WorldWideScience

Sample records for americium 237

  1. Americium-241 and plutonium-237 turnover in mussels ( Mytilus galloprovincialis) living in field enclosures

    Science.gov (United States)

    Guary, J. C.; Fowler, S. W.

    1981-02-01

    Loss of 241Am and 237Pu from contaminated mussels ( Mytilus galloprovincialis) living in situ in the Mediterranean Sea is described as the sum of three exponential functions. In the case of 241Am, two short-lived compartments representing a total of 80% of the incorporated radionuclide turned over rapidly with biological half-lives of 2 and 3 weeks. The remaining fraction of 241Am, associated with a long-lived compartment, was lost at an extremely slow rate ( Tb1/2=1·3 years). Plutonium-237 turnover in the two short-lived compartments (containing 70% of the Pu) was more rapid ( Tb1/2=1-2 days and 2 weeks) than that of 241Am; however, there was some indication that subsequent loss rates of the two radionuclides in long-lived compartments may be similar if determined over comparable periods of time. Loss rates of 241Am differed for the various tissues, with the most rapid rates occurring in gill, viscera and shell. Abrupt changes in loss observed in muscle and mantle suggested a translocation of 241Am to muscle and mantle during depuration. Whole shell contained by far the largest fraction (˜90%) of both 241Am and 237Pu taken up; in addition, these radionuclides are not irreversibly bound to mussel shell but readily leach into the water. These observations suggest that mollusc shell may influence the biogeochemistry of transuranic elements in littoral zones.

  2. Chemistry of americium

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, W.W.

    1976-01-01

    Essential features of the descriptive chemistry of americium are reviewed. Chapter titles are: discovery, atomic and nuclear properties, collateral reading, production and uses, chemistry in aqueous solution, metal, alloys, and compounds, and, recovery, separation, purification. Author and subject indexes are included. (JCB)

  3. The Biokinetic Model of Americium

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    To improve in vivo measurements for detecting internal exposure from transuranium radio nuclides, such as neptunium, plutonium, americium, the bioknetic model was studied. According to ICRP report (1993, 1995, 1997) and other research, the

  4. Aqueous Chloride Operations Overview: Plutonium and Americium Purification/Recovery

    Energy Technology Data Exchange (ETDEWEB)

    Kimball, David Bryan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Skidmore, Bradley Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-22

    Acqueous Chloride mission is to recover plutonium and americium from pyrochemical residues (undesirable form for utilization and storage) and generate plutonium oxide and americium oxide. Plutonium oxide is recycled into Pu metal production flowsheet. It is suitable for storage. Americium oxide is a valuable product, sold through the DOE-OS isotope sales program.

  5. 5f-Electron Delocalization in Americium

    DEFF Research Database (Denmark)

    Skriver, Hans Lomholt; Andersen, O. K.; Johansson, B.

    1980-01-01

    The pressure-volume relation for americium has been obtained without adjustable parameters from self-consistent, spin-polarized band calculations. Around 100 kbar we find a first-order transition to a state with low volume and no spin. This is consistent with preliminary high-pressure measurements....

  6. The relative physiological and toxicological properties of americium and plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Carter, R.E.; Busch, E.; Johnson, O. [and others

    1951-11-15

    The relative physiological and toxicological properties of americium and plutonium have been studied following their intravenous administration to rats. The urinary and fecal excretion of americium was similar to that of plutonium administered as Pu(N0{sub 3}){sub 4}. The deposition of americium the tissues and organs of the rat was also similar to that observed for plutonium. The liver and the skeleton were the major sites of deposition. Zirconium citrate administered 15 minutes after injection of americium increased the urinary excretion of americium and decreased the amount found in the liver and the skeleton at 4 and 16 days. LD{sub 30}{sup 50} studies showed americium was slightly less toxic when given in the acute toxic range than was plutonium. The difference was, however, too slight to be important in establishing a larger tolerance does for americium. Survival studies, hematological observations, bone marrow observations, comparison of tumor incidence and the incidence of skeletal abnormalities indicated that americium and plutonium have essentially the same chronic toxicity when given on an equal {mu}c. basis. These studies support the conclusion that the tolerance values for americium should be essentially the same as those for Plutonium.

  7. Experimental studies on the biokinetics of plutonium and americium in the cephalopod Octopus vulgaris

    Energy Technology Data Exchange (ETDEWEB)

    Guary, J.C.; Fowler, S.W.

    1982-03-05

    Radiotracer experiments using the photon-emitters /sup 237/Pu and /sup 241/Am were performed to examine uptake, tissue distribution and retention of plutonium and americium in the cephalopod Octopus vulgaris Cuvier. A 2 wk exposure in contaminated sea water resulted in twice as much /sup 237/Pu being taken up by whole octopus as /sup 241/Am. Immediately following uptake approximately 41% and 73% of the /sup 237/Pu and /sup 241/Am respectively were located in the branchial hearts. Depuration rates for both radionuclides were identical; approximately 46% of both radionuclides initially incorporated were associated with a long-lived compartment which turned over very slowly (Tbsub(1/2) = 1.5 yr). Longer exposures to /sup 241/Am resulted in an increase in the size of the slowly exchanging /sup 241/Am pool in the octopus. After 2 mo depuration, the majority of the residual activity of both radionuclides was in the branchial hearts. On average 33% of the /sup 241/Am ingested with food was assimilated into tissues, primarily the hepatopancreas. Different whole-body /sup 241/Am excretion rates were observed at different times following assimilation and were related to transfer processes taking place within internal tissues, most notably between hepatopancreas and the branchial hearts. Relationships between circulatory and excretory functions of these 2 organs are discussed and a physiological mechanism is proposed to explain the observed patterns of /sup 241/Am excretion in O. vulgaris.

  8. Surface complexation modeling of americium sorption onto volcanic tuff.

    Science.gov (United States)

    Ding, M; Kelkar, S; Meijer, A

    2014-10-01

    Results of a surface complexation model (SCM) for americium sorption on volcanic rocks (devitrified and zeolitic tuff) are presented. The model was developed using PHREEQC and based on laboratory data for americium sorption on quartz. Available data for sorption of americium on quartz as a function of pH in dilute groundwater can be modeled with two surface reactions involving an americium sulfate and an americium carbonate complex. It was assumed in applying the model to volcanic rocks from Yucca Mountain, that the surface properties of volcanic rocks can be represented by a quartz surface. Using groundwaters compositionally representative of Yucca Mountain, americium sorption distribution coefficient (Kd, L/Kg) values were calculated as function of pH. These Kd values are close to the experimentally determined Kd values for americium sorption on volcanic rocks, decreasing with increasing pH in the pH range from 7 to 9. The surface complexation constants, derived in this study, allow prediction of sorption of americium in a natural complex system, taking into account the inherent uncertainty associated with geochemical conditions that occur along transport pathways.

