most relevant isotopes, decay data, nuclear reaction channels and energy ranges which have to be investigated in more detail for improving the design of different advanced nuclear systems [1] and nuclear fuel cycles [2]. In this proposal, we aim at the measurement of the neutron capture cross sections of $^{238}$U, $^{241}$Am and $^{243}$Am. All three isotopes are listed in the NEA High Priority Request List [37], are recommended for measurements [1] and play an important role in the nuclear energy production and fuel cycle scenarios. The measurements will provide as well valuable nuclear structure data necessary for the...

  10. Neutron capture and fission cross section of Americium-243 in the energy range from 5 to 250 keV

    International Nuclear Information System (INIS)

    Wisshak, K.; Kaeppeler, F.

    1983-04-01

    The neutron capture and subthreshold fission cross section of 243 Am was measured in the energy range from 5 to 250 keV using 197 Au and 235 U as the respective standards. Neutrons were produced via the 7 Li(p,n) and the T(p,n) reaction with the Karlsruhe 3-MV pulsed Van de Graaff accelerator. Capture events were detected by two MoxonRae detectors with graphite and bismuthgraphite converters, respectively. Fission events were registered by a NE-213 liquid scintillator with pulse-shape discriminator equipment. Flight paths as short as 50-70 mm were used to obtain optimum signal-to-background ratio. After correction for the different efficiency of the individual converter materials the capture cross section could be determined with a total uncertainty of 3-6%. The respective values for the fission cross section are 8-12%. The results are compared to predictions of recent evaluations, which in some cases are severely discrepant. (orig.)

  11. Experiments on the Synthesis of Element 115 in the Reaction ^{243}Am (^{48}Ca, xn)^{291-x}115

    CERN Document Server

    Oganessian, Yu T; Lobanov, Yu V; Abdullin, F S; Polyakov, A N; Shirokovsky, I V; Tsyganov, Yu S; Gulbekyan, G G; Bogomolov, S L; Mezentsev, A N; Iliev, S; Subbotin, V G; Sukhov, A M; Voinov, A A; Buklanov, G V; Subotic, K M; Zagrebaev, V I; Itkis, M G; Patin, J B; Moody, K J; Wild, J F; Stoyer, M A; Stoyer, N J; Shaughnessy, D A; Kenneally, J M; Lougheed, R W

    2003-01-01

    The results of experiments designed to synthesize element 115 isotopes in the ^{243}Am(^{48}Ca,xn)^{291-x}115 reaction are presented. With a beam dose of 4.3\\cdot 10^{18} 248-Mev ^{48}Ca projectiles, we observed three similar decay chains consisting of five consecutive alpha-decays, all detected in time intervals of about 20 s and terminated at a later time by a spontaneous fission with a high energy release (TKE \\sim 220 MeV). At a higher bombarding energy of 253 MeV, with an equal ^{48}Ca beam dose, we registered a different decay chain of four consecutive alpha-decays detected in a time interval of about 0.5 s, also terminated by spontaneous fission. The alpha-decay energies and half-lives for nine new alpha-decaying nuclei were determined. The decay properties of these synthesized nuclei are consistent with consecutive alpha-decays originating from the parent isotopes of the new element 115, ^{288}115 and ^{287}115, produced in the 3n- and 4n-evaporation channels with cross sections of about 3 and 1 pb, r...

  12. Measurement of the 243Am capture cross section at the n{sub T}OF facility; Medida de la sección eficaz de captura del 243Am en la instalación n{sub T}OF

    Energy Technology Data Exchange (ETDEWEB)

    Mendoza Cembranos, E.

    2014-07-01

    Nuclear data for minor actinides are necessary for improving the design and performance of advanced reactors and transmutation devices for the incineration of radioactive nuclear waste [Sal08, Gon09, Ali04, Ali06]. In particular, the 243Am isotope is relevant since it is the minor actinide which contributes more to the radiotoxicity of the nuclear waste between s3 03 and s3 04 years. In addition, the neutron capture in 243Am is the main gate to the creation of 244Cm and higher mass isotopes. The purpose of the this work is to provide experimental data on the 243Am(n, ) for improving the current evaluations. At present, there is no published neutron capture measurement of 243Am below 250 eV, and all the existing evaluations of the elastic and capture cross sections are based essentially on a single transmission measurement [Sim74]. Above 250 eV there are only a few capture measurements available [Wes85, Wis83], which show discrepancies that make them incompatible. Due to the lack of experimental data on 243Am the standard ENDF-6 format libraries present sizeable di rences between each other...(Author)

  13. 243 ORIGINAL ARTICLE

    African Journals Online (AJOL)

    boaz

    Isolates were identified as A. baumannii using API 20NE and E-test was used to define IRAB. Out of 146 A. ... L'étude des facteurs de risque associe à l'infection IRAB est d'une importance capitale ..... Pimentel JD1, Low J, Styles K, Harris OC,.

  14. pmker 24(3)

    African Journals Online (AJOL)

    HP Pro 2000

    L. AFOUDA1, H. BAIMEY2, F. X. BACHABI2, D. H. SERO-KPERA1 et R. BALOGOUN1. 1Faculté ... rates ranging from 20 to 95 % 6 days after exposure. The effect of extracts was found ... integrated management of Meloidogyne spp. Keywords ...

  15. Fission-product yields for thermal-neutron fission of 243Cm determined from measurements with a high-resolution low-energy germanium gamma-ray detector

    International Nuclear Information System (INIS)

    Merriman, L.D.

    1984-04-01

    Cumulative fission-product yields have been determined for 13 gamma rays emitted during the decay of 12 fission products created by thermal-neutron fission of 243 Cm. A high-resolution low-energy germanium detector was used to measure the pulse-height spectra of gamma rays emitted from a 77-nanogram sample of 243 Cm after the sample had been irradiated by thermal neutrons. Analysis of the data resulted in the identification and matching of gamma-ray energies and half-lives to individual radioisotopes. From these results, 12 cumulative fission product yields were deduced for radionuclides with half-lives between 4.2 min and 84.2 min. 7 references

  16. In vitro evaluation of Lactobacillus crispatus K313 and K243: high-adhesion activity and anti-inflammatory effect on Salmonella braenderup infected intestinal epithelial cell.

    Science.gov (United States)

    Sun, Zhilan; Huang, Lihua; Kong, Jian; Hu, Shumin; Zhang, Xiaowei; Kong, Wentao

    2012-09-14

    Currently, there is an increasing interest in the use of probiotics as an alternative strategy to antimicrobial compounds. In this study, two high adhesive strains Lactobacillus crispatus K313 adhering to HT-29 cells as well as Lb. crispatus K243 adhering to collagen type IV were isolated from chicken intestines. SDS-PAGE analysis revealed the presence of the potential S-proteins SlpA and SlpB in Lb. crispatus K243 and K313. SlpA and SlpB, rich in hydrophobic amino acids, were proved to be involved in adhering to collagen type IV and HT-29 cells, respectively, based on the LiCl treatment assay. After removal of S-proteins, the viability and tolerance of the two Lb. crispatus strains to simulated gastric and small intestinal juice were reduced, indicating the protective role of S-proteins against the hostile environments. Lb. crispatus K313 exhibited the stronger autoaggregation ability and inhibitive activity against Salmonella braenderup H9812 adhesion to HT-29 cells than the strain K243. To elucidate the inhibitive mechanism, cultured epithelial cells were exposed with Lb. crispatus strains, and followed by a challenge with S. braenderup H9812. The pro-inflammatory signaling factors (IL-8, CXCL1 and CCL20) from HT-29 were detected by real-time PCR technology. The results showed that both of Lb. crispatus strains down-regulated the transcription level of those pro-inflammatory genes induced by S. braenderup H9812 by 36.2-58.8%. ELISA analysis was further confirmed that Lb. crispatus K243 and K313 inhibited the IL-8 secretion triggered by S. braenderup H9812 by 32.8% and 47.0%, indicating that the two isolates could attenuate the pro-inflammatory signaling induced by S. braenderup H9812, and have the potential application in clinical practice to prevent diarrhea. Copyright © 2012 Elsevier B.V. All rights reserved.

  17. Backbone and sidechain methyl Ile (δ1), Leu and Val chemical shift assignments of RDE-4 (1-243), an RNA interference initiation protein in C. elegans.

    Science.gov (United States)

    Chiliveri, Sai Chaitanya; Kumar, Sonu; Marelli, Udaya Kiran; Deshmukh, Mandar V

    2012-10-01

    The RNAi pathway of several organisms requires presence of double stranded RNA binding proteins for functioning of Dicer in gene regulation. In C. elegans, a double stranded RNA binding protein, RDE-4 (385 aa, 44 kDa) recognizes long exogenous dsRNA and initiates the RNAi pathway. We have achieved complete backbone and stereospecific methyl sidechain Ile (δ1), Leu and Val chemical shifts of first 243 amino acids of RDE-4, namely RDE-4ΔC.

  18. Decay properties of Bk97243 and Bk97244

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, I.; Kondev, F. G.; Greene, J. P.; Zhu, S.

    2018-01-01

    Electron capture decays of Bk-243 and Bk-244 have been studied by measuring the gamma-ray spectra of mass-separated sources and level structures of Cm-243 and Cm-244 have been deduced. In Cm-243, the electron capture population to the ground state, 1/2(+)[631], and 1/2(+)[620] Nilsson states have been observed. The octupole K-pi = 2(-) band was identified in Cm-244 at 933.6 keV. In addition, spins and parities were deduced for several other states and two-quasiparticle configurations have been tentatively assigned to them

  19. (-)-P7C3-S243 Protects a Rat Model of Alzheimer's Disease From Neuropsychiatric Deficits and Neurodegeneration Without Altering Amyloid Deposition or Reactive Glia.

    Science.gov (United States)

    Voorhees, Jaymie R; Remy, Matthew T; Cintrón-Pérez, Coral J; El Rassi, Eli; Khan, Michael Z; Dutca, Laura M; Yin, Terry C; McDaniel, Latisha N; Williams, Noelle S; Brat, Daniel J; Pieper, Andrew A

    2017-11-06

    In addition to cognitive deficits, Alzheimer's disease (AD) is associated with other neuropsychiatric symptoms, including severe depression. Indeed, depression often precedes cognitive deficits in patients with AD. Unfortunately, the field has seen only minimal therapeutic advances, underscoring the critical need for new treatments. P7C3 aminopropyl carbazoles promote neuronal survival by enhancing nicotinamide adenine dinucleotide flux in injured neurons. Neuroprotection with P7C3 compounds has been demonstrated in preclinical models of neurodegeneration by virtue of promoting neuronal survival independently of early disease-specific pathology, resulting in protection from cognitive deficits and depressive-like behavior. We hypothesize that P7C3 compounds might be uniquely applicable to patients with AD, given the comorbid presentation of depression and cognitive deficits. Aging male and female wild-type and TgF344-AD rats, a well-characterized preclinical AD model, were administered (-)-P7C3-S243 daily for 9 and 18 months, beginning at 6 months of age. Behavioral phenotypes related to cognition and depression were assessed at 15 and 24 months, and brain pathology and biochemistry were assessed at 24 months. (-)-P7C3-S243 safely protected aging male and female wild-type and TgF344-AD rats from cognitive deficits and depressive-like behavior. Depressive-like behavior occurred earlier than cognitive deficits in TgF344-AD rats, consistent with AD in many patients. Treatment with (-)-P7C3-S243 blocked neurodegeneration in TgF344-AD rats, without altering amyloid deposition or indicators of neuroinflammation. Neuronal cell death-specific treatment approaches, such as P7C3 compounds, may represent a new treatment approach for patients experiencing the combination of cognitive deficits and depression associated with AD. Published by Elsevier Inc.

  20. Interstitial deletion of 14q24.3-q32.2 in a male patient with plagiocephaly, BPES features, developmental delay, and congenital heart defects

    DEFF Research Database (Denmark)

    Cingöz, Sultan; Bache, Iben; Bjerglund, Lise

    2011-01-01

    Distal interstitial deletions of chromosome 14 involving the 14q24-q23.2 region are rare, and only been reported so far in 20 patients. Ten of these patients were analyzed both clinically and genetically. Here we present a de novo interstitial deletion of chromosome 14q24.3-q32.2 in a male patient...... on genotype-phenotype comparisons of the 10 previously published patients and the present case, we suggest that the shortest regions for deletion overlap may include candidate genes for speech impairment, mental retardation, and hypotonia....

  1. Remaining Sites Verification Package for the 600-243 Petroleum-Contaminated Soil Bioremediation Pad. Attachment to Waste Site Reclassification Form 2007-033

    International Nuclear Information System (INIS)

    Capron, J.M.

    2008-01-01

    The 600-243 waste site consisted of a bioremediation pad for petroleum-contaminated soils resulting from the 1100 Area Underground Storage Tank (UST) upgrades in 1994. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River

  2. Thermal neutron capture cross-section measurements of 243Am and 242Pu using the new mini-INCA α- and γ-spectroscopy station

    International Nuclear Information System (INIS)

    Marie, F.; Letourneau, A.; Fioni, G.; Deruelle, O.; Veyssiere, Ch.; Faust, H.; Mutti, P.; AlMahamid, I.; Muhammad, B.

    2006-01-01

    In the framework of the Mini-INCA project, dedicated to the study of Minor Actinide transmutation process in high neutron fluxes, an α- and γ-spectroscopy station has been developed and installed at the High Flux Reactor of the Laue-Langevin Institut. This set-up allows short irradiations as well as long irradiations in a high quasi-thermal neutron flux and post-irradiation spectroscopy analysis. It is well suited to measure precisely, in reference to 59 Co cross-section, neutron capture cross-sections, for all the actinides, in the thermal energy region. The first measurements using this set-up were done on 243 Am and 242 Pu isotopes. Cross-section values, at E n =0.025eV, were found to be (81.8+/-3.6)b for 243 Am and (22.5+/-1.1)b for 242 Pu. These values differ from evaluated data libraries by a factor of 9% and 17%, respectively, but are compatible with the most recent measurements, validating by the way the experimental apparatus

  3. The production of {sup 238-242}Pu(n,γ){sup 239-243}Pu fissionable fluids in a fusion-fission hybrid reactor

    Energy Technology Data Exchange (ETDEWEB)

    Guenay, Mehtap [Inoenue Univ., Malatya (Turkey). Physics Dept.

    2014-03-15

    In this study, the effect of spent fuel grade plutonium content on {sup 239-243}Pu was investigated in a designed hybrid reactor system. In this system, the fluids were composed of a molten salt, heavy metal mixture with increased mole fractions 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-Pu, 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-PuF{sub 4}, 99-95 % Li{sub 20}Sn{sub 80}-1-5 % SFG-PuO{sub 2}. Beryllium (Be) is a neutron multiplier by (n,2n) reactions. Thence, a Be zone of 3 cm thickness was used in order to contribute to fissile fuel breeding between the liquid first wall and a 9Cr2WVTa ferritic steel blanket which is used as structural material. The production of {sup 238-242}Pu(n,γ){sup 239-243}Pu was calculated in liquid first wall, blanket and shielding zones. Three-dimensional nucleonic calculations were performed by using the most recent version MCNPX-2.7.0 Monte Carlo code and nuclear data library ENDF/B-VII.0. (orig.)

  4. De novo 14q24.2q24.3 microdeletion including IFT43 is associated with intellectual disability, skeletal anomalies, cardiac anomalies, and myopia.

    Science.gov (United States)

    Stokman, Marijn F; Oud, Machteld M; van Binsbergen, Ellen; Slaats, Gisela G; Nicolaou, Nayia; Renkema, Kirsten Y; Nijman, Isaac J; Roepman, Ronald; Giles, Rachel H; Arts, Heleen H; Knoers, Nine V A M; van Haelst, Mieke M

    2016-06-01

    We report an 11-year-old girl with mild intellectual disability, skeletal anomalies, congenital heart defect, myopia, and facial dysmorphisms including an extra incisor, cup-shaped ears, and a preauricular skin tag. Array comparative genomic hybridization analysis identified a de novo 4.5-Mb microdeletion on chromosome 14q24.2q24.3. The deleted region and phenotype partially overlap with previously reported patients. Here, we provide an overview of the literature on 14q24 microdeletions and further delineate the associated phenotype. We performed exome sequencing to examine other causes for the phenotype and queried genes present in the 14q24.2q24.3 microdeletion that are associated with recessive disease for variants in the non-deleted allele. The deleted region contains 65 protein-coding genes, including the ciliary gene IFT43. Although Sanger and exome sequencing did not identify variants in the second IFT43 allele or in other IFT complex A-protein-encoding genes, immunocytochemistry showed increased accumulation of IFT-B proteins at the ciliary tip in patient-derived fibroblasts compared to control cells, demonstrating defective retrograde ciliary transport. This could suggest a ciliary defect in the pathogenesis of this disorder. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

  5. The use of isotopic correlation technique for determination of sup(241)Am and sup(243)Am concentration in nuclear irradiated fuels

    International Nuclear Information System (INIS)

    Souza Sarkis, J.E. de.

    1990-01-01

    In the last years the isotopic correlation technique is emerging as a powerful tool for the determination of concentration and isotopic composition of heavy nuclides in the nuclear fuel cycle. Accordingly, this technique has gained significant importance for the safeguard of the nuclear materials as well as for the accounting and build up of actinides elements in the irradiated nuclear fuels. In this work 42 isotopic correlations between the nuclides sup(241)Am and sup(243)Am and post irradiation isotopic data of 7 samples from fuel element BE-124 and 1 sample from fuel element BE-120 from the Obrigheim pressurized water nuclear power reactor, Federal Republic of Germany, were proposed. These isotopic correlations allowed to estimate the isotopic concentrations of sup(241)Am and sup(243)Am with an average deviation, relative to the experimental data obtained from isotopic dilution mass spectrometry technique, of 10%. These results are more precise than those found using the computer code ORIGEN 2 demonstrating the great potential of this technique for the determination of isotopic concentration and build up of those nuclides in irradiated nuclear fuels. The analytical and other experimental aspects of the post irradiation isotopic analysis of nuclear fuels are also discussed. (author)

  6. Fission Cross-section Measurements of (233)U, (245)Cm and (241,243)Am at CERN n_TOF Facility

    CERN Document Server

    Calviani, M; Andriamonje, S; Chiaveri, E; Vlachoudis, V; Colonna, N; Meaze, M H; Marrone, S; Tagliente, G; Terlizzi, R; Belloni, F; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C; Aerts, G; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A; Alvarez, H; Duran, I; Paradela, C; Alvarez-Velarde, F; Cano-Ott, D; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Villamarin, D; Vicente, M C; Andrzejewski, J; Marganiec, J; Assimakopoulos, P; Karadimos, D; Karamanis, D; Papachristodoulou, C; Patronis, N; Audouin, L; David, S; Ferrant, L; Isaev, S; Stephan, C; Tassan-Got, L; Badurek, G; Jericha, E; Leeb, H; Oberhummer, H; Pigni, M T; Baumann, P; Kerveno, M; Lukic, S; Rudolf, G; Becvar, F; Krticka, M; Calvino, F; Capote, R; Carrillo De Albornoz, A; Marques, L; Salgado, J; Tavora, L; Vaz, P; Cennini, P; Dahlfors, M; Ferrari, A; Gramegna, F; Herrera-Martinez, A; Kadi, Y; Mastinu, P; Praena, J; Sarchiapone, L; Wendler, H; Chepel, V; Ferreira-Marques, R; Goncalves, I; Lindote, A; Lopes, I; Neves, F; Cortes, G; Poch, A; Pretel, C; Couture, A; Cox, J; O'brien, S; Wiescher, M; Dillman, I; Heil, M; Kappeler, F; Mosconi, M; Plag, R; Voss, F; Walter, S; Wisshak, K; Dolfini, R; Rubbia, C; Domingo-Pardo, C; Tain, J L; Eleftheriadis, C; Savvidis, I; Frais-Koelbl, H; Griesmayer, E; Furman, W; Konovalov, V; Goverdovski, A; Ketlerov, V; Haas, B; Haight, R; Reifarth, R; Igashira, M; Koehler, P; Kossionides, E; Lampoudis, C; Lozano, M; Quesada, J; Massimi, C; Vannini, G; Mengoni, A; Oshima, M; Papadopoulos, C; Vlastou, R; Pavlik, A; Pavlopoulos, P; Plompen, A; Rullhusen, P; Rauscher, T; Rosetti, M; Ventura, A

    2011-01-01

    Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.

  7. Estimation of Ni63, Pu241, Pu242 and Am243 from Co60, Pu239, and Cm244 activities in groundwater samples

    International Nuclear Information System (INIS)

    Holcomb, H.P.

    1993-01-01

    The Part B Permit for F ampersand H Seepage Basins calls for analysis of several constituents of concern in groundwater monitoring wells. Four of these analytes are the radionuclides Ni 63 , Pu 241 , Pu 242 , and Am 243 . These are currently not being analyzed due to their very difficult, tedious analytical schemes coupled with their relatively low activity values. This report demonstrates how the activity value for Ni 63 , a week beta emitter, can be estimated from that of Co 60 , an easily detectable, high-energy gamma emitter. Similarly, estimates of Pu 241 , a beta emitter, and the alpha-emitting Pu 242 can be made from the activity value of the more easily detected Pu 239 . Am 243 can be estimated from the activity of Cm 244 , which is easier to detect because of a shorter half-life (higher specific activity) and the emission of higher energy alpha particles. These correlations are made under very specific parameters in order to ensure the validity of this approach. Therefore, assumptions must be established setting ground rules for establishing these activity relationships. Bases for these assumptions are explained and/or referenced. Their degree of uncertainty limits the accuracy of the data so that the term ''estimate'' is used. Such soundly-based, conservative estimates for these four rads can provide a tool for evaluating any hazards from their presence over the next several years. Hopefully, during this time, sufficient advances will be made in their radiochemical analyses and in counting techniques so that in the future, their activities may be quantitatively determined more easily and also more cost effectively

  8. Monozygotic twins with a de novo 0.32 Mb 16q24.3 deletion, including TUBB3 presenting with developmental delay and mild facial dysmorphism but without overt brain malformation

    DEFF Research Database (Denmark)

    Grønborg, Sabine; Kjaergaard, Susanne; Hove, Hanne

    2015-01-01

    been associated with missense mutations in this group of genes. Here, we report two patients, monozygotic twins, carrying a de novo 0.32 Mb deletion of chromosome 16q24.3 including the TUBB3 gene. The patients presented with global developmental delay, mild facial dysmorphism, secondary microcephaly...

  9. Intellectual disability, muscle weakness and characteristic face in three siblings: A newly described recessive syndrome mapping to 3p24.3-p25.3.

    Science.gov (United States)

    Kariminejad, Ariana; Nafissi, Shahriar; Nilipoor, Yalda; Tavasoli, Alireza; Van Veldhoven, Paul P; Bonnard, Carine; Ng, Yeng Ting; Majoie, Charles B; Reversade, Bruno; Hennekam, Raoul C

    2015-11-01

    We report on a sister and two brothers born to healthy Iranian parents with mild intellectual disability, progressive muscle weakness, and characteristic facies. including highly arched eyebrows, down-slanting palpebral fissures, prominent nasal bridge, prominent nose, columella extending below alae nasi, narrow mouth, narrow palate, and dental caries, and in one of them an inability to abduct the left eye. Electrophysiological studies showed signs of myopathy, and muscle biopsies demonstrated only nonspecific signs. Brain MRIs in two of the sibs showed leukencephalopathy with delayed myelination, frontal and parietal hyperintensities, and hippocampal atrophy in one. We have been unable to find a description of this association of features in literature. Based on the occurrence in siblings, no significant difference in phenotype between the brothers and sister, absence of manifestations in parents, and a likely consanguinity between parents we performed a homozygosity mapping. A single identical-by-descent bloc encompassing 57 genes located at 3p24.3-p25.3 was found to segregate within the family with this phenotype. © 2015 Wiley Periodicals, Inc. © 2015 Wiley Periodicals, Inc.

  10. Genome-wide linkage scan for maximum and length-dependent knee muscle strength in young men: significant evidence for linkage at chromosome 14q24.3.

    Science.gov (United States)

    De Mars, G; Windelinckx, A; Huygens, W; Peeters, M W; Beunen, G P; Aerssens, J; Vlietinck, R; Thomis, M A I

    2008-05-01

    Maintenance of high muscular fitness is positively related to bone health, functionality in daily life and increasing insulin sensitivity, and negatively related to falls and fractures, morbidity and mortality. Heritability of muscle strength phenotypes ranges between 31% and 95%, but little is known about the identity of the genes underlying this complex trait. As a first attempt, this genome-wide linkage study aimed to identify chromosomal regions linked to muscle and bone cross-sectional area, isometric knee flexion and extension torque, and torque-length relationship for knee flexors and extensors. In total, 283 informative male siblings (17-36 years old), belonging to 105 families, were used to conduct a genome-wide SNP-based multipoint linkage analysis. The strongest evidence for linkage was found for the torque-length relationship of the knee flexors at 14q24.3 (LOD = 4.09; p<10(-5)). Suggestive evidence for linkage was found at 14q32.2 (LOD = 3.00; P = 0.005) for muscle and bone cross-sectional area, at 2p24.2 (LOD = 2.57; p = 0.01) for isometric knee torque at 30 degrees flexion, at 1q21.3, 2p23.3 and 18q11.2 (LOD = 2.33, 2.69 and 2.21; p<10(-4) for all) for the torque-length relationship of the knee extensors and at 18p11.31 (LOD = 2.39; p = 0.0004) for muscle-mass adjusted isometric knee extension torque. We conclude that many small contributing genes rather than a few important genes are involved in causing variation in different underlying phenotypes of muscle strength. Furthermore, some overlap in promising genomic regions were identified among different strength phenotypes.

  11. Association of the −243A>G, +61450C>A Polymorphisms of the Glutamate Decarboxylase 2 (GAD2) Gene with Obesity and Insu¬lin Level in North Indian Population

    OpenAIRE

    Jai PRAKASH; Balraj MITTAL; Shally AWASTHI; Neena SRIVASTAVA

    2016-01-01

    Background: Obesity associated with type 2 diabetes, and hypertension increased mortality and morbidity. Glutamate decarboxylase 2 (GAD2) gene is associated with obesity and it regulate food intake and insulin level. We investigated the association of GAD-2gene −243A>G (rs2236418) and +61450C>A (rs992990) polymorphisms with obesity and related phenotypes.Methods: Insulin, glucose and lipid levels were estimated using standard protocols. All subjects were genotyped (PCR-RFLP) method.Resu...

  12. Viscosity of n-hexadecane, n-octadecane and n-eicosane at pressures up to 243 MPa and temperatures up to 534 K

    International Nuclear Information System (INIS)

    Baled, Hseen O.; Xing, Dazun; Katz, Harrison; Tapriyal, Deepak; Gamwo, Isaac K.; Soong, Yee; Bamgbade, Babatunde A.; Wu, Yue; Liu, Kun; McHugh, Mark A.; Enick, Robert M.

    2014-01-01

    Highlights: • A novel windowed Inconel rolling-ball viscometer is designed and used by our team. • Viscosity data are reported for n-hexadecane, n-octadecane, and n-eicosane at high temperatures and pressures. • The viscosity results are compared with the available literature data. • The viscosity results are modeled with the free volume theory model. - Abstract: Viscosity data are reported for n-hexadecane (C16), n-octadecane (C18), and n-eicosane (C20) at pressures between (3 and 243) MPa and temperatures between (304 and 534) K. These extreme conditions are representative of those encountered in ultra-deep petroleum formations beneath the deepwaters of the Gulf of Mexico. The measurements are taken with a novel windowed Inconel rolling-ball viscometer designed by our team that is calibrated with n-decane. A comparison of the reported viscosity values with the available literature data that cover limited pressure and temperature ranges, shows that the mean absolute percentage deviation, δ, ranges between 1.1% and 4.8%. The reported data extend the database of viscosity to the high-temperature, high-pressure region where most gaps occur in the literature data for n-hexadecane and n-octadecane. To the best of our knowledge, the results for n-eicosane are the first reported viscosity values at pressures above 2 MPa over the entire temperature range. The viscosity results are modeled with the free volume theory model in conjunction with density values obtained using the Peng–Robinson equation of state (EoS) and the PC-SAFT EoS. The δ values obtained with this model range from 2.0% to 3.5%. The data are also correlated by a non-linear surface fit as a simultaneous function of temperature and pressure that yields δ values of 0.40%, 0.43%, and 0.38% for C16, C18, and C20, respectively

  13. A DETAILED GRAVITATIONAL LENS MODEL BASED ON SUBMILLIMETER ARRAY AND KECK ADAPTIVE OPTICS IMAGING OF A HERSCHEL-ATLAS SUBMILLIMETER GALAXY AT z = 4.243 {sup ,} {sup ,}

    Energy Technology Data Exchange (ETDEWEB)

    Bussmann, R. S.; Gurwell, M. A. [Harvard-Smithsonian Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States); Fu Hai; Cooray, A. [Department of Physics and Astronomy, University of California, Irvine, CA 92697 (United States); Smith, D. J. B.; Bonfield, D.; Dunne, L. [Centre for Astrophysics, Science and Technology Research Institute, University of Hertfordshire, Hatfield, Herts AL10 9AB (United Kingdom); Dye, S.; Eales, S. [School of Physics and Astronomy, University of Nottingham, University Park, Nottingham NG7 2RD (United Kingdom); Auld, R. [Cardiff University, School of Physics and Astronomy, Queens Buildings, The Parade, Cardiff CF24 3AA (United Kingdom); Baes, M.; Fritz, J. [Sterrenkundig Observatorium, Universiteit Gent, Krijgslaan 281 S9, B-9000 Gent (Belgium); Baker, A. J. [Department of Physics and Astronomy, Rutgers, the State University of New Jersey, 136 Frelinghuysen Road, Piscataway, NJ 08854-8019 (United States); Cava, A. [Departamento de Astrofisica, Facultad de CC. Fisicas, Universidad Complutense de Madrid, E-28040 Madrid (Spain); Clements, D. L.; Dariush, A. [Imperial College London, Blackett Laboratory, Prince Consort Road, London SW7 2AZ (United Kingdom); Coppin, K. [Department of Physics, McGill University, Ernest Rutherford Building, 3600 Rue University, Montreal, Quebec, H3A 2T8 (Canada); Dannerbauer, H. [Universitaet Wien, Institut fuer Astronomie, Tuerkenschanzstrasse 17, 1180 Wien, Oesterreich (Austria); De Zotti, G. [Universita di Padova, Dipto di Astronomia, Vicolo dell' Osservatorio 2, IT 35122, Padova (Italy); Hopwood, R., E-mail: rbussmann@cfa.harvard.edu [Department of Physics and Astronomy, Open University, Walton Hall, Milton Keynes, MK7 6AA (United Kingdom); and others

    2012-09-10

    We present high-spatial resolution imaging obtained with the Submillimeter Array (SMA) at 880 {mu}m and the Keck adaptive optics (AO) system at the K{sub S}-band of a gravitationally lensed submillimeter galaxy (SMG) at z = 4.243 discovered in the Herschel Astrophysical Terahertz Large Area Survey. The SMA data (angular resolution Almost-Equal-To 0.''6) resolve the dust emission into multiple lensed images, while the Keck AO K{sub S}-band data (angular resolution Almost-Equal-To 0.''1) resolve the lens into a pair of galaxies separated by 0.''3. We present an optical spectrum of the foreground lens obtained with the Gemini-South telescope that provides a lens redshift of z{sub lens} = 0.595 {+-} 0.005. We develop and apply a new lens modeling technique in the visibility plane that shows that the SMG is magnified by a factor of {mu} = 4.1 {+-} 0.2 and has an intrinsic infrared (IR) luminosity of L{sub IR} = (2.1 {+-} 0.2) Multiplication-Sign 10{sup 13} L{sub Sun }. We measure a half-light radius of the background source of r{sub s} = 4.4 {+-} 0.5 kpc which implies an IR luminosity surface density of {Sigma}{sub IR} (3.4 {+-} 0.9) Multiplication-Sign 10{sup 11} L{sub Sun} kpc{sup -2}, a value that is typical of z > 2 SMGs but significantly lower than IR luminous galaxies at z {approx} 0. The two lens galaxies are compact (r{sub lens} Almost-Equal-To 0.9 kpc) early-types with Einstein radii of {theta}{sub E1} 0.57 {+-} 0.01 and {theta}{sub E2} = 0.40 {+-} 0.01 that imply masses of M{sub lens1} = (7.4 {+-} 0.5) Multiplication-Sign 10{sup 10} M{sub Sun} and M{sub lens2} = (3.7 {+-} 0.3) Multiplication-Sign 10{sup 10} M{sub Sun }. The two lensing galaxies are likely about to undergo a dissipationless merger, and the mass and size of the resultant system should be similar to other early-type galaxies at z {approx} 0.6. This work highlights the importance of high spatial resolution imaging in developing models of strongly lensed galaxies

  14. Impaction grafting in the femur in cementless modular revision total hip arthroplasty: a descriptive outcome analysis of 243 cases with the MRP-TITAN revision implant

    Directory of Open Access Journals (Sweden)

    Wimmer Matthias D

    2013-01-01

    Full Text Available Abstract Background We present a descriptive and retrospective analysis of revision total hip arthroplasties (THA using the MRP-TITAN stem (Peter Brehm, Weisendorf, GER with distal diaphyseal fixation and metaphyseal defect augmentation. Our hypothesis was that the metaphyseal defect augmentation (Impaction Bone Grafting improves the stem survival. Methods We retrospectively analyzed the aggregated and anonymized data of 243 femoral stem revisions. 68 patients with 70 implants (28.8% received an allograft augmentation for metaphyseal defects; 165 patients with 173 implants (71.2% did not, and served as controls. The mean follow-up was 4.4 ± 1.8 years (range, 2.1–9.6 years. There were no significant differences (p > 0.05 between the study and control group regarding age, body mass index (BMI, femoral defects (types I-III as described by Paprosky, and preoperative Harris Hip Score (HHS. Postoperative clinical function was evaluated using the HHS. Postoperative radiologic examination evaluated implant stability, axial implant migration, signs of implant loosening, periprosthetic radiolucencies, as well as bone regeneration and resorption. Results There were comparable rates of intraoperative and postoperative complications in the study and control groups (p > 0.05. Clinical function, expressed as the increase in the postoperative HHS over the preoperative score, showed significantly greater improvement in the group with Impaction Bone Grafting (35.6 ± 14.3 vs. 30.8 ± 15.8; p ≤ 0.05. The study group showed better outcome especially for larger defects (types II C and III as described by Paprosky and stem diameters ≥ 17 mm. The two groups did not show significant differences in the rate of aseptic loosening (1.4% vs. 2.9% and the rate of revisions (8.6% vs. 11%. The Kaplan-Meier survival for the MRP-TITAN stem in both groups together was 93.8% after 8.8 years. [Study group 95.7% after 8.54 years ; control group 93

  15. Separation and recovery of Cm from Cm-Pu mixed oxide samples containing Am impurity

    International Nuclear Information System (INIS)

    Hirokazu Hayashi; Hiromichi Hagiya; Mitsuo Akabori; Yasuji Morita; Kazuo Minato

    2013-01-01

    Curium was separated and recovered as an oxalate from a Cm-Pu mixed oxide which had been a 244 Cm oxide sample prepared more than 40 years ago and the ratio of 244 Cm to 240 Pu was estimated to 0.2:0.8. Radiochemical analyses of the solution prepared by dissolving the Cm-Pu mixed oxide in nitric acid revealed that the oxide contained about 1 at% of 243 Am impurity. To obtain high purity curium solution, plutonium and americium were removed from the solution by an anion exchange method and by chromatographic separation using tertiary pyridine resin embedded in silica beads with nitric acid/methanol mixed solution, respectively. Curium oxalate, a precursor compound of curium oxide, was prepared from the purified curium solution. 11.9 mg of Cm oxalate having some amounts of impurities, which are 243 Am (5.4 at%) and 240 Pu (0.3 at%) was obtained without Am removal procedure. Meanwhile, 12.0 mg of Cm oxalate (99.8 at% over actinides) was obtained with the procedure including Am removals. Both of the obtained Cm oxalate sample were supplied for the syntheses and measurements of the thermochemical properties of curium compounds. (author)

  16. Actinide production from xenon bombardments of curium-248

    International Nuclear Information System (INIS)

    Welch, R.B.

    1985-01-01

    Production cross sections for many actinide nuclides formed in the reaction of 129 Xe and 132 Xe with 248 Cm at bombarding energies slightly above the coulomb barrier were determined using radiochemical techniques to isolate these products. These results are compared with cross sections from a 136 Xe + 248 Cm reaction at a similar energy. When compared to the reaction with 136 Xe, the maxima in the production cross section distributions from the more neutron deficient projectiles are shifted to smaller mass numbers, and the total cross section increases for the production of elements with atomic numbers greater than that of the target, and decreases for lighter elements. These results can be explained by use of a potential energy surface (PES) which illustrates the effect of the available energy on the transfer of nucleons and describes the evolution of the di-nuclear complex, an essential feature of deep-inelastic reactions (DIR), during the interaction. The other principal reaction mechanism is the quasi-elastic transfer (QE). Analysis of data from a similar set of reactions, 129 Xe, 132 Xe, and 136 Xe with 197 Au, aids in explaining the features of the Xe + Cm product distributions, which are additionally affected by the depletion of actinide product yields due to deexcitation by fission. The PES is shown to be a useful tool to predict the general features of product distributions from heavy ion reactions

  17. LARGE SCALE METHOD FOR THE PRODUCTION AND PURIFICATION OF CURIUM

    Science.gov (United States)

    Higgins, G.H.; Crane, W.W.T.

    1959-05-19

    A large-scale process for production and purification of Cm/sup 242/ is described. Aluminum slugs containing Am are irradiated and declad in a NaOH-- NaHO/sub 3/ solution at 85 to 100 deg C. The resulting slurry filtered and washed with NaOH, NH/sub 4/OH, and H/sub 2/O. Recovery of Cm from filtrate and washings is effected by an Fe(OH)/sub 3/ precipitation. The precipitates are then combined and dissolved ln HCl and refractory oxides centrifuged out. These oxides are then fused with Na/sub 2/CO/sub 3/ and dissolved in HCl. The solution is evaporated and LiCl solution added. The Cm, rare earths, and anionic impurities are adsorbed on a strong-base anfon exchange resin. Impurities are eluted with LiCl--HCl solution, rare earths and Cm are eluted by HCl. Other ion exchange steps further purify the Cm. The Cm is then precipitated as fluoride and used in this form or further purified and processed. (T.R.H.)

  18. Gastrointestinal absorption of neptunium and curium in humans

    International Nuclear Information System (INIS)

    Popplewell, D.S.; Harrison, J.D.; Ham, G.J.

    1991-01-01

    The gastrointestinal absorption of Np and Cm has been determined in five male adult volunteers. The Np and Cm, which were in citrate solution, were taken with food. An initial experiment with each individual determined the fraction of each element excreted in the urine following intravenous administration. Subsequently, the results for urinary excretion for the two routes of administration were used to calculate the fractional absorption (f1) of ingested Np and Cm. The mean f1 values were: Np (2.0 +/- 0.2) X 10 - 4 , range (1.2-2.9) X 10 - 4 , and Cm (1.7 +/- 0.3) X 10 - 4 , range (0.95-3.0) X 10 - 4 , the quoted uncertainties being the standard error of the means. Currently, the International Commission on Radiological Protection recommends a value of 10 - 3 for both elements. Cumulative urinary excretion over 1 wk after intravenous injection accounted for about 20%-40% of administered Np and 7%-10% of Cm. At the conclusion of the experiment, the total committed effective dose equivalent for each volunteer was calculated to be in the range 130-250 microSv, based on the individual f1 values, and, in some cases, a knowledge of the rate of clearance of 239 Np through the gut as measured by whole-body counting

  19. Interaction of europium and curium with alpha-amylase

    Energy Technology Data Exchange (ETDEWEB)

    Barkleit, Astrid [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Div. Chemistry of the F-Elements; Heller, Anne [Technische Univ. Dresden (Germany). Inst. for Zoology, Molecular Cell Physiology and Endocrinology; Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Div. Biogeochemistry

    2016-07-01

    Time-resolved laser-induced fluorescence spectroscopy (TRLFS) revealed that Eu(III) and Cm(III) form two dominant species with the protein α-amylase (Amy): one with the coordination of a single carboxylate group of the protein and the other with three coordinating carboxylate groups.

  20. Removal of americium and curium from high-level wastes

    International Nuclear Information System (INIS)

    Bond, W.D.; Leuze, R.E.