  9. Self-irradiation and oxidation effects on americium sesquioxide and Raman spectroscopy studies of americium oxides

    Energy Technology Data Exchange (ETDEWEB)

    Horlait, Denis [CEA, DEN, DTEC/SDTC/LEMA, F-30207 Bagnols-sur-Cèze Cedex (France); Caraballo, Richard [CEA, DEN, DTCD/SECM/LMPA, F-30207 Bagnols-sur-Cèze Cedex (France); Lebreton, Florent [CEA, DEN, DTEC/SDTC/LEMA, F-30207 Bagnols-sur-Cèze Cedex (France); Jégou, Christophe [CEA, DEN, DTCD/SECM/LMPA, F-30207 Bagnols-sur-Cèze Cedex (France); Roussel, Pascal [Unité de Catalyse et Chimie du Solide, UMR 8012 CNRS, Ecole Nationale Supérieure de Chimie de Lille BP 90108, 59652 Villeneuve d’Ascq Cedex (France); Delahaye, Thibaud, E-mail: thibaud.delahaye@cea.fr [CEA, DEN, DTEC/SDTC/LEMA, F-30207 Bagnols-sur-Cèze Cedex (France)

    2014-09-15

    Americium oxides samples were characterized by X-ray diffraction (XRD) and Raman spectroscopy, with an emphasis on their structural behavior under oxidation and self-irradiation. Raman spectra of americium dioxide (AmO{sub 2}) and sesquioxide (Am{sub 2}O{sub 3}) were obtained for the first time. With the help of literature data on isostructural oxides, Raman signatures of Ia-3 C-type Am{sub 2}O{sub 3} and P-3m1 A-type Am{sub 2}O{sub 3} are identified. For AmO{sub 2,} a clear band is noted at 390 cm{sup −1}. Its nature is compared to that of the other actinide dioxides. Am{sub 2}O{sub 3} evolution under ambient conditions and against {sup 241}Am α self-irradiation was monitored by powder XRD. The sample, initially composed of A-type Am{sub 2}O{sub 3} as major phase as well as C2/m B-type and C-type structures as minor phases, progressively oxidizes to Fm-3m AmO{sub 2−δ} over a few months. On the basis of diffractogram refinements, evolutions of unit cell volumes caused by self-irradiation are also determined and discussed. - Graphical abstract: The evolution of americium oxide under ambient conditions was monitored using XRD (X-ray diffraction) and Raman spectroscopy. After a thermal treatment under reducing conditions, a polyphasic sample mainly composed of A- and C-type americium sesquioxides is evidenced by XRD and Raman spectroscopy. The sample then evolves through two processes: oxidation and self-irradiation. The first one provokes the progressive appearance of F-type americium dioxide while the initial phases disappear, whereas the main effect of the second is a structural swelling with time. - Highlights: • The first Raman spectroscopy measurements on americium oxides were performed. • Observed Am{sub 2}O{sub 3} Raman bands were identified thanks to data on analogue compounds. • AmO{sub 2} assumed T{sub 2g} band presents a shift compared to the actinide dioxide series. • Am{sub 2}O{sub 3} evolution under self-irradiation and oxidation was also

  10. 33 CFR 136.237 - Authorized claimants.

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Authorized claimants. 136.237 Section 136.237 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED... PROCEDURES; DESIGNATION OF SOURCE; AND ADVERTISEMENT Procedures for Particular Claims § 136.237...

  11. 49 CFR 237.131 - Design.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Design. 237.131 Section 237.131 Transportation... TRANSPORTATION BRIDGE SAFETY STANDARDS Repair and Modification of Bridges § 237.131 Design. Each repair or... component of a bridge shall be designed by a railroad bridge engineer. The design shall specify the...

  12. Plutonium and Americium Geochemistry at Hanford: A Site Wide Review

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J.; Felmy, Andrew R.

    2012-08-23

    This report was produced to provide a systematic review of the state-of-knowledge of plutonium and americium geochemistry at the Hanford Site. The report integrates existing knowledge of the subsurface migration behavior of plutonium and americium at the Hanford Site with available information in the scientific literature regarding the geochemistry of plutonium and americium in systems that are environmentally relevant to the Hanford Site. As a part of the report, key research needs are identified and prioritized, with the ultimate goal of developing a science-based capability to quantitatively assess risk at sites contaminated with plutonium and americium at the Hanford Site and the impact of remediation technologies and closure strategies.

  13. Americium/Curium Disposition Life Cycle Planning Study

    Energy Technology Data Exchange (ETDEWEB)

    Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

    1998-04-30

    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).

  14. Higher Americium Oxidation State Research Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    Mincher, Bruce J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Law, Jack D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Goff, George S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Moyer, Bruce A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Burns, Jon D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lumetta, Gregg J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sinkov, Sergey I. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Shehee, Thomas C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hobbs, David T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-12-18

    The partitioning of hexavalent Am from dissolved nuclear fuel requires the ability to efficiently oxidize Am(III) to Am(VI) and to maintain that oxidation state for a length of time sufficient to perform the separation. Several oxidants have been, or are being developed. Chemical oxidants include Ag-catalyzed ozone, Ag-catalyzed peroxydisulfate, Cu(III) periodate, and sodium bismuthate. Hexavalent americium has also now successfully been prepared by electrolysis, using functionalized electrodes. So-called auto-reduction rates of Am(VI) are sufficiently slow to allow for separations. However, for separations based on solvent extraction or ion exchange using organic resins, the high valence state must be maintained under the reducing conditions of the organic phase contact, and a holding oxidant is probably necessary. Until now, only Cu(III) periodate and sodium bismuthate oxidation have been successfully combined with solvent extraction separations. Bismuthate oxidation provided the higher DAm, since it acts as its own holding oxidant, and a successful hot test using centrifugal contactors was performed. For the other oxidants, Ag-catalyzed peroxydisulfate will not oxidize americium in nitric acid concentrations above 0.3 M, and it is not being further investigated. Peroxydisulfate in the absence of Ag catalysis is being used to prepare Am(V) in ion exchange work, discussed below. Preliminary work with Ag-catalyzed ozone has been unsuccessful for extractions of Am(VI) from 6.5 M HNO3, and only one attempt at extraction, also from 6.5 M HNO3, using the electrolytic oxidation has been attempted. However, this high acid concentration was based on the highest Am extraction efficiency using the bismuthate oxidant; which is only sparingly soluble, and thus the oxidation yield is based on bismuthate solubility. Lower acid concentrations may be sufficient with alternative oxidants and work with Ag-ozone, Cu(III) and electrolysis is on-going. Two non

  15. Aqueous Chloride Operations Overview: Plutonium and Americium Purification/Recovery

    Energy Technology Data Exchange (ETDEWEB)

    Gardner, Kyle Shelton [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kimball, David Bryan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Skidmore, Bradley Evan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-28

    These are a set of slides intended for an information session as part of recruiting activities at Brigham Young University. It gives an overview of aqueous chloride operations, specifically on plutonium and americium purification/recovery. This presentation details the steps taken perform these processes, from plutonium size reduction, dissolution, solvent extraction, oxalate precipitation, to calcination. For americium recovery, it details the CLEAR (chloride extraction and actinide recovery) Line, oxalate precipitation and calcination.