    1979-01-01

    The DHDECMP process was demonstrated to give a 99.5% removal of actinides from actual HLLW in small-scale, batch extraction tests. Results from cold tests indicate that it may be possible to carry out the oxalate precipitation step of the OPIX process continuously. About 90% recovery of the trivalent actinides and lanthanides can be achieved in the continuous precipitation. the presence of zirconium impurity in feed solutions to Talspeak process at concentrations of 10 -4 M (0.5% of the Zr in the original waste) affected phase separations but equipment could be operated satisfactory in cold tests. Zirconium concentrations of 10 -3 M seriously affected phase separations and substantial quantities of interfacial cruds were formed. Modest concentrations (0.006 M or less) of H 2 MEHP, a suspected degradation product of HDEHP, did not effect separation factors. The presence of impurities derived from the thermal degradation of DHDECMP did not inhibit the loading of the trivalent actinide and lanthanide elements in the cation exchange chromatographic process for their separation. It appears that the biodentate (DHDECMP) solvent extraction process and the OPIX process are the leading candidate process for the co-removal of trivalent actinide and lanthanide elements from HLLW. The cation exchange chromatography and the Talspeak processes, are the leading candidate processes for the subsequent separation of actinides and lanthanides. The bidentate and cation exchange processes are further along in their development than the other processes and are currently considered the reference processes for the partitioning of Am-Cm from HLLW. 4 figures, 4 tables

  1. A bioassay method for americium and curium in feces

    International Nuclear Information System (INIS)

    Alexandre Gagne; Dominic Lariviere; Joel Surette; Sheila Kramer-Tremblay; Xiongxin Dai; Candice Didychuk

    2013-01-01

    Fecal radiobioassay is an essential and sensitive tool to estimate the internal intake of actinides after a radiological incident. A new fecal analysis method, based on lithium metaborate fusion of fecal ash for complete sample dissolution followed by sequential column chromatography separation of actinides, has been developed for the determination of low-level Am and Cm in a large size sample. Spiked synthetic fecal samples were analyzed to evaluate method performance against the acceptance criteria for radiobioassay as defined by ANSI N13.30; both satisfactory accuracy and repeatability were achieved. This method is a promising candidate for reliable dose assessment of low level actinide exposure to meet the regulatory requirements of routine radiobioassay for nuclear workers and the public. (author)

  2. Role of the functional MNS16A VNTR-243 variant of the human telomerase reverse transcriptase gene in progression and response to therapy of patients with non-Hodgkin's B-cell lymphomas.

    Science.gov (United States)

    Wysoczanska, B; Wrobel, T; Dobrzynska, O; Mazur, G; Bogunia-Kubik, K

    2015-04-01

    MNS16A is a functional polymorphic tandem repeat within the human telomerase reverse transcriptase (hTERT) gene. To investigate whether any of the MNS16A repeats represents a genetic risk factor for NHL susceptibility, progression of or response to therapy in 75 patients with non-Hodgkin's lymphomas (NHLs) and 126 healthy individuals were genotyped using the PCR-VNTR technique. A slightly higher frequency of the MNS16A VNTR-243 variant was detected among patients who did not respond to treatment (NR) as compared to patients with complete or partial remission (0.83 vs. 0.51, P = 0.055). NR patients more frequently developed aggressive than indolent type of the disease (0.92 vs. 0.41, P = 0.001). The VNTR-243 allele was more frequently detected among patients with an intermediate-high/high International Prognostic Index (IPI 3-4) score (P = 0.063), especially in patients with advanced age and IPI 3-4 (P = 0.040). In multivariate analysis, higher IPI 3-4 score (OR = 11.364, P = 0.051) and aggressive type of the disease (OR = 18.182, P = 0.012) were found to be independent genetic markers associated with nonresponse to treatment. Presence of the MNS16A VNTR-243 variant also strongly tended to affect the risk of a less favourable response to therapy and was more frequently present among nonresponders (OR = 5.848, P = 0.059). Genetic variation within the hTERT gene may affect the progression and treatment of lymphoproliferative disorders. © 2015 John Wiley & Sons Ltd.

  3. Modified salicylanilide and 3-phenyl-2H-benzo[e][1,3]oxazine-2,4(3H)-dione derivatives as novel inhibitors of osteoclast differentiation and bone resorption.

    Science.gov (United States)

    Chen, Chun-Liang; Liu, Fei-Lan; Lee, Chia-Chung; Chen, Tsung-Chih; Ahmed Ali, Ahmed Atef; Sytwu, Huey-Kang; Chang, Deh-Ming; Huang, Hsu-Shan

    2014-10-09

    Inhibition of osteoclast formation is a potential strategy to prevent inflammatory bone resorption and to treat bone diseases. In the present work, the purpose was to discover modified salicylanilides and 3-phenyl-2H-benzo[e][1,3]oxazine-2,4(3H)-dione derivatives as potential antiosteoclastogenic agents. Their inhibitory effects on RANKL-induced osteoclastogenesis from RAW264.7 cells were evaluated by TRAP stain assay. The most potent compounds, 1d and 5d, suppressed RANKL-induced osteoclast formation and TRAP activity dose-dependently. The cytotoxicity assay on RAW264.7 cells suggested that the inhibition of osteoclastic bone resorption by these compounds did not result from their cytotoxicity. Moreover, both compounds downregulated RANKL-induced NF-κB and NFATc1 in the nucleus, suppressed the expression of osteoclastogenesis-related marker genes during osteoclastogenesis, and prevented osteoclastic bone resorption but did not impair osteoblast differentiation in MC3T3-E1. Therefore, these modified salicylanilides and 3-phenyl-2H-benzo[e][1,3]oxazine-2,4(3H)-diones could be potential lead compounds for the development of a new class of antiresorptive agents.

  4. Measurement of the Neutron Capture Cross Sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm with a Total Absorption Calorimeter at n_TOF

    CERN Multimedia

    Beer, H; Wiescher, M; Cox, J; Rapp, W; Embid, M; Dababneh, S

    2002-01-01

    Accurate and reliable neutron capture cross section data for actinides are necessary for the poper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems (ADS). The goal of this proposal is the measurement of the neutron capture cross sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm at n_TOF with an accuracy of 5~\\%. $^{233}$U plays an essential role in the Th fuel cycle, which has been proposed as a safer and cleaner alternative to the U fuel cycle. The capture cross sections of $^{237}$Np,$^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm play a key role in the design and optimization of a strategy for the Nuclear Waste Transmutation. A high accuracy can be achieved at n_TOF in such measurements due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the facility, innovative Data Acquisition System based on flash ADCs and t...

  5. Historical review of californium-252 discovery and development

    International Nuclear Information System (INIS)

    Stoddard, D.H.

    1985-01-01

    This paper discusses the discovery and history of californium 252. This isotope may be synthesized by irradiating plutonium 239, plutonium 242, americium 243, or curium 244 with neutrons in a nuclear reactor. Various experiments and inventions involving 252 Cf conducted at the Savannah River Plant are discussed. The evolution of radiotherapy using californium 252 is reviewed

  6. Neutron-induced fission cross-section of 233U, 241Am and 243Am in the energy range 0.5 MeV ≤ En ≤ 20 MeV

    International Nuclear Information System (INIS)

    Belloni, F.; Milazzo, P.M.; Calviani, M.

    2011-01-01

    Neutron-induced fission cross-sections of 233 U, 241 Am and 243 Am relative to 235 U have been measured in a wide energy range at the neutron time of flight facility n-TOF in Geneva to address the present discrepancies in evaluated and experimental databases for reactions and isotopes relevant for transmutation and new generation fast reactors. A dedicated fast ionization chamber was used. Each isotope was mounted in a different cell of the modular detector. The measurements took advantage of the characteristics of the n-TOF installation. Its intrinsically low background, coupled to its high instantaneous neutron flux, results in high accuracy data. Its wide energy neutron spectrum helps to reduce systematic uncertainties due to energy-domain matching problems while the 185 m flight path and a 6 ns pulse width assure an excellent energy resolution. This paper presents results obtained between 500 keV and 20 MeV neutron energy. (authors)

  7. Thermomechanical behavior and microstructural evolution of a Ni(Pd)-rich Ni{sub 24.3}Ti{sub 49.7}Pd{sub 26} high temperature shape memory alloy

    Energy Technology Data Exchange (ETDEWEB)

    Benafan, O., E-mail: othmane.benafan@nasa.gov [NASA Glenn Research Center, Structures and Materials Division, Cleveland, OH 44135 (United States); Garg, A. [University of Toledo, Toledo, OH 43606 (United States); NASA Glenn Research Center, Structures and Materials Division, Cleveland, OH 44135 (United States); Noebe, R.D.; Bigelow, G.S.; Padula, S.A. [NASA Glenn Research Center, Structures and Materials Division, Cleveland, OH 44135 (United States); Gaydosh, D.J. [Ohio Aerospace Institute, Cleveland, OH 44142 (United States); NASA Glenn Research Center, Structures and Materials Division, Cleveland, OH 44135 (United States); Vaidyanathan, R. [Advanced Materials Processing and Analysis Center, Materials Science and Engineering Department, University of Central Florida, Orlando, FL 32816 (United States); Clausen, B.; Vogel, S.C. [Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

    2015-09-15

    Highlights: • A Ni(Pd)-rich Ni{sub 24.3}Ti{sub 49.7}Pd{sub 26} high temperature shape memory alloy was characterized. • Aging resulted in fine dispersion of nano-sized precipitates. • Thermomechanical cycling resulted in dimensional instabilities due to lattice defects. • A two-way shape memory effect strain of 2% strain was obtained after cycling. - Abstract: The effect of thermomechanical cycling on a slightly Ni(Pd)-rich Ni{sub 24.3}Ti{sub 49.7}Pd{sub 26} (near stochiometric Ni–Ti basis with Pd replacing Ni) high temperature shape memory alloy was investigated. Aged tensile specimens (400 °C/24 h/furnace cooled) were subjected to constant-stress thermal cycling in conjunction with microstructural assessment via in situ neutron diffraction and transmission electron microscopy (TEM), before and after testing. It was shown that in spite of the slightly Ni(Pd)-rich composition and heat treatment used to precipitation harden the alloy, the material exhibited dimensional instabilities with residual strain accumulation reaching 1.5% over 10 thermomechanical cycles. This was attributed to insufficient strengthening of the material (insufficient volume fraction of precipitate phase) to prevent plasticity from occurring concomitant with the martensitic transformation. In situ neutron diffraction revealed the presence of retained martensite while cycling under 300 MPa stress, which was also confirmed by transmission electron microscopy of post-cycled samples. Neutron diffraction analysis of the post-thermally-cycled samples under no-load revealed residual lattice strains in the martensite and austenite phases, remnant texture in the martensite phase, and peak broadening of the austenite phase. Texture developed in the martensite phase was composed mainly of those martensitic tensile variants observed during thermomechanical cycling. Presence of a high density of dislocations, deformation twins, and retained martensite was revealed in the austenite state via in

  8. The investigation on the vapour liquid phase equilibrium of (ammonia + 1,1,1,2-tetrafluoroethane) system over the temperatures ranging from (243.150 to 283.150) K

    International Nuclear Information System (INIS)

    Zhao, Yanxing; Dong, Xueqiang; Zhong, Quan; Gong, Maoqiong; Shen, Jun

    2017-01-01

    Highlights: • The vapour liquid equilibrium for ammonia + 1,1,1,2-tetrafluoroethane system was studied. • Measurements were based on vapour phase single recirculation method. • A positive azeotropic behaviour was exhibited at the experimental temperature range. - Abstract: To blend ammonia with some hydrofluorocarbons may give these mixed refrigerants lower flammability and global warming potential. In this paper, the isothermal vapour liquid equilibrium (VLE) of (ammonia + 1,1,1,2-tetrafluoroethane) system at temperatures ranging from (243.150 to 283.150) K are presented. Two models were employed to regress the experimental VLE results, namely the Peng–Robinson (PR) equation of state with the simple van der waals (VDW) mixing rule; the Peng–Robinson equation of state combined non-random two-liquid (NRTL) activity coefficient model with the modified Huron-Vidal one-order (MHV1) mixing rule. The maximum average absolute relative deviation of pressure (AARDp) and average absolute deviation of the vapour phase mole fraction (AADy) for PR-VDW are 0.56% and 0.010, respectively, while the maximum AARDp and AADy for PR-MHV1-NRTL are 0.27% and 0.014, respectively. Positive azeotropic behaviour was exhibited at each temperature investigated.

  9. 15 CFR 24.3 - Definitions.

    Science.gov (United States)

    2010-01-01

    ..., nonexpendable, personal property having a useful life of more than one year and an acquisition cost of $5,000 or... are made for construction work according to the percentage of completion of the work, rather than to... the unobligated balance in a prior period; (2) Withdrawal of the unobligated balance as of the...

  10. Galileo photometry of asteroid 243 Ida

    Science.gov (United States)

    Helfenstein, P.; Veverka, J.; Thomas, P.C.; Simonelli, D.P.; Klaasen, K.; Johnson, T.V.; Fanale, F.; Granahan, J.; McEwen, A.S.; Belton, M.; Chapman, C.

    1996-01-01

    Galileo imaging observations over phase angles 19.5?? to 109.8?? are combined with near-opposition Earth-based data to derive the photometric properties of Ida. To first order these properties are uniform over the surface and well modeled at ?? = 0.55 ??m by Hapke parameters ????0 = 0.22, h = 0.020, B0 = 1.5, g = -0.33, and ?? = 18?? with corresponding geometric albedo p = 0.21??0.030.01 and Bond albedo AB = 0.081??0.0170.008. Ida's photometric properties are more similar to those of "average S-asteroids" (P. Helfenstein and J. Veverka 1989, Asteroids II, Univ. of Arizona Press, Tucson) than are those of 951 Gaspra. Two primary color units are identified on Ida: Terrain A exhibits a spectrum with relatively shallower 1-??m absorption and a relatively steeper red spectral slope than average Ida, while Terrain B has a deeper 1-??m absorption and a less steep red slope. The average photometric properties of Ida and Terrain A are similar while those of Terrain B differ mostly in having a slightly higher value of ????0 (0.22 versus 0.21), suggesting that Terrain B consists of slightly brighter, more transparent regolith particles. Galileo observations of Ida's satellite Dactyl over phase angles 19.5?? to 47.6?? suggest photometric characteristics similar to those of Ida, the major difference being Dactyl's slightly lower albedo (0.20 compared to 0.21). ?? 1990 Academic Press, Inc.

  11. Publications | Page 243 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    In Guyana and Colombia, as in most Latin American countries, mining has dramatically increased over the past two decades. But from the contamination of healthy rivers to the lawless atmosphere of mining towns, few have felt the ill effects. ... Collecting data in the slums of Nairobi, Kenya can be a dangerous job.

  12. 28 CFR 2.43 - Early termination.

    Science.gov (United States)

    2010-07-01

    ... terminated because there is a likelihood that the parolee will engage in conduct violating any criminal law... shall review the status of the parolee to determine the need for continued supervision. The Commission shall also conduct a status review whenever the supervision officer recommends early termination of the...

  13. 40 CFR 243.101 - Definitions.

    Science.gov (United States)

    2010-07-01

    ... means the act of removing solid waste (or materials which have been separated for the purpose of recycling) from a central storage point. (f) Collection frequency means the number of times collection is... the purpose of these guidelines. United States Government installations located on foreign soil or on...

  14. 40 CFR 243.200-1 - Requirement.

    Science.gov (United States)

    2010-07-01

    ... for the purpose of recycling) shall be stored in such a manner that they do not constitute a fire... recycling) must meet the standards established by the American National Standards Institute (ANSI) for waste...

  15. 40 CFR 243.202-1 - Requirement.

    Science.gov (United States)

    2010-07-01

    ... solid waste (or materials which have been separated for the purpose of recycling) which are considered... transportation of solid waste (or materials which have been separated for the purpose of recycling) shall be... materials which have been separated for the purpose of recycling) shall be constructed, operated, and...

  16. Publications | Page 243 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    IDRC works with developing-country researchers and institutions to build local ... aim to widen the impact of our investment and advance development research. ... A new window on the world for women ... In doing so, it emphasizes obstacles to peace rather than root causes of conflict. ... Declining poverty, rising inequality.

  17. 40 CFR 243.100 - Scope.

    Science.gov (United States)

    2010-07-01

    ... additional actions or preferred methods by which the objectives of the requirements can be realized. The... post offices, military recruiting stations, and other offices where local community solid waste...

  18. Radioactivity studies. Progress report. Volume II

    International Nuclear Information System (INIS)

    Cohen, N.

    1981-09-01

    The metabolism of 243 244 Cm in nine adult female baboons following intravenous injection was studied. Curium-243,244 was administered as a single injection of curium citrate in dosages of 0.053 to 0.220 μCi/kg. The behavior of 243 244 Cm at these low dosages was quantitated by external whole-body and partial-body counting, bioassay of blood, urine and feces samples, liver biopsies, and post-mortem tissues analysis. Curium-243,244 rapidly passed from the blood to other tissues. At 1 and 24 h after injection, the amounts circulating were 10% and 1%, respectively. At 24 h after injection 70% of the 243 244 Cm was located within soft tissues, probably associated with extracellular fluid; the liver alone contained 32% of the injected activity. During the first weeks the content of 243 244 Cm in soft tissues decreased sharply. As time progressed, significant deposition was noted in the liver and the skeleton. Approximately 20% of the injected activity was in the liver at 1 month with a 40 day half-time. The skeleton reached a maximum burden of 57% by 100 days; the half-time observed in bone was 4 to 16 y. During the first 24 h, 10% of the injected activity appeared in the urine decreasing to 0.1%/day at 30 days and 0.01%/day at 200 days. Fecal excretion increased reaching a maximum level at four weeks. The amount of 243 244 Cm excreted in the feces during the initial 4 to 5 months (approx. 20%) and the rate of elimination in the feces after the first month paralleled the retention in the liver indicating an hepatic-biliary-fecal pathway. A model illustrating the interaction of seven internal compartments with respect to the translocation kinetics of 243 244 Cm was derived based upon this data. Solutions of the model were derived for two specific time-related exposures

  19. Nuclear data needs for subcritical reactors with heavy-metal coolant

    International Nuclear Information System (INIS)

    Ignatyuk, A.V.

    2001-01-01

    Requests on improvement of evaluated data files for minor actinides (MA) are briefly reviewed. New evaluations of neutron cross sections for Np-237, Am-241 and Am-243 after the corresponding tests and verifications should satisfy the required accuracies of data for developing MA-burners. More difficult problems arise for curium isotopes, evaluated data of which are strongly divergent. International expertise of available evaluations could be very desirable. Needs in data improvements for perspective heavy-metal liquid coolants are outlined. (author)

  20. Results of Am isotopic ratio analysis in irradiated MOX fuels

    Energy Technology Data Exchange (ETDEWEB)

    Koyama, Shin-ichi; Osaka, Masahiko; Mitsugashira, Toshiaki; Konno, Koichi [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center; Kajitani, Mikio

    1997-04-01

    For analysis of a small quantity of americium, it is necessary to separate from curium which has similar chemical property. As a chemical separation method for americium and curium, the oxidation of americium with pentavalent bismuth and subsequent co-precipitation of trivalent curium with BIP O{sub 4} were applied to analyze americium in irradiated MOX fuels which contained about 30wt% plutonium and 0.9wt% {sup 241}Am before irradiation and were irradiated up to 26.2GWd/t in the experimental fast reactor Joyo. The purpose of this study is to measure isotopic ratio of americium and to evaluate the change of isotopic ratio with irradiation. Following results are obtained in this study. (1) The isotopic ratio of americium ({sup 241}Am, {sup 242m}Am and {sup 243}Am) can be analyzed in the MOX fuels by isolating americium. The isotopic ratio of {sup 242m}Am and {sup 243}Am increases up to 0.62at% and 0.82at% at maximum burnup, respectively, (2) The results of isotopic analysis indicates that the contents of {sup 241}Am decreases, whereas {sup 242m}Am, {sup 243}Am increase linearly with increasing burnup. (author)

  1. Rapid selective separation of americium/curium from simulated nuclear forensic matrices using triazine ligands

    Energy Technology Data Exchange (ETDEWEB)

    Higginson, Matthew A.; Livens, Francis R.; Heath, Sarah L. [Manchester Univ. (United Kingdom). Centre for Radiochemistry Research; Thompson, Paul; Marsden, Olivia J. [AWE, Aldermaston, Reading (United Kingdom); Harwood, Laurence M.; Hudson, Michael J. [Reading Univ. (United Kingdom). Dept. of Chemistry; Lewis, Frank W. [Reading Univ. (United Kingdom). Dept. of Chemistry; Northumbria Univ., Newcastle upon Tyne (United Kingdom). Dept. of Chemical and Forensic Sciences

    2015-07-01

    In analysis of complex nuclear forensic samples containing lanthanides, actinides and matrix elements, rapid selective extraction of Am/Cm for quantification is challenging, in particular due the difficult separation of Am/Cm from lanthanides. Here we present a separation process for Am/Cm(III) which is achieved using a combination of AG1-X8 chromatography followed by Am/Cm extraction with a triazine ligand. The ligands tested in our process were CyMe{sub 4}-BTPhen, CyMe{sub 4}-BTBP, CA-BTP and CA-BTPhen. Our process allows for purification and quantification of Am and Cm (recoveries 80% - 100%) and other major actinides in < 2 d without the use of multiple columns or thiocyanate. The process is unaffected by high level Ca(II)/Fe(III)/Al(III) (10 mg mL{sup -1}) and thus requires little pre-treatment of samples.

  2. Uptake of plutonium, americium, curium, and neptunium in plants cultivated under greenhouse conditions

    International Nuclear Information System (INIS)

    Pimpl, M.; Schmidt, W.

    1984-01-01

    The root-uptake of Np, Pu, Am, and Cm from three different artificially contaminated soils in grass, maize, spring wheat, and potatoes was investigated under greenhouse conditions in pots filled with 9 kg contaminated soil and in lysimeters with a surface area of 0,5 m 2 containing the soils in undisturbed profils up to a depth of 80 cm. Only the plough layer of 30 cm was contaminated with Np, Pu, Am, and Cm. Crop cultivation was done corresponding to usual practice in agriculture. Results of the 1st vegetation period are represented. Transfer factors obtained deviate considerably from those which are recommended for the estimation of long-term exposure of man in the Federal Republic of Germany. (orig.)

  3. Actinide production in the reaction of heavy ions with curium-248

    International Nuclear Information System (INIS)

    Moody, K.J.

    1983-07-01

    Chemical experiments were performed to examine the usefulness of heavy ion transfer reactions in producing new, neutron-rich actinide nuclides. A general quasi-elastic to deep-inelastic mechanism is proposed, and the utility of this method as opposed to other methods (e.g. complete fusion) is discussed. The relative merits of various techniques of actinide target synthesis are discussed. A description is given of a target system designed to remove the large amounts of heat generated by the passage of a heavy ion beam through matter, thereby maximizing the beam intensity which can be safely used in an experiment. Also described is a general separation scheme for the actinide elements from protactinium (Z=91) to mendelevium (Z=101), and fast specific procedures for plutonium, americium and berkelium. The cross sections for the production of several nuclides from the bombardment of 248 Cm with 18 O, 86 Kr and 136 Xe projectiles at several energies near and below the Coulomb barrier were determined. The results are compared with yields from 48 Ca and 238 U bombardments of 248 Cm. Simple extrapolation of the product yields into unknown regions of charge and mass indicates that the use of heavy ion transfer reactions to produce new, neutron-rich above-target species is limited. The substantial production of neutron-rich below-target species, however, indicates that with very heavy ions like 136 Xe and 238 U the new species 248 Am, 249 Am and 247 Pu should be produced with large cross sections from a 248 Cm target. A preliminary, unsuccessful attempt to isolate 247 Pu is outlined. The failure is probably due to the half life of the decay, which is calculated to be less than 3 minutes. The absolute gamma ray intensities from 251 Bk decay, necessary for calculating the 251 Bk cross section, are also determined

  4. Characteristics of plutonium, curium and uranium in hulls of FUGEN MOX spent fuel by destructive analysis

    International Nuclear Information System (INIS)

    Iijima, Shizuka; Goto, Yuichi; Samoto, Hirotaka; Shichi, Ryo; Shimizu, Takenori

    2011-01-01

    We have been developing a non-destructive assay system called hulls monitor for nuclear fuel materials retained in hulls at the Tokai Reprocessing Plant (TRP). The hulls monitor is based on a passive neutron measurement method, so its applicability should be evaluated by a destructive analysis of hulls that are recovered from the reprocessing process. In this study, hulls came from the Advanced Thermal Reactor (ATR) FUGEN were taken from the dissolution process of TRP and destructively analyzed. Two kinds of hulls from ATR-MOX spent fuel assemblies and from ATR-UO 2 spent fuel assemblies were taken and soaked with nitric acid then fused with ammonium hydrogen sulfate, followed by Pu, 244 Cm, U mass determination by alpha spectrometry and ICP-AES. The characteristics of hulls came from MOX spent fuel assemblies were revealed by comparison of ATR-MOX spent fuel with ATR-UO 2 spent fuel. (author)

  5. Americium-Curium Stabilization - 5'' Cylindrical Induction Melter System Design Basis

    International Nuclear Information System (INIS)

    Witt, D.C.

    1999-01-01

    Approximately 11,000 liters (3,600) gallons of solution containing isotopes of Am and Cm are currently stored in F-Canyon Tank 17.1. These isotopes were recovered during plutonium-242 production campaigns in the mid- and late-1970s. Experimental work for the project began in 1995 by the Savannah River Technology Center (SRTC). Details of the process are given in the various sections of this document

  6. Optimization conditions for the separation of rare earth elements, americium, curium and cesium with HPLC technique

    International Nuclear Information System (INIS)

    Goutelard, F.; Caussignac, C.; Brennetot, R.; Stadelmann, G.; Gautier, C.

    2009-01-01

    In order to validate the neutronic code calculations used in the nuclear field, it is necessary to quantify the isotopic composition of the nuclear irradiated fuels with high precision and accuracy. A separation step whose objective is to isolate the elements of interest in a fraction as pure as possible, is performed before mass spectrometry detection (MC-ICP-MS, TIMS), in order to eliminate isobaric interferences. In a first step, uranium and plutonium are separated from the fission products by ion exchange chromatography. Then, fission products are separated by high performance liquid chromatography (HPLC). A gradient separation with a silica sulphonated support as stationary phase and hydroxy-methyl butyric acid (HMB) as eluent solution provides a good degree of separation of the rare earth elements, Am, Cm and Cs. But, for a same manufacturer, the rate of sulphonated groups is variable from one column to another for a given production batch. For every replacement of column, it is necessary to adjust the separation conditions. Furthermore, the high radioactivity of the samples injected damages the stationary phase, dragging a regular renewal of the columns. The goal of this study is to determine the optimal separation conditions with a minimum of tests in order to limit the time assigned to this operation. A first Doehlert experimental design with pH and HMB concentration as variables has been implemented to optimize Gd, Eu separation, in isocratic initial conditions. A second one has been tested in order to separate the higher lanthanides and to fix the final conditions of the gradient separation. A last set of tests has been performed to characterize the cesium behaviour. Finally, the gradient conditions have been adjusted in order to perform the full separation of lanthanides, Cs, Am and Cm with nuclear facilities. (author)

  7. Temperature thresholds for surface blistering of platinum and stainless steel exposed to curium-242 alpha radiations

    International Nuclear Information System (INIS)

    McDonell, W.R.; Dillich, S.

    1981-01-01

    Implantation of helium in materials exposed to alpha-emitting radionuclides such as 242 Cm causes surface blistering at elevated temperatures. The temperature thresholds for such blistering are of practical importance to the selection of suitable container materials for radionuclides, and are of fundamental interest with regard to the mechanisms of helium blistering of materials in radiation environments. The purpose of this investigation was to establish temperature thresholds for surface blistering of platinum and stainless-steel container materials by post-irradiation heating of specimens exposed at room temperature to alpha particles from an external 242 Cm source. These thresholds were compared with (1) the analogous temperature thresholds for surface blistering of materials exposed to external beams of accelerator helium ions, and (2) thresholds for swelling and grain-boundary cracking of materials in which helium is generated internally by (n,α) reactions during reactor exposures

  8. Multi-recycling of plutonium and incineration of americium, curium, and technetium in PWRs

    International Nuclear Information System (INIS)

    Golfier, H.; Bergeron, J.; Puill, A.; Rohart, M.

    2000-01-01

    The future of nuclear power requires a clear strategy for radwaste and Plutonium management. Pressurized water reactors (PWR) and the associated fuel cycle installations represent the largest part of the French power plants (and are partly paid off). The reactors in service produce an annual 10 tons of Pu, 1.4 tons of minor actinides (MA), and 3.8 tons of long-lived fission products (LLFP). The spent fuel is reprocessed in La Hague plant to recover the energetic elements U and Pu. The latter was initially dedicated to power Fast Breeder Reactors that converted the depleted and reprocessed, thus ensuring a significant part of the French national energy resources. The shut-down of Super-Phenix, the postponement of building of Fast Breeder Reactors (FBR) and the relaxed need for stretching natural U resources raise the issue of Pu management. In fact, the Pu mono-recycling practiced in France since 1987 (St Laurent B1) only slows down the Pu accumulation in spent nuclear fuel, yet it is unable to stabilize the Pu inventory. Beyond the cooperation with its industrial partners, CEA investigates solutions for short and medium term Pu management thus contributing to research required for keeping nuclear power as an energy option. The range of these investigations shall cover both adaptations for light water reactors to facilitate Pu recycling and more innovative solutions concerning reactors, fuel and fuel cycle. The aim of using Pu more efficiently in PWR has led, not only for economic and non-proliferation reasons, but also for considerations related to the optimization of Pu and MA management. The mastery of Pu inventory is a requirement for all long-lived radwaste management methods. In this context, the potential of innovative PWRs has been investigated to control the Pu fluxes and to make them a milestone on the way to clean nuclear power. This paper presents the most recent results related to Pu utilization and MA and LLFP incineration like (Am+Cm) and Tc. To determine the influence of the Pu fluxes, a 1450 MWe PWR with one standard and one innovative concept (code named APA for Advanced Plutonium fuel Assembly) have been performed. A multi-recycling scenario is simulated with a 400 TWhe power plant park. (authors)

  9. Sorption of plutonium and curium on ion exchange resins in mixed aqueous organic solutions

    International Nuclear Information System (INIS)

    Haidvogel, N.; Reitsamer, G.; Grass, F.

    1974-12-01

    The sorption of the sulfate and nitrate-complexes of the actinides Pu(III), Pu(IV), Pu(VI), Am(III) and Om(III) on the ion-exchange-resins Dowex 1X8 and Dowex 50 WX8 is investigated. The strong sorbability of these actinide ions in solvents with high content of alcohol is explained by the existence of anionic complexes like Pu(III) (SO 4 ) 2 - , Pu(IV) (SO 4 ) 3 2 - , Pu(VI)O 2 (SO 4 ) 2 2 - , Am(SO 4 ) 2 - respectively Am(NO 3 ) 4 - and Om(NO 3 ) 4 - . The taking of autoradiographs from the thin-layer chromatograms by the aid of a special device and the evaluation of the autoradiographs by a particular photodensitometer are described. The measurement of the radioactivity of the α-emitting nuclides Pu 239, Am 241 and Om 242 are done by liquid-scintillation spectrometry. (author)

  10. Incorporation of plutonium, americium and curium into the Irish Sea seabed by biological activity

    Energy Technology Data Exchange (ETDEWEB)

    Kershaw, P J; Swift, D J; Pentreath, R J; Lovett, M B

    1984-12-01

    Bioturbation was considered as a potentially significant mechanism for the incorporation of long-lived radionuclides into the seabed and in particular the activities of a large echiuran Maximulleria lankesteri. Radionuclides of the transuranium elements plutonium, americium and cirium are discharged into the Irish Sea under authorization as part of the low-level liquid effluent from the British Nuclear Fuels plc reprocessing plant at Sellafield, Cumbria, England. The distribution of Pu-239, 240, Pu-238, Am-241, Cm-244 and Cm-242 concentrations and the Pu-239, 240/Pu-238 quotient in samples taken in April and May 1983 from the sediment surface, burrow linings, sediments adjacent to burrows, and the gut contents and body of a large M. lankesteri clearly indicate that bioturbation is responsible, at least in part, for the incorporation of these radionuclides to depths of up to 140 cm. This area of sediments represents a significant present-day sink, but the permanence of this sink and the likelihood that radioactivity will be remobilized and be returned to man, depends on a large number of factors. 15 references, 18 figures.

  11. Structural, electronic, and thermodynamic properties of curium dioxide: Density functional theory calculations

    Science.gov (United States)

    Hou, Ling; Li, Wei-Dong; Wang, Fangwei; Eriksson, Olle; Wang, Bao-Tian

    2017-12-01

    We present a systematic investigation of the structural, magnetic, electronic, mechanical, and thermodynamic properties of CmO2 with the local density approximation (LDA)+U and the generalized gradient approximation (GGA)+U approaches. The strong Coulomb repulsion and the spin-orbit coupling (SOC) effects on the lattice structures, electronic density of states, and band gaps are carefully studied, and compared with other A O2 (A =U , Np, Pu, and Am). The ferromagnetic configuration with half-metallic character is predicted to be energetically stable while a charge-transfer semiconductor is predicted for the antiferromagnetic configuration. The elastic constants and phonon spectra show that the fluorite structure is mechanically and dynamically stable. Based on the first-principles phonon density of states, the lattice vibrational energy is calculated using the quasiharmonic approximation. Then, the Gibbs free energy, thermal expansion coefficient, specific heat, and entropy are obtained and compared with experimental data. The mode Grüneisen parameters are presented to analyze the anharmonic properties. The Slack relation is applied to obtain the lattice thermal conductivity in temperature range of 300-1600 K. The phonon group velocities are also calculated to investigate the heat transfer. For all these properties, if available, we compare the results of CmO2 with other A O2 .

  12. Comparative uptake and distribution of plutonium, americium, curium and neptunium in four plant species

    Energy Technology Data Exchange (ETDEWEB)

    Schreckhise, R E; Cline, J F [Battelle Pacific Northwest Labs., Richland, WA (USA)

    1980-05-01

    Uptake of the nitrate forms of /sup 238/Pu, /sup 239/Pu, /sup 241/Am, /sup 244/Cm and /sup 237/Np from soil into selected parts of four different plant species grown under field conditions was compared Alfalfa, barley, peas and cheatgrass were grown outdoors in small weighing lysimeters filled with soil containing these radionuclides. The plants were harvested at maturity, divided into selected components and radiochemically analyzed by alpha-energy analysis. Soil concentration did not appear to affect the plant uptake of /sup 238/Pu, /sup 239/Pu, /sup 241/Am or /sup 244/Cm for the two levels utilized. The relative plant uptake of the five different transuranics was /sup 237/Np>/sup 244/Cm approximately equal /sup 241/Am>/sup 239/Pu approximately equal/sup 238/Pu. Relative uptake values of Np for various plant parts ranged from 2200 to 45,000 times as great as for Pu, while Am and Cm values were 10-20 times as great. The values for seeds were significantly lower than those for the other aboveground plant parts for all four transuranic elements. The legumes accumulated approx. 10 times more than the grasses. A comparison of the postulated radionuclide content of plants grown in soil contaminated with material from spent liquid metal fast breeder reactor fuels indicated that concentrations of isotopes of Am, Cm and Np would exceed /sup 239/Pu values.

  13. Assessment of Neptunium, Americium, and Curium in the Savannah River Site Environment

    International Nuclear Information System (INIS)

    Carlton, W.H.

    1997-01-01

    A series of documents has been published in which the impact of various radionuclides released to the environment by Savannah River Site (SRS) operations has been assessed. The quantity released, the disposition of the radionuclides in the environment, and the dose to offsite individuals has been presented for activation products, carbon cesium, iodine, plutonium, selected fission products, strontium, technetium, tritium, uranium, and the noble gases. An assessment of the impact of nonradioactive mercury also has been published.This document assesses the impact of radioactive transuranics released from SRS facilities since the first reactor became operational late in 1953. The isotopes reported here are 239Np, 241Am, and 244Cm

  14. Americium-curium separation by means of selective extraction of hexavalent americium using a centrifugal contactor

    International Nuclear Information System (INIS)

    Musikas, C.; Germain, M.; Bathellier, A.

    1979-01-01

    This paper deals with Am (VI) - Cm (III) separation in nitrate media. The kinetics of oxidation of Am (III) by sodium persulfate in the presence of Ag + ions were reinvestigated by studying the effect of additions of small amounts of reagents which do not drastically change the distribution coefficients of Am (VI) or Cm (III) ions. Organo phosphorus solvents were selected because they are radiation resistant, possess weak reductant properties and that their affinity for hexavalent ion is high. The operating procedure was selected by consideration of the results of the two previous investigations. This can be done by using a centrifugal contactor enabling in to set organic-aqueous phase contact time in accordance with the kinetics of extraction of Am (VI), oxidation of Am (III) in aqueous phase, and reduction of Am (VI) in organic phase

  15. UNDERWATER ANALYSIS OF IRRADIATED REACTOR SLUGS FOR Co-60 AND OTHER RADIONUCLIDES AT THE SAVANNAH RIVER SITE

    International Nuclear Information System (INIS)

    CASELLA, VITO

    2004-01-01

    Co-60 was produced in the Savannah River Site (SRS) reactors in the 1970s, and the irradiated cobalt reactor slugs were stored in a reactor basin at SRS. Since the activity rates of these slugs were not accurately known, assaying was required. A sodium iodide gamma detector was placed above a specially designed air collimator assembly, so that the slug was eight to nine feet from the detector and was shielded by the basin water. Also, 18 curium sampler slugs, used to produce Cm-244 from Pu-239, were to be disposed of with the cobalt slugs. The curium slugs were also analyzed with a High Purity Germanium (HPGE) detector in an attempt to identify any additional radionuclides produced from the irradiation. Co-60 concentrations were determined for reactor disassembly basin cobalt slugs and the 18 curium sampler slugs. The total Co-60 activity of all of the assayed slugs in this work summed to 31,783 curies on 9/15/03. From the Co-60 concentrations of the curium sampler slugs, the irradiation flux was determined for the known irradiation time. The amounts of Pu-238,-239,-240,-241,-242; Am-241,-243; and Cm-242,-244 produced were then obtained based on the original amount of Pu-239 irradiated

  16. Determination of 241Am and 244Cm in environmental samples

    International Nuclear Information System (INIS)

    Bonino, N.O.; Grinman, A.D.R.; Serdeiro, N.H.

    1998-01-01

    The present technique describes a method to separate, purify and measure low levels of americium and curium in different environmental samples such as sediments, soils, water, vegetables, and air filters. The determination of radionuclides in theses environmental matrices have analytical problems, since a simple method doesn't exist for the purification, which is indispensable for its later measuring alpha spectrometry. The developed technique consist on taking an aliquot of the sample to analyze, to add tracer as americium 243 and curium 242, and to dissolve the matrix in a such way to have a clear solution. For the isolation of the americium and curium of the other actinides ar used as separation techniques: precipitation with Fe 3+ , anionic and cationic exchange, and extraction with a appropriate organic solvent. The purification of the americium and curium is followed by the electrodeposition habitually used. The measurement is carried out by alpha spectrometry with a detector of implanted ion. The detection limit for this techniques is of 0,002 Bq/l or 0,2 mBq in the case of filters. (author)

  17. 48 CFR 252.243-7002 - Requests for equitable adjustment.

    Science.gov (United States)

    2010-10-01

    ... clause does not apply to— (1) Requests for routine contract payments; for example, requests for payment for accepted supplies and services, routine vouchers under a cost-reimbursement type contract, or progress payment invoices; or (2) Final adjustment under an incentive provision of the contract. (End of...

  18. All projects related to | Page 243 | IDRC - International Development ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Rethinking Political Legitimacy: Citizen Inclusion and Social Digital Media. Project. In Chile, a mobilized, invigorated civil society is using new digital technologies to transform political participation. ... Program: Agriculture and Food Security.

  19. 48 CFR 243.204-70-6 - Allowable profit.

    Science.gov (United States)

    2010-10-01

    ... profit allowed reflects— (a) Any reduced cost risk to the contractor for costs incurred during contract performance before negotiation of the final price; (b) The contractor's reduced cost risk for costs incurred during performance of the remainder of the contract; and (c) The extent to which costs have been incurred...