  16. Pyrochemical investigations into recovering plutonium from americium extraction salt residues

    Energy Technology Data Exchange (ETDEWEB)

    Fife, K.W.; West, M.H.

    1987-05-01

    Progress into developing a pyrochemical technique for separating and recovering plutonium from spent americium extraction waste salts has concentrated on selective chemical reduction with lanthanum metal and calcium metal and on the solvent extraction of americium with calcium metal. Both techniques are effective for recovering plutonium from the waste salt, although neither appears suitable as a separation technique for recycling a plutonium stream back to mainline purification processes. 17 refs., 13 figs., 2 tabs.

  17. Electrodeposition of americium and physicochemical behaviour of the solution

    Energy Technology Data Exchange (ETDEWEB)

    Becerril-Vilchis, A. (Inst. Nacional de Investigaciones Nucleares, CMRI-LPR, Mexico City (Mexico)); Meas, Y. (CIDETEQ, Queretaro (Mexico)); Rojas-Hernandez, A. (Univ. Autonoma Metropolitana Iztapalapa, Area de Electroquimica, Mexico City (Mexico))

    1994-01-01

    A new method based on concepts of generalized species and equilibria, was applied to represent the thermodynamic distribution of americium species (including condensed phases) in an electrochemical system. Diagrams of the predominance-zone, Existence-predominance and Pourbaix-type for the americium/support electrolyte/water system were constructed. On the basis of these diagrams, the initial distribution of the species in the electrolyte and the deposition conditions were predicted when a current density was applied to a rotating disc electrode in steady-state. These results were related with the Hansen model for actinide electrodeposition. (orig.)

  18. Dicty_cDB: SFC237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SF (Link to library) SFC237 (Link to dictyBase) - - - Contig-U16426-1 SFC237P (Link to Original site) SFC...237F 350 SFC237Z 745 SFC237P 1095 - - Show SFC237 Library SF (Link to library) Clone ID SFC...e URL http://dictycdb.biol.tsukuba.ac.jp/CSM/SF/SFC2-B/SFC237Q.Seq.d/ Representative seq. ID SFC...237P (Link to Original site) Representative DNA sequence >SFC237 (SFC237Q) /CSM/SF/SFC2-B/SFC...es producing significant alignments: (bits) Value SFC237 (SFC237Q) /CSM/SF/SFC2-B/SFC

  19. Supercritical Fluid Extraction of Plutonium and Americium from Soil

    Energy Technology Data Exchange (ETDEWEB)

    Fox, R.V.; Mincher, B.J.

    2002-05-23

    Supercritical fluid extraction (SFE) of plutonium and americium from soil was successfully demonstrated using supercritical fluid carbon dioxide solvent augmented with organophosphorus and beta-diketone complexants. Spiked Idaho soils were chemically and radiologically characterized, then extracted with supercritical fluid carbon dioxide at 2,900 psi and 65 C containing varying concentrations of tributyl phosphate (TBP) and thenoyltrifluoroacetone (TTA). A single 45 minute SFE with 2.7 mol% TBP and 3.2 mol% TTA provided as much as 88% {+-} 6.0 extraction of americium and 69% {+-} 5.0 extraction of plutonium. Use of 5.3 mol% TBP with 6.8 mol% of the more acidic beta-diketone hexafluoroacetylacetone (HFA) provided 95% {+-} 3.0 extraction of americium and 83% {+-} 5.0 extraction of plutonium in a single 45 minute SFE at 3,750 psi and 95 C. Sequential chemical extraction techniques were used to chemically characterize soil partitioning of plutonium and americium in pre-SFE soil samples. Sequential chemical extraction techniques demonstrated that spiked plutonium resides primarily (76.6%) in the sesquioxide fraction with minor amounts being absorbed by the oxidizable fraction (10.6%) and residual fractions (12.8%). Post-SFE soils subjected to sequential chemical extraction characterization demonstrated that 97% of the oxidizable, 78% of the sesquioxide and 80% of the residual plutonium could be removed using SFE. These preliminary results show that SFE may be an effective solvent extraction technique for removal of actinide contaminants from soil.

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

    Energy Technology Data Exchange (ETDEWEB)

    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. Criticality of a {sup 237}Np Sphere

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez, Rene G.; Hayes, David K.; Cappiello, Charlene C.; Myers, William L.; Jaegers, Peter J.; Clement, Steven D.

    2003-07-22

    A critical mass experiment using a 6-kg {sup 237}Np sphere has been performed. The purpose of the experiment is to get a better estimate of the critical mass of {sup 237}Np. To attain criticality, the {sup 237}Np sphere was surrounded with 93 wt % {sup 235}U shells. A 1/M as a function of uranium mass was performed. An MCNP neutron transport code was used to model the experiment. The MCNP code yielded a k{sub eff} of 0.99089 {+-} 0.0003 compared with a k{sub eff} 1.0026 for the experiment. Based on these results, it is estimated that the critical mass of {sup 237}Np ranges from kilogram weights in the high fifties to low sixties.

  2. Reduction Rates for Higher Americium Oxidation States in Nitric Acid

    Energy Technology Data Exchange (ETDEWEB)

    Grimes, Travis Shane [Idaho National Lab. (INL), Idaho Falls, ID (United States); Mincher, Bruce Jay [Idaho National Lab. (INL), Idaho Falls, ID (United States); Schmitt, Nicholas C [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-30

    The stability of hexavalent americium was measured using multiple americium concentrations and nitric acid concentrations after contact with the strong oxidant sodium bismuthate. Contrary to our hypotheses Am(VI) was not reduced faster at higher americium concentrations, and the reduction was only zero-order at short time scales. Attempts to model the reduction kinetics using zero order kinetic models showed Am(VI) reduction in nitric acid is more complex than the autoreduction processes reported by others in perchloric acid. The classical zero-order reduction of Am(VI) was found here only for short times on the order of a few hours. We did show that the rate of Am(V) production was less than the rate of Am(VI) reduction, indicating that some Am(VI) undergoes two electron-reduction to Am(IV). We also monitored the Am(VI) reduction in contact with the organic diluent dodecane. A direct comparison of these results with those in the absence of the organic diluent showed the reduction rates for Am(VI) were not statistically different for both systems. Additional americium oxidations conducted in the presence of Ce(IV)/Ce(III) ions showed that Am(VI) is reduced without the typical growth of Am(V) observed in the systems sans Ce ion. This was an interesting result which suggests a potential new reduction/oxidation pathway for Am in the presence of Ce; however, these results were very preliminary, and will require additional experiments to understand the mechanism by which this occurs. Overall, these studies have shown that hexavalent americium is fundamentally stable enough in nitric acid to run a separations process. However, the complicated nature of the reduction pathways based on the system components is far from being rigorously understood.

  3. Research program on development of advanced treatment technology for americium-containing aqueous waste in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Mineo, Hideaki; Matsumura, Tatsuro; Tsubata, Yasuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1996-10-01

    A research program was prepared on the development of an advanced treatment process for the americium-containing concentrated aqueous waste in NUCEF, than allows americium recovery for the reuse and the reduction of TRU waste generation. A preliminary analysis was conducted on the separation requirements based on the components estimated for the waste. An R and D strategy was proposed from the view to reduce TRU waste generated in the processing that the highest priority is given on the control of TRU leakage such as americium into the effluent stream after americium recovery and the minimization of salt used in the separation over the decontamination of impurities from americium. The extraction chromatographic method was selected as a candidate technology for americium separation under the principle to use reagents that are functional in acidic conditions such as bidentate extractants of DHEDECMP, CMPO or diamides, considering the larger flexibilities in process modification and possible multi-component separation with compact equipment and the past achievements on the recovery of kg quantities of americium. Major R and D items extracted are screening and evaluation of extractants for americium and plutonium, optimization of separation conditions, selection of denitration method, equipment developments and development of solidification methods of discarded americium after reuse and of various kinds of separation residues. In order to cope these items, four steps of R and D program were proposed, i.e., fundamental experiment in beaker-scale on screening and evaluation of extractants, flowsheet study in bench-scale using simulated and small amount of americium aqueous waste solution to evaluate candidate process, americium recovery test in iron-shielded cell to be installed in NUCEF. It is objected to make recovery of 100g orders of americium used for research on fundamental TRU fuel properties. (J.P.N.)

  4. Supercritical Fluid Extraction of Plutonium and Americium from Soil

    Energy Technology Data Exchange (ETDEWEB)

    Fox, Robert Vincent; Mincher, Bruce Jay

    2002-08-01

    Supercritical fluid extraction (SFE) of plutonium and americium from soil was successfully demonstrated using supercritical fluid carbon dioxide solvent augmented with organophosphorus and beta-diketone complexants. Spiked Idaho soils were chemically and radiologically characterized, then extracted with supercritical fluid carbon dioxide at 2,900 psi and 65°C containing varying concentrations of tributyl phosphate (TBP) and thenoyltrifluoroacetone (TTA). A single 45 minute SFE with 2.7 mol% TBP and 3.2 mol% TTA provided as much as 88% ± 6.0 extraction of americium and 69% ± 5.0 extraction of plutonium. Use of 5.3 mol% TBP with 6.8 mol% of the more acidic beta-diketone hexafluoroacetylacetone (HFA) provided 95% ± 3.0 extraction of americium and 83% ± 5.0 extraction of plutonium in a single 45 minute SFE at 3,750 psi and 95°C. Sequential chemical extraction techniques were used to chemically characterize soil partitioning of plutonium and americium in pre-SFE soil samples. Sequential chemical extraction techniques demonstrated that spiked plutonium resides primarily (76.6%) in the sesquioxide fraction with minor amounts being absorbed by the oxidizable fraction (10.6%) and residual fractions (12.8%). Post-SFE soils subjected to sequential chemical extraction characterization demonstrated that 97% of the oxidizable, 78% of the sesquioxide and 80% of the residual plutonium could be removed using SFE. These preliminary results show that SFE may be an effective solvent extraction technique for removal of actinide contaminants from soil.

  5. Isolation of americium (5) oxalate compounds from solutions

    Energy Technology Data Exchange (ETDEWEB)

    Zubarev, V.G.; Krot, N.N.

    1982-01-01

    Certain conditions of americium (5) isolation with solutions of ammonia and KOH are studied as well as the attitude of hydroxide obtained to heating. Like neptunium (5) hydroxide americium (5) hydroxide probably has the formula AmO/sub 2/OHxxH/sub 2/O, where x is approximately equal to 2.3. It is established that during heating in the air up to 120 deg C hydroxide transforms into AmO/sub 2/. It is shown that in solutions with a high concentration of oxalate-ion americium stability in oxidation state +5 depends greatly on the pH of solution. Complex salts KAmO/sub 2/C/sub 2/O/sub 4/xxH/sub 2/O and CsAmO/sub 2/C/sub 2/O/sub 4/xxH/sub 2/O are synthesized. The identification is made according to the method of preparation and results of analysis of C/sub 2/O/sub 4//sup 2 -/: AmO/sub 2//sup +/ ratio. It is found that the salts are non-isomorphous to similar salts of pentavalent neptunium. CsAmO/sub 2/C/sub 2/O/sub 4/xxH/sub 2/O is identified in cubic crystal system with the lattice constant a=1.25 nm.

  6. 50 CFR 648.237 - Framework provisions.

    Science.gov (United States)

    2010-10-01

    ... recommended management measures should be published first as a proposed rule, then the measures will be....237 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND ATMOSPHERIC ADMINISTRATION, DEPARTMENT OF COMMERCE FISHERIES OF THE NORTHEASTERN UNITED STATES Management Measures for...

  7. 33 CFR 117.237 - Christina River.

    Science.gov (United States)

    2010-07-01

    ... the Market Street Bridge, mile 3.0 at Wilmington shall open on signal if at least eight hours notice... DRAWBRIDGE OPERATION REGULATIONS Specific Requirements Delaware § 117.237 Christina River. (a) The owners of... open on signal except that the draw of a railroad bridge need not be opened when a train is in...

  8. Separation of americium and curium from complex chemical and radiochemical mixtures

    Energy Technology Data Exchange (ETDEWEB)

    Bochkarev, V.A.; Martynov, N.P.; Slivin, V.G.; Trikanov, A.E.; Fedyaeva, N.V.

    1988-11-01

    This work describes a method for separation and radiochemical purification of nanogram levels of americium and curium from complex chemical and radiochemical mixtures containing tens of milligrams of elements such as aluminum, iron, magnesium, calcium, barium, titanium, potassium, and others, microgram levels of uranium, neptunium, and plutonium, and fission products. Extraction coefficients of americium and curium from these elements are measured. The separation from the macrocomponents was carried out by extraction of americium and curium with butyric acid in the presence of sulfosalicylic acid. Uranium, neptunium, and plutonium were separated from hydrochloric acid solutions, while the rare earth elements were separated from lithium chloride solutions using a column of anion exchange resin AV-17. Alpha measurements were carried out on americium and curium deposited electrolytically on tantalum cathodes. The chemical yield of americium and curium was identical of greater than or equal to 94%, separation time approx. 8 h.