  20. Preface: phys. stat. sol. (b) 243/5

    Science.gov (United States)

    Artacho, Emilio; Beck, Thomas L.; Hernández, Eduardo

    Between 20 and 24 June 2005 the Centre Européen de Calcul Atomique et Moléculaire - or CECAM, as it is more widely known - hosted a workshop entitled State-of-the-art, developments and perspectives of real-space electronic structure methods in condensed-matter and chemical physics, organized with the support of CECAM itself and the ?k network. The workshop was attended by some forty participants coming from fifteen countries, and about thirty presentations were given. The workshop provided a lively forum for the discussion of recent methodological developments in electronic structure calculations, ranging from linear-scaling methods, mesh techniques, time-dependent density functional methods, and a long etcetera, which had been our ultimate objective when undertaking its organization.The first-principles simulation of solids, liquids and complex matter in general has jumped in the last few years from the relatively confined niches in condensed matter and materials physics and in quantum chemistry, to cover most of the sciences, including nano, bio, geo, environmental sciences and engineering. This effect has been propitiated by the ability of simulation techniques to deal with an ever larger degree of complexity. Although this is partially to be attributed to the steady increase in computer power, the main factor behind this change has been the coming of age of the main theoretical framework for most of the simulations performed today, together with an extremely active development of the basic algorithms for its computer implementation. It is this latter aspect that is the topic of this special issue of physica status solidi.There is a relentless effort in the scientific community seeking to achieve not only higher accuracy, but also more efficient, cost-effective and if possible simpler computational methods in electronic structure calculations [1]. From the early 1990s onwards there has been a keen interest in the computational condensed matter and chemical physics communities in methods that had the potential to overcome the unfavourable scaling of the computational cost with the system size, implicit in the momentum-space formalism familiar to solid-state physicists and the quantum chemistry approaches more common in chemical physics and physical chemistry. This interest was sparkled by the famous paper in which Weitao Yang [2] introduced the Divide and Conquer method. Soon afterwards several practical schemes aiming to achieve linear-scaling calculations, by exploiting what Walter Kohn called most aptly the near-sightedness of quantum mechanics [3], were proposed and explored (for a review on linear-scaling methods, see [4]). This search for novel, more efficient and better scaling algorithms proved to be fruitful in more than one way. Not only was it the start of several packages which are well-known today (such as Siesta, Conquest, etc.), but it also leads to new ways of representing electronic states and orbitals, such as grids [5, 6], wavelets [7], finite elements, etc. Also, the drive to exploit near-sightedness attracted computational solid state physicists to the type of atomic-like basis functions traditionally used in the quantum chemistry community. At the same time computational chemists learnt about plane waves and density functional theory, and thus a fruitful dialogue was started between two communities that hitherto had not had much contact.Another interesting development that has begun to take place over the last decade or so is the convergence of several branches of science, notably physics, chemistry and biology, at the nanoscale. Experimentalists in all these different fields are now performing highly sophisticated measurements on systems of nanometer size, the kind of systems that us theoreticians can address with our computational methods, and this convergence of experiment and theory at this scale has also been very fruitful, particularly in the fields of electronic transport and STM image simulation. It is now quite common to find papers at the cutting edge of nanoscience and nanotechnology co-authored by experimentalists and theorists, and it can only be expected that this fruitful interplay between theory and experiment will increase in the future.It was considerations such as these that moved us to propose to CECAM and ?k the celebration of a workshop devoted to the discussion of recent developments in electronic structure techniques, a proposal that was enthusiastically received, not just by CECAM and ?k, but also by our invited speakers and participants. Interest in novel electronic structure methods is now as high as ever, and we are therefore very happy that physica status solidi has given us the opportunity to devote a special issue to the topics covered in the workshop. This special issue of physica status solidi gathers invited contributions from several attendants to the workshop, contributions that are representative of the range of topics and issues discussed then, including progress in linear scaling methods, electronic transport, simulation of STM images, time-dependent DFT methods, etc. It rests for us to thank all the contributors to this special issue for their efforts, CECAM and ?k for funding the workshop, physica status solidi for agreeing to devote this special issue to the workshop, and last but not least Emmanuelle and Emilie, the CECAM secretaries, for their invaluable practical help in putting this workshop together

  1. 40 CFR 243.202-3 - Recommended procedures: Operations.

    Science.gov (United States)

    2010-07-01

    ... receive periodic vehicle safety checks, including, but not limited to, inspection of brakes, windshield wipers, taillights, backup lights, audible reverse warning devices, tires, and hydraulic systems. Any... should only be left in a vehicle overnight when this practice does not constitute a fire, health, or...

  2. 1935 15' Quad #243 Aerial Photo Mosaic Index

    Data.gov (United States)

    Earth Data Analysis Center, University of New Mexico — Aerial Photo Reference Mosaics contain aerial photographs that are retrievable on a frame by frame basis. The inventory contains imagery from various sources that...

  3. 48 CFR 1852.243-71 - Shared savings.

    Science.gov (United States)

    2010-10-01

    ... organizational support of a contract or group of contracts. These alternatives must result in a net reduction of... organizational support which are proposed to be changed. (2) A description of the difference between the current... make any structural or organizational changes in order to implement an approved CRP. (5) Government...

  4. 40 CFR 243.204-2 - Recommended procedures: Operations.

    Science.gov (United States)

    2010-07-01

    ... achieve the most efficient compaction. (3) Compactor trucks should be used to reduce the number of trips... commercial wastes which do not contain food wastes, storage capacity should be increased in lieu of more...

  5. 29 CFR 1910.243 - Guarding of portable powered tools.

    Science.gov (United States)

    2010-07-01

    ..., powered tampers, jack hammers, rock drills, garden appliances, household and kitchen appliances, personal... clearance between the wheel hole and the machine spindle (or wheel sleeves or adaptors) is essential to...

  6. Dicty_cDB: AFL243 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available llsc*rl*wwcs*twsirsh*trytnyldhfr***fsinesrr*rskskrcsyyrhyk *fnfg*tyrs*yhfnsk*wyfnctfscnsitiiaxkgncknmtqtskkl...SQVTVLSLVANWFAQHRGIEEG KRRQVNRFSSSFTNKFGYGITCS*tm*snrsknl*kefnlcfg*rfr*tnri*rcfen*r nhllsc*rl*wwcs*twsirsh*trytnyldhfr***fsines

  7. 40 CFR 243.200-2 - Recommended procedures: Design.

    Science.gov (United States)

    2010-07-01

    ... waste containers should be constructed of corrosion resistant metal or other material which will not.... Containers should have covers which are tight-fitting to resist the intrusion of water and vectors, and...

  8. 7 CFR 2.43 - Administrator, Foreign Agricultural Service.

    Science.gov (United States)

    2010-01-01

    ... the provisions concerning the end-use certificate system authorized pursuant to section 321(f) of that... amended (7 U.S.C. 5601 et seq.). (15) Formulate policies and administer barter programs under which... intelligence and reporting system, including provision for foreign agricultural representation abroad to...

  9. 19 CFR 10.243 - Articles eligible for preferential treatment.

    Science.gov (United States)

    2010-04-01

    ... articles had been imported directly from Canada or Mexico; or (iv) Fabrics or yarns that the President or... folklore apparel or other textile article of an ATPDEA beneficiary country that the President or his....61.00 of the HTSUS and that is entered free of duty from Canada, Mexico, or Israel. (d) Imported...

  10. 9 CFR 354.243 - Operations and procedures.

    Science.gov (United States)

    2010-01-01

    ... INSPECTION AND CERTIFICATION VOLUNTARY INSPECTION OF RABBITS AND EDIBLE PRODUCTS THEREOF Maintenance of..., and insects), considering the means intended to be employed in transporting the product from the plant... hygiene of personnel: (1) All employees coming in contact with exposed edible products or edible products...

  11. 40 CFR Appendix to Part 243 - Recommended Bibliography

    Science.gov (United States)

    2010-07-01

    .... Government Printing Office, 1974. 3. Grupenhoff, B. L., and K. A. Shuster. Paper and plastic solid waste... Sanitation Foundation standard no. 32 for paper refuse sacks. Ann Arbor, The National Sanitation Foundation..., General Services Administration, Washington, DC 20409. 9. Ralph Stone and Company, Inc. The use of bags...

  12. 48 CFR 1852.243-70 - Engineering change proposals.

    Science.gov (United States)

    2010-10-01

    ... reserves the right to request additional information if that provided by the Contractor is considered... cost or pricing data, it shall cite the exception and provide rationale for its applicability. (e) If...

  13. 29 CFR 1952.243 - Final approval determination.

    Science.gov (United States)

    2010-07-01

    ... over agricultural temporary labor camps for employees engaged in egg, poultry, or red meat production... Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION..., or the U.S. Department of Commerce—National Oceanic and Atmospheric Administration, and operated by...

  14. 12 CFR 303.243 - Brokered deposit waivers.

    Science.gov (United States)

    2010-01-01

    ... and use of brokered deposits; (7) A recent consolidated financial statement with balance sheet and income statements; and (8) The reasons the institution believes its acceptance, renewal or rollover of...) The time period for which the waiver is requested; (2) A statement of the policy governing the use of...

  15. Dicty_cDB: SHB243 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available R103667 |CR103667.1 Forward strand read from insert in 3'HPRT insertion targeting and chromosome engineering... in 3'HPRT insertion targeting and chromosome engineering clone MHPP186g09. 50 0.13 1 dna update 2005.12.21

  16. 40 CFR 243.201-2 - Recommended procedures: Operations.

    Science.gov (United States)

    2010-07-01

    ..., safety glasses, respirators, and footwear should be used by collection employees, as appropriate. This equipment should meet the applicable provisions of the Occupational Safety and Health Administration...

  17. Synthesis and characterization of a pentadentate Schiff base N3O2 ligand and its neutral technetium(V) complex. X-ray structure of (N,N'-3-azapentane-1,5-diylbis(3-(1-iminoethyl)-6-methyl-2H-pyran-2,4(3H)-dionato)(3-)-O,O',N,N',N double-prime)oxotechnetium(V)

    International Nuclear Information System (INIS)

    Shuang Liu; Rettig, S.J.; Orvig, C.

    1991-01-01

    Preparations of a potentially pentadentate ligand, N,N'-3-azapentane-1,5-diylbis(3-(1-iminoethyl)-6-methyl-2H-pyran-2,4-(3H)-dione) (H 3 apa), and its neutral technetium(V) complex, [TcO(apa)], are described. The 13 C and 1 H NMR, infrared, optical, and mass spectra of the pentadentate ligand and its technetium(V) complex are reported. The X-ray structure of [TcO(apa)] has been determined. Crystals are orthorhombic, space group Pbca, with a = 12.833 (2) angstrom, b = 33.320 (5) angstrom, c = 9.942(4) angstrom, V = 4251 (2) angstrom, and Z = 8. The structure was solved by Patterson and Fourier methods and was refined by full-matrix least-squares procedures to R = 0.028 and R W = 0.032 for 4054 reflections with I ≥ 3σ(I). The technetium(V) complex has a highly distorted octahedral coordination geometry comprising a [TcO] 3+ core and the triply deprotonated pentadentate ligand wrapping around the metal center. One of the two oxygen donor atoms of the pentadentate ligand is located trans to the Tc double-bond O bond while the remaining four donor atoms, N 3 O, occupy the equatorial sites. The distance between the deprotonated N(1) atom to the Tc center is significantly shorter than a normal Tc-N single bond length of 2.10 angstroms, but longer than that for a Tc-N triple bond. 1 H NMR spectral data reveal a rigid solution structure for the complex, which undergoes no conformational and configurational exchange at temperatures up to 50C

  18. Analysis of cascade impactor and EPA method 29 data from the americium/curium pilot melter system

    International Nuclear Information System (INIS)

    Zamecnik, J.R.

    1997-11-01

    The offgas system of the Am/Cm pilot melter at TNX was characterized by measuring the particulate evolution using a cascade impactor and EPA Method 29. This sampling work was performed by John Harden of the Clemson Environmental Technologies Laboratory, under SCUREF Task SC0056. Elemental analyses were performed by the SRTC Mobile Laboratory.Operation of the Am/Cm melter with B2000 frit has resulted in deposition of PbO and boron compounds in the offgas system that has contributed to pluggage of the High Efficiency Mist Eliminator (HEME). Sampling of the offgas system was performed to quantify the amount of particulate in the offgas system under several sets of conditions. Particulate concentration and particle size distribution were measured just downstream of the melter pressure control air addition port and at the HEME inlet. At both locations, the particulate was measured with and without steam to the film cooler while the melter was idled at about 1450 degrees Celsius. Additional determinations were made at the melter location during feeding and during idling at 1150 degrees Celsius rather than 1450 degrees Celsius (both with no steam to the film cooler). Deposition of particulates upstream of the melter sample point may have, and most likely did occur in each run, so the particulate concentrations measured do no necessarily reflect the total particulate emission at the melt surface. However, the data may be used in a relative sense to judge the system performance

  19. Evaluation of thermal neutron cross-sections and resonance integrals of protactinium, americium, curium, and berkelium isotopes

    International Nuclear Information System (INIS)

    Belanova, T.S.

    1994-12-01

    Data on the thermal neutron fission and capture cross-sections as well as their corresponding resonance integrals are reviewed and analysed. The data are classified according to the form of neutron spectra under investigation. The weighted mean values of the cross-sections and resonance integrals for every type of neutron spectra were adopted as evaluated data. (author). 87 refs, 2 tabs

  20. Chromatographic studies of the lanthanide element separation for the americium/curium large scale separation using ion exchange resins

    International Nuclear Information System (INIS)

    Ginisty, Claude.

    1981-06-01

    The Am/Cm large scale separations, operated by chromatography with the use of ion exchange resins, are described by numerous publications. The bibliographic studies allow to retain the followed points: use of sulfonate cationic resins, development by elution with the α-hydroxyisobutyric acid, column loadings between 1 and 30% of the capacity, possibility to use no radioactive lanthanides prior to actinides for trial purposes. The optimisation of such a process is the major part of this thesis. This point is realised by introducing a new definition for the resolution, for non symmetrical elution peaks, and a measure of this dissymmetry by introducing a shape factor F. For the separation itself and for the pressure drop in the column, the influence of the following parameters are studied: composition of the elution solution (concentration and pH), column temperature (20 to 90 0 C), resin size (9 to 27 μm), rate flow of mobile phase (70 ml.cm -2 .mn -1 ), column length and diameter. Symmetrical elution peaks may be obtained, even with a 27% loading. Elution conditions may be modified during the separation process in order to have the best recovery for the two components (1,3 [fr

  1. Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodology

    Energy Technology Data Exchange (ETDEWEB)

    Borrelli, R.A., E-mail: r.angelo.borrelli@gmail.com

    2014-10-01

    The deployment of nuclear energy systems (NESs) is expanding around the world. Nations are investing in NESs as a means to establish energy independence, grow national economies, and address climate change. Transitioning to the advanced nuclear fuel cycle can meet growing energy demands and ensure resource sustainability. However, nuclear facilities in all phases of the advanced fuel cycle must be ‘safeguardable,’ where safety, safeguards, and security are integrated into a practical design strategy. To this end, the High Reliability Safeguards (HRS) approach is a continually developing safeguardability methodology that applies intrinsic design features and employs a risk-informed approach for systems assessment that is safeguards-motivated. Currently, a commercial pyroprocessing facility is used as the example system. This paper presents a modeling study that investigates the neutron flux associated with processed materials. The intent of these studies is to determine if the neutron flux will affect facility design, and subsequently, safeguardability. The results presented in this paper are for the head-end subsystems in a pyroprocessing facility. The collective results from these studies will then be used to further develop the HRS methodology.

  2. Spectroscopic studies on the interaction of europium(III) and curium(III) with components of the human mucosa

    Energy Technology Data Exchange (ETDEWEB)

    Wilke, Claudia; Barkleit, Astrid [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Div. Chemistry of the F-Elements

    2016-07-01

    To evaluate the health risks of lanthanides (Ln) and radiotoxic actinides (An) in case of ingestion accidents etc., investigations into the chemical reactions of these metals in the human gastrointestinal tract are necessary. Our previous study revealed that mucin, an important part of the protective mucosa layer in the digestive system, shows a strong interaction with Eu(III). Based on these results, the present study focuses on the components of this glycoprotein and identified N-acetylneuraminic acid (NANA) as the dominant binding carbohydrate of mucin. TRLFS measurements suggest the formation of a 1: 1 complex with log β of 3.2 ± 0.1 for Eu(III) and 3.3 ± 0.1 for Cm(III), respectively.

  3. Oxidation-reduction properties of americium, curium, berkelium, californium, einsteinium and fermium, and thermodynamic consequences for the 5f series

    International Nuclear Information System (INIS)

    Samhoun, K.

    1976-01-01

    The amalgamation of 5f elements from Am to Fm has been studied by using 241 Am, 244 Cm, 249 Bk, 249 Cf, 252 Cf, 253 Es, 254 Es, 252 Fm and 255 Fm with two electrochemical methods, radiocoulometry and radiopolarography, perfectly adapted to investigate extremely diluted solutions when the concentration of electroactive species is as low as 10 -16 M. The theory of radiocoulometry has been developed in the general cases of reversible and irreversible electrode process. It has been used to interpret the experimental data on the kinetic curves of amalgamation, and to estimate the standard rate constant of the electrode process in complexing medium (citric). On the other hand the radiopolarographic method has been applied to study the mechanism of reduction at the dropping mercury electrode of cations M 3+ in aqueous medium to the metal M with formation of amalgam. The results are exploited into two directions: 1- Acquisition of some data concerning the oxidation-reduction properties of elements from Am to Fm. Therefore the standard electrode E 0 [M(III-0)] potentials for Bk, Cf and Es, and the standard electrode E 0 [M(II-0)] potential for Fm are estimated and the relative stability of each oxidation state (from II to VII) of 5f elements is discussed; 2- Acquisition of unknown thermodynamic data on transcalifornium elements. Correlations between 4f and 5f elements are precised and some divergences appear for the second half of 4f and 5f series (i.e. for 65 [fr

  4. Investigation of neutron resonances of 247Cm in the 0.5-20 eV energy range

    International Nuclear Information System (INIS)

    Belanova, T.S.; Kolesov, A.G.; Klinov, A.V.; Nikol'skij, S.N.; Poruchikov, V.A.; Nefedov, V.N.; Artamonov, V.S.; Ivanov, R.N.; Kalebin, S.M.

    1979-01-01

    The neutron resonance parameters of 247 Cm were calculated from the transmission of a curium sample measured by the time-of-flight method. The neutron resonance parameters were calculated by the shape method using the single-level Breit-Wigner formula. Since the neutron resonance parameters of 244 Cm, 245 Cm, 246 Cm, 248 Cm, 243 Am and 240 Pu are well known, it was possible to identify the neutron resonances of 247 Cm from the measured transmission and calculate their parameters. We identified only five neutron resonances of 247 Cm with high values of 2gGAMMAsub(n). This is due to the fact that the 247 Cm content of the sample is low (1.7mg) and the resonances of this isotope are identified against the background of a large number of resonances of 244 Cm, 245 Cm, 246 Cm, 248 Cm, 243 Am and 240 Pu situated in the energy range in question

  5. Transuranium analysis methodologies for biological and environmental samples

    International Nuclear Information System (INIS)

    Wessman, R.A.; Lee, K.D.; Curry, B.; Leventhal, L.

    1978-01-01

    Analytical procedures for the most abundant transuranium nuclides in the environment (i.e., plutonium and, to a lesser extent, americium) are available. There is a lack of procedures for doing sequential analysis for Np, Pu, Am, and Cm in environmental samples, primarily because of current emphasis on Pu and Am. Reprocessing requirements and waste disposal connected with the fuel cycle indicate that neptunium and curium must be considered in environmental radioactive assessments. Therefore it was necessary to develop procedures that determine all four of these radionuclides in the environment. The state of the art of transuranium analysis methodology as applied to environmental samples is discussed relative to different sample sources, such as soil, vegetation, air, water, and animals. Isotope-dilution analysis with 243 Am ( 239 Np) and 236 Pu or 242 Pu radionuclide tracers is used. Americium and curium are analyzed as a group, with 243 Am as the tracer. Sequential extraction procedures employing bis(2-ethyl-hexyl)orthophosphoric acid (HDEHP) were found to result in lower yields and higher Am--Cm fractionation than ion-exchange methods

  6. Boiling water reactors with Uranium-Plutonium mixed oxide fuel. Report 1: Accuracy of the nuclide concentrations calculated by CASMO-4

    International Nuclear Information System (INIS)

    Demaziere, C.

    1999-01-01

    This report is a part of the project titled 'Boiling Water Reactors With Uranium-Plutonium Mixed Oxide (MOx) Fuel'. The aim of this study is to model the impact of a core loading pattern containing MOx bundles upon the main characteristics of a BWR (reactivity coefficients, stability, etc.). The tools that are available to perform a modeling in the Department of Reactor Physics in Chalmers are CASMO-4/TABLES-3/SIMULATE-3 from Studsvik of America. These CMS (Core Management System) programs have been extensively compared with both measurements and reference codes. Nevertheless some data are proprietary in particular the comparison of the calculated nuclide concentrations versus experiments (because of the cost of this kind of experimental study). This is why this report describes such a comparative investigation carried out with a General Electric 7x7 BWR bundle. Unfortunately, since some core history parameters were unknown, a lot of hypotheses have been adopted. This invokes sometimes a significant discrepancy in the results without being able to determine the origin of the differences between calculations and experiments. Yet one can assess that, except for four nuclides - Plutonium-238, Curium-243, Curium-244 and Cesium-135 - for which the approximate power history (history effect) can be invoked, the accuracy of the calculated nuclide concentrations is rather good if one takes the numerous approximations into account

  7. SU-F-T-243: Major Risks in Radiotherapy. A Review Based On Risk Analysis Literature

    Energy Technology Data Exchange (ETDEWEB)

    López-Tarjuelo, J; Guasp-Tortajada, M; Iglesias-Montenegro, N; Monasor-Denia, P [Servicio de Radiofísica y Protección Radiológica, Consorcio Hospitalario Provincial de Castellón, Castellón de la Plana, España/Spain (Spain); Bouché-Babiloni, A; Morillo-Macías, V; Ferrer-Albiach, C [Servicio de Oncología Radioterápica, Consorcio Hospitalario Provincial de Castellón, Castellón de la Plana, España/Spain (Spain)

    2016-06-15

    Purpose: We present a literature review of risk analyses in radiotherapy to highlight the most reported risks and facilitate the spread of this valuable information so that professionals can be aware of these major threats before performing their own studies. Methods: We considered studies with at least an estimation of the probability of occurrence of an adverse event (O) and its associated severity (S). They cover external beam radiotherapy, brachytherapy, intraoperative radiotherapy, and stereotactic techniques. We selected only the works containing a detailed ranked series of elements or failure modes and focused on the first fully reported quartile as much. Afterward, we sorted the risk elements according to a regular radiotherapy procedure so that the resulting groups were cited in several works and be ranked in this way. Results: 29 references published between 2007 and February 2016 were studied. Publication trend has been generally rising. The most employed analysis has been the Failure mode and effect analysis (FMEA). Among references, we selected 20 works listing 258 ranked risk elements. They were sorted into 31 groups appearing at least in two different works. 11 groups appeared in at least 5 references and 5 groups did it in 7 or more papers. These last sets of risks where choosing another set of images or plan for planning or treating, errors related with contours, errors in patient positioning for treatment, human mistakes when programming treatments, and planning errors. Conclusion: There is a sufficient amount and variety of references for identifying which failure modes or elements should be addressed in a radiotherapy department before attempting a specific analysis. FMEA prevailed, but other studies such as “risk matrix” or “occurrence × severity” analyses can also lead professionals’ efforts. Risk associated with human actions ranks very high; therefore, they should be automated or at least peer-reviewed.

  8. 243 The Challenges of Theatre Workshop in Katsina-Ala and Oju ...

    African Journals Online (AJOL)

    USER

    recommends more funding by the College management for Theatre. Arts Department ... exploring and expressing human feelings and predicaments. This is because .... atmosphere where talents and creativity is built in students, fostering ...

  9. Sor/88-243, 21 April 1988, uranium and thorium mining regulations

    International Nuclear Information System (INIS)

    1988-05-01

    These Regulations deal with radiological health and safety in uranium mining facilities and in effect, they formalise previous requirements imposed on such facilities through licence conditions. Licences are required for removing or excavating uranium or thorium; siting, constructing or operating a mine or a mill; and for decommissioning a mining facility. Applications for licences include technical conditions relevant to each type of activity concerned, the common condition being detailed descriptions of the activity, the radiation protection and environmental protection measures as well as the radiation monitoring programme [fr

  10. 43 CFR 30.243 - How will the judge decide my petition for reopening?

    Science.gov (United States)

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false How will the judge decide my petition for... the judge decide my petition for reopening? (a) If the judge finds that proper grounds are not shown, the judge will issue an order denying the petition for reopening and giving the reasons for the denial...

  11. : tous les projets | Page 243 | CRDI - Centre de recherches pour le ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Sujet: Climate change, ADAPTATION TO CHANGE, DROUGHT, FLOODS, HYDROLOGY, AGRICULTURAL LAND, CULTIVATED LAND, LAND USE, PLANNING. Région: Argentina, South America, Paraguay, North and Central America. Programme: Changements climatiques. Financement total : CA$ 391,900.00.

  12. Synthesis of [2,4-3H] 17β-dihydroequilin sulfate

    International Nuclear Information System (INIS)

    Bhavnani, B.R.

    1994-01-01

    [2,4- 3 H] 17β-dihydroequilin-3-sulfate ammonium salt suitable for in vivo pharmacokinetic studies was synthesized from [2,4- 3 H] equilin. Sulfation of [2,4- 3 H] equilin with pyridine-chlorosulfonic acid mixture gave in high yields [2,4- 3 H] equilin sulfate, which was then reduced with sodium borohydride to yield [2,4- 3 H] 17β-dihydroequilin sulfate. The reduction was sterospecific and no 17α-reduced products were formed. (author)

  13. People and things. CERN Courier, Apr 1984, v. 24(3)

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1984-04-15

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The CERN Accelerator School, in collaboration with the Orsay and Saclay Laboratories, is organizing a 'General Accelerator Physics' course at the Ecole Supérieure d'Electricité, Gif-sur-Yvette, France, from 3-14 September.The Scottish Universities Summer School in Physics will be held in St. Andrews from 12 August to 1 September. This is the twenty-seventh school in a series of NATO Advanced Study Institutes organized by the Scottish Universities.From 10-14 September, Geneva University will host the first of a planned biennial series of scientific lectures, sponsored by Dudley Wright. A Conference on the Intersections between Particle and Nuclear Physics' will be held from 23-30 May in Steamboat Springs, Colorado, USA. The meetings will focus on the physics interests of the many diverse groups who work in Particle and/or Nuclear Physics.

  14. 243 Caractérisation floristique et analyse des formes de pression ...

    African Journals Online (AJOL)

    Afrique Sciences

    Résumé. L'objectif de cette étude est d'évaluer les ressources biologiques des forêts sacrées en vue de définir des stratégies pour leur maintien. Le SIG a permis de réaliser la carte de végétation de la forêt qui a servi de base pour la collecte des données floristiques et dendrométriques. La classification hiérarchique des ...

  15. SU-F-T-243: Major Risks in Radiotherapy. A Review Based On Risk Analysis Literature

    International Nuclear Information System (INIS)

    López-Tarjuelo, J; Guasp-Tortajada, M; Iglesias-Montenegro, N; Monasor-Denia, P; Bouché-Babiloni, A; Morillo-Macías, V; Ferrer-Albiach, C

    2016-01-01

    Purpose: We present a literature review of risk analyses in radiotherapy to highlight the most reported risks and facilitate the spread of this valuable information so that professionals can be aware of these major threats before performing their own studies. Methods: We considered studies with at least an estimation of the probability of occurrence of an adverse event (O) and its associated severity (S). They cover external beam radiotherapy, brachytherapy, intraoperative radiotherapy, and stereotactic techniques. We selected only the works containing a detailed ranked series of elements or failure modes and focused on the first fully reported quartile as much. Afterward, we sorted the risk elements according to a regular radiotherapy procedure so that the resulting groups were cited in several works and be ranked in this way. Results: 29 references published between 2007 and February 2016 were studied. Publication trend has been generally rising. The most employed analysis has been the Failure mode and effect analysis (FMEA). Among references, we selected 20 works listing 258 ranked risk elements. They were sorted into 31 groups appearing at least in two different works. 11 groups appeared in at least 5 references and 5 groups did it in 7 or more papers. These last sets of risks where choosing another set of images or plan for planning or treating, errors related with contours, errors in patient positioning for treatment, human mistakes when programming treatments, and planning errors. Conclusion: There is a sufficient amount and variety of references for identifying which failure modes or elements should be addressed in a radiotherapy department before attempting a specific analysis. FMEA prevailed, but other studies such as “risk matrix” or “occurrence × severity” analyses can also lead professionals’ efforts. Risk associated with human actions ranks very high; therefore, they should be automated or at least peer-reviewed.

  16. Electrochemical oxidation of 243Am(III) in nitric acid by a terpyridyl-derivatized electrode

    Energy Technology Data Exchange (ETDEWEB)

    Dares, C. J.; Lapides, A. M.; Mincher, B. J.; Meyer, T. J.

    2015-11-05

    A high surface area, tin-doped indium oxide electrode surface-derivatized with a terpyridine ligand has been applied to the oxidation of trivalent americium to Am(V) and Am(VI) in nitric acid. Potentials as low as 1.8 V vs. the saturated calomel electrode are used, 0.7 V lower than the 2.6 V potential for one-electron oxidation of Am(III) to Am(IV) in 1 M acid. This simple electrochemical procedure provides, for the first time, a method for accessing the higher oxidation states of Am in non-complexing media for developing the coordination chemistries of Am(V) and Am(VI) and, more importantly, for separation of americium from nuclear waste streams.

  17. 243 The Challenges of Theatre Workshop in Katsina-Ala and Oju ...

    African Journals Online (AJOL)

    USER

    primary and secondary methods of carrying out research with interviews, focus ... people working together in order to communicate ideas and also explore social issues to ... affected the effective teaching and learning of Theatre Arts thereby affecting the training of ..... making it different for students to misbehave. Besides, he ...

  18. Mercado/Robb/Buchdahl coefficients: an update of 243 common glasses

    Science.gov (United States)

    Bolser, Michael

    2002-12-01

    The 1983 Mercado/Robb listing of Buchdahl chromatic coordinate coefficients is supplemented with glasses from the Schott and O'Hara catalogues. The coefficients were calculated by using Buchdahl's cubic model. Appropriately selected materials yield a superachromat.

  19. People and things. CERN Courier, Apr 1984, v. 24(3)

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The article reports on achievements of various people, staff changes and position opportunities within the CERN organization and contains news updates on upcoming or past events. The CERN Accelerator School, in collaboration with the Orsay and Saclay Laboratories, is organizing a 'General Accelerator Physics' course at the Ecole Supérieure d'Electricité, Gif-sur-Yvette, France, from 3-14 September.The Scottish Universities Summer School in Physics will be held in St. Andrews from 12 August to 1 September. This is the twenty-seventh school in a series of NATO Advanced Study Institutes organized by the Scottish Universities.From 10-14 September, Geneva University will host the first of a planned biennial series of scientific lectures, sponsored by Dudley Wright. A Conference on the Intersections between Particle and Nuclear Physics' will be held from 23-30 May in Steamboat Springs, Colorado, USA. The meetings will focus on the physics interests of the many diverse groups who work in Particle and/or Nuclear Physics

  20. 30 CFR 250.243 - What general information must accompany the DPP or DOCD?

    Science.gov (United States)

    2010-07-01

    ... characteristics of the produced oil (see definition under 30 CFR 254.6) that you will handle or store at the... definition under § 250.200) you will use to carry out your proposed development and production activities. In... that you expect will have the highest volume of liquid hydrocarbons. Include the estimated flow rate...

  1. Sud du Sahara | Page 243 | CRDI - Centre de recherches pour le ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    Langue English. Read more about Autres modèles de prestation de services publics dans les domaines de la santé, de l'eau et de l'éléctricité (Afrique, Asie, Amérique latine)103828. Langue French. Read more about Alternative Public Service Delivery Models in Health, Water and Electricity (Africa, Asia, Latin America).

  2. Chemical speciation of strontium, americium, and curium in high level waste: Predictive modeling of phase partitioning during tank processing. Annual progress report, October 1996--September 1997

    International Nuclear Information System (INIS)

    Choppin, G.; Felmy, A.R.

    1997-01-01

    'The program at Florida State University was funded to collaborate with Dr. A. Felmy (PNNL) on speciation in high level wastes and with Dr. D. Rai (PNNL) on redox of Pu under high level waste conditions. The funding provided support for 3 research associates (postdoctoral researchers) under Professor G. R. Choppin as P.I. Dr. Kath Morris from U. Manchester (Great Britain), Dr. Dean Peterman and Dr. Amy Irwin (both from U. Cincinnati) joined the laboratory in the latter part of 1996. After an initial training period to become familiar with basic actinide chemistry and radiochemical techniques, they began their research. Dr. Peterman was assigned the task of measuring Th-EDTA complexation prior to measuring Pu(IV)-EDTA complexation. These studies are associated with the speciation program with Dr. Felmy. Drs. Morris and Irwin initiated research on redox of plutonium with agents present in the Hanford Tanks as a result of radiolysis or from use in separations. The preliminary results obtained thus far are described in this report. It is expected that the rate of progress will continue to increase significantly as the researchers gain more experience with plutonium chemistry.'

  3. The distribution of plutonium, americium and curium isotopes in pond and stream sediments of the Savannah River Plant, South Carolina, USA

    International Nuclear Information System (INIS)

    Alberts, J.J.; Halverson, J.E.; Orlandini, K.A.

    1986-01-01

    The concentrations of 238 Pu, 239 , 240 Pu, 241 Am and 244 Cm were determined in sediment samples from five streams and two ponds on the Savannah River Plant (SRP) and in four sediment samples from the Savannah River above and below the plant site. The following concentration ranges were determined: 238 Pu, 0.07-386 fCi g -1 ; 239 , 240 Pu, 0.37-1410 fCi g -1 ; 241 Am, 0.1-4360 fCi g -1 ; 244 Cm, -1 . Comparisons of the elemental and isotopic ratios of the sediments show that the majority of the sediments studied have been impacted upon by plant operations and that sediments outside the plant boundary in the Savannah River have only been influenced by aerial releases. Atom ratios of 240 Pu/ 239 Pu indicate that up to 86% of the Pu in these sediments is derived from plant operations. However, comparisons of the concentration data with values for other impacted sediments near nuclear facilities indicate that the levels are relatively small. Finally, <13% of the Pu, Am or Cm in pond sediments is associated with humic or fulvic acids, indicating that little of the material should be remobilized in oxic environments through organic complexation. (author)

  4. Structural characterisations and mechanistic investigations of the selective dissolution of americium by the ferricyanide ions in alkaline media. Application for the partitioning americium curium

    International Nuclear Information System (INIS)

    Fouchard, Sebastien

    2000-01-01

    Americium exhibits a high solubility form in basic media under oxidant conditions, unlike the other Transplutonium elements (TPE). This property can be used in the frame of High Level Liquid Waste (HLLW) treatment in order to extract preferentially the americium element, the main responsible of the long term radiotoxicity of the nuclear waste. This soluble compound can be obtained by addition of a concentrated basic solution of Fe(CN) 6 3- ions on Am(OH) 3 precipitates. This technique enables a rapid extraction of Am by the synthesis of this soluble form in alkaline solutions. Under these conditions, the other TPE remain in the solid state as trivalent hydroxide solids, strongly insoluble. In the case of dissolutions involving large amounts of Am(OH) 3 , the formation of the soluble complex is concomitant with the appearance of a reddish precipitate in the basic solution. Dissolution experiments which were carried out on this solid in NaOH/Fe(CN) 6 3- have demonstrated the dependency of the solubility equilibria with the media. Spectroscopic studies (UV Visible, XAS) on the precipitate have enabled the determination of the chemical structure and the oxidation state of the americium in the solid: Na 2 Am(V)O 2 (OH) 3 ,nH 2 O. Electrochemical studies on the americium solution have confirmed that the oxidation of Am(OH) 3 by the Fe(CN) 6 3- ions in basic media could only lead to the pentavalent form. A stoichiometric study carries out between a AmO 2 + ion and one Fe(CN) 6 3- ion and the spectroscopic characterisation of this reaction have demonstrated that the Fe(CN) 6 3- ion didn't remain as an un-complexed form in solution after the alkaline mixing. These results tend to prove that this dissolution of Am(OH) 3 is much more complex than a simple oxidation by the Fe(CN) 6 3- ions. The existence of molecular interactions between AmO 2 + and Fe(CN) 6 3- has been postulated and a mechanistic scheme has been proposed in order to explain the appearance of the soluble form of Am in basic ferricyanide media. (author) [fr

  5. Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies

    Energy Technology Data Exchange (ETDEWEB)

    Gourgiotis, A.; Isnard, H.; Aubert, M.; Dupont, E.; AlMahamid, I.; Cassette, P.; Panebianco, S.; Letourneau, A.; Chartier, F.; Tian, G.; Rao, L.; Lukens, W.

    2011-02-01

    The French Atomic Energy Commission has carried out several experiments including the mini-INCA (INcineration of Actinides) project for the study of minor-actinide transmutation processes in high intensity thermal neutron fluxes, in view of proposing solutions to reduce the radiotoxicity of long-lived nuclear wastes. In this context, a Cm sample enriched in {sup 248}Cm ({approx}97 %) was irradiated in thermal neutron flux at the High Flux Reactor (HFR) of the Laue-Langevin Institute (ILL). This work describes a quadrupole ICP-MS (ICP-QMS) analytical procedure for precise and accurate isotopic composition determination of Cm before sample irradiation and of Cm and Cf after sample irradiation. The factors that affect the accuracy and reproducibility of isotopic ratio measurements by ICP-QMS, such as peak centre correction, detector dead time, mass bias, abundance sensitivity and hydrides formation, instrumental background, and memory blank were carefully evaluated and corrected. Uncertainties of the isotopic ratios, taking into account internal precision of isotope ratio measurements, peak tailing, and hydrides formations ranged from 0.3% to 1.3%. This uncertainties range is quite acceptable for the nuclear data to be used in transmutation studies.

  6. Luminescence study on solvation of americium(III), curium(III) and several lanthanide(III) ions in nonaqueous and binary mixed solvents

    International Nuclear Information System (INIS)

    Kimura, T.; Nagaishi, R.; Kato, Y.; Yoshida, Z.

    2001-01-01

    The luminescence lifetimes of An(III) and Ln(III) ions [An=Am and Cm; Ln=Nd, Sm, Eu, Tb and Dy] were measured in dimethyl sulfoxide(DMSO), N,N-dimethylformamide(DMF), methanol(MeOH), water and their perdeuterated solvents. Nonradiative decay rates of the ions were in the order of H 2 O > MeOH > DMF > DMSO, indicating that O-H vibration is more effective quencher than C-H, C=O, and S=O vibrations in the solvent molecules. Maximal lifetime ratios τ D /τ H were observed for Eu(III) in H 2 O, for Sm(III) in MeOH and DMF, and for Sm(III) and Dy(III) in DMSO. The solvent composition in the first coordination sphere of Cm(III) and Ln(III) in binary mixed solvents was also studied by measuring the luminescence lifetime. Cm(III) and Ln(III) were preferentially solvated by DMSO in DMSO-H 2 O, by DMF in DMF-H 2 O, and by H 2 O in MeOH-H 2 O over the whole range of the solvent composition. The order of the preferential solvation, i.e., DMSO > DMF > H 2 O > MeOH, correlates with the relative basicity of these solvents. The Gibbs free energy of transfer of ions from water to nonaqueous solvents was further estimated from the degree of the preferential solvation. (orig.)

  7. Assessment of the radionuclide composition of "hot particles" sampled in the Chernobyl nuclear power plant fourth reactor unit.

    Science.gov (United States)

    Bondarkov, Mikhail D; Zheltonozhsky, Viktor A; Zheltonozhskaya, Maryna V; Kulich, Nadezhda V; Maksimenko, Andrey M; Farfán, Eduardo B; Jannik, G Timothy; Marra, James C

    2011-10-01

    Fuel-containing materials sampled from within the Chernobyl Nuclear Power Plant (ChNPP) Unit 4 Confinement Shelter were spectroscopically studied for gamma and alpha content. Isotopic ratios for cesium, europium, plutonium, americium, and curium were identified, and the fuel burn-up in these samples was determined. A systematic deviation in the burn-up values based on the cesium isotopes in comparison with other radionuclides was observed. The studies conducted were the first ever performed to demonstrate the presence of significant quantities of 242Cm and 243Cm. It was determined that there was a systematic underestimation of activities of transuranic radionuclides in fuel samples from inside of the ChNPP Confinement Shelter, starting from 241Am (and going higher) in comparison with the theoretical calculations.

  8. Actinide analytical program for characterization of Hanford waste

    International Nuclear Information System (INIS)

    Johnson, S.J.; Winters, W.I.

    1977-01-01

    The objective of this program has been to develop faster, more accurate methods for the concentration and determination of actinides at their maximum permissible concentration (MPC) levels in a controlled zone. These analyses are needed to characterize various forms of Hanford high rad waste and to support characterization of products and effluents from new waste management processes. The most acceptable methods developed for the determination of 239 Pu, 238 Pu, 237 Np, 241 Am, and 243 Cm employ solvent extraction with the addition of tracer isotopes. Plutonium and neptunium are extracted from acidified waste solutions into Aliquat-336. Americium and curium are then extracted from the waste solution at the same acidity into dihexyl-N,N-diethylcarbamylmethylenephosphonate (DHDECMP). After back extraction into an aqueous matrix, these actinides are electrodeposited on steel disks for alpha energy analysis. Total uranium and total thorium are also isolated by solvent extraction and determined spectrophotometrically

  9. Determination of the first ionization potential of actinides by resonance ionization mass spectroscopy

    International Nuclear Information System (INIS)

    Koehler, S.; Albus, F.; Dibenberger, R.; Erdmann, N.; Funk, H.; Hasse, H.; Herrmann, G.; Huber, G.; Kluge, H.; Nunnemann, M.; Passler, G.; Rao, P.M.; Riegel, J.; Trautmann, N.; Urban, F.

    1995-01-01

    Resonance ionization mass spectroscopy (RIMS) is used for the precise determination of the first ionization potential of transuranium elements. The first ionization potentials (IP) of americium and curium have been measured for the first time to IP Am =5.9738(2) and IP Cm =5.9913(8) eV, respectively, using only 10 12 atoms of 243 Am and 248 Cm. The same technique was applied to thorium, neptunium, and plutonium yielding IP T H =6.3067(2), IP N P =6.2655(2), and IP Pu =6.0257(8) eV. The good agreement of our results with the literature data proves the precision of the method which was additionally confirmed by the analysis of Rydberg seris of americium measured by RIMS. copyright American Institute of Physics 1995

  10. 324 Building Baseline Radiological Characterization

    International Nuclear Information System (INIS)

    Reeder, R.J.; Cooper, J.C.

    2010-01-01

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building. A total of 85 technical (100 square centimeter (cm 2 )) smears were collected from the Room 147 hoods, the Shielded Materials Facility (SMF), and the Radiochemical Engineering Cells (REC). Exposure rate readings (window open and window closed) were taken at a distance of 2.5 centimeters (cm) and 30 cm from the surface of each smear. Gross beta-gamma and alpha counts of each smear were also performed. The smear samples were analyzed by gamma energy analysis (GEA). Alpha energy analysis (AEA) and strontium-90 analysis were also performed on selected smears. GEA results for one or more samples reported the presence of manganese-54, cobalt-60, silver-108m antimony-125, cesium-134, cesium-137, europium-154, europium-155, and americium-241. AEA results reported the presence of plutonium-239/240, plutonium-238/ 241 Am, curium-243/244, curium-242, and americium-243. Tables 5 through 9 present a summary by location of the estimated maximum removable and total contamination levels in the Room 147 hoods, the SMF, and the REC. The smear sample survey data and laboratory analytical results are presented in tabular form by sample in Appendix A. The Appendix A tables combine survey data documented in radiological survey reports found in Appendix B and laboratory analytical results reported in the 324 Building Physical and Radiological Characterization Study (Berk, Hill, and Landsman 1998), supplemented by the laboratory analytical results found in Appendix C.

  11. Transplutonium elements production program: extraction chromatographic process for plutonium irradiated targets

    International Nuclear Information System (INIS)

    Bourges, J.; Madic, C.; Koehly, G.

    1980-01-01

    The treatment of irradiated plutonium targets by extraction chromatography allowed the purification of the isotopes 243 Am and 244 Cm on the scale of few tens of grams. This process proved to be extremely simple and flexible, and yielded results which are reproducible in time. The chief advantage of the TBP process over the HDEHP process in high and medium activity conditions lies in the rapid absorption/desorption kinetics of the elements to be purified and in the separation of americium from curium, which largely offsets its lower selectivity for lanthanide elements. it is certainly possible to improve the performance of this process by: a) optimization of the characteristics of the stationary phase, b) improvement in the filling technique and in hydraulic operation of the columns, c) on-line analysis of americium (the key element in actinide/lanthanide separation) in the eluate. The application of extraction chromatography with HD(DiBM)P to the purification of 243 Am of the end of treatment makes the process more consistent, eliminates the delicate stages implemented in hot cell, and considerably improves final product quality

  12. Development of a multi-functional reprocessing process based on ion-exchange method by using tertiary pyridine-type resin

    International Nuclear Information System (INIS)

    Koyama, Shin-ichi; Ozawa, Masaki; Suzuki, Tatsuya; Fujii, Yasuhiko

    2006-01-01

    A series of separation experiment was performed in order to study a multi-functional spent fuel reprocessing process based on ion-exchange technique. The tertiary pyridine-type anion-exchange resin was used in this experiment and the mixed oxide fuel highly irradiated in the experimental fast reactor ''JOYO'' was used as a reference spent fuel. As the result, 106 Ru + 125 Sb, 137 Cs + 155 Eu + 144 Ce, plutonium, americium and curium could be separated from the irradiated fuel by only three steps of ion-exchange. The decontamination factor of 137 Cs and trivalent lanthanides ( 155 Eu, 144 Ce) in the final americium product exceeded 3.9 x 10 4 and 1.0 x 10 5 , respectively. The decontamination factor for the mutual separation of 243 Cm and 241 Am was larger than 2.2 x 10 3 for the americium product and, moreover, the content of 137 Cs, trivalent lanthanides and 243 Cm included in 241 Am product did not exceed 2 ppm. These results prove that the proposed simplified separation process has a reality as a candidate for future reprocessing process based on the partitioning and transmutation concept. (author)

  13. SU-E-T-243: Design of a Novel Testing Port for Radiation Protection and Shielding Measurements

    International Nuclear Information System (INIS)

    Tanny, S; Parsai, E; Harrell, D; Noller, J; Chopra, M

    2015-01-01

    Purpose: The majority of radiation shielding research utilizes Monte Carlo simulation because of the difficulty in eliminating secondary radiations from measurements. We have designed a test port into a primary barrier of our newest vault to allow for shielding measurements while ensuring adequate protection to the public and staff during normal machine operation. This port allows for measurement of attenuation values of shielding materials, differential dose albedos, and radiation scatter fractions. Methods: The vault design utilized the maze as part of a compound primary barrier. The test port is contained within the maze and is centered along isocenter. The inner 30 cm has a 20×20 cm 2 opening, while the remaining length has a 30×30 cm 2 opening. The block that contains the port has a density of 200 pcf to minimize internal scatter. The 30×30 cm 2 opening is occupied by removable 215 pcf concrete blocks. The innermost and outermost blocks activate an interlock wired into the beam-enable loop. This disallows beam-on in treatment mode if the interlock isn’t closed. The interlock can be overridden in service mode, or by-passed via an override switch in case of circuit failure. Results: The test port was installed in August. The beam is disabled when the interlock is tripped. Measurements taken when the primary beam is not incident on the port are indistinguishable from background. Ambient dose levels surrounding the vault with the designed shielding blocks in place are all within allowable limits for occupational workers. Conclusions: We have designed and installed a unique testing port for radiation protection and shielding measurements. This port is appropriately interlocked and designed to mitigate any risks of incidental exposure to staff or members of the public. The test port design allows measurements with “good geometry” and efficient removal of contaminating sources of radiation present in many shielding measurements. Daniel Harrell and Jim Noller are employees of Shielding Construction Solutions, Inc, the shielding construction company that built the vault discussed in this abstract. Manjit Chopra is an employee of Universal Minerals International, Inc, the company that provided the aggregates for the high density concretes used in the vault construction

  14. Homeopathy and Isopathy in the periodontal maintenance therapy of aggressive periodontitis patients - doi:10.5020/18061230.2007.p243

    Directory of Open Access Journals (Sweden)

    Edivaldo Barbosa da Silva

    2012-01-01

    Full Text Available Periodontal maintenance care is an essential part of periodontal therapy for patients diagnosed with Aggressive Periodontitis, being, however, hard to instruct and to motivate these patients to follow a careful and effective program of maintenance for all their lives. A literature review was done, by means of relevant papers published on the last four decades, pointing out the importance of individual susceptibility for the appearance of aggressive periodontitis and to discuss the importance of a maintenance therapy on its treatment, applying Homeopathy and Isopathy. Homeopathy consists on a complex therapeutic system mainly based on the “Law of Similarity”, that is, the illness may be healed by drugs that produce similar symptoms in a healthy organism and, in this conception, the disease is understood as an energetic unbalance, in which internal and external factors acting on the subject’s susceptibility are considered and can be expressed by an individual symptomathology that goes from the rational sphere to the somatic sphere. On the other hand, Isopathy is the method of treatment with therapeutic agent, which actions on a healthy subject consist on pharmacodynamic manifestations similar to those observed in a sick person. Based on these concepts, the authors establish a hypothesis of the effectiveness of Homeopathy and Isopathy, the latter through auto-medications or auto-biotherapies, that are products which the active principal is obtained from the patient himself (gingival tissue and secretions, and that may be used as auxiliary treatments in the maintenance therapy of Aggressive Periodontitis.

  15. Chromosome 12q24.3 controls sensitization to cat allergen in patients with asthma from Siberia, Russia

    Czech Academy of Sciences Publication Activity Database

    Gusareva, Elena; Bragina, E.J.; Buinova, S.N.; Chernyak, B.A.; Puzyrev, V.P.; Ogorodova, L.M.; Lipoldová, Marie

    2009-01-01

    Roč. 125, č. 1 (2009), s. 1-6 ISSN 0165-2478 R&D Projects: GA ČR GA310/06/1745; GA MŠk(CZ) LC06009 Grant - others:EC(XE) 05-1000004-7761 Institutional research plan: CEZ:AV0Z50520514 Keywords : IgE * asthma * cat allergens Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 2.906, year: 2009

  16. Geologic interpretation of seismic data relocation Route 2, Littleton Road grade separation stations 243-252 in Harvard, Mass.

    Science.gov (United States)

    May, James E.; Linehan, Rev. Daniel

    1950-01-01

    During parts of June and July 1949 nine seismic traverses were made at this site. Upon preliminary office development, the velocity data for some of these traverses were though to be inadequate and it was recommended that these lines be re-surveyed. Later surveys (March 1950), however, of nearby sites indicated that the original data were reliable and that a re-survey was unnecessary. The work was done as part of a cooperative program of the Massachusetts Department of Public Works and the United States Geological Survey.

  17. Beliefs and opinions in caregiving of elderly with AIDS: an exploratory study - doi:10.5020/18061230.2010.p243

    Directory of Open Access Journals (Sweden)

    Raquel Farias Diniz

    2012-01-01

    Full Text Available Objective: To explore what informal caregivers of elderly with AIDS think about the disease itself, the infection in elderly people, and about being a caregiver. Methods: A qualitative study in which the thematic content analysis of interviews resulted in the emergence of three categories: “conceptions about AIDS”, “AIDS in old age” and “being a caregiver”. Results: We observed the emergence of issues related to the three aspects, which must be considered in a broader analysis within the patient-caregiver relationship. Such questions involve information about the disease, living with the patient, gender differences and the specificities resulting from the infection at this stage of life. Conclusion: From this study, it is expected that greater attention be given to relationships of care provided by informal network of support to elderly people living with AIDS, in order to foster researches on social, affective, motivational and behavior aspects of caregivers.

  18. Angelman syndrome associated with an inversion of chromosome 15q11.2q24.3

    Energy Technology Data Exchange (ETDEWEB)

    Greger, V.; Knoll, J.H.M.; Wagstaff, J.; Lalande, M. [and others

    1997-03-01

    Angelman syndrome (AS) most frequently results from large ({ge}5 Mb) de novo deletions of chromosome 15q11-q13. The deletions are exclusively of maternal origin, and a few cases of paternal uniparental disomy of chromosome 15 have been reported. The latter finding indicates that AS is caused by the absence of a maternal contribution to the imprinted 15q11-q13 region. Failure to inherit a paternal 15q11-q13 contribution results in the clinically distinct disorder of Prader-Willi syndrome. Cases of AS resulting from translocations or pericentric inversions have been observed to be associated with deletions, and there have been no confirmed reports of balanced rearrangements in AS. We report the first such case involving a paracentric inversion with a breakpoint located {approximately}25 kb proximal to the reference marker D15S10. This inversion has been inherited from a phenotypically normal mother. No deletion is evident by molecular analysis in this case, by use of cloned fragments mapped to within {approximately}1 kb of the inversion breakpoint. Several hypotheses are discussed to explain the relationship between the inversion and the AS phenotype. 47 refs., 3 figs.

  19. 75 FR 60655 - Airworthiness Directives; Airbus Model A330-201, -202, -203, -223, and -243 Airplanes; Airbus...

    Science.gov (United States)

    2010-10-01

    ... time during which fuel tanks are exposed to flammable conditions is one of these criteria. The other... flammable fuel vapors, could result in fuel tank explosions and consequent loss of the airplane. [[Page... information and, in general, agree with their substance. But we might have found it necessary to use different...

  20. Fission Meter Information Barrier Attribute Measurement System - NA-243 FNI/UKC FY2017 Task 1-2 Report

    Energy Technology Data Exchange (ETDEWEB)

    Kerr, P. L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Decman, D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Prasad, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Castro, P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2018-01-03

    An SNM attribute Information Barrier (IB) system was developed for a 2011 US/UK Exercise. The system was modified and extensively tested in a 2013-2014 US-UK Measurement Campaign. This work demonstrated rapid deployment of an IB system for potential treaty use. The system utilizes an Ortec Fission Meter neutron multiplicity counter and custom computer code. The system demonstrates a proof-of-principle automated Pu-240 mass determination with an information barrier. After a software start command is issued, the system automatically acquires and downloads data, performs an analysis, and displays the results. This system conveys the results of a Pu mass threshold measurements in a way the does not reveal sensitive information. In full IB mode, only the pass/fail result is displayed as a “Mass <= Threshold Amount” or “Mass >= Threshold Amount” as shown in Figure 4. This can easily be adapted to a red/green “lights” display similar to the Detective IB system for Pu isotopics as shown in Figure 6. In test mode, more detailed information is displayed. The code can also read in, analyze, and display results from previously acquired or simulated data. Because the equipment is commercial-off-the-shelf (COTS), the system demonstrates a low-cost short-lead-time technology for treaty SNM attribute measurements. A deployed system will likely require integration of additional authentication and tamper-indicating technologies. This will be discussed for the project in this and future progress reports.

  1. Extractability of plutonium-238 and curium-242 from a contaminated soil as a function of pH and certain soil components. CH3COOH-NH4OH system

    International Nuclear Information System (INIS)

    Nishita, H.

    1978-01-01

    Extractability of 238 Pu and 242 Cm from an artificially contaminated soil as a function of pH and certain soil components was examined with an equilibrium batch technique by the use of a CH 3 COOH--NH 4 OH extracting system. The influence of various soil components on 238 Pu and 242 Cm extractability was determined indirectly by selective removal of the components from the soil. The soil organic matter appeared to have a major influence on the extractability of these radionuclides. Though to a lesser extent, free iron oxides exerted an influence also. Before removal of soil organic matter, the extractability curves for these radionuclides were qualitatively similar in general form. The nature of this form is discussed. Within the contaminated, untreated soil, the 238 Pu and 242 Cm extractability ranged from 0.60 to 30.8% and 0.11 to 14.83% of dose, respectively, depending on the pH of the extracting solution. The liquid-to soild-phase ratio (K'/sub d/) values ranged from 3.5 x 10 -4 to 2.7 x 10 -2 for 238 Pu and 0.9 x 10 -4 to 1.4 x 10 -2 for 242 Cm. Very low extractability occurred in the pH range from approx. 8.6 to approx. 9.7 for 238 Pu and from 7.6 to approx. 9.7 for 242 Cm

  2. Neutron-induced Fission Cross Sections of Am and Cm isotopes (Final Report of Research Contract 14485). Resonance and Fast Neutron Induced Fission Cross Sections of Americium and Curium Nuclides (Third-year Progress Report of Research Contract 14485)

    International Nuclear Information System (INIS)

    Alekseev, A.A.; Bergman, A.A.; Berlev, A.I.; Koptelov, E.A.; Egorov, A.S.; Samylin, B.F.; Trufanov, A.M.; Fursov, B.I.; Shorin, V.S.

    2012-01-01

    The neutron induced fission cross sections of Am and Cm isotopes were measured relative to 239 Pu in the neutron energy range from 1 eV to 20 keV at the INR RAS lead slowing down spectrometer LSDS-100. The fission resonance integrals were also estimated using the measured cross section data. The results have been compared with the available experimental and evaluated data. This analysis has shown the present status of the measured fission cross sections and the necessity to revise the evaluated cross sections libraries for the minor actinides. (author)

  3. Transuranium Processing Plant semiannual report of production, status, and plans for period ending December 31, 1976

    International Nuclear Information System (INIS)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1977-10-01

    During the period July 1, 1976, through December 31, 1976, transuranium elements were obtained from 11 irradiated HFIR targets; products recovered are 0.3 g 243 Am, 16.6 g 244 Cm, 23 g 249 Bk, 211 g 252 Cf, 1.15 mg 253 Es, and 0.4 pg 247 Fm. Two batches of high-purity 248 Cm were purified chemically for shipment, and another batch containing about 62 mg of 248 Cm was separated from 252 Cf. Thirty shipments were made from TRU during the period; recipients and the amounts of nuclides are listed in tabular form. Nine HFIR targets, each containing 8 to 9 g of curium, were fabricated. The sequence of chemical processing steps used to purify the californium product was changed; this change yielded a shorter recovery time for high-purity 253 Es, which enabled a 50% increase in the amount obtained. Eight neutron sources were fabricated during this report period, bringing the total fabricated to date to 92. Three sources that had previously been returned to TRU were reassigned; two others are also available for reassignment. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

  4. Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1974

    International Nuclear Information System (INIS)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1975-07-01

    During the period July 1, 1974, through December 31, 1974, the following amounts of transuranium elements were recovered from 11 irradiated HFIR targets: 1.5 g 243 Am, 45 g 244 Cm, 24 mg 249 Bk, 252 mg 252 Cf, 1.25 mg 253 Es, and 0.5 pg 257 Fm. In addition, 34 mg of high-purity 248 Cm was separated from 252 Cf which had been recovered and purified during earlier periods. Nine HFIR targets, each containing 8 to 9 g of actinides (predominantly curium), were fabricated. Some of the chemical processing steps used for processing HFIR targets were added, deleted, or rearranged in order to reduce processing time and increase product yields. One cubicle equipment rack was replaced and the out-of-cell piping and equipment associated with the remotely operated valves in the TRU cubicles was revised. One neutron source was fabricated. Three sources that had been used previously in various projects and returned to TRU were reloaned. A special project was begun to recover 126 Sn from TRU process solutions. The values currently in use for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix. (U.S.)

  5. Transuranium processing plant semiannual report of production, status, and plans for period ending June 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1977-02-01

    During the period January 1, 1976, through June 30, 1976, the following amounts of transuranium elements were recovered from ten irradiated HFIR targets: 2 g /sup 243/Am, 50 g /sup 244/Cm, 29 mg /sup 249/Bk, 277 mg /sup 252/Cf, 1.7 mg /sup 253/Es, and 0.5 pg /sup 257/Fm. About 50 mg of high-purity /sup 248/Cm was purified chemically for shipment, and another 75 mg of /sup 248/Cm was separated from /sup 252/Cf. Nineteen HFIR targets, each containing approximately 9 g of curium, were fabricated. There have been no changes during this report period in the chemical processing flowsheets normally used at TRU. Five neutron sources were fabricated, bringing the total fabricated to 84. Six sources that were used previously in various projects have been returned to TRU and are available for reassignment. Special projects included (1) the continued study of /sup 250/Cm production by irradiation of /sup 248/Cm; (2) the production of 0.54 mg of /sup 250/Cf by irradiation of /sup 249/Bk; (3) the separation of approximately 200 pg of /sup 254/Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 ..mu..g of /sup 253/Es; and (4) the determination of process steps needed to obtain rare-earth fission products in an oxide form from LiCl-based anion exchange raffinate solution.

  6. Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1977

    International Nuclear Information System (INIS)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1978-08-01

    Transuranium elements were obtained from 13 irradiated HFIR targets. One batch of high-purity 248 Cm (approximately 75 mg) was separated from 252 Cf. Eighteen shipments were made from TRU during the period. Seven HFIR targets, each containing 8 to 9 g of curium, were fabricated. A new scrubber system was installed in the dissolver off-gas (DOG) stream to remove the bulk of the 131 I and to reduce the amount sorbed in the Hopcalite--charcoal system. During TRU target Campaign 53, the DOG stream was scrubbed with hyperazeotropic nitric acid (the IODOX process). Both the equipment and the process performed satisfactorily. Three neutron sources were fabricated during this report period, bringing the total fabricated to date to 100. Six sources were returned to TRU and are available for reassignment. Special projects included the production of several grams of ultrahigh-purity 243 Am and the development of a method for purification of the ZnBr 2 solution from a shielding window. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated

  7. Characteristics of Private Schools in the United States: Results from the 2013-14 Private School Universe Survey. First Look. NCES 2016-243

    Science.gov (United States)

    Broughman, Stephen P.; Swaim, Nancy L.

    2016-01-01

    In 1988, the National Center for Education Statistics (NCES) developed a private school data collection that improved on the sporadic collection of private school data dating back to 1890 and at the same time developed an alternative to commercially available private school sampling frames. Since 1989, the U.S. Bureau of the Census has conducted…

  8. Benjamin Fondane notebooks. Benjamin Fondane facing the History. About the Existential Monday. The Poem time, no. 14/2011, Editions Kedem, Tel Aviv, 243 p.

    Directory of Open Access Journals (Sweden)

    Speranţa Sofia MILANCOVICI

    2011-01-01

    Full Text Available Luna august reprezintă, pentru membrii sau colaboratorii Socièté d’Etudes Benjamin Fondane, momentul întâlnirii ştiinţifice anuale sub genericul Rencontres de Peyresq. Fiecare astfel de reuniune este succedată de apariţia unui volum critic realizat cu sprijinul Centre National du Livre – France. Este vorba despre seria deja cunoscutelor, în bibliografia de specialitate, Cahiers Benjamin Fondane.Volumul recent apărut poartă titlul Benjamin Fondane devant l’Histoire. Autour du Lundi existentiel. Au temps du Poème şi este cel de al paisprezecelea număr din seria caietelor.În îngrijirea energicei şi competentei preşedinte a Société d’Etudes Benjamin Fondane, prof. dr. Monique Jutrin, volumul propune spre lectură cercetătorilor de specialitate un corpus de eseuri critice grupate pe secţiuni: editorial, filosofie, poezie, opera în limba română a lui Benjamin Fundoianu, bibliografie de specialitate etc.

  9. SCRIB and PUF60 are primary drivers of the multisystemic phenotypes of the 8q24.3 copy-number variant

    DEFF Research Database (Denmark)

    Dauber, Andrew; Golzio, Christelle; Guenot, Cécile

    2013-01-01

    phenotype, and the combinatorial suppression of both genes exacerbated some, but not all, phenotypic components. Consistent with these findings, we identified an individual with microcephaly, short stature, intellectual disability, and heart defects with a de novo c.505C>T variant leading to a p.His169Tyr...... genetic disease and demonstrate how CNVs can exhibit complex genetic architecture, with the phenotype being the amalgam of both discrete dosage dysfunction of single transcripts and also of binary genetic interactions....

  10. OPTICAL VARIABILITY OF THE ACCRETION DISK AROUND THE INTERMEDIATE-MASS BLACK HOLE ESO 243-49 HLX-1 DURING THE 2012 OUTBURST

    Energy Technology Data Exchange (ETDEWEB)

    Webb, N. A.; Godet, O.; Barret, D. [Université de Toulouse, UPS-OMP, IRAP, Toulouse (France); Wiersema, K. [University of Leicester, University Road, Leicester LE1 7RH (United Kingdom); Lasota, J.-P. [Institut d' Astrophysique de Paris, UMR 7095, CNRS, UPMC Université Paris 06, 98bis Boulevard Arago, F-75014 Paris (France); Farrell, S. A. [Sydney Institute for Astronomy, School of Physics, The University of Sydney, NSW 2006 (Australia); Maccarone, T. J. [Department of Physics, Box 41051, Texas Tech University, Lubbock TX 79409-1051 (United States); Servillat, M., E-mail: natalie.webb@irap.omp.eu [Laboratoire AIM (CEA/DSM/IRFU/SAp, CNRS, Université Paris Diderot), CEA Saclay, Bat. 709, F-91191 Gif-sur-Yvette (France)

    2014-01-01

    We present dedicated quasi-simultaneous X-ray (Swift) and optical (Very Large Telescope, V-, and R-band) observations of the intermediate-mass black hole candidate HLX-1 before and during the 2012 outburst. We show that the V-band magnitudes vary with time, thus proving that a portion of the observed emission originates in the accretion disk. Using the first quiescent optical observations of HLX-1, we show that the stellar population surrounding HLX-1 is fainter than V ∼ 25.1 and R ∼ 24.2. We show that the optical emission may increase before the X-ray emission consistent with the scenario proposed by Lasota et al. in which the regular outbursts could be related to the passage at periastron of a star circling the intermediate-mass black hole in an eccentric orbit, which triggers mass transfer into a quasi-permanent accretion disk around the black hole. Further, if there is indeed a delay in the X-ray emission we estimate the mass-transfer delivery radius to be ∼10{sup 11} cm.

  11. A comprehensive study of fission in 24.3 MeV/nucleon U reactions induced on C, Si, Ni, Au targets

    International Nuclear Information System (INIS)

    Piasecki, E.; Pienkowski, L.; Czosnyka, T.; Iwanicki, J.; Muchorowska, M.; Tucholski, A.; Czarnacki, W.; Chbihi, A.; Galin, J.; Crema, E.; Sao Paulo Univ., SP

    1995-01-01

    Fission is a powerful tool for studying the primary reaction mechanisms in nucleus-nucleus collisions involving at least one fissionable nucleus. This is well shown when an additional information on the violence of the collision is provided by a totally independent observable such as the neutron multiplicity. The mass asymmetry in the entrance channel and the impact parameter are shown to have a decisive influence on the fate of the collision leading to either fusion or a two-body deeply inelastic reaction, analogous to what is known at lower bombarding energies. The experimental approach allows also to single out electromagnetic fission of U after interaction with Au and to provide some characteristics of such a process. (author)

  12. A Rare Interstitial Duplication of 8q22.1–8q24.3 Associated with Syndromic Bilateral Cleft Lip/Palate

    Directory of Open Access Journals (Sweden)

    Regina Ferreira Rezek

    2014-01-01

    Full Text Available We present a rare case of 8q interstitial duplication derived from maternal balanced translocations in a patient with bilateral cleft lip and palate in syndromic form associated with other congenital malformations. G-banding cytogenetic analysis revealed a chromosomal abnormality in the form of the karyotype 46,XX der(22t(8;22(q22.1;p11.1mat. Chromosome microarray analysis evidenced a 49 Mb duplicated segment of chromosome 8q with no pathogenic imbalances on chromosome 22. Two siblings also carry the balanced translocation. We have compared this case with other “pure” trisomies of 8q patients reported in the literature and with genome wide association studies recently published. This work highlights the involvement of chromosome 8q in orofacial clefts.

  13. The synthesis of 7-chloro-5-pentadeuteriophenyl-1-methyl-1H-1, 5-benzodiazepine-2,4(3H, 5H)dione ([2H5]clobazam)

    International Nuclear Information System (INIS)

    Borel, A.G.; Abbott, F.S.

    1990-01-01

    Pentadeuteriophenyl clobazam was synthesized in essentially quantitative isotopic purity, and characterized by 1 H-NMR and mass spectroscopy. The title compound was found to be >98% pure by HPLC, and its retention time (t R 6.17 min) was less than that of an authentic clobazam standard (t R 6.32 min). Of the five steps in the synthesis of clobazam, the most susceptible to deuterium exchange was the nucleophilic substitution of 2,4-dichloronitrobenzene by aniline-d 7 to form N-(5-chloro-2-nitrophenyl)penta-deuteriophenylamine. In this step, the isotopic impurity aniline-2,3,4,5-d 5 introduced protons from nitrogen into the ortho and para positions of the deuteriophenyl ring of N-(5-chloro-2-nitrophenyl)pentadeuteriophenylamine. (author)

  14. Intellectual disability, muscle weakness and characteristic face in three siblings: A newly described recessive syndrome mapping to 3p24.3-p25.3

    NARCIS (Netherlands)

    Kariminejad, Ariana; Nafissi, Shahriar; Nilipoor, Yalda; Tavasoli, Alireza; van Veldhoven, Paul P.; Bonnard, Carine; Ng, Yeng Ting; Majoie, Charles B.; Reversade, Bruno; Hennekam, Raoul C.

    2015-01-01

    We report on a sister and two brothers born to healthy Iranian parents with mild intellectual disability, progressive muscle weakness, and characteristic facies. including highly arched eyebrows, down-slanting palpebral fissures, prominent nasal bridge, prominent nose, columella extending below alae

  15. Determinant factors of cardiorespiratory fitness in Portuguese adolescents of different ethnicities. DOI: 10.5007/1980-0037.2011v13n4p243

    Directory of Open Access Journals (Sweden)

    Diana Aguiar Santos

    2011-08-01

    Full Text Available Cardiorespiratory fitness is an important health indicator in young people. The aim of this study was to investigate the effects of age, gender, body adiposity, and ethnicity on cardiorespiratory fitness in a sample of Portuguese adolescents. The sample consisted of 266 adolescents aged 12-18 years [112 boys (80 Caucasians and 32 African-Portuguese, AP and 154 girls (109 Caucasians and 45 AP]. Percent body fat was estimated with a hand-to-hand bioelectrical impedance device (BF300, OMROM. Cardiorespiratory fitness was assessed by a shuttle run test (Fitnessgram battery. Multiple regression models were used for statistical analysis. The results showed that girls presented lower maximal oxygen consumption and higher percent body fat than boys. Cardiorespiratory fitness was lower in Caucasian than in AP girls. Multiple regression analysis showed that percent body fat, age and the interaction of age with being Caucasian and age with female gender were significant determinants that were negatively associated with cardiorespiratory fitness. The results suggest that maximal oxygen consumption is lower in adolescents with higher adiposity and in older adolescents. The findings highlight the importance of promoting physical fitness in schools across ages, especially in older adolescents, adjusting for determinant factors such as gender and ethnicity

  16. Comment on ”John’s stone: A possible fragment of the 1908 Tunguska meteorite” (Anfinogenov et al., 2014, Icarus 243, 139-147)

    DEFF Research Database (Denmark)

    Haack, Henning; Greenwood, Richard; Busemann, Henner

    2016-01-01

    et al. However, since sandstones can only form on a parent body with liquid water and by inference, also an atmosphere, we argue that there are only two possible parent bodies in the Solar System: the Earth and Mars. Mars can be ruled out for several reasons, including the oxygen isotopic and noble...... gas composition of John’s stone, which is clearly distinct from martian meteorites. Consistent with the O study, the noble gases do not provide any evidence for an extraterrestrial origin of the samples. The lack of any cosmogenic noble gases (particularly striking in 3He, 21Ne, 38Ar) is consistent...... with a terrestrial origin or an extraterrestrial origin under large shielding. Based on the combined evidence obtained in this study we infer that John’s stone is a terrestrial rock unrelated to the Tunguska impactor....

  17. 30 CFR 243.7 - What must a person do when posting a bond or other surety instrument or demonstrating financial...

    Science.gov (United States)

    2010-07-01

    ...(a), or any other theory, as a defense if MMS calls your bond or requires you to pay based on your... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must a person do when posting a bond or....7 Mineral Resources MINERALS MANAGEMENT SERVICE, DEPARTMENT OF THE INTERIOR MINERALS REVENUE...

  18. Synthesis of 24S and 24R-hydroxy-[24-3H] vitamin D3 and their metabolism in rachitic rats

    International Nuclear Information System (INIS)

    Tanaka, Y.; DeLuca, H.F.; Akaiwa, A.; Morisaki, M.; Ikekawa, N.

    1976-01-01

    An epimeric mixture of 24-hydroxy-[24- 3 H] vitamin D 3 was synthesized by the reduction of 24-ketovitamin D 3 by sodium borotritide. The epimeric mixture was converted to the trimethylsilylether derivatives and subjected to high-pressure liquid chromatography using silica gel columns to separate the 24-hydroxy-[24- 3 H] vitamin D 3 isomers. The 24R-hydroxy-[24- 3 H]vitamin D 3 induced calcification in rachitic rats while the 24S-hydroxy-[24- 3 H]vitamin D 3 had little or no such activity. As both isomers of 24-hydroxy-vitamin D 3 are metabolized to 24,25-dihydroxyvitamin D 3 , it appears that the 24-hydroxyvitamin D 3 -25-hydroxylase does not discriminate between the isomers. Only the R-isomer of 24-hydroxyvitamin D 3 is metabolized to 1,24-dihydroxyvitamin D 3 , although only trace amounts of this compound were found 2 days after the administration of 24-hydroxyvitamin D 3 . The striking difference in the metabolism of the isomers is the high selectivity of the 1-hydroxylase for the R-isomer. It is suggested that the high specificity of biological activity for the R-isomer of 24-hydroxyvitamin D 3 is because of the specificity of the 1-hydroxylation of 24,25-dihydroxyvitamin D 3 for the R configuration

  19. Konference o srovnávacím výzkumu bydlení, Delft, Nizozemsko, 24.3. – 25.3. 2010

    Czech Academy of Sciences Publication Activity Database

    Sládek, Jan

    2010-01-01

    Roč. 8, č. 5 (2010), s. 9 ISSN 1214-1720 R&D Projects: GA ČR GA403/09/1915 Institutional research plan: CEZ:AV0Z70280505 Keywords : methodology * city * theory Subject RIV: AO - Sociology, Demography http://www.socioweb.cz/upl/editorial/download/179_soc.web._05-2010%20final!.pdf

  20. 49 CFR 40.243 - What is the procedure for an alcohol screening test using an EBT or non-evidential breath ASD?

    Science.gov (United States)

    2010-10-01

    ...-evidential breath ASD? As the BAT or STT, you must take the following steps: (a) Select, or allow the... individually wrapped or sealed mouthpiece in view of the employee and insert it into the device in accordance... the mouthpiece for at least six seconds or until the device indicates that an adequate amount of...

  1. 76 FR 24832 - Airworthiness Directives; Airbus Model A330-201, -202, -203, -223, and -243 Airplanes, A330-300...

    Science.gov (United States)

    2011-05-03

    ... include vacuum loss and elasticity laminate checker inspections for damage including de-bonding between... exist or develop on other products of the same type design. Differences Between This AD and the MCAI or... elasticity laminate checker inspection on the trailing edge area (Area 2) for damage including de-bonding...

  2. SU-E-T-243: MonteCarlo Simulation Study of Polymer and Radiochromic Gel for Three-Dimensional Proton Dose Distribution

    International Nuclear Information System (INIS)

    Park, M; Jung, H; Kim, G; Ji, Y; Kim, K; Park, S

    2014-01-01

    Purpose: To estimate the three dimensional dose distributions in a polymer gel and a radiochromic gel by comparing with the virtual water phantom exposed to proton beams by applying Monte Carlo simulation. Methods: The polymer gel dosimeter is the compositeness material of gelatin, methacrylic acid, hydroquinone, tetrakis, and distilled water. The radiochromic gel is PRESAGE product. The densities of polymer and radiochromic gel were 1.040 and 1.0005 g/cm3, respectively. The shape of water phantom was a hexahedron with the size of 13 × 13 × 15 cm3. The proton beam energies of 72 and 116 MeV were used in the simulation. Proton beam was directed to the top of the phantom with Z-axis and the shape of beam was quadrangle with 10 × 10 cm2 dimension. The Percent depth dose and the dose distribution were evaluated for estimating the dose distribution of proton particle in two gel dosimeters, and compared with the virtual water phantom. Results: The Bragg-peak for proton particles in two gel dosimeters was similar to the virtual water phantom. Bragg-peak regions of polymer gel, radiochromic gel, and virtual water phantom were represented in the identical region (4.3 cm) for 72 MeV proton beam. For 116 MeV proton beam, the Bragg-peak regions of polymer gel, radiochromic gel, and virtual water phantom were represented in 9.9, 9.9 and 9.7 cm, respectively. The dose distribution of proton particles in polymer gel, radiochromic gel, and virtual water phantom was approximately identical in the case of 72 and 116 MeV energies. The errors for the simulation were under 10%. Conclusion: This work indicates the evaluation of three dimensional dose distributions by exposing proton particles to polymer and radiochromic gel dosimeter by comparing with the water phantom. The polymer gel and the radiochromic gel dosimeter show similar dose distributions for the proton beams

  3. Decree 243/994 National Direction of Especial Subjects it create and will operate in the orbit of the External Relation Ministere

    International Nuclear Information System (INIS)

    1994-01-01

    Creates in the Ministry of External Relationships the Direction of Special Matters, to which concerns to study, to coordinate and to execute in the pertinent thing, the foreign policy of the Republic in the related with Nuclear Energy, Dismantle, human rights and Humanitarian Right, Population, Migration and Refugees, Drug traffic, Terrorism, Space Right and all those topics of political character that require to be considered in form separated by their special characteristic . The Direction of Special Political Matters in opinion of the Ministry of External Relationships will depend directly on the General Direction for Political Matters [es

  4. Uranium and transuranium analysis

    International Nuclear Information System (INIS)

    Regnaud, F.

    1989-01-01

    Analytical chemistry of uranium, neptunium, plutonium, americium and curium is reviewed. Uranium and neptunium are mainly treated and curium is only briefly evoked. Analysis methods include coulometry, titration, mass spectrometry, absorption spectrometry, spectrofluorometry, X-ray spectrometry, nuclear methods and radiation spectrometry [fr

  5. Decree 243/994 National Direction of Especial Subjects it create and will operate in the orbit of the External Relation Ministere; Decreto 243/994 Direccion de Asuntos Especiales crease y funcionara en la orbita del Ministerio de Relaciones Exteriores

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-10

    Creates in the Ministry of External Relationships the Direction of Special Matters, to which concerns to study, to coordinate and to execute in the pertinent thing, the foreign policy of the Republic in the related with Nuclear Energy, Dismantle, human rights and Humanitarian Right, Population, Migration and Refugees, Drug traffic, Terrorism, Space Right and all those topics of political character that require to be considered in form separated by their special characteristic . The Direction of Special Political Matters in opinion of the Ministry of External Relationships will depend directly on the General Direction for Political Matters. [Spanish] Crease en el Ministerio de Relaciones Exteriores la Direccion de Asuntos Especiales, a la que compete estudiar, coordinar y ejecutar en lo pertinente, la politica exterior de la Republica en lo relacionado con Energia Nuclear, Desarme, Derechos Humanos y Derecho Humanitario, Poblacion, Migracion y Refugiados, Narcotrafico, Terrorismo, Derecho Espacial y todos aquellos temas de caracter politico que a juicio del Ministerio de Relaciones Exteriores requieran ser considerados en forma separada por sus caracteristicas especiales.La Direccion de Asuntos Politicos Especiales dependera directamente de la Direccion General para Asuntos Politicos.

  6. Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1977

    International Nuclear Information System (INIS)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1977-12-01

    During the period January 1, 1977, through June 30, 1977, the following amounts of transuranium elements were recovered from 12 irradiated HFIR targets: 0.1g 243 Am, 21g 244 Cm, 29.5 mg 249 Bk, 288 mg 252 Cf, 1.48 mg 253 Es, and 0.7 pg 257 Fm. One batch of high-purity 248 Cm (approximately 50 mg) was separated from 252 Cf. Twenty-three shipments were made from TRU during the period; recipients and the amounts of nuclides are tabulated. Five HFIR targets, each containing 8 to 9 g of curium, were fabricated. During the next 18 months, we expect to obtain totals of 92 mg of 249 Bk, 910 mg of 252 Cf, 3.8 mg of 253 Es (in a mixture of isotopes), 615 μg of high-purity 253 Es, and 1.6 pg of 257 Fm; we also expect to make available 250 mg of high-purity 248 Cm. No process or equipment changes were made during this report period. Five neutron sources were fabricated during this report period, bringing the total fabricated to date to 97. Two sources that had previously been returned to TRU were reassigned. Special projects included the following: (1) the enrichment of the 244 Pu concentration in 100 mg of plutonium by irradiation to burn out the lighter isotopes, (2) the separation of 245 pg of 254 Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 μg of 253 Es, and (3) an experimental separation of cerium from the other rare-earth elements in a TRU process waste solution. The values that we are currently using for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

  7. Estimation of 244Cm intake by bioassay measurements following a contamination incident

    International Nuclear Information System (INIS)

    Thein, M.; Bogard, J.S.; Eckerman, K.F.