  9. Uncertainty analysis of doses from ingestion of plutonium and americium.

    Science.gov (United States)

    Puncher, M; Harrison, J D

    2012-02-01

    Uncertainty analyses have been performed on the biokinetic model for americium currently used by the International Commission on Radiological Protection (ICRP), and the model for plutonium recently derived by Leggett, considering acute intakes by ingestion by adult members of the public. The analyses calculated distributions of doses per unit intake. Those parameters having the greatest impact on prospective doses were identified by sensitivity analysis; the most important were the fraction absorbed from the alimentary tract, f(1), and rates of uptake from blood to bone surfaces. Probability distributions were selected based on the observed distribution of plutonium and americium in human subjects where possible; the distributions for f(1) reflected uncertainty on the average value of this parameter for non-specified plutonium and americium compounds ingested by adult members of the public. The calculated distributions of effective doses for ingested (239)Pu and (241)Am were well described by log-normal distributions, with doses varying by around a factor of 3 above and below the central values; the distributions contain the current ICRP Publication 67 dose coefficients for ingestion of (239)Pu and (241)Am by adult members of the public. Uncertainty on f(1) values had the greatest impact on doses, particularly effective dose. It is concluded that: (1) more precise data on f(1) values would have a greater effect in reducing uncertainties on doses from ingested (239)Pu and (241)Am, than reducing uncertainty on other model parameter values and (2) the results support the dose coefficients (Sv Bq(-1) intake) derived by ICRP for ingestion of (239)Pu and (241)Am by adult members of the public.

  10. 34 CFR 237.3 - How are awards distributed?

    Science.gov (United States)

    2010-07-01

    ... 34 Education 1 2010-07-01 2010-07-01 false How are awards distributed? 237.3 Section 237.3 Education Regulations of the Offices of the Department of Education OFFICE OF ELEMENTARY AND SECONDARY EDUCATION, DEPARTMENT OF EDUCATION CHRISTA MCAULIFFE FELLOWSHIP PROGRAM General § 237.3 How are awards distributed? (a) Except as provided in section...

  11. Np-237 in peat and lichen in Finland

    DEFF Research Database (Denmark)

    Salminen, S.; Paatero, J.; Roos, Per;

    2009-01-01

    Activity concentrations of 237Np in peat and lichen samples in Finland were determined and contributions from nuclear weapons testing in 1950–1960s and the Chernobyl accident were estimated. 237Np was determined with ICP-MS using 235Np as a tracer. Activity concentrations of 237Np in peat samples...

  12. 48 CFR 1852.237-71 - Pension portability.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Pension portability. 1852.237-71 Section 1852.237-71 Federal Acquisition Regulations System NATIONAL AERONAUTICS AND SPACE... 1852.237-71 Pension portability. As prescribed at 1837.110-70(b), insert the following clause:...

  13. Kilogram-scale purification of americium by ion exchange

    Energy Technology Data Exchange (ETDEWEB)

    Wheelwright, E. J.

    1979-01-01

    Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of the absorbed band down 3 to 4 successive beds of the same resin, preloaded with Zn/sup 2 +/, with an NH/sub 4/OH buffered chelating agent. The recovery of mixed /sup 241/Am-/sup 243/Am from power reactor reprocessing waste has been demonstrated. Solvent extraction was used to recover a HNO/sub 3/ solution of mixed lanthanides and actinides from waste generated by the reprocessng of 13.5 tons of Shippingport Power Reactor blanket fuel. Sequential cation exchange band-displacement processes were then used to separate americium and curium from the lanthanides and then to separate approx. 60 g of /sup 244/Cm from 1000 g of mixed /sup 241/Am-/sup 243/Am.

  14. Hexavalent Americium Recovery Using Copper(III) Periodate

    Energy Technology Data Exchange (ETDEWEB)

    McCann, Kevin; Brigham, Derek M.; Morrison, Samuel; Braley, Jenifer C.

    2016-11-21

    Separation of americium from the lanthanides is considered one of the most difficult separation steps in closing the nuclear fuel cycle. One approach to this separation could involve oxidizing americium to the hexavalent state to form a linear dioxo cation while the lanthanides remain as trivalent ions. This work considers aqueous soluble Cu3+ periodate as an oxidant under molar nitric acid conditions to separate hexavalent Am with diamyl amylphosphonate (DAAP) in n-dodecane. Initial studies assessed the kinetics of Cu3+ periodate auto-reduction in acidic media to aid in development of the solvent extraction system. Following characterization of the Cu3+ periodate oxidant, solvent extraction studies optimized the recovery of Am from varied nitric acid media and in the presence of other fission product, or fission product surrogate, species. Short aqueous/organic contact times encouraged successful recovery of Am (distribution values as high as 2) from nitric acid media in the absence of redox active fission products. In the presence of a post-PUREX simulant aqueous feed, precipitation of tetravalent species (Ce, Ru, Zr) occurred and the distribution values of 241Am were suppressed, suggesting some oxidizing capacity of the Cu3+ periodate is significantly consumed by other redox active metals in the simulant. The manuscript demonstrates Cu3+ periodate as a potentially viable oxidant for Am oxidation and recovery and notes the consumption of oxidizing capacity observed in the presence of the post-PUREX simulant feed will need to be addressed for any approach seeking to oxidize Am for separations relevant to the nuclear fuel cycle.

  15. Analysis list: nhr-237 [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available nhr-237 Embryo,Larvae + ce10 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/nhr-237.1.tsv http:...//dbarchive.biosciencedbc.jp/kyushu-u/ce10/target/nhr-237.5.tsv http://dbarchive.bioscie...ncedbc.jp/kyushu-u/ce10/target/nhr-237.10.tsv http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/nhr-237.Embryo.tsv,http:...//dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/nhr-237.Larvae.tsv http:...//dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Embryo.gml,http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/colo/Larvae.gml ...

  16. Oxidative Alkaline leaching of Americium from simulated high-level nuclear waste sludges

    Energy Technology Data Exchange (ETDEWEB)

    Reed, Wendy A.; Garnov, Alexander Yu.; Rao, Linfeng; Nash, Kenneth L.; Bond, Andrew H.

    2004-01-23

    Oxidative alkaline leaching has been proposed to pre-treat the high-level nuclear waste sludges to remove some of the problematic (e.g., Cr) and/or non-radioactive (e.g., Na, Al) constituents before vitrification. It is critical to understand the behavior of actinides, americium and plutonium in particular, in oxidative alkaline leaching. We have studied the leaching behavior of americium from four different sludge simulants (BiPO{sub 4}, BiPO{sub 4 modified}, Redox, PUREX) using potassium permanganate and potassium persulfate in alkaline solutions. Up to 60% of americium sorbed onto the simulants is leached from the sludges by alkaline persulfate and permanganate. The percentage of americium leached increases with [NaOH] (between 1.0 and 5.0 M). The initial rate of americium leaching by potassium persulfate increases in the order BiPO{sub 4} sludge < Redox sludge < PUREX sludge. The data are most consistent with oxidation of Am{sup 3+} in the sludge to either AmO{sub 2}{sup +} or AmO{sub 2}{sup 2+} in solution. Though neither of these species is expected to exhibit long-term stability in solution, the potential for mobilization of americium from sludge samples would have to be accommodated in the design of any oxidative leaching process for real sludge samples.

  17. The transmutation of americium: the Ecrix experiments in Phenix; Transmutation de l'americium: les experiences ecrix dans Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, J.C.; Schmidt, N. [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SESC), 13 - Saint-Paul-lez-Durance (France); Croixmarie, Y.; Ottaviani, J.P. [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SPUA), 13 - Saint-Paul-lez-Durance (France); Varaine, F.; Saint Jean, C. de [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPRC), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    The first americium transmutation experiment in a specific target in PHENIX will occur with the ECRIX-B and ECRIX-H experiments. Beside material testing, the objective is also to represent a concept of transmutation whose specificity is to enhance the kinetics of transmutation by using a moderated spectrum. The moderator materials will be {sup 11}B{sub 4}C and CaH{sub 2} for ECRIX-B and ECRIXH respectively, the irradiation conditions have been predicted for both the neutronics and thermal. The targets (MgO-AmO{sub X} pellets) are manufactured in the ATALANTE laboratory and the design is performed according to the PHENIX operating conditions. (authors)

  18. Transmutation of 129I, 237Np, 238Pu, 239Pu, and 241Am using neutrons produced in target-blanket system `Energy plus Transmutation' by relativistic protons

    Indian Academy of Sciences (India)

    J Adam; K Katovsky; A Balabekyan; V G Kalinnikov; M I Krivopustov; H Kumawat; A A Solnyshkin; V I Stegailov; S G Stetsenko; V M Tsoupko-Sitnikov; W Westmeier

    2007-02-01

    Target-blanket facility `Energy + Transmutation' was irradiated by proton beam extracted from the Nuclotron Accelerator in Laboratory of High Energies of Joint Institute for Nuclear Research in Dubna, Russia. Neutrons generated by the spallation reactions of 0.7, 1.0, 1.5 and 2 GeV protons and lead target interact with subcritical uranium blanket. In the neutron field outside the blanket, radioactive iodine, neptunium, plutonium and americium samples were irradiated and transmutation reaction yields (residual nuclei production yields) have been determined using -spectroscopy. Neutron field's energy distribution has also been studied using a set of threshold detectors. Results of transmutation studies of 129I, 237Np, 238Pu, 239Pu and 241Am are presented.

  19. 49 CFR 237.133 - Supervision of repairs and modifications.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Supervision of repairs and modifications. 237.133... Supervision of repairs and modifications. Each repair or modification pursuant to this part shall be performed under the immediate supervision of a railroad bridge supervisor as defined in § 237.55 of this part...

  20. 48 CFR 1452.237-71 - Utilization of Woody Biomass.

    Science.gov (United States)

    2010-10-01

    ... Biomass. 1452.237-71 Section 1452.237-71 Federal Acquisition Regulations System DEPARTMENT OF THE INTERIOR... Utilization of Woody Biomass. As prescribed in § 1437.7202, insert the following clause: Utilization of Woody Biomass (MAY 2005) (a) The contractor may remove and utilize woody biomass, if: (1) Project work...

  1. 48 CFR 252.237-7017 - Individual laundry.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Individual laundry. 252... Provisions And Clauses 252.237-7017 Individual laundry. As prescribed in 237.7101(f), use the following clause: Individual Laundry (DEC 1991) (a) The Contractor shall provide laundry service under...

  2. 48 CFR 652.237-71 - Identification/Building Pass.

    Science.gov (United States)

    2010-10-01

    ... Pass. 652.237-71 Section 652.237-71 Federal Acquisition Regulations System DEPARTMENT OF STATE CLAUSES... Identification/Building Pass. As prescribed in 637.110(b), insert the following clause. Identification/Building Pass (APR 2004) (a) Contractors working in domestic facilities who already possess a security...

  3. 34 CFR 237.8 - What definitions apply?

    Science.gov (United States)

    2010-07-01

    ... 77.1: Department EDGAR Elementary school Local educational agency Private Public Secondary school... 34 Education 1 2010-07-01 2010-07-01 false What definitions apply? 237.8 Section 237.8 Education Regulations of the Offices of the Department of Education OFFICE OF ELEMENTARY AND SECONDARY...

  4. Effect of americium-241 on luminous bacteria. Role of peroxides

    Energy Technology Data Exchange (ETDEWEB)

    Alexandrova, M., E-mail: maka-alexandrova@rambler.r [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Rozhko, T. [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Vydryakova, G. [Institute of Biophysics SB RAS, Akademgorodok 50, 660036 Krasnoyarsk (Russian Federation); Kudryasheva, N. [Siberian Federal University, Svobodny 79, 660041 Krasnoyarsk (Russian Federation); Institute of Biophysics SB RAS, Akademgorodok 50, 660036 Krasnoyarsk (Russian Federation)

    2011-04-15

    The effect of americium-241 ({sup 241}Am), an alpha-emitting radionuclide of high specific activity, on luminous bacteria Photobacterium phosphoreum was studied. Traces of {sup 241}Am in nutrient media (0.16-6.67 kBq/L) suppressed the growth of bacteria, but enhanced luminescence intensity and quantum yield at room temperature. Lower temperature (4 {sup o}C) increased the time of bacterial luminescence and revealed a stage of bioluminescence inhibition after 150 h of bioluminescence registration start. The role of conditions of exposure the bacterial cells to the {sup 241}Am is discussed. The effect of {sup 241}Am on luminous bacteria was attributed to peroxide compounds generated in water solutions as secondary products of radioactive decay. Increase of peroxide concentration in {sup 241}Am solutions was demonstrated; and the similarity of {sup 241}Am and hydrogen peroxide effects on bacterial luminescence was revealed. The study provides a scientific basis for elaboration of bioluminescence-based assay to monitor radiotoxicity of alpha-emitting radionuclides in aquatic solutions. - Highlights: {yields} Am-241 in water solutions (A = 0.16-6.7 kBq/L) suppresses bacterial growth.{yields} Am-241 (A = 0.16-6.7 kBq/L) stimulate bacterial luminescence. {yields} Peroxides, secondary radiolysis products, cause increase of bacterial luminescence.

  5. Particulate distribution of plutonium and americium in surface waters from the Spanish Mediterranean coast

    Energy Technology Data Exchange (ETDEWEB)

    Molero, J.; Sanchez-Cabeza, J.A.; Merino, J.; Vidal-Quadras, A. [Universidad Autonoma de Barcelona (Spain); Vives Batlle, J.; Mitchell, P.I. [University Coll., Dublin (Ireland)

    1995-12-31

    Measurements of the particulate distribution of plutonium and americium in Spanish Mediterranean coastal waters have been carried out. Plutonium-239,340 and {sup 241}Am concentrations have been measured in suspended particulate matter by filtering (< 0.22 {mu}m) large volume (200-300 litres) sea water samples. Results indicate that particulate plutonium constitutes on average 11 {+-} 4% of the total concentration in sea water. In the case of americium this percentage rises to 45 {+-} 14%. From the {sup 241}Am/{sup 239,240}Pu activity ratios it is clear that suspended particulate matter is enriched in {sup 241}Am relative to {sup 239,240}Pu by a factor 8 {+-} 4. Plutonium and americium in surface Mediterranean coastal waters appear to be fractionated as they present a different transfer rate to the particles. Our measurements allowed us to estimate sediment-water distribution coefficients (K{sub d}), which are a key parameter to interpret differences between the behaviour of plutonium and americium in sea water. Distribution coefficients K{sub d} have been estimated to be (1.4 {+-} 0.5) x 10{sup 5} litres kg{sup -1} for plutonium and (0.9 {+-} 0.5) x 10{sup 6} litres kg{sup -1} for americium in surface Mediterranean coastal waters. (author).