    1990-01-01

    An employee was contaminated with radioactive material consisting primarily of 244 Cm and 246 Cm as a consequence of handling a curium nitrate solution at a reprocessing facility. In vivo gamma analysis and in vitro (urine and fecal) bioassay measurements were performed. A sample of the curium solution from the workplace was obtained to confirm that the nitrate was the chemical form and to identify the isotopes of curium present. The mass ratio of 244 Cm/ 246 Cm was determined to be 91 to 7. Observed excretion rates were consistent with available information on curium. The results of the in vivo and in vitro measurements are presented and intake estimates for the incident are developed. (author) 11 refs.; 3 figs.; 2 tabs

  8. Chemistry of pyroprocessing for nuclear waste transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Ackerman, J.P. [Argonne National Laboratory, IL (United States)

    1995-10-01

    Pyrochemical treatment of spent nuclear fuel is an attractive approach for separating the transuranium (TRU) elements neptunium, plutonium, americium, and curium because of its simplicity, diversion resistance, and potentially low cost.

  9. Consistent evaluation of neutron cross sections for the 242-244Cm isotopes

    International Nuclear Information System (INIS)

    Ignatyuk, A.V.; Maslov, V.M.

    1989-01-01

    The knowledge of neutron cross-sections for Curium isotopes is necessary for solving the problems of the external fuel cycle. Experimental information on the cross-sections is very meager and does not satisfy requirements and existing evaluations in different libraries differ substantially for fission and (n,2n) reaction cross-sections. This situation requires a critical review of the entire set of evaluations of the neutron cross-sections for Curium. 17 refs, 3 figs

  10. Some basic advantages of accelerator-driven transmutation of minor actinides and iodine-129

    Energy Technology Data Exchange (ETDEWEB)

    Shmelev, A.N.; Apse, V.A.; Kulikov, G.G. [Moscow Engineering Physics Institute (Russian Federation)

    1995-10-01

    The blanket of accelerator-driven facility designed for I-129 transmutation doesn`t contain fissile and fertile materials. So the overheating of iodine compounds transmuted is practically excluded. The efficacy of I-129 transmutation is estimated. Curium being accumulated in nuclear reactors can be incinerated in blanket of accelerator-driven facility. The deep depletion of curium diluted with inert material can be achieved.

  11. VLBI observations of the quasars CTD20 (0234+285), OJ248 (0827+243), and 4C19.44 (1354+195), and the millimeter-x-ray connection

    International Nuclear Information System (INIS)

    Marscher, A.P.; Broderick, J.J.

    1983-01-01

    We have obtained limited VLBI data on the quasars CTD20, OJ248, and 4C19.44 at 2.8 cm. CTD20 was also observed at 6 and 18 cm. All three sources contain multicomponent structure, and rather large fractions of the 2.8-cm flux densities arise in unresolved regions. All of the radio flux density of CTD20 originates in compact components. 4C19.44 is dominated at low frequencies by a steep-spectrum component which exceeds about 7 mas in size. Above 2 GHz the spectrum is flat and variable owing to several compact components. CTD20 and OJ248 belong to a sample of millimeter-excess quasars which were shown by Owen, Helfand, and Spangler to have highly predictable ratios of 90 GHz to 2-keV flux densities. A self-Compton explanation of this relationship is supported by the existence of unresolved radio components. However, the rapid 90-GHz variability of OJ248 and other quasars with strong millimeter emission should destroy the observed tight correlation except under special circumstances. A synchrotron origin of the radio-to-x-ray emission requires that any variations in the radio should be time delayed relative to the x ray

  12. The synthesis of 7-chloro-5-pentadeuteriophenyl-1-methyl-1H-1, 5-benzodiazepine-2,4(3H, 5H)dione (( sup 2 H sub 5 )clobazam)

    Energy Technology Data Exchange (ETDEWEB)

    Borel, A.G.; Abbott, F.S. (British Columbia Univ., Vancouver, BC (Canada). Dept. of Pharmaceutical Sciences)

    1990-07-01

    Pentadeuteriophenyl clobazam was synthesized in essentially quantitative isotopic purity, and characterized by {sup 1}H-NMR and mass spectroscopy. The title compound was found to be >98% pure by HPLC, and its retention time (t{sub R} 6.17 min) was less than that of an authentic clobazam standard (t{sub R} 6.32 min). Of the five steps in the synthesis of clobazam, the most susceptible to deuterium exchange was the nucleophilic substitution of 2,4-dichloronitrobenzene by aniline-d{sub 7} to form N-(5-chloro-2-nitrophenyl)penta-deuteriophenylamine. In this step, the isotopic impurity aniline-2,3,4,5-d{sub 5} introduced protons from nitrogen into the ortho and para positions of the deuteriophenyl ring of N-(5-chloro-2-nitrophenyl)pentadeuteriophenylamine. (author).

  13. Frequency band analysis of muscle activation during cycling to exhaustion.DOI: http://dx.doi.org/10.5007/1980-0037.2012v14n3p243

    Directory of Open Access Journals (Sweden)

    Marco Aurélio Vaz

    2012-05-01

    Full Text Available Lower limb muscles activation was assessed during cycling to exhaustion using frequency band analysis. Nine cyclists were evaluated in two days. On the first day, cyclists performed a maximal incremental cycling exercise to measure peak power output, which was used on the second day to define the workload for a constant load time to exhaustion cycling exercise (maximal aerobic power output from day 1. Muscle activation of vastus lateralis (VL, long head of biceps femoris (BF, lateral head of gastrocnemius (GL, and tibialis anterior (TA from the right lower limb was recorded during the time to exhaustion cycling exercise. A series of nine band-pass Butterworth digital filters was used to analyze muscle activity amplitude for each band. The overall amplitude of activation and the high and low frequency components were defined to assess the magnitude of fatigue effects on muscle activity via effect sizes. The profile of the overall muscle activation during the test was analyzed using a second order polynomial, and the variability of the overall bands was analyzed by the coefficient of variation for each muscle in each instant of the test. Substantial reduction in the high frequency components of VL and BF activation was observed. The overall and low frequency bands presented trivial to small changes for all muscles. High relationship between the second order polynomial fitting and muscle activity was found (R2 > 0.89 for all muscles. High variability (~25% was found for muscle activation at the four instants of the fatigue test. Changes in the spectral properties of the EMG signal were only substantial when extreme changes in fatigue state were induced.

  14. SU-E-J-243: Possibility of Exposure Dose Reduction of Cone-Beam Computed Tomography in An Image Guided Patient Positioning System by Using Various Noise Suppression Filters

    International Nuclear Information System (INIS)

    Kamezawa, H; Arimura, H; Ohki, M; Shirieda, K; Kameda, N

    2014-01-01

    Purpose: To investigate the possibility of exposure dose reduction of the cone-beam computed tomography (CBCT) in an image guided patient positioning system by using 6 noise suppression filters. Methods: First, a reference dose (RD) and low-dose (LD)-CBCT (X-ray volume imaging system, Elekta Co.) images were acquired with a reference dose of 86.2 mGy (weighted CT dose index: CTDIw) and various low doses of 1.4 to 43.1 mGy, respectively. Second, an automated rigid registration for three axes was performed for estimating setup errors between a planning CT image and the LD-CBCT images, which were processed by 6 noise suppression filters, i.e., averaging filter (AF), median filter (MF), Gaussian filter (GF), bilateral filter (BF), edge preserving smoothing filter (EPF) and adaptive partial median filter (AMF). Third, residual errors representing the patient positioning accuracy were calculated as an Euclidean distance between the setup error vectors estimated using the LD-CBCT image and RD-CBCT image. Finally, the relationships between the residual error and CTDIw were obtained for 6 noise suppression filters, and then the CTDIw for LD-CBCT images processed by the noise suppression filters were measured at the same residual error, which was obtained with the RD-CBCT. This approach was applied to an anthropomorphic pelvic phantom and two cancer patients. Results: For the phantom, the exposure dose could be reduced from 61% (GF) to 78% (AMF) by applying the noise suppression filters to the CBCT images. The exposure dose in a prostate cancer case could be reduced from 8% (AF) to 61% (AMF), and the exposure dose in a lung cancer case could be reduced from 9% (AF) to 37% (AMF). Conclusion: Using noise suppression filters, particularly an adaptive partial median filter, could be feasible to decrease the additional exposure dose to patients in image guided patient positioning systems

  15. SU-E-J-243: Possibility of Exposure Dose Reduction of Cone-Beam Computed Tomography in An Image Guided Patient Positioning System by Using Various Noise Suppression Filters

    Energy Technology Data Exchange (ETDEWEB)

    Kamezawa, H [Graduate School of Medical Sciences, Kyushu University, Higashi-ku, Fukuoka (Japan); Fujimoto General Hospital, Miyakonojo, Miyazaki (Japan); Arimura, H; Ohki, M [Faculty of Medical Sciences, Kyushu University, Higashi-ku, Fukuoka (Japan); Shirieda, K; Kameda, N [Fujimoto General Hospital, Miyakonojo, Miyazaki (Japan)

    2014-06-01

    Purpose: To investigate the possibility of exposure dose reduction of the cone-beam computed tomography (CBCT) in an image guided patient positioning system by using 6 noise suppression filters. Methods: First, a reference dose (RD) and low-dose (LD)-CBCT (X-ray volume imaging system, Elekta Co.) images were acquired with a reference dose of 86.2 mGy (weighted CT dose index: CTDIw) and various low doses of 1.4 to 43.1 mGy, respectively. Second, an automated rigid registration for three axes was performed for estimating setup errors between a planning CT image and the LD-CBCT images, which were processed by 6 noise suppression filters, i.e., averaging filter (AF), median filter (MF), Gaussian filter (GF), bilateral filter (BF), edge preserving smoothing filter (EPF) and adaptive partial median filter (AMF). Third, residual errors representing the patient positioning accuracy were calculated as an Euclidean distance between the setup error vectors estimated using the LD-CBCT image and RD-CBCT image. Finally, the relationships between the residual error and CTDIw were obtained for 6 noise suppression filters, and then the CTDIw for LD-CBCT images processed by the noise suppression filters were measured at the same residual error, which was obtained with the RD-CBCT. This approach was applied to an anthropomorphic pelvic phantom and two cancer patients. Results: For the phantom, the exposure dose could be reduced from 61% (GF) to 78% (AMF) by applying the noise suppression filters to the CBCT images. The exposure dose in a prostate cancer case could be reduced from 8% (AF) to 61% (AMF), and the exposure dose in a lung cancer case could be reduced from 9% (AF) to 37% (AMF). Conclusion: Using noise suppression filters, particularly an adaptive partial median filter, could be feasible to decrease the additional exposure dose to patients in image guided patient positioning systems.

  16. Minerals and Trace Elements in Milk, Milk Products, Infant Formula, and Adult/Pediatric Nutritional Formula, ICP-MS Method: Collaborative Study, AOAC Final Action 2015.06, ISO/DIS 21424, IDF 243.

    Science.gov (United States)

    Pacquette, Lawrence H; Thompson, Joseph J; Malaviole, I; Zywicki, R; Woltjes, F; Ding, Y; Mittal, A; Ikeuchi, Y; Sadipiralla, B; Kimura, S; Veltman, H; Miura, A

    2018-03-01

    AOAC Final Action Official MethodSM 2015.06 "Minerals and Trace Elements in Milk, Milk Products, Infant Formula and Adult/Pediatric Nutritional Formula, ICP-MS Method" was collaboratively studied. Note that "milk, milk products" has now been added to the title of the Final Action method because whole milk and several dairy ingredients were successfully incorporated into the collaborative study for the purpose of developing an International Organization for Standardization/International Dairy Federation standard (ISO/DIS 21424; in progress). The method determines sodium, magnesium, phosphorus, potassium, calcium, iron, manganese, zinc, copper, chromium, molybdenum, and selenium by inductively coupled plasma (ICP)-MS after microwave digestion. Ten laboratories participated in the study, and data from five different model ICP-MS units were represented. Thirteen products, five placebo products, and six dairy samples were tested as blind duplicates in this study, along with a standard reference material, for a total 50 samples. The overall repeatability and reproducibility for all samples met Standard Method Performance Requirements put forth by the AOAC Stakeholder Panel on Infant Formula and Adult Nutritionals, with a few exceptions. Comparisons are made to ICP-atomic emission data from a collaborative study of AOAC Official Method 2011.14 carried out concurrently on these same samples.

  17. As Aventuras de Huckleberry Finn de Mark Twain, Tradução de Rosaura Eichenberg.DOI: 10.5007/2175-7968.2011v2n28p243

    Directory of Open Access Journals (Sweden)

    Vanessa Lopes Lourenço Hanes

    2011-12-01

    Full Text Available A obra The Adventures of Huckleberry Finn é tida pela maioria dos críticos literários como a obra-prima de Mark Twain. Este livro, escrito em 1885, foi inclusive considerado a origem de toda a literatura americana moderna pelo célebre Hemingway.

  18. Phytoremediation: role of terrestrial plants and aquatic macrophytes in the remediation of radionuclides and heavy metal contaminated soil and water.

    Science.gov (United States)

    Sharma, Sunita; Singh, Bikram; Manchanda, V K

    2015-01-01

    Nuclear power reactors are operating in 31 countries around the world. Along with reactor operations, activities like mining, fuel fabrication, fuel reprocessing and military operations are the major contributors to the nuclear waste. The presence of a large number of fission products along with multiple oxidation state long-lived radionuclides such as neptunium ((237)Np), plutonium ((239)Pu), americium ((241/243)Am) and curium ((245)Cm) make the waste streams a potential radiological threat to the environment. Commonly high concentrations of cesium ((137)Cs) and strontium ((90)Sr) are found in a nuclear waste. These radionuclides are capable enough to produce potential health threat due to their long half-lives and effortless translocation into the human body. Besides the radionuclides, heavy metal contamination is also a serious issue. Heavy metals occur naturally in the earth crust and in low concentration, are also essential for the metabolism of living beings. Bioaccumulation of these heavy metals causes hazardous effects. These pollutants enter the human body directly via contaminated drinking water or through the food chain. This issue has drawn the attention of scientists throughout the world to device eco-friendly treatments to remediate the soil and water resources. Various physical and chemical treatments are being applied to clean the waste, but these techniques are quite expensive, complicated and comprise various side effects. One of the promising techniques, which has been pursued vigorously to overcome these demerits, is phytoremediation. The process is very effective, eco-friendly, easy and affordable. This technique utilizes the plants and its associated microbes to decontaminate the low and moderately contaminated sites efficiently. Many plant species are successfully used for remediation of contaminated soil and water systems. Remediation of these systems turns into a serious problem due to various anthropogenic activities that have

  19. Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1975

    Energy Technology Data Exchange (ETDEWEB)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1976-03-01

    During the period January 1, 1975, through June 30, 1975, the following amounts of transuranium elements were recovered from 22 irradiated HFIR targets: 2g /sup 243/Am, 59 g /sup 244/Cm, 51 mg /sup 249/Bk, 465 mg /sup 252/Cf, 2.5 mg /sup 253/Es, and 1.4 pg /sup 257/Fm. In addition, 45 mg of high-purity /sup 248/Cm was operated from /sup 252/Cf which had been recovered and purified during earlier periods, and 56 mg of a lower-quality /sup 248/Cm was separated from californium purification rework solutions. Five HFIR targets, each containing approximately 9 g of actinides (predominantly curium), were fabricated. A new long-term projection showed that /sup 252/Cf production in the TRU-HFIR complex could increase to as much as 2.5 g/year. During the next 18 months, we expect to recover totals of 46 mg of /sup 249/Bk, 520 mg of /sup 252/Cf, 2.0 mg of /sup 253/Es (in a mixture of isotopes), 220 ..mu..g of high-purity /sup 253/Es, and 1.6 pg of /sup 257/Fm. We also expect to obtain 125 mg of high-purity /sup 248/Cm from purified californium now in storage. There are no plans to process any of the remaining SRP Pu-Al tubes or to irradiate any plutonium targets in the HFIR; thus, we do not expect to recover any /sup 244/Pu. No changes were made in the chemical processing flowsheets normally used at TRU. Two neutron sources were fabricated, bringing the total fabricated to 77. In special projects, we (1) produced about 1 mg of /sup 250/Cf by irradiation of /sup 249/Bk in HFIR rabbits, and (2) processed some irradiated /sup 248/Cm samples and obtained yield and isotopic composition data for use in determining the capture cross section of /sup 249/Cm in the HFIR. The values that are currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix.

  20. Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1975

    International Nuclear Information System (INIS)

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1976-03-01

    During the period January 1, 1975, through June 30, 1975, the following amounts of transuranium elements were recovered from 22 irradiated HFIR targets: 2g 243 Am, 59 g 244 Cm, 51 mg 249 Bk, 465 mg 252 Cf, 2.5 mg 253 Es, and 1.4 pg 257 Fm. In addition, 45 mg of high-purity 248 Cm was operated from 252 Cf which had been recovered and purified during earlier periods, and 56 mg of a lower-quality 248 Cm was separated from californium purification rework solutions. Five HFIR targets, each containing approximately 9 g of actinides (predominantly curium), were fabricated. A new long-term projection showed that 252 Cf production in the TRU-HFIR complex could increase to as much as 2.5 g/year. During the next 18 months, we expect to recover totals of 46 mg of 249 Bk, 520 mg of 252 Cf, 2.0 mg of 253 Es (in a mixture of isotopes), 220 μg of high-purity 253 Es, and 1.6 pg of 257 Fm. We also expect to obtain 125 mg of high-purity 248 Cm from purified californium now in storage. There are no plans to process any of the remaining SRP Pu-Al tubes or to irradiate any plutonium targets in the HFIR; thus, we do not expect to recover any 244 Pu. Two neutron sources were fabricated, bringing the total fabricated to 77. Two sources that had been used previously in various projects were returned to the TRU inventory and are available for reassignment. In special projects, we (1) produced about 1 mg of 250 Cf by irradiation of 249 Bk in HFIR rabbits, and (2) processed some irradiated 248 Cm samples and obtained yield and isotopic composition data for use in determining the capture cross section of 249 Cm in the HFIR. The values that are currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

  1. Critical Masses for Unreflected Metal Spheres

    International Nuclear Information System (INIS)

    Westfall, Robert Michael; Wright, Richard Q.

    2009-01-01

    Calculated critical masses of bare metal spheres for 28 actinide isotopes, using the SCALE/XSDRNPM one-dimensional, discrete-ordinates system, are presented. ENDF/B-VI, ENDF/B-VII, and JENDL-3.3 cross sections were used in the calculations. Results are given for isotopes of uranium, neptunium, plutonium, americium, curium, californium, and for one isotope of einsteinium. Calculated k values for these same nuclides are also given. We show that, for non-threshold or low-threshold fission nuclides, a good approximation for the nuclide k is the value of nubar at 1 MeV. A plot of the critical mass versus k values is given for 19 nuclides with A-numbers between 232 and 250. The peaks in the critical mass curve (for seven nuclides) correspond to dips in the k curve. For the seven cases with the largest critical mass, six are even-even nuclides. Neptunium-237, with a critical mass of about 62.7 kg (ENDF/B-VI calculation), has an odd number of protons and an even number of neutrons. However, two cases with quite small critical masses, 232U and 236Pu, are also even-even. These two nuclides do not exhibit threshold fission behavior like most other even-even nuclides. The largest critical mass is 208.8 kg for 243Am and the smallest is 2.44 kg for 251Cf. The calculated k values vary from 1.5022 for 234U to 4.4767 for 251Cf. A correlation between the calculated critical mass (kg) and the fission spectrum averaged value of is given for the elements U, Np, Pu, Am, Cm, and Cf. For each of the five elements, a fit to the data for that element is provided. In each case the fit employs a negative exponential of the form mass = exp(A + B ∼ ln). The values of A and B are element dependent and vary slightly for each of the five elements. The method described here is mainly applicable for non-threshold fission nuclides (15 of the 28 nuclides considered in this paper). There are three exceptions, 238Pu, 244Cm, and 250Cf, which all exhibit threshold fission behavior.

  2. Recovery of trans-plutonium elements; Recuperation des elements transplutoniens

    Energy Technology Data Exchange (ETDEWEB)

    Espie, J Y; Poncet, B; Simon, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1970-07-01

    The object of this work is to study the recovery of americium and curium from the fission-product solution obtained from the processing of irradiated fuel elements made of natural metallic uranium alloyed with aluminium, iron and silicon; these elements have been subjected to an average irradiation of 4000 MW days/ton in a gas-graphite type reactor having a thermal power of 3.7 MW/ton of uranium. The process used consists of 3 extraction cycles and one americium-curium separation: - 1) extraction cycle in 40 per cent TBP: extraction of actinides and lanthanides; elimination of fission products; - 2) extraction cycle in 8 per cent D2EHPA: decontamination from the fission products, decontamination of actinides from lanthanides; - 3) extraction cycle in 40 per cent TBP: separation of the complexing agent and concentration of the actinides; - 4) americium-curium separation by precipitation. (authors) [French] Cette etude a pour objet, la recuperation de l'americium et du curium de la solution de produits de fission provenant du traitement de combustibles irradies a base d'uranium naturel metallique allie a l'aluminium, le fer, et le silicium, et ayant subi une irradiation moyenne de 4000 MWj/t dans une pile du type graphite-gaz, dont la puissance thermique est de 3.7 MW/t d'uranium. Le procede utilise comprend 3 cycles d'extraction et une separation americium-curium: - 1. cycle d'extraction dans le TBP a 40 pour cent: extraction des actinides et des lanthanides, elimination des produits de fission; - 2. cycle d'extraction dans le D2EHPA a 8 pour cent: decontamination en produits de fission, decontamination des actinides en lanthanides; - 3. cycle d'extraction dans le TBP a 40 pour cent: separation du complexant et concentration des actinides; - 4. separation americium-curium par precipitation. (auteurs)

  3. Identification of colloids in nuclear waste glass reactions

    International Nuclear Information System (INIS)

    Cunnane, J.C.; Bates, J.K.

    1991-01-01

    Characterization data for particulates formed under a variety of laboratory leaching conditions that simulate glass reaction in a repository environment are presented. Data on the particle size distributions and filterable fractions for neptunium, plutonium, americium, and curium were obtained by filtrations through a series of filters with pore sizes ranging from 1 μm to 3.8 nm. The neptunium was found to be largely nonfilterable. Americium and plutonium were associated with filterable particles. The particles with which the americium, plutonium, and curium were associated were characterized using transmission electron microscopy (TEM) examination techniques. 8 refs., 1 fig., 2 tabs

  4. JPRS Report, Science & Technology, USSR: Space.

    Science.gov (United States)

    1988-08-17

    Half-life, years Specific Heat Release W/hr Plutonium-238 87.5 0.46 Curium-244 18.4 2.8 Curium-242 0.45 120 Polonium - 210 0.38 144 Polonium - 210 ...begun train- ing a year before the flight. The prospective space travelers had to be trained to stay in a special capsule and to use nozzles for food ...conditions of extended weight- lessness. On command, the animals are given food and water, waste is removed, and day/night conditions are regulated

  5. Low-level determination of transuranic elements in marine environment samples

    International Nuclear Information System (INIS)

    Ballestra, S.; Holm, E.; Fukai, R.

    1978-01-01

    The procedures developed and currently employed in the Monaco Laboratory for determining transuranic elements in seawater, marine sediments and organisms are described and discussed. While the standard anion-exchange procedure from the hydrochloric acid medium is used for the separation of plutonium isotopes from americium, purification of americium and curium is achieved by an ion-exchange sorption from the methanol-nitric acid medium, followed by an elution with the methanol-hydrochloric acid mixture. Satisfactory clean-up of plutonium as well as americium and curium can be achieved by applying the described procedures. (author)

  6. ORF Alignment: NC_005071 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available GLDPKRGQCLEVGAILFHAPQRAVLAQHSFLLPVETNAAESI 60 ... Query: 190 DIAWPVDRQLRSRPSVRDLALAYGVPVWAAHRALTDCIYLAEVFARCKDL...ETLL 243 ... DIAWPVDRQLRSRPSVRDLALAYGVPVWAAHRALTDCIYLAEVFARCKDLETLL Sbjct: 121 DIAWPVDRQLRSRPSVRDLALAYGVPVWAAHRALTDCIYLAEVFARCKDLETLL 174

  7. Actinides compounds for the transmutation: scientific contributions of american and japanese collaborations; Composes d'actinides pour la transmutation: apports scientifiques de collaborations americaines et japonaises

    Energy Technology Data Exchange (ETDEWEB)

    Raison, Ph.; Albiot, T

    2000-07-01

    This paper deals with the minor actinides transmutation and the scientific contribution of the ORNL and the JAERI. It presents researches on the Am-Zr-Y-O system in the framework of the heterogeneous reprocessing, the curium and pyrochlore structures, with the ORNL contribution and phase diagrams, data of Thermodynamics, actinides nitrides, with the JAERI. (A.L.B.)

  8. Fuel selection for radioisotope thermoelectric generators

    International Nuclear Information System (INIS)

    Menezes, A.

    1988-06-01

    The availability of Radioisotope Thermoeletric Generator fuels is evaluated based on the amount of fuel discharged from selected power reactors. In general, the best alternatives are either to use Plutonium-238 produced by irradiation of Neptunium-237 generated in typical thermal reactors or to use Curium-244 directly separated from the discharged fuels of fast or thermal reactors. (author) [pt

  9. Analysis of large soil samples for actinides

    Science.gov (United States)

    Maxwell, III; Sherrod, L [Aiken, SC

    2009-03-24

    A method of analyzing relatively large soil samples for actinides by employing a separation process that includes cerium fluoride precipitation for removing the soil matrix and precipitates plutonium, americium, and curium with cerium and hydrofluoric acid followed by separating these actinides using chromatography cartridges.

  10. Transmutation Scenarios Impacts on Advanced Nuclear Cycles. Fabrication, Reprocessing and Transportation

    International Nuclear Information System (INIS)

    Saturnin, A.; Sarrat, P.; Hancok, H.; Milot, J.-F.; Duret, B.; Jasserand, F.; Fillastre, E.; Giffard, F.-X.; Chabert, C.; Van Den Durpel, L.; Caron-Charles, M.; Lefevre, J.C.; Carlier, B.; Arslan, M.; Favet, D.; Garzenne, C.; Barbrault, P.

    2013-01-01

    Conclusions: First detailed assessment of plants and transportation in various transmutation scenarios. In case of curium transmutation: large difficulties and uncertainties requiring whole new technology development (more pronounced for ADS option). For Am transmutation: more feasible, still to be demonstrated on specific points for industrial extrapolation

  11. Cylindrical Induction Melter Modicon Control System

    International Nuclear Information System (INIS)

    Weeks, G.E.

    1998-04-01

    In the last several years an extensive R ampersand D program has been underway to develop a vitrification system to stabilize Americium (Am) and Curium (Cm) inventories at SRS. This report documents the Modicon control system designed for the 3 inch Cylindrical Induction Melter (CIM)

  12. Actinides compounds for the transmutation: scientific contributions of american and japanese collaborations

    International Nuclear Information System (INIS)

    Raison, Ph.; Albiot, T.

    2000-01-01

    This paper deals with the minor actinides transmutation and the scientific contribution of the ORNL and the JAERI. It presents researches on the Am-Zr-Y-O system in the framework of the heterogeneous reprocessing, the curium and pyrochlore structures, with the ORNL contribution and phase diagrams, data of Thermodynamics, actinides nitrides, with the JAERI. (A.L.B.)

  13. Neutron resonance parameters of CM isotopes

    International Nuclear Information System (INIS)

    Belanova, T.S.; Kolesov, A.G.; Poruchikov, V.A.

    1977-01-01

    The total neutron cross sections of isotopes 244, 245, 246, 248 Curium have been measured on reactor CM-2 using the time-of-flight method. Single-level Breit-Wigner resonance parameters: energy E 0 , neutron width 2g GITAn, total width GITA, total neutron cross section in resonance sigma 0 have been obtained by the shape and area methods

  14. Test Review: Wilkinson, G. S., & Robertson, G. J. (2006). Wide Range Achievement Test--Fourth Edition. Lutz, FL: Psychological Assessment Resources. WRAT4 Introductory Kit (Includes Manual, 25 Test/Response Forms [Blue and Green], and Accompanying Test Materials): $243.00

    Science.gov (United States)

    Dell, Cindy Ann; Harrold, Barbara; Dell, Thomas

    2008-01-01

    The Wide Range Achievement Test-Fourth Edition (WRAT4) is designed to provide "a quick, simple, psychometrically sound assessment of academic skills". The test was first published in 1946 by Joseph F. Jastak, with the purpose of augmenting the cognitive performance measures of the Wechsler-Bellevue Scales, developed by David Wechsler.…

  15. [Dimitri Steinke: Die Zivilrechtsordnungen des Baltikums unter dem Einfluss ausländischer, insbesondere deutscher Rechtsquellen. (Osnabrücker Schriften zur Rechtsgeschichte, Bd. 16.) V&R unipress. Göttingen 2009. 243 S. ISBN 978-3-89971-573-6] / M

    Index Scriptorium Estoniae

    Luts-Sootak, Marju, 1966-

    2011-01-01

    Arvustus: Dimitri Steinke. Die Zivilrechtsordnungen des Baltikums unter dem Einfluss ausländischer, insbesondere deutscher Rechtsquellen. (Osnabrücker Schriften zur Rechtsgeschichte ; 16). Göttingen, 2009

  16. Further Study is Needed to Define and Measure the Use of Reflective Practice in Library and Information Science. A review of: Grant, Maria J. “The Role of Reflection in the Library and Information Sector: A Systematic Review.” Health Information and Libraries Journal 24.3 (2007: 155‐66.

    Directory of Open Access Journals (Sweden)

    Carol Perryman

    2008-03-01

    Full Text Available Objectives ‐ To identify and review the literature of reflective practice in library and information science (LIS in order to understand its role, particularly with regard to health libraries.Design ‐ Systematic reviewSetting ‐ LIS English‐language articles published between 1969 and 2006, and indexed in the Library and Information Science Abstracts (LISA database.Subjects ‐ 929 citations retrieved from the LISA database.Methods ‐ The author conducted free text searches in the LISA database for the terms ‘reflective,’ ‘reflection*,’ or ‘reflexion*.’ An initial search series was conducted in 2004 in order to retrieve items published between 1969‐2003, then in 2007 for articles published between 2004‐2006. In all, 929 article citations were retrieved. Exclusion criteria included those articles addressing the facilitation of reflective practices in others, as well as non‐English language materials,and those pre-dating 1969. After review, 55 articles met the author’s relevance standard.Citation tracking then added 10 articles to the total. From this dataset, full‐text articles were obtained where possible, if determined on initial scrutiny to be deserving of further examination. Thirteen articles (.013% were ultimately selected for analysis. These articles were categorized as analytical or non‐analytical, with respect to perspective (individual or organizational, and recency of events (retrospective or recent. In addition, a determination was made about whether the articles’ foci were reflection occurring on (in retrospect to or in (during practice.Main results ‐ Of thirteen articles, five were found to be non‐analytical, with the other six being analytical. Three of the non-analytical items were the reflections of an individual, while the remaining two offered an organizational perspective. The non-analytical accounts were found to be descriptive accounts by an individual, mostly retrospective and offering no consideration of implications for LIS practice. Analytical reflective accounts attempt to systematically appraise events from the recent past, and draw conclusions in order to improve future actions.Conclusion – A gradual increase in the use of analytical reflective practice is demonstrated over the period from 1969‐2006, although insufficient examples of the practice were found in the published literature. Reflective practice is likely to be beneficial to LIS practitioners, especially when time is spent in considering the implications of lessons learned from practice.

  17. El servicio público de las telecomunicaciones: un reto para la regulación económica OECD (2014, Estudio de la OCDE sobre políticas y regulación de telecomunicaciones en Colombia, OECD, Publishing, 184 pp. 243

    Directory of Open Access Journals (Sweden)

    María Carolina Espitia Becerra

    2014-12-01

    Full Text Available The study, about the Organization for Economic Co-operation and Development (OECD, analyzes the socioeconomic role upon Colombia’s telecommunications (TIC. Colombia has profited from the importance of this new public service, therefore the country has orientated its legal framework to ensure the access and universal service of these technologies. This analysis is centered on the telecommunication sector; it studies the markets, the regulation structure and their amendments. Given the relevance of regulations to the administrative law, this paper will center on three fundamental axes: (i the TIC as a public service that is guided towards the universal access and service, (ii The need for an independent regulatory body (iii the adequacy or otherwise of the Telecommunications Regulatory Commission to Colombian reality, other institutions and the regulatory framework. Even though Colombia has strived to create regulatory institutions in this sector, there’s still the questionable matter of the independence of some administrative entities such as the TIC Regulation Commission (crc, for its Spanish initials. This independence would be of extreme importance for the effectiveness of the regulations they are to impose.

  18. El servicio público de las telecomunicaciones: un reto para la regulación económica OECD (2014), Estudio de la OCDE sobre políticas y regulación de telecomunicaciones en Colombia, OECD, Publishing, 184 pp. 243

    OpenAIRE

    María Carolina Espitia Becerra

    2014-01-01

    The study, about the Organization for Economic Co-operation and Development (OECD), analyzes the socioeconomic role upon Colombia’s telecommunications (TIC). Colombia has profited from the importance of this new public service, therefore the country has orientated its legal framework to ensure the access and universal service of these technologies. This analysis is centered on the telecommunication sector; it studies the markets, the regulation structure and their amendments. Given the releva...

  19. University Students Are Unaware of the Role of Academic Librarians. A Review of: Bickley, R. & Corral, S. (2011. Student perceptions of staff in the information commons: A survey at the University of Sheffield. Reference Services Review, 39(2, 223-243. doi:10.1108/00907321111135466

    Directory of Open Access Journals (Sweden)

    Kirsty Thomson

    2012-06-01

    Full Text Available Objective – To discover students’ perceptionsof information commons staff, and todetermine how these perceptions influence theuse of library resources.Design – Post-experience survey with onefollow-up interview.Setting – The University of Sheffield, a postsecondaryinstitution in England.Subjects – All undergraduate andpostgraduate students were invited to takepart. Just over 1% of the student population, or250 students, completed the survey.Methods – Information about the survey wassent to students’ institutional email addresses.One follow up interview was carried out viaemail using the critical incident technique.Main Results – Students do not understandthe academic roles of librarians. They areunlikely to approach library staff for academicsupport, preferring to turn to instructors, otherstudents, friends, and family. Most studentshad positive opinions about assistancereceived in the Information Commons, but asmall number reflected on previous badexperiences with staff, or on a fear of beingmade to feel foolish. The vast majority ofstudents who did not seek help in theInformation Commons stated that this wasbecause they did not require assistance. Most students do not perceive a difference between Information Commons staff and library staff.Conclusion – Students have positive views of Information Commons staff at the University of Sheffield, but have low awareness of the roles of professional librarians. Librarians need to develop partnerships with academic staff and strengthen their presence in both physical and online learning environments to promote their academic roles.

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    Lifescience Database Archive (English)

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  1. Protein (Cyanobacteria): 230634 [PGDBj - Ortholog DB

    Lifescience Database Archive (English)

    Full Text Available ZP_11685390.1 1117:4412 1118:3009 263510:243 263511:243 423471:1998 Na-Ca exchanger/integri...n-beta4, partial Crocosphaera watsonii WH 0003 MDNTQFRGAFSRETNTIYFSEKLVRDTVLQFETVEDINSDNQYIQAFVAVWLEEIGHSVEAQLNEEEIAGDEGRI

  2. Zajímavý záchyt korynebakterie, maskující se jako koagulázanegativní stafylokok

    Czech Academy of Sciences Publication Activity Database

    Petráš, P.; Novotná, Gabriela; Machová, I.; Glavach-Hlaváčová, N.; Šimečková, E.

    2005-01-01

    Roč. 14, č. 5 (2005), s. 243-243 ISSN 1211-7358 Institutional research plan: CEZ:AV0Z50200510 Keywords : staphylococci * corynebacterium * biochemical identification Subject RIV: EE - Microbiology, Virology

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    Lifescience Database Archive (English)

    Full Text Available QFGKLISAYKRWGNEEALEE Sbjct: 121 AKPFHVGHLFTTAIGHSLYRMLNFEGYNPIRINHLGDWGTQFGKLISAYKRWGNEEALEE 180 ... Query: 243 DMLGVDFDSWAGES...FYNDKMDKVVEELEKANILTESNGAKVVMLDEYNMPPCIVVKSDGA 302 ... DMLGVDFDSWAGESFYNDKMDKVVEELEKAN...ILTESNGAKVVMLDEYNMPPCIVVKSDGA Sbjct: 241 DMLGVDFDSWAGESFYNDKMDKVVEELEKANILTESNGAK

  4. ORF Alignment: NC_006814 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available IANLVTENNTKIKAISISF 60 ... Query: 123 VSDFAVXXXXXXXXXXXXXXXKLFRGTSFSAGEFGMMITDYTGHGFKSAHELASTSALIS 182 ... ... ... VSDFAV ... KLFRGTSFSAGEFGMMITDYTGHGFKSAHELASTSALIS Sbjct: 121 VSDFAV...ITLGNGVGGGIFINNKLFRGTSFSAGEFGMMITDYTGHGFKSAHELASTSALIS 180 ... Query: 243 SQNSELIPIIKEKLNQIPNWTDFQAEIQSCRFFNDAS

  5. Protein (Cyanobacteria): 647660116 [PGDBj - Ortholog DB

    Lifescience Database Archive (English)

    Full Text Available :162 ... hypothetical protein, partial Prochlorococcus sp. scB243_496A2 MRILLAAAECAPMIKVGGMGDVVGSLPPSLIKLGHDVRVIIPGYGKLWSLLEVSNEPVFRTNTMGTDFAVYEAKHPIHNYVIYLVGHPTFDSDQIYGGENEDWRFTFFASAT

  6. Protein (Cyanobacteria): 661290558 [PGDBj - Ortholog DB

    Lifescience Database Archive (English)

    Full Text Available SPYFYASWMPEKEDDYRFTNKKRTPLECSTGTKDARSAALKAISWVKEKQKDCLRKITEYQEVKTKCLEHYWEEHFIDFSSTRASRKSVTKLINDEKLKWCSPTYGIG...6:352 ... hypothetical protein Prochlorococcus sp. scB243_495N4 MTSLSAMDGKLNDRTWINISESRYELELGNRVSFPINLYLKKRVN

  7. Quantum-chemical consideration of extermal valent forms of actinides

    International Nuclear Information System (INIS)

    Ionova, G.V.; Pershina, V.G.; Spitsyn, V.I.

    1982-01-01

    Stability of valent forms of actinides that has not yet studied experimentally, is considered within the framework of quantum-chemical considerations. Oxidizing potentials E 0 for actinide elements are determined theoretically. A dependence of the definite valent state stability on relativistic effect is shown. A conclusion is made that oxidizing potential E 0 (4-5) for americium should be higher than E 0 (4-5) for plutonium. A relatively small oxidizing potential E 0 (4-5) for curium speaks about principle possibility of production of five-valent curium in solution, though it is less stable than the six-valent one. Oxidizing potential corresponding to transition of three-valent californium into the four-valent state should be less than the value adopted in literature. A relatively small oxidizing potential of californium E 0 (4-5) speaks about possible existence of five-valent californium in solution

  8. Fabrication and Pre-irradiation Characterization of a Minor Actinide and Rare Earth Containing Fast Reactor Fuel Experiment for Irradiation in the Advanced Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Timothy A. Hyde

    2012-06-01

    The United States Department of Energy, seeks to develop and demonstrate the technologies needed to transmute the long-lived transuranic actinide isotopes contained in spent nuclear fuel into shorter lived fission products, thereby decreasing the volume of material requiring disposal and reducing the long-term radiotoxicity and heat load of high-level waste sent to a geologic repository. This transmutation of the long lived actinides plutonium, neptunium, americium and curium can be accomplished by first separating them from spent Light Water Reactor fuel using a pyro-metalurgical process, then reprocessing them into new fuel with fresh uranium additions, and then transmuted to short lived nuclides in a liquid metal cooled fast reactor. An important component of the technology is developing actinide-bearing fuel forms containing plutonium, neptunium, americium and curium isotopes that meet the stringent requirements of reactor fuels and materials.

  9. Managing radioactive wastes of nuclear power plants in operation and site decommissioning phases

    International Nuclear Information System (INIS)

    Ardalani, E.; Khadivi, S.

    2008-01-01

    A large nuclear reactor annually produces about 25-50 tons consumed Uranium. These consumed materials consist of Uranium and also Plutonium and Curium. In total, about three percent of these materials are remained from fission. Existing actinides (Uranium, Plutonium, and Curium) cause long-term and short-term radiation that could have harmful effects on the environment. In order to reduce the diverse effects of radioactive wastes in Nuclear Power Plants, different procedures are employed such as compaction, chemical treatment, vitrification, canning and sealing with concrete and safe storage. In this paper, the harmful effects of nuclear wastes on the environment are introduced and a management procedure is presented to minimize its diverse effects

  10. Removal of actinides from high-level wastes generated in the reprocessing of commercial fuels

    International Nuclear Information System (INIS)

    Bond, W.D.; Leuze, R.E.

    1975-09-01

    Progress is reported on a technical feasibility study of removing the very long-lived actinides (uranium, neptunium, plutonium, americium, and curium) from high-level wastes generated in the commercial reprocessing of spent nuclear fuels. The study was directed primarily at wastes from the reprocessing of light water reactor (LWR) fuels and specifically to developing satisfactory methods for reducing the actinide content of these wastes to values that would make 1000-year-decayed waste comparable in radiological toxicity to natural uranium ore deposits. Although studies are not complete, results thus far indicate the most promising concept for actinide removal includes both improved recovery of actinides in conventional fuel reprocessing and secondary processing of the high-level wastes. Secondary processing will be necessary for the removal of americium and curium and perhaps some residual plutonium. Laboratory-scale studies of separations methods that appear most promising are reported and conceptual flowsheets are discussed. (U.S.)

  11. Sorption studies of radioelements on geological materials

    International Nuclear Information System (INIS)

    Berry, John A.; Yui, Mikazu; Kitamura, Akira

    2007-11-01

    Batch sorption experiments have been carried out to study the sorption of uranium, technetium, curium, neptunium, actinium, protactinium, polonium, americium and plutonium onto bentonite, granodiorite and tuff. Mathematical modelling using the HARPHRQ program and the HATCHES database was carried out to predict the speciation of uranium and technetium in the equilibrated seawater, and neptunium, americium and plutonium in the rock equilibrated water. Review of the literature for thermodynamic data for curium, actinium, protactinium and polonium was carried out. Where sufficient data were available, predictions of the speciation and solubility were made. This report is a summary report of the experimental work conducted by AEA Technology during April 1991-March 1998, and the main results have been presented at Material Research Society Symposium Proceedings and published as proceedings of them. (author)

  12. On possibility of transuranium element by the method of transport reactions

    International Nuclear Information System (INIS)

    Sinitsyna, G.S.; Krashenitsyn, G.N.; Shestakov, B.I.

    1983-01-01

    A possibility to use chemical transport reaction for separation of uranium, plutonium and some transplutonium elements is shown. The method is based on the use of the known plutonium property to form tetrachloride existing only in the gaseous phase in chlorine atmosphere, which is transported ever the temperature gradiept. Two ways of transport reaction realization - the method of flow and the method of diffusion in closed volume are tested. The experiments are made using specially synthesized plutonium dioxide, containing uranium, americium, curium, lanthanum, terbium, barium. Chlorination is realized by the mixture of chlorine and carbon tetrachloride at temperatures 723-953 K. Plutonium trichloride is deposited in the range 613-653 K, uranium - in the range 473-523 K, curium, americium, lanthanum, terbium, barium remain in the start zone if its temperature does not exceed 873 K

  13. A warning on fission resonance intergrals: Caveat utor

    International Nuclear Information System (INIS)

    Holden, N.E.

    1988-01-01

    A common error is made in defining the resonance integral in most tabulations and handbooks. Although it has a minor effect on the capture resonance integral and on the fission resonance integral for the fissile nuclides, it leads to gross errors in the fission resonance integral for the fertile nuclides. The errors in the fission resonance integral for fertile nuclides of the elements from thorium through curium in the ENDF/B-V library will be presented. Let the user beware

  14. Recent solvent extraction experience at Savannah River

    International Nuclear Information System (INIS)

    Gray, L.W.; Burney, G.A.; Gray, J.H.; Hodges, M.E.; Holt, D.L.; Macafee, I.M.; Reif, D.J.; Shook, H.E.

    1986-01-01

    Tributyl phosphate-based solvent extraction processes have been used at Savannah River for more than 30 years to separate and purify thorium, uranium, neptunium, plutonium, americium, and curium isotopes. This report summarizes the advancement of solvent extraction technology at Savannah River during the 1980's. Topics that are discussed include equipment improvements, solvent treatment, waste reduction, and an improved understanding of the various chemistries in the process streams entering, within, and leaving the solvent extraction processes

  15. Analog elements for transuranic chemistries

    International Nuclear Information System (INIS)

    Weimer, W.C.

    1982-01-01

    The analytical technique for measuring trace concentrations of the analog rare earth elements has been refined for optimal detection. The technique has been used to determine the rare earth concentrations in a series of geological and biological materials, including samples harvested from controlled lysimeter investigations. These studies have demonstrated that any of the trivalent rare earth elements may be used as analog elements for the trivalent transuranics, americium and curium

  16. Computation of actinide pourbaix diagrams at 298 K and 550 K (U,Np,Pu,Am,Cm - H{sub 2}O)

    Energy Technology Data Exchange (ETDEWEB)

    Piro, M.H.; Bruni, G.M.F.; Lewis, B.J.; Thompson, W.T., E-mail: thompson-w@rmc.ca [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada); Iglesias, F.C. [Candesco Corp., Toronto, Ontario (Canada); Guoping, M.A.; Nashiem, R. [Bruce Power Limited., Tiverton, Ontario (Canada); Roberts, J.G. [Cantech Associates Limited, Burlington, Ontario (Canada)

    2011-07-01

    Pourbaix diagrams for the actinides ranging from uranium to curium have been developed from the enthalpy of formation, entropy and heat capacity (or estimates thereof) for the phases and aqueous species. Emphasis has been given to the region between hydrogen and oxygen gas saturation.Additional thermodynamic computations illustrate how the data may be employed in better understanding the chemical behaviour of fuel debris circulating in CANDU reactor coolant. (author)

  17. Analysis of Americium in Transplutonium Process Solutions

    International Nuclear Information System (INIS)

    Ferguson, R.B.

    2001-01-01

    One of the more difficult analyses in the transplutonium field is the determination of americium at trace levels in a complex matrix such as a process dissolver solution. Because of these conditions a highly selective separation must precede the measurement of americium. The separation technique should be mechanically simple to permit remote operation with master-slave manipulators. For subsequent americium measurement by the mass spectroscopic isotopic-dilution technique, plutonium and curium interferences must also have been removed

  18. Device for the determination of concentrations of fissile and/or fertile materials by means of x-ray fluorescence spectrometry

    International Nuclear Information System (INIS)

    Von Baeckmann, A.; Neuber, J.

    1975-01-01

    In analyzing fissile and/or fertile materials in the thorium, uranium, neptunium, plutonium, americium and curium group, time and accuracy are significant factors. An automated system for rapidly analyzing these materials includes: sample preparation device in which aliquots of sample are weighed and mixed with known amounts of solution; x-ray fluorescence spectrometer; and, a central control system for controlling the operation and analyzing the data. (auth)

  19. Safety analysis report for packaging: neutron shipping cask, model 0.5T

    International Nuclear Information System (INIS)

    Peterson, R.T.

    1976-01-01

    The Safety Analysis Report for Packaging demonstrates that the neutron shipping cask can safely transport, in solid or powder form, all isotopes of uranium, plutonium, americium, curium, berkelium, californium, einsteinium, and fermium. The shipping cask and its contents are described. It also evaluates transport conditions, structural parameters (e.g., load resistance, pressure and impact effects, lifting and tiedown devices), and shielding. Finally, it discusses compliance with Chapter 0529 of the Energy Research and Development Administration Manual

  20. Directed evolution of the periodic table: probing the electronic structure of late actinides.

    Science.gov (United States)

    Marsh, M L; Albrecht-Schmitt, T E

    2017-07-25

    Recent investigations of the coordination chemistry and physical properties of berkelium (Z = 97) and californium (Z = 98) have revealed fundamental differences between post-curium elements and lighter members of the actinide series. This review highlights these developments and chronicles key findings and concepts from the last half-century that have helped usher in a new understanding of the evolution of electronic structure in the periodic table.

  1. Actinide nuclides in environmental air and precipitation samples after the Chernobyl accident

    International Nuclear Information System (INIS)

    Rosner, G.; Hoetzl, H.; Winkler, R.

    1988-01-01

    The present paper describes the analysis of isotopes of uranium, neptunium, plutonium, americium and curium, in air and deposition samples taken at our laboratory site 10 km north of Munich, subsequent to the Chernobyl accident. Uranium-234, 237 U, 238 U, 239 Np, 238 Pu, 239+240 Pu and 242 Cm have been identified and upper limits of detection have been established for 241 Am and 244 Cm. Deposition and air concentration values are discussed. 12 refs., 1 fig., 2 tabs

  2. The uptake of radionuclides by plants

    International Nuclear Information System (INIS)

    Cawse, P.A.; Turner, G.S.

    1982-02-01

    A review of the literature, since 1970, on the research into the uptake of radionuclides by plants, with references to earlier soil and plant studies on the fate of nuclear weapons fallout. Experimental data on the uptake of plutonium isotopes, americium 241, cesium 137, radium 226, curium 244 and neptunium 237 and details of the chemical form of the radionuclide, soil type and plant growth period are tabulated. (U.K.)

  3. Space Handbook,

    Science.gov (United States)

    1985-01-01

    thle early life * of" the system. Figure 4-2 shows the variation in power output for polonium - 210 (Po- 210 ) with a 138-day half-life, curium-242 (Cm...miles above the earth’s surface. Above this altitude they must take everything they need with them. The environment will supply them with neither food ...can move large payloads through space. The radioisotope heat cycle engines use high-energy particle sources such as plutonium and polonium . The walls

  4. Reevaluation of the average prompt neutron emission multiplicity (nubar) values from fission of uranium and transuranium nuclides

    International Nuclear Information System (INIS)

    Holden, N.E.; Zucker, M.S.

    1984-01-01

    In response to a need of the safeguards community, we have begun an evaluation effort to upgrade the recommended values of the prompt neutron emission multiplicity distribution, P/sub nu/ and its average value, nubar. This paper will report on progress achieved thus far. The evaluation of the uranium, plutonium, americium and curium nuclide's nubar values will be presented. The recommended values will be given and discussed. 61 references

  5. State-of-art technology of fuels for burning minor actinides. An OECD/NEA study

    International Nuclear Information System (INIS)

    Ogawa, Toru; Konings, R.J.M.; Pillon, S.; Schram, R.P.C.; Verwerft, M.; Wallenius, J.

    2005-01-01

    At OECD/NEA, Working Party on Scientific Issues in Partitioning and Transmutation was formed for 2000-2004, which studied the status and trends of scientific issues in Partitioning and Transmutation (P and T). The study included the scientific and technical issues of fuels and materials, which are related to dedicated systems for transmutation. This paper summarizes the state-of-art technology of the fuels for burning minor actinides (neptunium, americium and curium). (author)

  6. Effects of actinide burning on waste disposal at Yucca Mountain

    International Nuclear Information System (INIS)

    Hirschfelder, J.

    1992-01-01

    Release rates of 15 radionuclides from waste packages expected to result from partitioning and transmutation of Light-Water Reactor (LWR) and Actinide-Burning Liquid-Metal Reactor (ALMR) spent fuel are calculated and compared to release rates from standard LWR spent fuel packages. The release rates are input to a model for radionuclide transport from the proposed geologic repository at Yucca Mountain to the water table. Discharge rates at the water table are calculated and used in a model for transport to the accessible environment, defined to be five kilometers from the repository edge. Concentrations and dose rates at the accessible environment from spent fuel and wastes from reprocessing, with partitioning and transmutation, are calculated. Partitioning and transmutation of LWR and ALMR spent fuel reduces the inventories of uranium, neptunium, plutonium, americium and curium in the high-level waste by factors of 40 to 500. However, because release rates of all of the actinides except curium are limited by solubility and are independent of package inventory, they are not reduced correspondingly. Only for curium is the repository release rate much lower for reprocessing wastes

  7. Studies of selected transuranium and lanthanide tri-iodides under pressure using absorption spectrophotometry

    International Nuclear Information System (INIS)

    Haire, R.G.; Young, J.P.; Peterson, J.R.; Tennessee Univ., Knoxville; Benedict, U.

    1987-01-01

    The anhydrous tri-iodides of plutonium, americium and curium under pressure have been investigated using absorption spectrophotometry. These initial studies on plutonium and curium tri-iodides together with the published data for americium tri-iodide show that the rhombohedral form of these compounds (BiI 3 -type structure) can be converted to the orthorhombic form (PuBr 3 -type structure) by applying pressure at room temperature. Absorption spectrophotometry can often differentiate between two crystallographic forms of a material and has been used in the present high-pressure studies to monitor the effects of pressure on the tri-iodides. A complication in these studies of the tri-iodides is a significant shift of their absorption edges with pressure from the near UV to the visible spectral region. With curium tri-iodide this shift causes interference with the major f-f absorption peaks and precludes identification by absorption spectrophotometry of the high pressure phase of CmI 3 . (orig.)

  8. Peculiarities of extraction of carbonate complexes of trivalent transplutonium elements by alkylpyrocatechins

    International Nuclear Information System (INIS)

    Karalova, Z.K.; Bukina, T.I.; Myasoedov, B.F.; Fedorov, L.A.; Sokolovskij, S.A.

    1987-01-01

    Extraction of trivalent americium, curium, californium and europium by technical mixture of mono- and didecylpyrocatechin (TAP) in various diluents from carbonate solutions is investigated. Effect of many factors (pH, K 2 CO 3 concentration, TAP, metal; the time of phase contact) on the completeness of element isolation and separation is clarified. It is ascertained that the elements listed are quantitatively extracted by TAP solution in toluene and cyclohexane in the range of K 2 CO 3 concentrations from 0.25 to 1.5 mol/l. The difference in americium and curium distribution coefficient during their extraction by TAP from 0.25 mol/l of K 2 CO 3 solution is detected. Separation coefficients of the pair increase with the increase of carbonate solution pH. The separation can be improved at the stage of element reextraction by the mixture of K 2 CO 3 and DTPA or EDTA from alkylpyrocatechin, sunce rate constants of americium and curium reextraction differ greatly. Using 13 C NMR the composition of compounds in organic phase on the basis of 4-(α, α-dioctylethyl)pyrocatechin is investigated

  9. Root uptake of transuranic elements

    International Nuclear Information System (INIS)

    Schulz, R.K.

    1977-01-01

    The uptake of elements by plant roots is one of the important pathways of entry of many elements into the food chain of man. Data are cited showing plutonium concentration ratios, plant/soil, ranging from 10 -10 to 10 -3 . Concentration ratios for americium range from 10 -7 to 10 +1 . Limited experiments with curium and neptunium indicate that root uptake of curium is similar to that of americium and that plant uptake of neptunium is substantially larger than that of curium and americium. The extreme ranges of concentration ratios cited for plutonium and americium are due to a number of causes. Experimental conditions such as very intensive cropping will lead to abnormally high concentration ratios. In some experiments, addition of chelating agents markedly increased plant root uptake of transuranic elements. Particle size and composition of the source material influenced uptake of the transuranics by plants. Translocation within the plant, and soil factors such as pH and organic matter content, all affect concentration ratios

  10. Theoretical and experimental evaluation of waste transport in selected rocks: 1977 annual report of LBL Contract No. 45901AK. Waste Isolation Safety Assessment Program: collection and generation of transport data

    International Nuclear Information System (INIS)

    Apps, J.A.; Benson, L.V.; Lucas, J.; Mathur, A.K.; Tsao, L.

    1977-09-01

    During fiscal year 1977, the following subtasks were performed. (1) Thermodynamic data were tabulated for those aqueous complexes and solid phases of plutonium, neptunium, americium, and curium likely to form in the environment. (2) Eh-pH diagrams were computed and drafted for plutonium, neptunium, americium and curium at 25 0 C and one atmosphere. (3) The literature on distribution coefficients of plutonium, neptunium, americium, and curium was reviewed. (4) Preliminary considerations were determined for an experimental method of measuring radionuclide transport in water-saturated rocks. (5) The transport mechanisms of radionuclides in water-saturated rocks were reviewed. (6) A computer simulation was attempted of mass transfer involving actinides in water-saturated rocks. Progress in these tasks is reported. Subtasks 1, 2, 3, and 4 are complete. The progress made in subtask 5 is represented by an initial theoretical survey to define the conditions needed to characterize the transport of radionuclides in rocks. Subtask 6 has begun but is not complete

  11. Routine radiochemical method for the determination of 90Sr, 238Pu, 239+240Pu, 241Am and 244Cm in environmental samples

    International Nuclear Information System (INIS)

    Ageyev, V.A.; Sajeniouk, A.D.

    2005-01-01

    Routine analytical procedures have been developed for the reliable simultaneous determination of 90 Sr, 238 Pu, 239+240 Pu, 241 Am and 242-244 Cm, Chernobyl derived radioisotopes and fallout after nuclear weapon tests in a wide range of environmental samples: soil (100-200 g), sediments, aerosols, water and vegetation. This procedure has been applied to thousands of soil and sediment samples and hundreds of biological and water samples taken in the exclusive zone of Chernobyl NPP and different regions of Ukraine from 1989 to the present. After the sample has been properly prepared and isotopic tracers added, plutonium, americium and curium are precipitated with calcium oxalate and then lanthanum fluoride. Plutonium is separated from americium and curium by anion-exchange. Americium and curium are separated from rare earths by cation-exchange with gradient elute α-hydroxy-iso-butyric acid. During projects by AQCS IAEA 'Evaluation of Methods for 90 Sr in a Mineral Matrix' and 'Proficiency Test for 239 Pu, 241 Pu and 241 Am Measurement in a Mineral Matrix' accuracy and precision for 90 Sr, 239 Pu and 241 Am by present procedure was evaluated. Advantages, difficulties and limitations of the method are discussed. (author)

  12. Report on the scientifical feasibility of advanced separation

    International Nuclear Information System (INIS)

    2001-01-01

    The advanced separation process Purex has been retained for the recovery of neptunium, technetium and iodine from high level and long lived radioactive wastes. Complementary solvent extraction processes will be used for the recovery of americium, curium and cesium from the high activity effluents of the spent fuel reprocessing treatment. This document presents the researches carried out to demonstrate the scientifical feasibility of the advanced separation processes: the adaptation of the Purex process would allow the recovery of 99% of the neptunium, while the association of the Diamex and Sanex (low acidity variant) processes, or the Paladin concept (single cycle with selective de-extraction of actinides) make it possible the recovery of 99.8% of the actinides III (americium and curium) with a high lanthanides decontamination factor (greater than 150). The feasibility of the americium/curium separation is demonstrated with the Sesame process (extraction of americium IV after electrolytic oxidation). Iodine is today recovered at about 99% with the Purex process and the dissolved fraction of technetium is also recovered at 99% using an adaptation of the Purex process. The non-dissolved fraction is retained by intermetallic compounds in dissolution residues. Cesium is separable from other fission products with recovery levels greater than 99.9% thanks to the use of functionalized calixarenes. The scientifical feasibility of advanced separation is thus demonstrated. (J.S.)

  13. Alpha self irradiation effects in nuclear borosilicate glass

    International Nuclear Information System (INIS)

    Peuget, S.; Roudil, D.; Deschanels, X.; Jegou, C.; Broudic, V.; Bart, J.M.

    2004-01-01

    The properties of actinide glasses are studied in the context of high-level waste management programs. Reprocessing high burnup fuels in particular will increase the minor actinide content in the glass package, resulting in higher cumulative alpha decay doses in the glass, and raising the question of the glass matrix behavior and especially its containment properties. The effect of alpha self-irradiation on the glass behavior is evaluated by doping the glass with a short-lived actinide ( 244 Cm) to reach in several years the alpha dose received by the future glass packages over several thousand years. 'R7T7' borosilicate glasses were doped with 3 different curium contents (0.04, 0.4 and 1.2 wt% 244 CmO 2 ). The density and mechanical properties of the curium-doped glasses were characterized up to 2. 10 18 α/g, revealing only a slight evolution of the macroscopic behavior of R7T7 glass in this range. The leaching behavior of curium-doped glass was also studied by Soxhlet tests. The results do not show any significant evolution of the initial alteration rate with the alpha dose. (authors)

  14. Criticality and thermal analyses of separated actinides

    International Nuclear Information System (INIS)

    Bakker, E.

    2004-01-01

    Curium and americium pose special problems in the chemical preparation of spent fuel for transmutation. Once separated from the other actinides, the isotopes can lead to nuclear fission with the subsequent release of a large amount of radiation. A neutron criticality code was used to determine k eff for varying quantities of Cm 2 O 3 and Am 2 O 3 held within spherical or cylindrical containers. These geometries were investigated both in air and in water. Recommendations are made on the maximum amount of Cm 2 O 3 and Am 2 O 3 that can be safely stored or handled before encountering criticality. Several isotopes of curium and americium also generate a significant amount of heat by radioactive decay. If kilogram quantities are stored in a container, for example, the material may heat to an equilibrium temperature that exceeds its melting temperature. The heat generation of curium and americium present even more restriction on the mass of that can safely be contained in one location. (author)

  15. Proliferation resistance of the lithium reduction process

    International Nuclear Information System (INIS)

    Ko, W. I.; Ha, J. H.; Lee, S. Y.; Song, D. Y.; Kim, H. D.; Park, S. W.

    2002-01-01

    This paper addresses the characteristics of proliferation resistance of the lithium reduction process and international domestic safeguarding methods. In addition to dealing with qualitative features of the proliferation resistance, this study is emphasizing on the quantitative analysis of radiation barrier, which could be a significant accessibility barrier if the field is high enough to force a theft to shield the object during a theft. From the radiation barrier analysis, it is indicated that whole-body radiation dose is about 20 rem/hr at one meter of smelt and ingot metal of 40 kgHM, which could be considered to be a significant reduction in risk of theft. For safeguarding of this process, we propose a NDA concept for nuclear material accounting which is to measure the amount of curium in the reduction metal and associated process samples using a neutron coincidence counter and then to convert the curium mass into special nuclear material with predetermined curium ratios. For this, a well-type neutron coincidence counter with substantial shielding to protect the system from high gamma radiation is conceptually designed

  16. Local Purchasing of Journals is Required in Addition to a Nationally Purchased Collection to Meet the Information Needs of NHS Staff. A review of: Glover, Steven William, John Addison, Colette Gleghorn, and John Bramwell. “Journal Usage in NHS Hospitals: A Comparison Report of Total Usage at an Acute NHS Trust and a Specialist NHS Trust in the North West of England.” Health Information and Libraries Journal 24.3 (2007: 193‐9.

    Directory of Open Access Journals (Sweden)

    Jennie Kelson

    2008-03-01

    Full Text Available Objective ‐ To compare journal usage between an acute National Health Service (NHS Trust and a specialist NHS Trust located in North West England to provide some evidence as to how well the National Core Content Collection (provided by ProQuest meets the needs of staff in these settings.Design ‐ Comparative studySetting ‐ An acute NHS Trust, comprising four hospital sites, and a cancer specialist NHS Trust based on a single site. Both Trusts are located in North West England. The cancer specialist NHS Trust is a teaching hospital with undergraduate nurses, medical students, and student radiographers. This Trust is also closely associated with an adjoining cancer research institute. The acute NHS Trust has a large number of healthcare staff in training and was not described as a teaching hospital.Subjects ‐ Staff of the respective NHS Trusts. The staff numbers for each organisation were not provided.Methods ‐ COUNTER usage statistics of online journals, obtained from publisher administration tools, were collected for one year covering the period 1 December 2005 to 30 November 2006. Where available, the number of photocopies made from print journals during the same period by library users for their own use was also included. All full‐text downloads of journal articles were counted as part of this study, hence the possibility of double counting if a single article was requested in both HTML and PDF versions. Details of free or open access articles accessed without the need for a username and password were not included in the study. To encourage use of the electronic journals, library services at both Trusts implemented a number of initiatives to maximize publicity. These included direct e‐mails to staff, posters, and presentations to staff. Athens registration, required for access to the electronic journal collections, was promoted as part of the induction process for new library users. Staff members were encouraged to apply for the electronic table of contents alert for journals in their area of specialty. An A‐Z list of journals was accessible via the Trusts’ intranet and internet sites, and direct links to electronic journals were added to the NHS Dialog/Datastar databases and on PubMed.Main results ‐ The libraries at both Trusts in the study provide the majority of their journals in electronic‐only format. In addition to the National Core Content titles, the cancer specialist Trust provides access to an additional five journal collections: Science Direct Health Sciences, Blackwell Synergy Medical and Nursing collection, five journals selected from Nature Publishing Group, selected society journals via HighWire Press and Oxford University Press titles. Staff members of the acute Trust have access to an additional three journal collections: Science Direct Health Sciences, the BMJ Publishing Group (BMJPG collection and 16 LWW titles via Ovid. During the study period, a total of 93,376 articles were downloaded or copied. Of these, 47,079 articles were downloaded or copied by staff of the cancer specialist NHS Trust and 46,297 articles were downloaded or copied by staff of the acute NHS Trust. The usage of each of the journal collections during the study period for each Trust is shown in the table below with the most used resource shown in bold. (See article for table General information regarding some of the commonly used journal titles by staff of each Trust was included in the commentary, but levels of use were not enumerated. Staff of the cancer specialist NHS Trust favoured cancer‐related titles, whilst staff of the acute NHS Trust accessed journal titles over a greater range of subject areas. Details of the top titles accessed from the National Core Content collection were not provided for either Trust. A possible reason given for the lower usage level of the National Core Content collection by the cancer specialist NHS Trust compared to the acute NHS Trust was the presence of embargoes on many cancer‐related titles within the National Core Content collection. Information about training offered to staff, their level of access to computer facilities,or familiarity with accessing electronic journal collections was not provided.Conclusion ‐ Staff of both Trusts in the study recorded a high level of journal use, with a total of 93,376 articles downloaded or photocopied during the study period. There was a marked difference in the usage patterns of the National Core Content journals between the two Trusts studied with the acute NHS Trust showing a higher proportion of usage (29.9%compared with the cancer specialist Trust(4.5%. Staff members of the acute NHS Trust accessed a greater range of subject areas, while staff those at the cancer specialist NHS Trust favoured cancer related titles.The results indicated that the National Core Content collection did not meet the information needs of the specialist cancer Trust as well as it met the needs of the more generalist acute Trust. The National Core Content collection appears insufficient to meet the diverse information needs of all NHS staff. Local purchasing of journals, in addition to national level provision, is therefore required to ensure that the needs of local specialties are adequately supported.

  17. Protein (Cyanobacteria): 661286037 [PGDBj - Ortholog DB

    Lifescience Database Archive (English)

    Full Text Available 0:477 ... hypothetical protein, partial Prochlorococcus sp. scB243_498P3 MSTKSDSLKEKLIENFSDFSKLSDYSFMNYLRADPQ...STKDGNDHKPRSVYSGHYVPVLPTAIPEPEYISHSKKLFKELRLSSDLTKDKNFCLFFSGDISVANYPMSPVGWATGYALSIYGTEYTQQCPFGTGNGYGDGIAISVFEGLFNGKRMEMQLKGGGPTPYCRGA

  18. ORF Alignment: NC_004605 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available VIATLDKHDYQVSLEELQARMLE Sbjct: 1 ... SFSGIVKAKETASLSFRVPGTVESVFVNKGSVVEKGQVIATLDKHDYQVSLEELQARMLE 60 ... Query: 184 TLRAPFTGIVADVSVDPHE...QTLPGGSVVSIQQEDSWEVDIDVPENMIAQFALGQPASLTW 243 ... TLRAPFTGIVADVSVDPHEQTLPGGSVVS...IQQEDSWEVDIDVPENMIAQFALGQPASLTW Sbjct: 121 TLRAPFTGIVADVSVDPHEQTLPGGSVVSIQQEDSWEVDIDVPENMIAQFALGQPASLTW 180 ...

  19. ORF Alignment: NC_006513 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available ding ... response regulator [Azoarcus sp. EbN1] ... Length = 243 ... Query: 139 GRSRAMQDLYQKVLRVAASEAN...VLITGESGVGKELVARALHDNSTRAKGPYVAVHCASLP 198 ... GRSRAMQDLYQKVLRVAASEAN...VLITGESGVGKELVARALHDNSTRAKGPYVAVHCASLP Sbjct: 1 ... GRSRAMQDLYQKVLRVAASEANVLITGESGVGKELVARALHDNSTRAKGPYVAVHCAS

  20. ORF Alignment: NC_002754 [GENIUS II[Archive

    Lifescience Database Archive (English)

    Full Text Available SYPGDVYRNYKKHLEIIESSSADCVIFPELSLTGYIIKDLTYEIYKDAEEA 60 ... Query: 123 DPLKDLKIFEYKDLKFGVVICEDAWHPEPIEALSLMGADAIFIPSAS...PMRKLRENLAIEE 182 ... DPLKDLKIFEYKDLKFGVVICEDAWHPEPIEALSLMGADAIFIPSAS...PMRKLRENLAIEE Sbjct: 121 DPLKDLKIFEYKDLKFGVVICEDAWHPEPIEALSLMGADAIFIPSASPMRKLRENLAIEE 180 ... Query: 243 TENEL

  1. Nanoscale materials in chemistry

    National Research Council Canada - National Science Library

    Klabunde, Kenneth J; Richards, Ryan

    2009-01-01

    ...: Disordered, Porous Nanostructures Stephanie L. Brock 209 9 Ordered Microporous and Mesoporous Materials Freddy Kleitz 243 10 Applications of Microporous and Mesoporous Materials Anirban Ghosh,...

  2. Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Ashwood, T.L.; Marsh, J.D. Jr.

    1994-04-01

    This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L)

  3. Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Ashwood, T.L.; Marsh, J.D. Jr.

    1994-04-01

    This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L).

  4. New Developments in Actinides Burning with Symbiotic LWR-HTR-GCFR Fuel Cycles

    International Nuclear Information System (INIS)

    Bomboni, Eleonora

    2008-01-01

    The long-term radiotoxicity of the final waste is currently the main drawback of nuclear power production. Particularly, isotopes of Neptunium and Plutonium along with some long-lived fission products are dangerous for more than 100000 years. 96% of spent Light Water Reactor (LWR) fuel consists of actinides, hence it is able to produce a lot of energy by fission if recycled. Goals of Generation IV Initiative are reduction of long-term radiotoxicity of waste to be stored in geological repositories, a better exploitation of nuclear fuel resources and proliferation resistance. Actually, all these issues are intrinsically connected with each other. It is quite clear that these goals can be achieved only by combining different concepts of Gen. IV nuclear cores in a 'symbiotic' way. Light-Water Reactor - (Very) High Temperature Reactor ((V)HTR) - Fast Reactor (FR) symbiotic cycles have good capabilities from the viewpoints mentioned above. Particularly, HTR fuelled by Plutonium oxide is able to reach an ultra-high burn-up and to burn Neptunium and Plutonium effectively. In contrast, not negligible amounts of Americium and Curium build up in this core, although the total mass of Heavy Metals (HM) is reduced. Americium and Curium are characterised by an high radiological hazard as well. Nevertheless, at least Plutonium from HTR (rich in non-fissile nuclides) and, if appropriate, Americium can be used as fuel for Fast Reactors. If necessary, dedicated assemblies for Minor Actinides (MA) burning can be inserted in Fast Reactors cores. This presentation focuses on combining HTR and Gas Cooled Fast Reactor (GCFR) concepts, fuelled by spent LWR fuel and depleted uranium if need be, to obtain a net reduction of total mass and radiotoxicity of final waste. The intrinsic proliferation resistance of this cycle is highlighted as well. Additionally, some hints about possible Curium management strategies are supplied. Besides, a preliminary assessment of different chemical forms of

  5. Speciation of radionuclides in natural groundwaters: Annual report for the period October 1986 through September 1987

    International Nuclear Information System (INIS)

    Doxtader, M.M.; Beitz, J.V.; Reed, D.T.; Bates, J.K.

    1988-02-01

    Two ultrasensitive laser techniques, laser photoacoustic spectroscopy (LPAS) and laser-induced fluorescence (LIF), are being developed for the detection and speciation of trace levels of actinides in solutions typical of those expected in a high-level waste repository. An LPAS system was set up for these studies. Experiments were carried out to determine the detection limits of plutonium and americium in solution. Concurrently with the LPAS work, LIF studies were carried out on uranyl ion and curium in solution. 32 refs., 35 figs., 8 tabs

  6. Radiological safety considerations in the design and operation of the ORNL Transuranium Research Laboratory (TRL)

    International Nuclear Information System (INIS)

    Haynes, C.E.

    1976-01-01

    The Transuranium Research Laboratory (TRL) is the central facility at Oak Ridge National Laboratory (ORNL) for chemical and physical research involving transuranium elements. Transuranium Research Laboratory investigations are about equally divided between studies of inorganic and structural chemistry of the heavy elements and nuclear structure and properties of their isotopes. Elements studied include neptunium, plutonium, americium, curium, berkelium, californium, and einsteinium, each in microgram-to-gram quantities depending upon availability and experimental requirements. This paper describes an eight-step safety procedure followed in planning and approving individual research projects. This procedure should provide an optimum margin of safety and should permit the accomplishment of successful research

  7. Hydrothermal syntheses, structural, Raman, and luminescence studies of Cm[M(CN)2]3.3H2O and Pr[M(CN)2]3.3H2O (M=Ag, Au)

    International Nuclear Information System (INIS)

    Assefa, Zerihun; Haire, Richard G.; Sykora, Richard E.

    2008-01-01

    We have prepared Cm[Au(CN) 2 ] 3 .3H 2 O and Cm[Ag(CN) 2 ] 3 .3H 2 O as a part of our continuing investigations into the chemistry of the 5f-elements' dicyanometallates. Single crystals of Cm[Au(CN) 2 ] 3 .3H 2 O were obtained from the reaction of CmCl 3 and KAu(CN) 2 under mild hydrothermal conditions. Due to similarities in size, the related praseodymium compounds were also synthesized and characterized for comparison with the actinide systems. The compounds crystallize in the hexagonal space group P6 3 /mcm, where the curium and the transition metals interconnect through cyanide bridging. Crystallographic data (Mo Kα, λ=0.71073 A): Cm[Au(CN) 2 ] 3 .3H 2 O (1), a=6.6614(5) A, c=18.3135(13) A, V=703.77(9), Z=2; Pr[Au(CN) 2 ] 3 .3H 2 O (3), a=6.6662(8) A, c=18.497(3) A, V=711.83(17), Z=2; Pr[Ag(CN) 2 ] 3 .3H 2 O (4), a=6.7186(8) A, c=18.678(2) A, V=730.18(14), Z=2. The Cm 3+ and/or Pr 3+ ions are coordinated to six N-bound CN - groups resulting in a trigonal prismatic arrangement. Three oxygen atoms of coordinated water molecules tricap the trigonal prismatic arrangement providing a coordination number of nine for the f-elements. The curium ions in both compounds exhibit a strong red emission corresponding to the 6 D 7/2 → 8 S 7/2 transition. This transition is observed at 16,780 cm -1 , with shoulders at 17,080 and 16,840 cm -1 for the Ag complex, while the emission is red shifted by ∼100 cm -1 in the corresponding gold complex. The Pr systems also provide well-resolved emissions upon f-f excitation. - Graphical abstract: Coordination polymeric compounds between a trans-plutonium element, curium and transition metal ions, gold(I) and silver(I), were prepared using the hydrothermal synthetic procedure. The curium ion and the transition metals are interconnected through cyanide bridging. The Cm ion has a tricapped trigonal prismatic coordination environment with coordination number of nine. Detail photoluminescence studies of the complexes are also reported

  8. The speciation of dissolved elements in aquatic solution. Radium and actinides

    International Nuclear Information System (INIS)

    Haesaenen, E.

    1994-01-01

    In the publication, the chemistry and speciation of radium, thorium, protactinium, uranium, neptunium, lutonium, americium and curium in ground-water environment is reviewed. Special attention is given to the transuranium elements, which have a central role in the repository of nuclear wastes. The most important methods used in the speciation of these elements is presented. The laser-induced methods, developed in the 1980's, are especially discussed. These have made it possible, e.g., to speciate the transuranium elements in their very low, actual repository ground-water concentrations (10-100 ng/l). (54 refs., 10 figs., 3 tabs.)

  9. Radiation protection data sheet. Radiation protection data sheets for the use of radionuclides in unsealed sources

    International Nuclear Information System (INIS)

    Anon.

    1999-01-01

    These radiation protection data sheet are devoted to responsible persons and employees of various laboratories or medical, pharmaceutical, university and industrial departments where radionuclides are handled as well as all the persons who attend to satisfy in this field. They contain the essential radiation protection data for the use of unsealed sources: physical characteristics, risk assessment, administrative procedures, recommendations, regulations and bibliography. This new series includes the following radionuclides: californium 252, curium 244, gallium 67, indium 113m, plutonium 238, plutonium 239, polonium 210, potassium 42, radium 226, thorium 232, uranium 238 and zinc 65. (O.M.)

  10. Proceedings of the Sandia Laboratories workshop on the use of titanate ion exchangers for defense waste management

    International Nuclear Information System (INIS)

    Schwoebel, R.L.; Northrup, C.J.

    1978-01-01

    Abstracts and visual aids from the following talks are presented: removal of radionuclides from Hanford defense waste solutions; waste management programs at Savannah River Plant; application of defense waste decontamination; americium and curium recovery from nuclear waste using inorganic ion exchanger materials; removal of trace 106 Ru in nuclear waste processing; and titanate characterization and consolidation processes. Copies of three memos are included: 90 Sr radiation effects on sodium titanate loaded macroreticular resin; 238 239 Pu content in defense waste; and preparation and physical properties of sodium titanate in ion exchange resin

  11. Composition containing transuranic elements for use in the homeopathic treatment of aids

    International Nuclear Information System (INIS)

    Lustig, D.

    1996-01-01

    A homeopathic remedy consisting of a composition containing one or more transuranic elements, particularly plutonium, for preventing and treating acquired immunodeficiency syndrome (AIDS) in humans, as well as seropositivity for human immunodeficiency virus (HIV). Said composition is characterized in that it uses any chemical or isotopic form of one or more transuranic elements (neptunium, plutonium, americium, curium, berkelium, californium or einsteinium), particularly plutonium, said form being diluted and dynamized according to conventional homeopathic methods, particularly the so-called Hahnemann and Korsakov methods, and provided preferably but not exclusively in the form of lactose and/or saccharose globules or granules impregnated with the active principle of said composition. (author)

  12. Analogs for transuranic elements

    International Nuclear Information System (INIS)

    Weimer, W.C.; Laul, J.C.; Kutt, J.C.

    1981-01-01

    A combined theoretical and experimental approach is being used to estimate the long-term environmental and biogeochemical behaviors of selected transuranic elements. The objective of this research is to estimate the effect that long-term (hundreds of years) environmental weathering has on the behavior of the transuranic elements americium and curium. This is achieved by investigating the actual behavior of naturally occurring rare earth elements, especially neodymium, that serve as transuranic analogs. Determination of the analog element behavior provides data that can be used to estimate the ultimate availability to man of transuranic materials released into the environment

  13. Natural Transmutation of Actinides via the Fission Reaction in the Closed Thorium-Uranium-Plutonium Fuel Cycle

    Science.gov (United States)

    Marshalkin, V. Ye.; Povyshev, V. M.

    2017-12-01

    It is shown for a closed thorium-uranium-plutonium fuel cycle that, upon processing of one metric ton of irradiated fuel after each four-year campaign, the radioactive wastes contain 54 kg of fission products, 0.8 kg of thorium, 0.10 kg of uranium isotopes, 0.005 kg of plutonium isotopes, 0.002 kg of neptunium, and "trace" amounts of americium and curium isotopes. This qualitatively simplifies the handling of high-level wastes in nuclear power engineering.