  6. Isotopic and elemental composition of plutonium/americium oxides influence pulmonary and extra-pulmonary distribution after inhalation in rats.

    Science.gov (United States)

    Van der Meeren, A; Grémy, O

    2010-09-01

    The biodistribution of plutonium and americium has been studied in a rat model after inhalation of two PuO(2) powders in lungs and extra-pulmonary organs from 3 d to 3 mo. The main difference between the two powders was the content of americium (approximately 46% and 4.5% of total alpha activity). The PuO(2) with a higher proportion of americium shows an accelerated transfer of activity from lungs to blood as compared to PuO(2) with the lower americium content, illustrated by increased urinary excretion and higher bone and liver actinide retention. The total alpha activity measured reflects mostly the americium biological behavior. The activity contained in epithelial lining fluid, recovered in the acellular phase of broncho-alveolar lavages, mainly contains americium, whereas plutonium remains trapped in macrophages. Epithelial lining fluid could represent a transitional pulmonary compartment prior to translocation of actinides to the blood and subsequent deposition in extra-pulmonary retention organs. In addition, differential behaviors of plutonium and americium are also observed between the PuO(2) powders with a higher dissolution rate for both plutonium and americium being obtained for the PuO(2) with the highest americium content. Our results indicate that the biological behavior of plutonium and americium after translocation into blood differ two-fold: (1) for the two actinides for the same PuO(2) aerosol, and (2) for the same actinide from the two different aerosols. These results highlight the importance of considering the specific behavior of each contaminant after accidental pulmonary intake when assessing extra-pulmonary deposits from the level of activity excreted in urine or for therapeutic strategy decisions.

  7. 48 CFR 452.237-76 - Progress Reporting.

    Science.gov (United States)

    2010-10-01

    ... FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Texts of Provisions and Clauses 452.237-76 Progress... month's narrative. (c) Section II—A description of overall progress plus a separate description of...

  8. National low-level waste management program radionuclide report series, Volume 14: Americium-241

    Energy Technology Data Exchange (ETDEWEB)

    Winberg, M.R.; Garcia, R.S.

    1995-09-01

    This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ({sup 241}Am). This report also includes discussions about waste types and forms in which {sup 241}Am can be found and {sup 241}Am behavior in the environment and in the human body.

  9. Understanding the Chemistry of Uncommon Americium Oxidation States for Application to Actinide/Lanthanide Separations

    Energy Technology Data Exchange (ETDEWEB)

    Leigh Martin; Bruce J. Mincher; Nicholas C. Schmitt

    2007-09-01

    A spectroscopic study of the stability of Am(V) and Am(VI) produced by oxidizing Am(III) with sodium bismuthate is presented, varying the initial americium concentration, temperature and length of the oxidation was seen to have profound effects on the resultant solutions.

  10. TCM and Western Medical History of 237 Cases of Adult Migraine%237例成人偏头痛中西医完全病史研究

    Institute of Scientific and Technical Information of China (English)

    黄小星; 陈宝田; 陈敏; 黄瑞凝; 伍志勇; 商建青

    2013-01-01

    Objective To investigate the historical characteristics of adult migraine and to evaluate the diagnostic value of each historical characteristic. Methods Complete medical history of 237 adult migraine cases were collected and the independent diagnostic value of each case's characteristics was analyzed using statistical methods. In addition, history and types of childhood migraine were explored. Results Female patients accounted for 73. 4% of all cases ( 174/237 ) of adult migraine. The historical characteristics of migraine ( in descending frequency of occurrence ) included severe headache ( 71.7% , 170/ 237 ), temporal headache ( 64. 1% , 152/237 ), nausea and vomiting ( 61. 2% , 145/237 ), pulsatile headache ( 55. 7% , 132/237), history of childhood migraine (51.9%, 123/237), swelling headache (46.8%, 111/237), family history ( 44. 3% , 105/237 ), phonophobia ( 42. 2% , 100/237 ), dizziness ( 36. 3% , 86/237 ), and photophobia ( 33. 8% , 80/ 237 ). Most cases were influenced by alcohol consumption ( 66. 2% , 102/154 ), sleep ( 62. 4% , 148/237 ), six climatic evils ( 59. 5% , 141/237 ) and seven emotions ( 56. 1% , 133/237 ). Nearly half of the female cases were affected by their menstrual cycles ( 42. 5% , 74/174 ). Conclusion Migraine diagnosis should incorporate the patient's complete medical history including TCM and Western medicine and take consideration of both adult and childhood medical history.%目的 研究成人偏头痛患者病史特征,明确各病史特征的诊断价值大小,寻找适合我国的偏头痛诊断方法.方法 对237例成人偏头痛患者采集完全病史,统计分析每个病史特征的独立诊断价值;追溯研究对象儿童时期是否有小儿偏头痛,进行小儿偏头痛类型研究.结果 237例偏头痛患者中,女性占73.4%(174/237),对偏头痛诊断价值较高的病史特征依次为重度头痛(71.7%,170/237)、颞部头痛(64.1%,152/237)、恶心呕吐(61.2%,145/237)、跳痛(55.7%,132/237)

  11. SKIN DOSIMETRY IN CONDITIONS OF ITS CONSTANT SURFACE CONTAMINATION WITH SOLUTIONS OF PLUTONIUM-239 AND AMERICIUM-241

    Directory of Open Access Journals (Sweden)

    E. B. Ershov

    2012-01-01

    Full Text Available The article considers, on the basis of experimental data, the issue of assessing dose burdens to the skin basal layer in conditions of its permanent contamination with solutions of plutonium-239 and americium-241 and subsequent decontamination.

  12. Influence of biofilms on migration of uranium, americium and europium in the environment; Einfluss von Biofilmen auf das Migrationsverhalten von Uran, Americium und Europium in der Umwelt

    Energy Technology Data Exchange (ETDEWEB)

    Baumann, Nils; Zirnstein, Isabel; Arnold, Thuro

    2015-07-01

    The report on the influence of biofilms on migration of uranium, americium and europium in the environment deals with the contamination problems of uranium mines such as SDAG WISMUT in Saxonia and Thuringia. In mine waters microorganisms form a complex microbiological biocoenosis in spite of low pH values and high heavy metal concentrations including high uranium concentrations. The analyses used microbiological methods like confocal laser scanning microscopy and molecular-biological techniques. The interactions of microorganism with fluorescent radioactive heavy metal ions were performed with TRLFS (time resolved laser-induced fluorescence spectroscopy).