  14. Sorption and chromatographic techniques for processing liquid waste of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Gelis, V.M.; Milyutin, V.V.; Chuveleva, E.A.; Maslova, G.B.; Kudryavtseva, S.P.; Firsova, L.A.; Kozlitin, E.A.

    2000-01-01

    In the spent nuclear fuel processing procedures the significant quantity of high level liquid waste containing long-lived high toxic radionuclides of cesium, strontium, promethium, americium, curium, etc. is generated. Separation of those radionuclides from the waste not merely simplifies the further safe waste handling but also reduces the waste processing operation costs due to the market value of certain individual radionuclide preparations. Recovery and separation of high grade pure long-lived radionuclide preparations is frequently performed by means of chromatographic techniques. (authors)

  15. Diethylene-triamine-penta-acetate administration protocol for radiological emergency medicine in nuclear fuel reprocessing plants.

    Science.gov (United States)

    Jin, Yutaka

    2008-01-01

    Inhalation therapy of diethylene-triamine-penta-acetate (DTPA) should be initiated immediately to workers who have significant incorporation of plutonium, americium or curium in the nuclear fuel reprocessing plant. A newly designed electric mesh nebulizer is a small battery-operated passive vibrating mesh device, in which vibrations in an ultrasonic horn are used to force drug solution through a mesh of micron-sized holes. This nebulizer enables DTPA administration at an early stage in the event of a radiation emergency from contamination from the above radioactive metals.

  16. Actinides

    International Nuclear Information System (INIS)

    Martinot, L.; Fuger, J.

    1985-01-01

    The oxidation behavior of the actinides is explained on the basis of their electronic structure. The actinide elements, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium, mendelevium, nobelium, and laurencium are included. For all except the last three elements, the points of discussion are oxidation states, Gibbs energies and potentials, and potential diagram for the element in acid solution; and thermodynamic properties of these same elements are tabulated. References are cited following discussion of each element with a total of 97 references being cited. 13 tables

  17. Safety analysis report for packaging: neutron shipping cask, model 4T

    International Nuclear Information System (INIS)

    Peterson, R.T.

    1977-01-01

    This Safety Analysis Report for Packaging demonstrates that the neutron shipping cask can safely transport, in solid or powder form, all isotopes of uranium, plutonium, americium, curium, berkelium, californium, einsteinium, and fermium. The cask and its contents are described. It also evaluates transport conditions, structural parameters (e.g., load resistance, pressure and impact effects, lifting and tiedown devices), and shielding. Finally, it discusses compliance with Chapter 0529 of the Energy Research and Development Administration Manual, Safety Standards for the Packaging of Fissile and Other Radioactive Materials

  18. Ground depositions and air concentrations of Chernobyl fallout radionuclides at Munich-Neuherberg

    Energy Technology Data Exchange (ETDEWEB)

    Hoetzl, H.; Rosner, G.; Winkler, R.

    1987-01-01

    Southern Bavaria has received a comparatively high deposition of fallout radionuclides from the reactor accident at Chernobyl. As a result, in addition to the measurement of numerous gamma emitting nuclides and of strontium isotopes, the determination of several actinides, including isotopes of uranium, neptunium, plutonium and curium was possible. The observed radionuclide composition of the fallout and the time course of ground deposition and air concentration at the site of the Gesellschaft fuer Strahlen- und Umweltforschung (GSF) at Neuherberg, 10 km north of Munich, are reported and discussed.

  19. Ground depositions and air concentrations of Chernobyl fallout radionuclides at Munich-Neuherberg

    International Nuclear Information System (INIS)

    Hoetzl, H.; Rosner, G.; Winkler, R.

    1987-01-01

    Southern Bavaria has received a comparatively high deposition of fallout radionuclides from the reactor accident at Chernobyl. As a result, in addition to the measurement of numerous gamma emitting nuclides and of strontium isotopes, the determination of several actinides, including isotopes of uranium, neptunium, plutonium and curium was possible. The observed radionuclide composition of the fallout and the time course of ground deposition and air concentration at the site of the Gesellschaft fuer Strahlen- und Umweltforschung (GSF) at Neuherberg, 10 km north of Munich, are reported and discussed. (orig.)

  20. Actinide nuclides in environmental air and precipitation samples after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Rosner, G.; Hoetzl, H.; Winkler, R. (Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen (West Germany))

    1988-01-01

    The present paper describes the analysis of isotopes of uranium, neptunium, plutonium, americium and curium, in air and deposition samples taken at our laboratory site 10 km north of Munich, subsequent to the Chernobyl accident. Uranium-234, {sup 237}U, {sup 238}U, {sup 239}Np, {sup 238}Pu, {sup 239+240}Pu and {sup 242}Cm have been identified and upper limits of detection have been established for {sup 241}Am and {sup 244}Cm. Deposition and air concentration values are discussed. 12 refs., 1 fig., 2 tabs.

  1. Thermodynamics of carbothermic synthesis of actinide mononitrides

    International Nuclear Information System (INIS)

    Ogawa, T.; Shirasu, Y.; Minato, K.; Serizawa, H.

    1997-01-01

    Carbothermic synthesis will be further applied to the fabrication of nitride fuels containing minor actinides (MA) such as neptunium, americium and curium. A thorough understanding of the carbothermic synthesis of UN will be beneficial in the development of the MA-containing fuels. Thermodynamic analysis was carried out for conditions of practical interest in order to better understand the recent fabrication experiences. Two types of solution phases, oxynitride and carbonitride phases, were taken into account. The Pu-N-O ternary isotherm was assessed for the modelling of M(C, N, O). With the understanding of the UN synthesis, the fabrication problems of Am-containing nitrides are discussed. (orig.)

  2. Researches on nuclear criticality safety evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-10-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  3. Researches on nuclear criticality safety evaluation

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Nomura, Yasushi

    2003-01-01

    For criticality safety evaluation of burnup fuel, the general-purpose burnup calculation code, SWAT, was revised, and its precision was confirmed through comparison with other results from OECD/NEA's burnup credit benchmarks. Effect by replacing the evaluated nuclear data from JENDL-3.2 to ENDF/B-VI and JEF-2.2 was also studied. Correction factors were derived for conservative evaluation of nuclide concentrations obtained with the simplified burnup code ORIGEN2.1. The critical masses of curium were calculated and evaluated for nuclear criticality safety management of minor actinides. (author)

  4. Browse Title Index

    African Journals Online (AJOL)

    Items 201 - 243 of 243 ... Vol 23, No 2 (2013), The Kidney in Pregnancy, Abstract. S Adam. Vol 12, No 4 ... Vol 14, No 2 (2004), The role of chemotherapy in the management of cervical cancer: review article, Details. WPW Mdluli ... Vol 13, No 3 (2003), The role of radiation therapy in epithelial ovarian cancer, Abstract. G Dreyer.

  5. Marine data and information management system for the Indian Ocean

    Digital Repository Service at National Institute of Oceanography (India)

    Sarupria, J.S.

    stream_size 8 stream_content_type text/plain stream_name IGBP_India_2000_243.pdf.txt stream_source_info IGBP_India_2000_243.pdf.txt Content-Encoding ISO-8859-1 Content-Type text/plain; charset=ISO-8859-1 ...

  6. 77 FR 26998 - Airworthiness Directives; Airbus Airplanes

    Science.gov (United States)

    2012-05-08

    ...-0428; Directorate Identifier 2011-NM-078-AD] RIN 2120-AA64 Airworthiness Directives; Airbus Airplanes...: We propose to adopt a new airworthiness directive (AD) for all Airbus Model A330-243, -243F, -342..., between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. For Airbus service information...

  7. Threats to Aircraft Structural Safety Including a Compendium of Selected Structural Accidents/Incidents

    Science.gov (United States)

    2010-03-01

    April 28, 1988 Aloha Airlines Flight No. 243 departed Hilo , Hawaii with a crew and 89 passengers on board. When leveling off at 24,000 feet, there was an...89/03, “Aloha Airlines, Flight 243, Boeing 737-200, N73711, Near Maui, Hawaii April 28, 1988,” adopted on 14 June 1989, Washington DC. http

  8. Male gender, Charnley class C, and severity of bone defects predict the risk for aseptic loosening in the cup of ABG I hip arthroplasty

    Czech Academy of Sciences Publication Activity Database

    Gallo, J.; Havránek, Vítězslav; Zapletalová, J.; Lošťák, J.

    2010-01-01

    Roč. 11, č. 10 (2010), 243/1-243/7 E-ISSN 1471-2474 Institutional research plan: CEZ:AV0Z10100522 Keywords : hip arthroplasty * ABG I Subject RIV: BH - Optics, Masers, Lasers Impact factor: 1.941, year: 2010

  9. U.S. Trends in Solid Waste Management and GHG Emissions

    Science.gov (United States)

    In 2009, 243 million tons of municipal solid waste (MSW) was produced in the United States. Currently, 34% of the 243 million tons of MSW is recovered and recycled or composted which conserves energy and natural resources as well as avoid waste disposal. Of the remaining MSW th...

  10. Maslov. Evaluated neutron reaction data for Am and Cm isotopes. Summary documentation

    International Nuclear Information System (INIS)

    Lemmel, H.D.

    1996-01-01

    The nuclear data file by V.M. Maslov et al includes evaluated neutron reaction data for Am-241,243 Cm-243-245,246 in EDNF-6 format. The data are available from the IAEA Nuclear Data Section, costfree upon request. (author)

  11. Petroleum hydrocarbons in surface sediments in Kandla creek (Gujarat)

    Digital Repository Service at National Institute of Oceanography (India)

    Kadam, A.N.

    stream_size 6 stream_content_type text/plain stream_name Mahasagar_20_243.pdf.txt stream_source_info Mahasagar_20_243.pdf.txt Content-Encoding ISO-8859-1 Content-Type text/plain; charset=ISO-8859-1 ...

  12. Sacred Space and Sublime Sacramental Piety

    DEFF Research Database (Denmark)

    Petersen, Nils Holger

    2012-01-01

    Analyses and Discussions of Mozart's Sacramental Litanies K. 125 and K. 243 in relation to the notions of the Sacred and the Sublime.......Analyses and Discussions of Mozart's Sacramental Litanies K. 125 and K. 243 in relation to the notions of the Sacred and the Sublime....

  13. Multiple recycling of plutonium in advanced PWRs

    International Nuclear Information System (INIS)

    Kloosterman, J.L.

    1998-04-01

    The influence of the moderator-to-fuel ratio in MOX fueled PWRs on the moderator void coefficient, the fuel temperature coefficient, the moderator temperature coefficient, the boron reactivity worth, the critical boron concentration, the mean neutron generation time and the effective delayed neutron fraction has been assessed. Increasing the moderator-to-fuel ratio to values larger than three, gives a moderator void coefficient sufficiently large to recycle the plutonium at least four times. Scenario studies show that four times recycling of plutonium in PWRs reduces the plutonium mass produced with a factor of three compared with a reference once-through reactor park, but that the americium and curium production triple. If the minor actinides and the remaining plutonium after four times recycling are disposed of, the reduction of the radiotoxicity reaches only a factor of two. This factor increases to five at the maximum when the plutonium is further recycled. Recycling of americium and curium is needed to further reduce the radiotoxicity of the spent fuel. 4 refs

  14. NEW METHOD FOR DETERMINATION OF ACTINIDES AND STRONTIUM IN ANIMAL TISSUE

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S; Jay Hutchison, J; Don Faison, D

    2007-05-07

    The analysis of actinides in animal tissue samples is very important for environmental monitoring. There is a need to measure actinide isotopes with very low detection limits in animal tissue samples, including fish, deer, hogs, beef and shellfish. A new, rapid actinide separation method has been developed and implemented that allows the measurement of plutonium, neptunium, uranium, americium, curium and strontium isotopes in large animal tissue samples (100-200 g) with high chemical recoveries and effective removal of matrix interferences. This method uses stacked TEVA Resin{reg_sign}, TRU Resin{reg_sign} and DGA-Resin{reg_sign} cartridges from Eichrom Technologies (Darien, IL, USA) that allows the rapid separation of plutonium (Pu), neptunium (Np), uranium (U), americium (Am), and curium (Cm) using a single multi-stage column combined with alpha spectrometry. Sr-90 is collected on Sr Resin{reg_sign} from Eichrom Technologies (Darien, IL, USA). After acid digestion and furnace heating of the animal tissue samples, the actinides and Sr-89/90 are separated using column extraction chromatography. This method has been shown to be effective over a wide range of animal tissue matrices. By using vacuum box cartridge technology with rapid flow rates, sample preparation time is minimized.

  15. Impact of Transmutation Scenarios on Fuel Transportation

    International Nuclear Information System (INIS)

    Saturnin, A.; Duret, B.; Allou, A.; Jasserand, F.; Fillastre, E.; Giffard, F.X.; Chabert, C.; Caron-Charles, M.; Garzenne, C.; Laugier, F.

    2015-01-01

    Minor actinides transmutation scenarios have been studied in the frame of the French Sustainable Radioactive Waste Management Act of 28 June 2006. Transmutation scenarios supposed the introduction of a sodium-cooled fast reactor fleet using homogeneous or heterogeneous recycling modes for the minor actinides. Americium, neptunium and curium (MA) or americium alone (Am) can be transmuted together in a homogeneous way embedded in FR-MOX fuel or incorporated in MA or Am-Bearing radial Blankets (MABB or AmBB). MA transmutation in Accelerator Driven System has also been studied while plutonium is being recycled in SFR. Assessments and comparisons of these advanced cycles have been performed considering technical and economic criteria. Transportation needs for fresh and used transmutation fuels is one of these criteria. Transmutation fuels have specific characteristics in terms of thermal load and neutron emissions. Thermal, radiation and criticality constraints have been taken into account in this study to suggest cask concepts for routine conditions of transport, to estimate the number of assemblies to be transported in a cask and the number of annual transports. Comparison with the no transmutation option, i.e. management of uranium and plutonium in SFRs, is also presented. Regarding these matters, no high difficulties appear for assemblies with limited content of Am (homogeneous or heterogeneous recycling modes). When fuels contain curium, technical transport uncertainties increase because of the important heat release requiring dividing fresh fuels and technological innovations development (MABB and ADS). (authors)

  16. Rapid column extraction method for actinides and strontium in fish and other animal tissue samples

    International Nuclear Information System (INIS)

    Maxwell III, S.L.; Faison, D.M.

    2008-01-01

    The analysis of actinides and radiostrontium in animal tissue samples is very important for environmental monitoring. There is a need to measure actinide isotopes and strontium with very low detection limits in animal tissue samples, including fish, deer, hogs, beef and shellfish. A new, rapid separation method has been developed that allows the measurement of plutonium, neptunium, uranium, americium, curium and strontium isotopes in large animal tissue samples (100-200 g) with high chemical recoveries and effective removal of matrix interferences. This method uses stacked TEVA Resin R , TRU Resin R and DGA Resin R cartridges from Eichrom Technologies (Darien, IL, USA) that allows the rapid separation of plutonium (Pu), neptunium (Np), uranium (U), americium (Am), and curium (Cm) using a single multi-stage column combined with alphaspectrometry. Strontium is collected on Sr Resin R from Eichrom Technologies (Darien, IL, USA). After acid digestion and furnace heating of the animal tissue samples, the actinides and 89/90 Sr are separated using column extraction chromatography. This method has been shown to be effective over a wide range of animal tissue matrices. Vacuum box cartridge technology with rapid flow rates is used to minimize sample preparation time. (author)

  17. Validation of KENOREST with LWR-PROTEUS phase II samples

    Energy Technology Data Exchange (ETDEWEB)

    Wagner, M.; Kilger, R.; Pautz, A.; Zwermann, W. [GRS, Garching (Germany); Grimm, P.; Vasiliev, A.; Ferroukhi, H. [Paul Scherrer Institut, Villigen (Switzerland)

    2012-11-01

    In order to broaden the validation basis of the reactivity and nuclide inventory code KENOREST two samples of the LWR-PROTEUS phase II program have been calculated and compared to the experimental results. In general most nuclides are reproduced very well and agree within about ten percent with the experiment. Some already known problems, the overprediction of metallic fission products and the underprediction of the higher curium isotopes, have been confirmed. One of the largest uncertainties in the calculation was the burnup of the samples due to differences between a core simulation of the fuel vendor and the burnup determined from the measured values of the burnup indicator Nd-148. Two different models taking into account the environment for a peripheral fuel rod have been studied. The more detailed model included the three direct neighbor fuel assemblies depleted along with the fuel rod of interest. The influence on the results has been found to be very small. Compared to the uncertainties from the burnup, this effect can be considered negligible. The reason for the low influence was basically that the spectrum did not get considerably harder with increasing burnup beyond about 20GWd/tHM. Since the sample reached burnups far beyond that value, an effect could not be seen. In the near future an update of the used libraries is planned and it will be very interesting to study the effect on the results, especially for Curium. (orig.)

  18. First calorimetric determination of heat of extraction of 248Cm in a bi-phasic system

    International Nuclear Information System (INIS)

    Martin, Leigh R.; Zalupski, Peter R.

    2011-01-01

    This report presents a summary of the work performed to meet FCR and D level 2 milestone M21SW050201, 'Complete the first calorimetric determination of heat of extraction of 248Cm in a bi-phasic system'. This work was carried out under the auspices of the Thermodynamics and Kinetics FCR and D work package. To complement previous work undertaken under this work package we have extended out heat of extraction studies by di-2-ethyl-hexyl-phosphoric acid to curium. This report also details the heat of extraction of samarium in the same system. This work was performed to not only test the methodology but also to check for consistency with the heats of extraction obtained with those in the prior literature. The heat of extraction for samarium that was obtained in this study was -9.6 kJ mol-1, which is in reasonable agreement with the previously obtained value of -10.9 kJ mol-1. The curium heat of extraction was performed under two sets of conditions and the obtained heats of extraction were in reasonable agreement with each other at -16.0 ± 1.1 and -16.8 ± 1.5 kJ mol-1.

  19. Determining the dissolution rates of actinide glasses: A time and temperature Product Consistency Test study

    International Nuclear Information System (INIS)

    Daniel, W.E.; Best, D.R.

    1995-01-01

    Vitrification has been identified as one potential option for the e materials such as Americium (Am), Curium (Cm), Neptunium (Np), and Plutonium (Pu). A process is being developed at the Savannah River Site to safely vitrify all of the highly radioactive Am/Cm material and a portion of the fissile (Pu) actinide materials stored on site. Vitrification of the Am/Cm will allow the material to be transported and easily stored at the Oak Ridge National Laboratory. The Am/Cm glass has been specifically designed to be (1) highly durable in aqueous environments and (2) selectively attacked by nitric acid to allow recovery of the valuable Am and Cm isotopes. A similar glass composition will allow for safe storage of surplus plutonium. This paper will address the composition, relative durability, and dissolution rate characteristics of the actinide glass, Loeffler Target, that will be used in the Americium/Curium Vitrification Project at Westinghouse Savannah River Company near Aiken, South Carolina. The first part discusses the tests performed on the Loeffler Target Glass concerning instantaneous dissolution rates. The second part presents information concerning pseudo-activation energy for the one week glass dissolution process

  20. Helium behaviour in nuclear glasses

    International Nuclear Information System (INIS)

    Fares, T.

    2011-01-01

    The present thesis focuses on the study of helium behavior in R7T7 nuclear waste glass. Helium is generated by the minor actinides alpha decays incorporated in the glass matrix. Therefore, four types of materials were used in this work. These are non radioactive R7T7 glasses saturated with helium under pressure, glasses implanted with 3 He + ions, glasses doped with curium and glasses irradiated in nuclear reactor. The study of helium solubility in saturated R7T7 glass has shown that helium atoms are inserted in the glass free volume. The results yielded a solubility of about 10 16 at. cm -3 atm. -1 . The incorporation limit of helium in this type of glass has been determined; its value amounted to about 2*10 21 at. cm -3 , corresponding to 2.5 at.%. Diffusion studies have shown that the helium migration is controlled by the single population dissolved in the glass free volume. An ideal diffusion model was used to simulate the helium release data which allowed to determine diffusion coefficients obeying to the following Arrhenius law: D = D 0 exp(-E a /kBT), where D 0 = 2.2*10 -2 and 5.4*10 -3 cm 2 s -1 and E a = 0.61 eV for the helium saturated and the curium doped glass respectively. These results reflect a thermally activated diffusion mechanism which seems to be not influenced by the glass radiation damage and helium concentrations studied in the present work (up to 8*10 19 at. g -1 , corresponding to 0.1 at.%). Characterizations of the macroscopic, structural and microstructural properties of glasses irradiated in nuclear reactor did not reveal any impact associated with the presence of helium at high concentrations. The observed modifications i.e. a swelling of 0.7 %, a decrease in hardness by 38 %, an increase between 8 and 34 % of the fracture toughness and a stabilization of the glass structure under irradiation, were attributed to the glass nuclear damage induced by the irradiation in reactor. Characterizations by SEM and TEM of R7T7 glasses implanted

  1. Objectives, Strategies, and Challenges for the Advanced Fuel Cycle Initiative

    International Nuclear Information System (INIS)

    Steven Piet; Brent Dixon; David Shropshire; Robert Hill; Roald Wigeland; Erich Schneider; J. D. Smith

    2005-01-01

    This paper will summarize the objectives, strategies, and key chemical separation challenges for the Advanced Fuel Cycle Initiative (AFCI). The major objectives are as follows: Waste management--defer the need for a second geologic repository for a century or more, Proliferation resistance--be more resistant than the existing PUREX separation technology or uranium enrichment, Energy sustainability--turn waste management liabilities into energy source assets to ensure that uranium ore resources do not become a constraint on nuclear power, and Systematic, safe, and economic management of the entire fuel cycle. There are four major strategies for the disposal of civilian spent fuel: Once-through--direct disposal of all discharged nuclear fuel, Limited recycle--recycle transuranic elements once and then direct disposal, Continuous recycle--recycle transuranic elements repeatedly, and Sustained recycle--same as continuous except previously discarded depleted uranium is also recycled. The key chemical separation challenges stem from the fact that the components of spent nuclear fuel vary greatly in their influence on achieving program objectives. Most options separate uranium to reduce the weight and volume of waste and the number and cost of waste packages that require geologic disposal. Separated uranium can also be used as reactor fuel. Most options provide means to recycle transuranic (TRU) elements--plutonium (Pu), neptunium (Np), americium (Am), curium (Cm). Plutonium must be recycled to obtain repository, proliferation, and energy recovery benefits. U.S. non-proliferation policy forbids separation of plutonium by itself; therefore, one or more of the other transuranic elements must be kept with the plutonium; neptunium is considered the easiest option. Recycling neptunium also provides repository benefits. Americium recycling is also required to obtain repository benefits. At the present time, curium recycle provides relatively little benefit; indeed, recycling

  2. 78 FR 3029 - Notice of Lodging of Proposed Amended Consent Decree Under the Comprehensive Environmental...

    Science.gov (United States)

    2013-01-15

    ... (represented by Kenneth Senser as the Executor the Estate of Saul Senser) will pay the United States $243,250... claim, the Estate of Saul Senser, together with Kenneth Senser in his capacity as Executor of the Estate...

  3. K některým otázkám etnochoreologického studia: tanec, gender a politika

    Czech Academy of Sciences Publication Activity Database

    Stavělová, Daniela

    2010-01-01

    Roč. 20, č. 4 (2010), s. 239-243 ISSN 0862-8351 Institutional research plan: CEZ:AV0Z90580513 Keywords : dance * gender * politics * national movement * identity Subject RIV: AC - Archeology, Anthropology, Ethnology

  4. Integration of the information problem-solving skill in an educational programme: The effects of learning with authentic tasks.

    NARCIS (Netherlands)

    Brand-Gruwel, Saskia; Wopereis, Iwan

    2008-01-01

    Brand-Gruwel, S., & Wopereis, I. (2006). Integration of the information problem-solving skill in an educational programme: The effects of learning with authentic tasks. Technology, Instruction, Cognition, and Learning, 4, 243-263.

  5. (obese) gene of mithun (Bos frontalis)

    African Journals Online (AJOL)

    Nishant-3

    2Division of Animal Genetics, Indian Veterinary Research Institute, Izatnagar, Bareilly-243 122, India. 3Department of Animal ... closely associated with social, cultural, religious and livelihood of the tribes .... Southeast Asia (Gupta et al., 1999).

  6. Large-scale evaluation of carnivore road mortality: the effect of landscape and local scale characteristics

    Czech Academy of Sciences Publication Activity Database

    Červinka, J.; Riegert, J.; Grill, S.; Šálek, Martin

    2015-01-01

    Roč. 60, č. 3 (2015), s. 233-243 ISSN 2199-2401 Institutional support: RVO:68081766 Keywords : Carnivores * Landscape characteristics * Linear structures * Local characteristics * Road mortality * Temporal pattern Subject RIV: EH - Ecology, Behaviour

  7. Potential emigration of Siberian cattle germplasm on Chirikof Island ...

    Indian Academy of Sciences (India)

    2USDA Agricultural Research Service, 243 Fort Keogh Road, Miles City, MT 59301, USA ... 4Department of Environmental and Biological Sciences, University of ..... Food and. Agriculture Organization of the United Nations, Rome, Italy.

  8. Cyclotella hinziae sp. nov. – a small Cyclotella (Bacillariophyceae) from subalpine lake Schliersee (Bavaria, Germany)

    Czech Academy of Sciences Publication Activity Database

    Houk, Václav; König, C.; Klee, R.

    2015-01-01

    Roč. 15, č. 2 (2015), s. 235-243 ISSN 1802-5439 Institutional support: RVO:67985939 Keywords : halassiosiraceae * taxonomy * valve ultrastructure Subject RIV: EF - Botanics Impact factor: 2.026, year: 2015

  9. Estimation of radioactive contaminants in Cm242 and Cm244 isotopic fuels

    International Nuclear Information System (INIS)

    Terent'ev, V.P.; Makarenko, A.I.

    1972-01-01

    The radiation properties of Cm 242 and Cm 244 preparations and the effect on them of possible contaminants are considered. One of the most important requirements for K alpha active fuels for radioisotope thermoelectric batteries is ensuring a low ionizing radiation background. In determining the effect of impurities on the radiation properties of a preparation, quantitative evaluation of certain factors is sufficient. In a Cm 242 preparation it is possible to show that Am 241 and Cm 243 are undesirable impurities. The presence of Am 241 increases the soft gamma output by 20%. The presence of Cm 243 may double the dose rate from an unshielded preparation and increase the hard gamma output 10-fold. The properties of Cm 242 preparations deteriorate when Am 243 and Cm 243 are present

  10. Nápěvy písní k tanci "do kolečka"– textová výstavba a deklamace

    Czech Academy of Sciences Publication Activity Database

    Vejvoda, Zdeněk

    2006-01-01

    Roč. 93, č. 3 (2006), s. 243-258 ISSN 0009-0794 Institutional research plan: CEZ:AV0Z90580513 Keywords : round and round * structural analysis * declamation Subject RIV: AC - Archeology, Anthropology, Ethnology

  11. The pink pigment prodigiosin: Vibrational spectroscopy and DFT calculations

    Czech Academy of Sciences Publication Activity Database

    Jehlička, J.; Němec, I.; Varnali, T.; Culka, A.; Svatoš, A.; Frank, Otakar; Oren, A.; Edwards, G.M.

    2016-01-01

    Roč. 134, NOV 2016 (2016), s. 234-243 ISSN 0143-7208 Institutional support: RVO:61388955 Keywords : prodigiosin * serratia marcescens * raman spectroscopy Subject RIV: CG - Electrochemistry Impact factor: 3.473, year: 2016

  12. delta-Thiolactones as Prodrugs of Thiol-Based Glutamate Carboxypeptidase II (GCPII) Inhibitors

    Czech Academy of Sciences Publication Activity Database

    Ferraris, D. V.; Majer, Pavel; Ni, C.; Slusher, C. E.; Rais, R.; Wu, Y.; Wozniak, K. M.; Alt, J.; Rojas, C.; Slusher, B. S.; Tsukamoto, T.

    2014-01-01

    Roč. 57, č. 1 (2014), s. 243-247 ISSN 0022-2623 Institutional support: RVO:61388963 Keywords : pharmacokinetics * discovery * disorders * diagnosis * pain Subject RIV: CC - Organic Chemistry Impact factor: 5.447, year: 2014

  13. Enforcement and Effectiveness of Consumer Law in the Czech Republic

    Czech Academy of Sciences Publication Activity Database

    Pauknerová, Monika; Skalská, H.

    2017-01-01

    Roč. 7, č. 4 (2017), s. 243-254 ISSN 1805-8396 Institutional support: RVO:68378122 Keywords : consumer law * enforcement * alternative dispute resolution Subject RIV: AG - Legal Sciences OBOR OECD: Law

  14. Enhancement of the feeding value of wheat offal for broiler feeding ...

    African Journals Online (AJOL)

    Dr. &Mrs Tunde Lawal

    2012-08-14

    Aug 14, 2012 ... ... Ladoke Akintola University of Science and Technology, Ogbomosho, ... degraded the WTO, it was observed that there was improvement in crude protein value from 2.43 g/100 ..... Principles and Procedures of statistics.

  15. PRESUMPTIVE DIAGNOSIS OF SCHISTOSOMA HAEMATOBIUM ...

    African Journals Online (AJOL)

    boaz

    AFRICAN JOURNAL OF CLINICAL AND EXPERIMENTAL MICROBIOLOGY .... study. Sample Collection and Processing. Two specimen containers were given to each subject and the ... false positive results and 24.3% true negative results.

  16. S¯adhan¯a Vol. 32, 2007 Subject Index

    Indian Academy of Sciences (India)

    confined high strength concrete. 243. Control. Laminar separation bubbles: ... Hybrid LES-Review and assessment. 501 ... control. 103. Fatality risk. Prediction of traffic fatalities and prospects for ... treatment furnaces of steel casting industries.

  17. Arsenic mineralogy of near-neutral soils and mining waste at the Smolotely-Líšnice historical gold district, Czech Republic

    Czech Academy of Sciences Publication Activity Database

    Drahota, P.; Kulakowski, O.; Culka, A.; Knappová, M.; Rohovec, Jan; Veselovský, F.; Racek, M.

    2018-01-01

    Roč. 89, February (2018), s. 243-254 ISSN 0883-2927 Institutional support: RVO:67985831 Keywords : soil * mining waste * pharmacosiderite * yukonite * arseniosiderite Subject RIV: DB - Geology ; Mineralogy OBOR OECD: Mineralogy Impact factor: 2.581, year: 2016

  18. Effect of low protein diets and lysine supplementation on growth ...

    African Journals Online (AJOL)

    Dr. Ajit

    2012-07-17

    Jul 17, 2012 ... 3Division of Livestock Product Technology, Indian Veterinary Research Institute, Izatnagar – 243 ... Key words: Carcass trait, low protein, lysine, meat quality, pigs. ... functional activities, reproduction and disease resistance.

  19. Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1993

    International Nuclear Information System (INIS)

    1994-07-01

    The results of the joint researches by utilizing the facilities of JAERI in 1993 fiscal year were summarized. The number of research themes in 1993 was 228 cases. In this book, 243 reports are collected. (J.P.N.)

  20. 46 CFR 391.0 - Statutory provisions; section 607, Merchant Marine Act, 1936, as amended.

    Science.gov (United States)

    2010-10-01

    ... under section 243 of the Internal Revenue Code of 1954, and (D) Interest income exempt from taxation... for research, development, and design expenses incident to new and advanced ship design, machinery and...

  1. Three new, seemingly-cryptic species in the lichen genus Caloplaca (Teloschistaceae) distinguished in two-phase phenotype evaluation

    Czech Academy of Sciences Publication Activity Database

    Frolov, I.; Vondrák, Jan; Fernández-Mendoza, F.; Wilk, K.; Khodosovtsev, A.; Halici, M.G.

    2016-01-01

    Roč. 53, 3-4 (2016), s. 243-262 ISSN 0003-3847 Institutional support: RVO:67985939 Keywords : phylogenetic analyses * partition schemes * forming ascomycota Subject RIV: EF - Botanics Impact factor: 0.600, year: 2016

  2. Cervical cancer in South Africa: An over- view of current status and ...

    African Journals Online (AJOL)

    Current estimates are that 493 243 women are diagnosed with cervical cancer per ... estimated that 78 897 women are diagnosed with cervical cancer annually and 61 671 ..... eye aided by a bright light source. ... References. 1. Ferly Bray F ...

  3. Rozhovor s prof. RNDr. Pavlem Zemánkem, Ph.D., zástupcem ředitelky Ústavu přístrojové techniky Akademie věd ČR v Brně.

    Czech Academy of Sciences Publication Activity Database

    Číp, Ondřej

    2017-01-01

    Roč. 62, č. 10 (2017), s. 243-244 ISSN 0447-6441 Institutional support: RVO:68081731 Keywords : CAS ISI * optics Subject RIV: BH - Optics, Masers, Lasers OBOR OECD: Optics (including laser optics and quantum optics)

  4. Dealing with food allergies in babies and children

    National Research Council Canada - National Science Library

    Joneja, Janice M. Vickerstaff

    2007-01-01

    ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 231 CHAPTER 14 CornAllergy ...243 CHAPTER 15 SeafoodAllergy ...253 CHAPTER 16 The Top Ten Allergens: Avoidance of Milk, Egg, Wheat, Corn, Peanuts, Soy, Tree Nuts...

  5. Improvement of the banana "Musa acuminata" reference sequence using NGS data and semi-automated bioinformatics methods

    Czech Academy of Sciences Publication Activity Database

    Martin, G.; Baurens, F.C.; Droc, G.; Rouard, M.; Cenci, A.; Kilian, A.; Hastie, A.; Doležel, Jaroslav; Aury, J. M.; Alberti, A.; Carreel, F.; D'Hont, A.

    2016-01-01

    Roč. 17, MAR 16 (2016), s. 243 ISSN 1471-2164 Institutional support: RVO:61389030 Keywords : Musa acuminata * Genome assembly * Bioinformatics tool Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 3.729, year: 2016

  6. Mohelno-Plevovce: Lokalita osídlená v průběhu posledního glaciálního maxima a pozdního glaciálu

    Czech Academy of Sciences Publication Activity Database

    Škrdla, Petr; Rychtaříková, Tereza; Eigner, J.; Bartík, J.; Nikolajev, P.; Vokáč, M.; Nývltová Fišáková, Miriam; Čerevková, A.; Knotková, J.

    2014-01-01

    Roč. 66, č. 2 (2014), s. 243-270 ISSN 0323-1267 Institutional support: RVO:68081758 Keywords : Moravia * Mohelno * MIS-2 * LGM * dwelling * pavement * Epigravettian * Epiaurignacian Subject RIV: AC - Archeology, Anthropology, Ethnology

  7. Tagasi Pariisis / Karl Rumor

    Index Scriptorium Estoniae

    Rumor, Karl, pseud., 1886-1971

    2008-01-01

    Prantsusmaa sisepoliitilisest olustikust. Poliitilistest oludest 1937. aasta Euroopas, sõjameeleoludest Vahemerel, Nyloni konverentsist. Varem ilmunud: Uus Eesti 21. juuni 1937, nr. 166; 8., 13. sept. 1937, nr. 243, 248

  8. Arthroscopic subacromial decompression results in normal shoulder function after two years in less than 50% of patients

    DEFF Research Database (Denmark)

    Konradsen, Lars Aage Glud; Jensen, Claus Hjorth

    2015-01-01

    additional resection of the acromioclavicular joint. RESULTS: WORC scores improved significantly from preoperatively (median: 1,392) to three months (median: 204) and two years post-operatively (median: 243) (p

  9. Mineralogy of halloysites and their interaction with porphyrine

    Czech Academy of Sciences Publication Activity Database

    Vašutová, V.; Bezdička, Petr; Lang, Kamil; Hradil, David

    2013-01-01

    Roč. 57, č. 3 (2013), s. 243-250 ISSN 0862-5468 Institutional support: RVO:61388980 Keywords : organoclays * mineralogy * porphyrine * CEC Subject RIV: CA - Inorganic Chemistry Impact factor: 0.434, year: 2013

  10. Optická tloušťka atmosféry jako parametr pro stanovení obyvatelných zón exoplanet

    Czech Academy of Sciences Publication Activity Database

    Pintr, Pavel

    2013-01-01

    Roč. 58, č. 9 (2013), s. 243-246 ISSN 0447-6441 Institutional support: RVO:61389021 Keywords : Habitable zones * exoplanets * stellar spectral classes Subject RIV: JA - Electronics ; Optoelectronics, Electrical Engineering

  11. Database Description - ClEST | LSDB Archive [Life Science Database Archive metadata

    Lifescience Database Archive (English)

    Full Text Available filiation: National Institute of Advanced Industrial Science and Technology Contact address Symbiotic Evolut...2012 Aug; 47(3):233-243. External Links: Original website information Database maintenance site Symbiotic Ev

  12. Potential Navy Force Structure and Shipbuilding Plans: Background and Issues for Congress

    National Research Council Canada - National Science Library

    O'Rourke, Ronald

    2005-01-01

    In February 2005, the Navy testified that the Navy in future years may require a total of 260 to 325 ships, or possibly 243 to 302 ships, depending on how much the Navy uses new technologies and a new...

  13. Ergot alkaloids as chiral selectors in capillary electrophoresis and other electromigration methods

    Czech Academy of Sciences Publication Activity Database

    Sinibaldi, M.; Messina, A.; Stodůlková, Eva; Flieger, Miroslav

    2010-01-01

    Roč. 1, č. 3 (2010), s. 233-243 ISSN 0976-5514 Institutional research plan: CEZ:AV0Z50200510 Keywords : capillary electrophoresis * capillary electrochromatography * chiral analysis Subject RIV: CB - Analytical Chemistry, Separation

  14. A small-molecule inhibitor of the ubiquitin activating enzyme for cancer treatment.

    Science.gov (United States)

    Hyer, Marc L; Milhollen, Michael A; Ciavarri, Jeff; Fleming, Paul; Traore, Tary; Sappal, Darshan; Huck, Jessica; Shi, Judy; Gavin, James; Brownell, Jim; Yang, Yu; Stringer, Bradley; Griffin, Robert; Bruzzese, Frank; Soucy, Teresa; Duffy, Jennifer; Rabino, Claudia; Riceberg, Jessica; Hoar, Kara; Lublinsky, Anya; Menon, Saurabh; Sintchak, Michael; Bump, Nancy; Pulukuri, Sai M; Langston, Steve; Tirrell, Stephen; Kuranda, Mike; Veiby, Petter; Newcomb, John; Li, Ping; Wu, Jing Tao; Powe, Josh; Dick, Lawrence R; Greenspan, Paul; Galvin, Katherine; Manfredi, Mark; Claiborne, Chris; Amidon, Benjamin S; Bence, Neil F

    2018-02-01

    The ubiquitin-proteasome system (UPS) comprises a network of enzymes that is responsible for maintaining cellular protein homeostasis. The therapeutic potential of this pathway has been validated by the clinical successes of a number of UPS modulators, including proteasome inhibitors and immunomodulatory imide drugs (IMiDs). Here we identified TAK-243 (formerly known as MLN7243) as a potent, mechanism-based small-molecule inhibitor of the ubiquitin activating enzyme (UAE), the primary mammalian E1 enzyme that regulates the ubiquitin conjugation cascade. TAK-243 treatment caused depletion of cellular ubiquitin conjugates, resulting in disruption of signaling events, induction of proteotoxic stress, and impairment of cell cycle progression and DNA damage repair pathways. TAK-243 treatment caused death of cancer cells and, in primary human xenograft studies, demonstrated antitumor activity at tolerated doses. Due to its specificity and potency, TAK-243 allows for interrogation of ubiquitin biology and for assessment of UAE inhibition as a new approach for cancer treatment.

  15. The Leucocytozoidae of South African birds. The Coliiformes and ...

    African Journals Online (AJOL)

    1991-12-03

    Dec 3, 1991 ... light staining parasite nucleus, typical of the apicomplexan parasites. In the ..... descriptions of blood parasites made by de Mello and others,. Bhatia took de Mello .... Newfoundland Occasional Papers in Biology No.5. 243 pp.

  16. Carbohydrate-modified magnetic nanoparticles for radical scavenging

    Czech Academy of Sciences Publication Activity Database

    Moskvin, Maksym; Horák, Daniel

    2016-01-01

    Roč. 65, Suppl. 2 (2016), S243-S251 ISSN 0862-8408 R&D Projects: GA MŠk(CZ) LQ1604 Institutional support: RVO:61389013 Keywords : magnetic nanoparticles * silica * glucose Subject RIV: EB - Genetics ; Molecular Biology Impact factor: 1.461, year: 2016 http://www.biomed.cas.cz/physiolres/pdf/65%20Suppl%202/65_S243.pdf

  17. Case report of newborn with de novo partial trisomy 2q31.2–37.3 ...

    Indian Academy of Sciences (India)

    Case report of newborn with de novo partial trisomy 2q31.2–37.3 and monosomy 9p24.3 ... This is the first report of molecular cytogenetic characterization of a partial trisomy 2q31.2–37.3 with monosomy 9p24.3. ... Manuscript received: 10 November 2016; Manuscript revised: 13 March 2017; Accepted: 21 March 2017 ...

  18. Obesity/Overweight in Persons With Early and Chronic SCI: A Randomized, Multicenter, Controlled Lifestyle Intervention

    Science.gov (United States)

    2014-10-01

    decrease in insulin resistance ( HOMA - IR ) (Table 3, Figure 3; appendix). The 2 tetraplegic participants have completed 6-month clinical...ISI   HOMA -­‐ IR   Page 1 of 2 Ph.: 305-243-3195 Fax: 305-243-3328 www.hsro.miami.edu University of Miami Human Subjects Research Office (M8089) P.O...training (CRT) on fasting and postprandial (PP) blood glucose (BG) and insulin, the homeostasis model assessment ( HOMA ) for insulin resistance ( IR

  19. Radionuclide interactions with marine sediments

    International Nuclear Information System (INIS)

    Higgo, J.J.W.

    1987-09-01

    A critical review of the literature on the subject of the interactions of radionuclides with marine sediments has been carried out. On the basis of the information available, an attempt has been made to give ranges and 'best estimates' for the distribution ratios between seawater and sediments. These estimates have been based on an understanding of the sediment seawater system and the porewater chemistry and mineralogy. Field measurements, laboratory measurements and estimates based on stable-element geochemical data are all taken into account. Laboratory measurements include distribution-ratio and diffusion-coefficient determinations. The elements reviewed are carbon, chlorine, calcium, nickel, selenium, strontium, zirconium, niobium, technetium, tin, iodine, caesium, lead, radium, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium and curium. (author)

  20. Effects of deposited nuclear and electronic energy on the hardness of R7T7-type containment glass

    Energy Technology Data Exchange (ETDEWEB)

    Peuget, S. [Commissariat a l' Energie Atomique, CEA Marcoule, DEN/DTCD/SECM/LMPA, Batiment 166, BP 17171, F-30207 Bagnols-sur-Ceze Cedex (France)]. E-mail: sylvain.peuget@cea.fr; Noel, P.-Y. [Commissariat a l' Energie Atomique, CEA Marcoule, DEN/DTCD/SECM/LMPA, Batiment 166, BP 17171, F-30207 Bagnols-sur-Ceze Cedex (France); Loubet, J.-L. [Laboratoire de Tribologie et Dynamique des Systemes, UMR CNRS 5513, Ecole Centrale de Lyon 36, avenue Guy de Collongue, 69134 Ecully Cedex (France); Pavan, S. [Laboratoire de Tribologie et Dynamique des Systemes, UMR CNRS 5513, Ecole Centrale de Lyon 36, avenue Guy de Collongue, 69134 Ecully Cedex (France); Nivet, P. [Commissariat a l' Energie Atomique, CEA Marcoule, DEN/DTCD/SECM/LMPA, Batiment 166, BP 17171, F-30207 Bagnols-sur-Ceze Cedex (France); Chenet, A. [Commissariat a l' Energie Atomique, CEA Marcoule, DEN/DTCD/SECM/LMPA, Batiment 166, BP 17171, F-30207 Bagnols-sur-Ceze Cedex (France)

    2006-05-15

    The effects of elastic and inelastic interactions induced by cumulative alpha decay on the hardness of R7T7-type nuclear containment glass were investigated on actinide-doped glass specimens and by external irradiation of inactive glass by light and heavy ions. Vickers microindentation and nanoindentation hardness measurements showed that in the deposited energy range investigated (below 3 x 10{sup 22} keV/cm{sup 3}) inelastic effects have no influence on the plastic response of the glass. Conversely, identical hardness variations versus the nuclear energy deposited in the material were observed on curium-doped glass and on glass irradiated by ion bombardment. The observed hardness variation stabilized after the deposited energy reached about 3 x 10{sup 2} keV{sub nucl}/cm{sup 3}. These findings indicate that the change in the plastic response of the glass is a consequence of ballistic effects.

  1. Comments on chelation therapy

    International Nuclear Information System (INIS)

    Wrenn, M.E.

    1981-01-01

    The primary purpose of actinide chelation is to decrease the risk from radiation-induced cancer. While occupational exposures in the past have mainly involved low specific activity 239 Pu, future exposures will increasingly involve high specific activity plutonium, americium, and curium - all of which clear more rapidly from the lung. This will tend to shift the cancer risk from lung to bone and liver. Although therapy with Ca- or Zn-DTPA rapidly removes 241 Am from the canine, the sub-human primate, and the human liver, improved methods for removal from bone and lung are needed. DTPA can remove 241 Am more easily from the growing skeleton of a child than from the mature skeleton of an adult. Investigators at Karlsruhe are developing chelation agents for oral administration and are investigating the reduction in local dose to bone resulting from chelation therapy

  2. A neutron source of variable fluence

    International Nuclear Information System (INIS)

    Brachet, Guy; Demichel, Pascal; Prigent, Yvon; Riche, J.C.

    1975-01-01

    The invention concerns a variable fluence neutron source, like those that use in the known way a reaction between a radioactive emitter and a target, particularly of type (α,n). The emitter being in powder form lies in a carrier fluid forming the target, inside a closed containment. Facilities are provided to cause the fluidisation of the emitter by the carrier fluid in the containment. The fluidisation of the emitting powder is carried out by a booster with blades, actuated from outside by a magnetic coupling. The powder emitter is a α emitter selected in the group of curium, plutonium, thorium, actinium and americium oxides and the target fluid is formed of compounds of light elements selected from the group of beryllium, boron, fluorine and oxygen 18. The target fluid is a gas used under pressure or H 2 O water highly enriched in oxygen 18 [fr

  3. Analysis of the Neutron Generator and Target for the LSDTS System

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang Je; Lee, Yong Deok; Song, Jae Hoon; Song, Kee Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-11-15

    A preliminary analysis was performed based on the literatures and the patents for the neutron generators and targets for the lead slowing down time spectrometer (LSDTS) system. It was found that local neutron generator did not exhibit enough neutron intensity such as 1E+12 n/s, which is a minimum requirement for the LSDTS system to overcome curium backgrounds. However, a neutron generator implemented with an electron accelerator may provide a higher intensity around 1E+13 n/s and it is required to investigate further including a detail analysis. In addition to the neutron generator, a study on target was performed with the Monte Carlo simulation. In the study, an optimal design of target was suggested to provide a high neutron yield and a better thermal resistance. The suggested target consists several cylindrical plates with a certain cooling gap, which have increasing thickness and increasing radius.

  4. Systematic thermodynamic properties of actinide metal-oxygen systems at high temperatures: Emphasis on lower valence states

    International Nuclear Information System (INIS)

    Ackermann, R.J.; Chandrasekharaiah, M.S.

    1975-01-01

    The thermodynamic data for the actinide metals and oxides (thorium to curium ) have been assessed, examined for consistency, and compared with the lanthanides. Correlations relating the enthalpies of formation of the solid oxides with the corresponding aquo ions make possible the estimation of the thermodynamic properties of AmO 2 (s) and Am 2 O 3 (s) which are in accordance with vaporization data. The known thermodynamic properties of the substoichiometric dioxides MOsub(2-x)(s) at high temperatures demonstrate the relative stabilities of valence states less than 4+ and lead to the examination of stability requirements for the sesquioxides M 2 O 3 (s) and the monoxides MO(s). Sequential trends in the gaseous metals, monoxides and dioxides are examined, compared, and contrasted with the lanthanides. (author)

  5. Incineration by accelerator

    International Nuclear Information System (INIS)

    Cribier, M.; FIoni, G.; Legrain, R.; Lelievre, F.; Leray, S.; Pluquet, A.; Safa, H.; Spiro, M.; Terrien, Y.; Veyssiere, Ch.

    1997-01-01

    The use MOX fuel allows to hope a stabilization of plutonium production around 500 tons for the French park. In return, the flow of minor actinides is increased to several tons. INCA (INCineration by Accelerator), dedicated instrument, would allow to transmute several tons of americium, curium and neptunium. It could be able to reduce nuclear waste in the case of stopping nuclear energy use. This project needs: a protons accelerator of 1 GeV at high intensity ( 50 m A), a window separating the accelerator vacuum from the reactor, a spallation target able to produce 30 neutrons by incident proton, an incineration volume where a part of fast neutrons around the target are recovered, and a thermal part in periphery with flows at 2.10 15 n/cm 2 .s; a chemical separation of elements burning in thermal (americium) from the elements needing a flow of fast neutrons. (N.C.)

  6. Environmental, safety, and health plan for the remedial investigation of Waste Area Grouping 10, Operable Unit 3, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1993-10-01

    This document outlines the environmental, safety, and health (ES ampersand H) approach to be followed for the remedial investigation of Waste Area Grouping (WAG) 10 at Oak at Ridge National Laboratory. This ES ampersand H Plan addresses hazards associated with upcoming Operable Unit 3 field work activities and provides the program elements required to maintain minimal personnel exposures and to reduce the potential for environmental impacts during field operations. The hazards evaluation for WAG 10 is presented in Sect. 3. This section includes the potential radiological, chemical, and physical hazards that may be encountered. Previous sampling results suggest that the primary contaminants of concern will be radiological (cobalt-60, europium-154, americium-241, strontium-90, plutonium-238, plutonium-239, cesium-134, cesium-137, and curium-244). External and internal exposures to radioactive materials will be minimized through engineering controls (e.g., ventilation, containment, isolation) and administrative controls (e.g., procedures, training, postings, protective clothing)

  7. Partitioning of minor actinides: research at Juelich and Karlsruhe Research Centres

    International Nuclear Information System (INIS)

    Geist, A.; Weigl, M.; Gompper, K.; Modolo, G.

    2007-01-01

    Full text of publication follows. The work on minor actinide (MA) partitioning carried out at Karlsruhe and Juelich is integrated in the EC FP6 programme, EUROPART. Studies include the DIAMEX process (co-extraction of MA and lanthanides from PUREX raffinate) and the SANEX process (separation of MA from lanthanides). Aspects ranging from developing and improving highly selective and efficient extraction reagents, to fundamental structural studies, to process development and testing are covered. SANEX is a challenge in separation chemistry because of the chemical similarity of trivalent actinides and lanthanides. The extracting agents 2,6-di(5,6-di-propyl-1,2,4-triazine-3-yl)pyridine (n-Pr-BTP), developed at Karlsruhe, and the synergetic mixture of di(chloro-phenyl)di-thio-phosphinic acid (R2PSSH) with tri-n-octyl-phosphine oxide (TOPO), developed at Juelich, are considered a breakthrough because of their high separation efficiency in acidic systems. Separation factors for americium over lanthanides of more than 30 (R2PSSH+TOPO) and 130 (n-Pr-BTP) are achieved. To gain understanding of these selectivities, comparative investigations on the structures of curium and europium complexed with these SANEX ligands were performed at Karlsruhe. Extended X-ray absorption fine structure (EXAFS) analysis revealed distinct structural differences between curium and europium complexed with R2PSSH + TOPO, though no such differences were found for n-Pr-BTP. These investigations were therefore complemented by time-resolved laser fluorescence spectroscopic investigations (TRLFS), showing complex stabilities and speciation to differ between n-Pr-BTP complexes of curium and europium. Kinetics of mass transfer was studied for both R2PSSH+TOPO and n-Pr-BTP systems. For the R2PSSH + TOPO system, diffusion was identified to control extraction rates. For the n-Pr-BTP system, a slow chemical reaction was identified as the rate-controlling process. These results were implemented into computer

  8. Measurement of leached hulls

    International Nuclear Information System (INIS)

    Reilly, T.D.

    1979-07-01

    Leached hulls are the short lengths of fuel rod cladding and fuel element hardware which constitute a major waste product of a reprocessing plant employing a chop-and-leach head-end process. The small, undissolved fuel residue (0.1 to 1.0% of original fuel content) which is discarded with this waste must be measured for safeguards, material accountability, and process control reasons. This report gives a critical analysis of hull measurement techniques involving the analysis of fission product gamma rays, spontaneous fission neutrons from curium, and delayed neutron activation. Major emphasis is given to the measurement of 2186-keV gamma rays from 144 Ce-- 144 Pr. A detailed description of typical leached hull characteristics is presented at the beginning of the report. An extensive review of experience gained from existing hull measurement systems in the United Kingdom, France, Japan, Germany, Italy, and the United States is presented

  9. Separation of 248Cm (III) from 252Cf (III) and its use in time resolved fluorescence spectroscopic (TRFS) studies

    International Nuclear Information System (INIS)

    Murali, M.S.; Nair, A.G.C.; Gujar, R.B.; Jain, A.; Tomar, B.S.; Godbole, S.V.; Reddy, A.V.R.; Manchanda, V.K.

    2008-07-01

    The present report gives a description of the methodology for the separation of 248 Cm(III) from decayed 252 Cf (III) waste solution. The waste solution was first assayed for 252 Cf content by neutron counting using a neutron well coincidence counter. The sample was subjected to the chemical separation of 248 Cm (III) from 252 Cf (III) following anion and cation exchange chromatography. The alpha spectrum of the separated curium fraction showed peaks due to 246 Cm and 248 Cm while the corresponding alpha spectrum of californium fraction showed 249,250,251,252 Cf. The gamma ray abundances of 249 Cf were determined with respect to its gamma rays of 387 keV and the data agreed well with that in literature. Separated Cm(III) was further characterized by recording its time resolved fluorescence spectrum (TRFS) in aqueous medium. (author)

  10. Actinide elements in aquatic and terrestrial environments

    International Nuclear Information System (INIS)

    Bondietti, E.A.

    1978-01-01

    Progress is reported in terrestrial ecology studies with regard to plutonium in biota from the White Oak Creek forest; comparative distribution of plutonium in two forest ecosystems; an ecosystem model of plutonium dynamics; actinide element metabolism in cotton rats; and crayfish studies. Progress is reported in aquatic studies with regard to transuranics in surface waters, frogs, benthic algae, and invertebrates from pond 3513; and radioecology of transuranic elements in cotton rats bordering waste pond 3513. Progress is also reported in stability of trivalent plutonium in White Oak Lake water; chemistry of plutonium, americium, curium, and uranium in pond water; uranium, thorium, and plutonium in small mammals; and effect of soil pretreatment on the distribution of plutonium

  11. Performance of the multiple target He/PbI sub 2 aerosol jet system for mass separation of neutron-deficient actinide isotopes

    CERN Document Server

    Ichikawa, S; Asai, M; Haba, H; Sakama, M; Kojima, Y; Shibata, M; Nagame, Y; Oura, Y; Kawade, K

    2002-01-01

    A multiple target He/PbI sub 2 aerosol jet system coupled with a thermal ion source was installed in the isotope separator on line (JAERI-ISOL) at the JAERI tandem accelerator facility. The neutron-deficient americium and curium isotopes produced in the sup 2 sup 3 sup 3 sup , sup 2 sup 3 sup 5 U( sup 6 Li, xn) and sup 2 sup 3 sup 7 Np( sup 6 Li, xn) reactions were successfully mass-separated and the overall efficiency including the ionization of Am atoms was evaluated to be 0.3-0.4%. The identification of a new isotope sup 2 sup 3 sup 7 Cm with the present system is reported.

  12. Trivalent lanthanide/actinide separation in the spent nuclear fuel wastes' reprocessing

    International Nuclear Information System (INIS)

    Narbutt, J.; Krejzler, J.

    2006-01-01

    Separation of trivalent actinides, in particular americium and curium, from lanthanides is an important step in an advanced partitioning process for future reprocessing of spent nuclear fuels. Since the trivalent actinides and lanthanides have similar chemistries, it is rather difficult to separate them from each other. The aim of presented work was to study solvent extraction of Am(III) and Eu(III) in a system containing diethylhemi-BTP (6-(5,6-diethyl-1,2,4-triazin-3-yl)-2,2'-bipyridine) and COSAN (protonated bis(chlorodicarbollido)cobalt(III)). The system was chosen by several groups working in the integrated EC research Project EUROPART. Several physicochemical properties of the extraction system were analyzed and discussed

  13. Engineering product storage under the advanced fuel cycle initiative. Part I: An iterative thermal transport modeling scheme for high-heat-generating radioactive storage forms

    International Nuclear Information System (INIS)

    Kaminski, Michael D.

    2005-01-01

    The US Department of Energy is developing an integrated nuclear fuel cycle technology under its Advanced Fuel Cycle Initiative (AFCI). Under the AFCI, waste minimization is stressed. Engineered product storage materials will be required to store concentrated radioactive cesium, strontium, americium, and curium for periods of tens to hundreds of years. The fabrication of such engineered products has some precedence but the concept is largely novel. We thus present a theoretical model used to calculate the maximum radial dimensions of right cylinder storage forms under several scenarios. Maximum dimensions are small, comparable to nuclear fuel pins in some cases, to avoid centerline melting temperatures; this highlights the need for a careful strategy for engineered product storage fabrication and storage

  14. Transuranic biokinetic parameters for marine invertebrates--a review.

    Science.gov (United States)

    Ryan, T P

    2002-04-01

    A catalogue of biokinetic parameters for the transuranic elements plutonium, americium, curium, neptunium, and californium in marine invertebrates is presented. The parameters considered are: the seawater-animal concentration factor (CF); the sediment-animal concentration ratio (CR); transuranic assimilation efficiency; transuranic tissue distribution and transuranic elimination rates. With respect to the seawater-animal CF, authors differ considerably on how they define this parameter and a seven-point reporting system is suggested. Transuranic uptake from sediment by animals is characterised by low CRs. The assimilation efficiencies of transuranic elements in marine invertebrates are high compared to vertebrates and mammals in general and the distribution of transuranics within the body tissue of an animal is dependent on the uptake path. The elimination of transuranics from most species examined conformed to a standard biphasic exponential model though some examples with three elimination phases were identified.

  15. Historical review of transuranic analytical methodology

    International Nuclear Information System (INIS)

    Wessman, R.A.; Leventhal, L.

    1977-01-01

    The methods used for the analysis of the transuranic elements neptunium, plutonium, americium, and curium are reviewed. Particular attention is given to those procedures suitable for low-level environmental and biological assessment. The preparation of such samples, derived from a variety of sources and incorporated in different masses and volumes of soils, water, vegetation, and biological matrices, is described. A comprehensive discussion of matrix dissolution and equilibration techniques indicates that complete dissolution employing tracer techniques is to be preferred. Leaching of large soil samples is satisfactory for worldwide fallout. Individual and sequential separation and purification procedures, including precipitation, extraction, and ion exchange methods, are described. Sample preparation techniques for radiometric assay, such as stippling, evaporation, and plating, are reviewed. For both tracer and nuclide assay, electroplating provides the thin samples suitable for alpha pulse height analysis. Past and current counting methods for the transuranic alpha, beta, and gamma emitters are reviewed

  16. Influence of FIMA burnup on actinides concentrations in PWR reactors

    Directory of Open Access Journals (Sweden)

    Oettingen Mikołaj

    2016-01-01

    Full Text Available In the paper we present the study on the dependence of actinides concentrations in the spent nuclear fuel on FIMA burnup. The concentrations of uranium, plutonium, americium and curium isotopes obtained in numerical simulation are compared with the result of the post irradiation assay of two spent fuel samples. The samples were cut from the fuel rod irradiated during two reactor cycles in the Japanese Ohi-2 Pressurized Water Reactor. The performed comparative analysis assesses the reliability of the developed numerical set-up, especially in terms of the system normalization to the measured FIMA burnup. The numerical simulations were preformed using the burnup and radiation transport mode of the Monte Carlo Continuous Energy Burnup Code – MCB, developed at the Department of Nuclear Energy, Faculty of Energy and Fuels of AGH University of Science and Technology.

  17. The design of the DUPIC spent fuel bundle counter

    International Nuclear Information System (INIS)

    Menlove, H.O.; Rinard, P.M.; Kroncke, K.E.; Lee, Y.G.

    1997-05-01

    A neutron coincidence detector had been designed to measure the amount of curium in the fuel bundles and associated process samples used in the direct use of plutonium in Canadian deuterium-uranium (CANDU) fuel cycle. All of the sample categories are highly radioactive from the fission products contained in the pressurized water reactor (PWR) spent fuel feed stock. Substantial shielding is required to protect the He-3 detectors from the intense gamma rays. The Monte Carlo neutron and photon calculational code has been used to design the counter with a uniform response profile along the length of the CANDU-type fuel bundle. Other samples, including cut PWR rods, process powder, waste, and finished rods, can be measured in the system. This report describes the performance characteristics of the counter and support electronics. 3 refs., 23 figs., 6 tabs

  18. Pyro-electrochemical reprocessing of irradiated MOX fast reactor fuel, testing of the reprocessing process with direct MOX fuel production

    Energy Technology Data Exchange (ETDEWEB)

    Kormilitzyn, M.V.; Vavilov, S.K.; Bychkov, A.V.; Skiba, O.V.; Chistyakov, V.M.; Tselichshev, I.V

    2000-07-01

    One of the advanced technologies for fast reactor fuel recycle is pyro-electrochemical molten salt technology. In 1998 we began to study the next phase of the irradiated oxide fuel reprocessing new process MOX {yields} MOX. This process involves the following steps: - Dissolution of irradiated fuel in molten alkaline metal chlorides, - Purification of melt from fission products that are co-deposited with uranium and plutonium oxides, - Electrochemical co-deposition of uranium and plutonium oxides under the controlled cathode potential, - Production of granulated MOX (crushing,salt separation and sizing), and - Purification of melt from fission products by phosphate precipitation. In 1998 a series of experiments were prepared and carried out in order to validate this process. It was shown that the proposed reprocessing flowsheet of irradiated MOX fuel verified the feasibility of its decontamination from most of its fission products (rare earths, cesium) and minor-actinides (americium, curium)

  19. Measurements of the neutron capture cross sections and incineration potentials of minor-actinides in high thermal neutron fluxes: Impact on the transmutation of nuclear wastes; Mesures des sections efficaces de capture et potentiels d'incineration des actinides mineurs dans les hauts flux de neutrons: Impact sur la transmutation des dechets

    Energy Technology Data Exchange (ETDEWEB)

    Bringer, O

    2007-10-15

    This thesis comes within the framework of minor-actinide nuclear transmutation studies. First of all, we have evaluated the impact of minor actinide nuclear data uncertainties within the cases of {sup 241}Am and {sup 237}Np incineration in three different reactor spectra: EFR (fast), GT-MHR (epithermal) and HI-HWR (thermal). The nuclear parameters which give the highest uncertainties were thus highlighted. As a result of fact, we have tried to reduce data uncertainties, in the thermal energy region, for one part of them through experimental campaigns in the moderated high intensity neutron fluxes of ILL reactor (Grenoble). These measurements were focused onto the incineration and transmutation of the americium-241, the curium-244 and the californium-249 isotopes. Finally, the values of 12 different cross sections and the {sup 241}Am isomeric branching ratio were precisely measured at thermal energy point. (author)

  20. Radionuclide toxicity

    International Nuclear Information System (INIS)

    Galle, P.

    1982-01-01

    The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

  1. New strategies in actinide separation - water-soluble complexing agents for the innovative SANEX process

    International Nuclear Information System (INIS)

    Ruff, Christian M.; Muelllich, Udo; Geist, Andreas; Panak, Petra J.

    2012-01-01

    Reduction of the radiotoxicity and thermal output of radioactive wastes prior to their permanent disposal is a topic of extreme interest for the issue of final nuclear waste disposal. One possibility to this end is a process referred to as actinide separation. This process can be optimised by means of a newly developed water-soluble molecule, as has been shown in studies on the molecule's complex chemistry using ultra-modern laser-based spectroscopy methods under process-relevant reaction conditions. Through the use of curium (III) and europium (III), which as members of the trivalent actinides and lanthanides family have excellent spectroscopic properties, it has been possible to generate spectroscopic and thermodynamic data which will facilitate our understanding of the complex chemistry and extraction chemistry of this molecule family.

  2. Pyro-electrochemical reprocessing of irradiated MOX fast reactor fuel, testing of the reprocessing process with direct MOX fuel production

    International Nuclear Information System (INIS)

    Kormilitzyn, M.V.; Vavilov, S.K.; Bychkov, A.V.; Skiba, O.V.; Chistyakov, V.M.; Tselichshev, I.V.

    2000-01-01

    One of the advanced technologies for fast reactor fuel recycle is pyro-electrochemical molten salt technology. In 1998 we began to study the next phase of the irradiated oxide fuel reprocessing new process MOX → MOX. This process involves the following steps: - Dissolution of irradiated fuel in molten alkaline metal chlorides, - Purification of melt from fission products that are co-deposited with uranium and plutonium oxides, - Electrochemical co-deposition of uranium and plutonium oxides under the controlled cathode potential, - Production of granulated MOX (crushing,salt separation and sizing), and - Purification of melt from fission products by phosphate precipitation. In 1998 a series of experiments were prepared and carried out in order to validate this process. It was shown that the proposed reprocessing flowsheet of irradiated MOX fuel verified the feasibility of its decontamination from most of its fission products (rare earths, cesium) and minor-actinides (americium, curium)

  3. Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets

    International Nuclear Information System (INIS)

    Grouiller, J.P.; Pillon, S.; Saint Jean, C. de; Varaine, F.; Leyval, L.; Vambenepe, G.; Carlier, B.

    2003-01-01

    Using current technologies, we have demonstrated in this study that it is theoretically possible to obtain different minor actinide transmutation scenarios with a significant gain on the waste radiotoxicity inventory. The handling of objects with Am+Cm entails the significant increase of penetrating radiation sources (neutron and γ) whatever mixed scenario is envisioned; the PWR and FR scenario involving the recycling of Am + Cm in the form of targets results in the lowest flow. In the light of these outcomes, the detailed studies has allowed to design a target sub assembly with a high fission rate (90%) and define a drawing up of reprocessing diagram with the plant head, the minor actinide separation processes (PUREX, DIAMEX and SANEX). Some technological difficulties appear in manipulating curium, principally in manufacturing where the wet process ('sol-gel') is not acquired for (Am+Cm). (author)

  4. Review of Integral Experiments for Minor Actinide Management

    International Nuclear Information System (INIS)

    Gil, C.S.; Glinatsis, G.; Hesketh, K.; Iwamoto, O.; Okajima, S.; Tsujimoto, K.; Jacqmin, R.; Khomyakov, Y.; Kochetkov, A.; Kormilitsyn, M.; Palmiotti, G.; Salvatores, M.; Perret, G.; Rineiski, A.; Romanello, V.; Sweet, D.

    2015-01-01

    Spent nuclear fuel contains minor actinides (MAs) such as neptunium, americium and curium, which require careful management. This becomes even more important when mixed oxide (MOX) fuel is being used on a large scale since more MAs will accumulate in the spent fuel. One way to manage these MAs is to transmute them in nuclear reactors, including in light water reactors, fast reactors or accelerator-driven subcritical systems. The transmutation of MAs, however, is not straightforward, as the loading of MAs generally affects physics parameters, such as coolant void, Doppler and burn-up reactivity. This report focuses on nuclear data requirements for minor actinide management, the review of existing integral data and the determination of required experimental work, the identification of bottlenecks and possible solutions, and the recommendation of an action programme for international co-operation. (authors)

  5. Radionuclides retention: from macroscopic to microscopic

    International Nuclear Information System (INIS)

    Simoni, E.

    2002-01-01

    In order to determine the radionuclides' sorption constants on solid natural minerals, both thermodynamic and structural investigations, using spectroscopic techniques, are presented. The natural clays, that could be used as engineering barriers in the nuclear waste geological repository, are rather complex minerals. Therefore, in order to understand how these natural materials retain the radionuclides, it is necessary first to perform these studies on simple substrates such as single crystal, oxides and silicates, and then extrapolate the obtained results on the natural minerals. We examine in this paper the sorption processes of the hexavalent uranium on zircon (ZrSiO 4 ) and the trivalent curium on a natural clay (bentonite). The corresponding sorption curves are simulated using the results obtained with the following spectroscopic techniques: laser induced spectro-fluorimetry, X-ray photoelectron spectroscopy (XPS), X-ray absorption spectroscopy (EXAFS), diffuse reflectance infrared Fourier transform (DRIFT). (authors)

  6. The analysis and handling concept of minor actinides of NPP’s waste by using Ads technology

    International Nuclear Information System (INIS)

    Silakhuddin

    2008-01-01

    The contents of minor actinide elements (americium, neptunium and curium) on the spent fuel inventory from PWR operation of NPP have been calculated using Vista program. The calculation used parameters: enrichment 3.968%, power 1000 M We and burn-up is 60 M Wd/kg. The result of calculation showed that the arising of minor actinide elements on the spent fuel is 16.205 kg/year and 43.471 kg/year for PWR-UOX and PWR-MOX respectively. It is also discussed a concept of the use of ADS technology for transmuting the minor actinide elements contained in spent fuels. The result of the discussion showed that an ADS of 400 M Wth will serve 7 PWRs-UOX, and on the PWR system using UOX and MOX fuels an ADS will serve 3 PWRs. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2006-04-15

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

  8. Studies of high-level radioactive waste form performance at Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Banba, Tsunetaka; Kamizono, Hiroshi; Mitamura, Hisayoshi

    1992-02-01

    The recent studies of high-level radioactive waste form at Japan Atomic Energy Research Institute can be classified into the following three categories; (1) Study on the leaching behavior of the nuclear waste glass placing the focus on the alteration layer and the chemical composition of leachant for the prediction of the long-term corrosion of the waste glass. (2) Study on the radiation (alpha-radiation) effects which have relation to the long-term stability of the nuclear waste glass. (3) Study on the long-term self-irradiation damage of a SYNROC waste form using a curium-doped sample. In the present report, the recent results corresponding to the above categories are described. (author)

  9. Final report on fabrication and study of SYNROC containing radioactive waste elements

    International Nuclear Information System (INIS)

    Reeve, K.D.; Levins, D.M.; Seatonberry, B.W.; Ryan, R.K.; Hart, K.P.; Stevens, G.T.

    1987-01-01

    Two facilities for the fabrication and testing of Synroc samples containing separate additions of the transuranic actinides americium, plutonium, curium and neptunium, a fission product solution, and two radioisotopes of caesium and strontium were designed, built and operated by the AAEC at the Lucas Heights Research Laboratories. Twenty-one 75 g batches of radioactive Synroc were made and representative samples were characterised by alpha track etching, scanning electron microscopy and aqueous leach testing, mostly at 70 deg C. Where comparisons were possible, radioactive fission products behaved as expected from non-radioactive tests. The leaching behaviour of the actinides was complex but as a group they were the least leachable of all the elements studied

  10. Chelation and stabilization of berkelium in oxidation state +IV

    Science.gov (United States)

    Deblonde, Gauthier J.-P.; Sturzbecher-Hoehne, Manuel; Rupert, Peter B.; An, Dahlia D.; Illy, Marie-Claire; Ralston, Corie Y.; Brabec, Jiri; de Jong, Wibe A.; Strong, Roland K.; Abergel, Rebecca J.

    2017-09-01

    Berkelium (Bk) has been predicted to be the only transplutonium element able to exhibit both +III and +IV oxidation states in solution, but evidence of a stable oxidized Bk chelate has so far remained elusive. Here we describe the stabilization of the heaviest 4+ ion of the periodic table, under mild aqueous conditions, using a siderophore derivative. The resulting Bk(IV) complex exhibits luminescence via sensitization through an intramolecular antenna effect. This neutral Bk(IV) coordination compound is not sequestered by the protein siderocalin—a mammalian metal transporter—in contrast to the negatively charged species obtained with neighbouring trivalent actinides americium, curium and californium (Cf). The corresponding Cf(III)-ligand-protein ternary adduct was characterized by X-ray diffraction analysis. Combined with theoretical predictions, these data add significant insight to the field of transplutonium chemistry, and may lead to innovative Bk separation and purification processes.

  11. JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes. Refinement of thermodynamic data for trivalent actinoids and samarium

    International Nuclear Information System (INIS)

    Kitamura, Akira; Fujiwara, Kenso; Yui, Mikazu

    2010-01-01

    Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the refinement of the thermodynamic data for the inorganic compounds and complexes of trivalent actinoids (actinium(III), plutonium(III), americium(III) and curium(III)) and samarium(III) was carried out. Refinement of thermodynamic data for these elements was based on the thermodynamic database for americium published by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Based on the similarity of chemical properties among trivalent actinoids and samarium, complementary thermodynamic data for their species expected under the geological disposal conditions were selected to complete the thermodynamic data set for the performance assessment of geological disposal of radioactive wastes. (author)

  12. Results from ISTC frame work

    Energy Technology Data Exchange (ETDEWEB)

    Fukahori, Tokio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Under International Science Research Center (ISTC) projects, JAERI Nuclear Data Center has been taking a role of collaborator and monitor for following items; (1) Measurement of the Fission Neutron Spectra of the Minor Actinides and Spontaneous Fission of Curium Isotopes (ISTC no. 183: V.I. Khlopin Radium Institute, KRI, St. Petersburg, Russia), (2) Measurement and Analysis of the Basic Nuclear Data for Minor Actinides (ISTC no. 304: Institute of Physics and Power Engineering, IPPE, Obninsk, Russia), and Evaluation of Actinide Nuclear Data (ISTC no. CIS-3: Radiation Physics and Chemistry Problems Institute, RPCPI, Minsk, Belarus). These are related to the Japanese OMEGA Project and expected to supply minor actinide (MA) nuclear data, since Russia has good quality MA samples, experimental technique and nuclear data evaluation experiences. In this report, out-line and some results of above three projects are reviewed. (author)

  13. Extraction of Trivalent Actinides and Lanthanides from Californium Campaign Rework Solution Using TODGA-based Solvent Extraction System

    Energy Technology Data Exchange (ETDEWEB)

    Benker, Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Delmau, Laetitia Helene [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dryman, Joshua Cory [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-07-01

    This report presents the studies carried out to demonstrate the possibility of quantitatively extracting trivalent actinides and lanthanides from highly acidic solutions using a neutral ligand-based solvent extraction system. These studies stemmed from the perceived advantage of such systems over cationexchange- based solvent extraction systems that require an extensive feed adjustment to make a low-acid feed. The targeted feed solutions are highly acidic aqueous phases obtained after the dissolution of curium targets during a californium (Cf) campaign. Results obtained with actual Cf campaign solutions, but highly diluted to be manageable in a glove box, are presented, followed by results of tests run in the hot cells with Cf campaign rework solutions. It was demonstrated that a solvent extraction system based on the tetraoctyl diglycolamide molecule is capable of quantitatively extracting trivalent actinides from highly acidic solutions. This system was validated using actual feeds from a Cf campaign.

  14. Mobility of U, Np, Pu, Am and Cm from spent nuclear fuel into bentonite clay

    International Nuclear Information System (INIS)

    Ramebaeck, H.; Skaalberg, M.; Eklund, U.B.; Kjellberg, L.; Werme, L.

    1998-01-01

    The mobility of uranium, neptunium, plutonium, americium and curium from spent nuclear fuel (UO 2 ) into compacted bentonite was studied. Pieces of spent BWR UO 2 fuel was embedded in a compacted bentonite clay/low saline synthetic groundwater system. After a contact time of six years the bentonite was sliced into 0.1 mm thick slices and analysed for its content of actinides. Radiometric as well as inductively coupled plasma mass spectrometry (ICP-MS) were used for the analysis. The influence on the mobility by the addition of metallic iron, metallic copper and vivianite (Fe(II)-mineral) to the bentonite clay was investigated. The results show a low mobility of actinides in bentonite clay. Except for uranium the mobility of the other actinides could, after six years of diffusion time, only be detected less than 1 mm from the spent fuel. (orig.)

  15. Summary of ALSEP Test Loop Solvent Irradiation Testing

    Energy Technology Data Exchange (ETDEWEB)

    Peterman, Dean Richard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Olson, Lonnie Gene [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-01

    Separating the minor actinide elements (americium and curium) from the fission product lanthanides is an important step in closing the nuclear fuel cycle. Isolating the minor actinides will allow transmuting them to short lived or stable isotopes in fast reactors, thereby reducing the long-term hazard associated with these elements. The Actinide Lanthanide Separation Process (ALSEP) is being developed by the DOE-NE Material Recovery and Waste Form Development Campaign to accomplish this separation with a single process. To develop a fundamental understanding of the solvent degradation mechanisms for the ALSEP Process, testing was performed in the INL Radiolysis/Hydrolysis Test Loop for the extraction section of the ALSEP flowsheet. This work culminated in the completion of the level two milestone (M2FT-16IN030102021) "Complete ALSEP test loop solvent irradiation test.” This report summarizes the testing performed and the impact of radiation on the ALSEP Process performance as a function of dose.

  16. Potentialities of innovating concepts for the management of radioactive wastes

    International Nuclear Information System (INIS)

    Boullis, B.

    2001-01-01

    Nuclear energy has very good assets for the future: economic competitiveness, respect of the environment (no emission of greenhouse gas) and preservation of natural resources (breeding capacity). The main challenge concerns nuclear fuel cycle back-end that is the future of spent fuel but in fact all the cycle is involved because new reactor concepts and multi-recycle strategies can be defined to reduce the amount of high level radioactive wastes. Studies confirm that for an annual production of 400 TWh, it is possible to get a drastic reduction of radiotoxicity of wastes: of about a 3 to 5 ratio by multi-recycling plutonium, of about a 10 to 20 ratio by multi-recycling both plutonium and americium, of about a 100 ratio by multi-recycling plutonium, americium and curium. (A.C.)

  17. Conceptual methods for actinide partitioning

    International Nuclear Information System (INIS)

    Leuze, R.E.; Bond, W.D.; Tedder, D.W.

    1978-01-01

    The conceptual processing sequence under consideration is based on a combination of modified Purex processing and secondary processing of the high-level waste. In this concept, iodine will be removed from dissolver solution prior to extraction, and the Purex processing will be modified so that low- and intermediate-level wastes, all the way through final product purification, are recycled. A supplementary extraction is assumed to ensure adequate recovery of uranium, neptunium and possibly plutonium. Technetium may be removed from the high-level waste if a satisfactory method can be developed. Extraction into a quaternary amine is being evaluated for this removal. Methods that have been used in the past to recover americium and curium have some rather serious deficiencies, including inadequate recovery, solids formation and generation of large volumes of low- and intermediate-level wastes containing significant quantities of chemical reagents

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

    International Nuclear Information System (INIS)

    Sidhu, R.

    2006-04-01

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

  19. Measurements of the neutron capture cross sections and incineration potentials of minor-actinides in high thermal neutron fluxes: Impact on the transmutation of nuclear wastes

    International Nuclear Information System (INIS)

    Bringer, O.

    2007-10-01

    This thesis comes within the framework of minor-actinide nuclear transmutation studies. First of all, we have evaluated the impact of minor actinide nuclear data uncertainties within the cases of 241 Am and 237 Np incineration in three different reactor spectra: EFR (fast), GT-MHR (epithermal) and HI-HWR (thermal). The nuclear parameters which give the highest uncertainties were thus highlighted. As a result of fact, we have tried to reduce data uncertainties, in the thermal energy region, for one part of them through experimental campaigns in the moderated high intensity neutron fluxes of ILL reactor (Grenoble). These measurements were focused onto the incineration and transmutation of the americium-241, the curium-244 and the californium-249 isotopes. Finally, the values of 12 different cross sections and the 241 Am isomeric branching ratio were precisely measured at thermal energy point. (author)

  20. Nuclear fission and the transuranium elements

    International Nuclear Information System (INIS)

    Seaborg, G.T.

    1989-02-01

    Many of the transuranium elements are produced and isolated in large quantities through the use of neutrons furnished by nuclear fission reactions: plutonium (atomic number 94) in ton quantities; neptunium (93), americium (95), and curium (96) in kilogram quantities; berkelium (97) in 100 milligram quantities; californium (98) in gram quantities; and einsteinium (99) in milligram quantities. Transuranium isotopes have found many practical applications---as nuclear fuel for the large-scale generation of electricity, as compact, long-lived power sources for use in space exploration, as means for diagnosis and treatment in the medical area, and as tools in numerous industrial processes. Of particular interest is the unusual chemistry and impact of these heaviest elements on the periodic table. This account will feature these aspects. 9 refs., 5 figs