  13. 49 CFR 237.33 - Content of bridge management programs.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Content of bridge management programs. 237.33... Content of bridge management programs. Each bridge management program adopted in compliance with this part... spans, span lengths, and all other information necessary to provide for the management of bridge...

  14. 18 CFR 367.2370 - Account 237, Interest accrued.

    Science.gov (United States)

    2010-04-01

    ... ACT Balance Sheet Chart of Accounts Current and Accrued Liabilities § 367.2370 Account 237, Interest... accrued. 367.2370 Section 367.2370 Conservation of Power and Water Resources FEDERAL ENERGY REGULATORY COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER THE PUBLIC UTILITY HOLDING COMPANY ACT OF 2005,...

  15. The 237U(n,f) Cross Section

    Energy Technology Data Exchange (ETDEWEB)

    Younes, W; Britt, H C; Wilhelmy, J B

    2003-03-03

    The purpose of this note is to combine existing information on the {sup 237}U(n,f) cross section to determine if some consistency can be obtained for the neutron induced fission excitation of {sup 237}U. The neutron induced fission cross section of the 6.8 day {sup 237}U was measured directly by McNally et al. in 1968 using the Pommard nuclear device test. At the same time critical assembly measurements were done at Los Alamos using the Flattop assembly. A previous measurement was also made at LASL in 1954 with two different neutron sources, each peaked near 200 keV. The results were 0.66 {+-} 0.10 b and 0.70 {+-} 0.07 b for the (n,f) cross section. More recently Younes and Britt have reanalyzed direct reaction charged particle data of Cramer and Britt that had determined the fission probability of the {sup 238}U compound nucleus as a function of nuclear excitation energy. They have combined fission probabilities with calculated neutron absorption cross sections, including corrections for the differences in angular momentum between the direct and neutron induced reactions. From this analysis they have extracted equivalent {sup 237}U(n,f) cross sections. The technique for extracting surrogate (n,f) cross sections from (t,pf) data has been demonstrated in a recent publication for the test case {sup 235}U(n,f). In addition to this experimental information, Lynn and Hayes have recently done a new theoretical study of the fission cross sections for a series of isotopes in this region. A summary plot of the data is shown in Fig. 1. Below 0.5 MeV the McNally, Cowan, and Younes-Britt results are in reasonable agreement. The average cross section in the Younes-Britt results, for En = 0.1 to 0.4 MeV, is 0.80 times the McNally values which is well within the errors of the McNally experiment. Above 0.5 MeV the McNally results diverge toward higher values. It should be noted that this divergence begins approximately at the {sup 237}Np threshold and that {sup 237}Np is the

  16. Standard test method for quantitative determination of americium 241 in plutonium by Gamma-Ray spectrometry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1994-01-01

    1.1 This test method covers the quantitative determination of americium 241 by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters. 1.2 This test method can be used to determine the americium 241 in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  17. Calcium and zinc DTPA administration for internal contamination with plutonium-238 and americium-241.

    Science.gov (United States)

    Kazzi, Ziad N; Heyl, Alexander; Ruprecht, Johann

    2012-08-01

    The accidental or intentional release of plutonium or americium can cause acute and long term adverse health effects if they enter the human body by ingestion, inhalation, or injection. These effects can be prevented by rapid removal of these radionuclides by chelators such as calcium or zinc diethylenetriaminepentaacetate (calcium or zinc DTPA). These compounds have been shown to be efficacious in enhancing the elimination of members of the actinide family particularly plutonium and americium when administered intravenously or by nebulizer. The efficacy and adverse effects profile depend on several factors that include the route of internalization of the actinide, the type, and route time of administration of the chelator, and whether the calcium or zinc salt of DTPA is used. Current and future research efforts should be directed at overcoming limitations associated with the use of these complex drugs by using innovative methods that can enhance their structural and therapeutic properties.

  18. Final Radiological Assessment of External Exposure for CLEAR-Line Americium Recovery Operations

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Adam C. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Belooussova, Olga N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hetrick, Lucas Duane [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-11-12

    Los Alamos National Laboratory is currently planning to implement an americium recovery program. The americium, ordinarily isotopically pure 241Am, would be extracted from existing Pu materials, converted to an oxide and shipped to support fabrication of americium oxide-beryllium neutron sources. These operations would occur in the currently proposed Chloride Extraction and Actinide Recovery (CLEAR) line of glove boxes. This glove box line would be collocated with the currently-operational Experimental Chloride Extraction Line (EXCEL). The focus of this document is to provide an in-depth assessment of the currently planned radiation protection measures and to determine whether or not further design work is required to satisfy design-goal and ALARA requirements. Further, this document presents a history of americium recovery operations in the Department of Energy and high-level descriptions of the CLEAR line operations to provide a basis of comparison. Under the working assumptions adopted by this study, it was found that the evaluated design appears to mitigate doses to a level that satisfies the ALARA-in-design requirements of 10 CFR 835 as implemented by the Los Alamos National Laboratory procedure P121. The analyses indicate that extremity doses would also meet design requirements. Dose-rate calculations were performed using the radiation transport code MCNP5 and doses were estimated using a time-motion study developed in consort with the subject matter expert. A copy of this report and all supporting documentation are located on the Radiological Engineering server at Y:\\Rad Engineering\\2013 PROJECTS\\TA-55 Clear Line.

  19. On the Convergence of the Electronic Structure Properties of the FCC Americium (001) Surface

    OpenAIRE

    Gao, Da; Ray, Asok K.

    2006-01-01

    Electronic and magnetic properties of the fcc Americium (001) surface have been investigated via full-potential all-electron density-functional electronic structure calculations at both scalar and fully relativistic levels. Effects of various theoretical approximations on the fcc Am (001) surface properties have been thoroughly examined. The ground state of fcc Am (001) surface is found to be anti-ferromagnetic with spin-orbit coupling included (AFM-SO). At the ground state, the magnetic mome...

  20. Proposed 237U Evaluation for the next ENDL Release

    Energy Technology Data Exchange (ETDEWEB)

    Brown, D; Summers, N; Thompson, I; Younes, W

    2007-11-07

    We detail the new LLNL evaluation of {sup 237}U for inclusion in both the next release of the ENDL and ENDF/B-VII databases. This evaluation is based on a combination of TALYS calculations, data fits and the earlier JEFF-3.1 evaluation. Our evaluation is in excellent agreement with published surrogate (n, f) data [11, 12, 13, 14, 18] and the unpublished LLNL surrogate (n,2n) data [16].

  1. File list: Oth.Lar.50.nhr-237.AllCell [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available Oth.Lar.50.nhr-237.AllCell ce10 TFs and others nhr-237 Larvae SRX331182,SRX331178,S...RX331184,SRX331176,SRX331174,SRX331180 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/assembled/Oth.Lar.50.nhr-237.AllCell.bed ...

  2. File list: Oth.Lar.20.nhr-237.AllCell [Chip-atlas[Archive

    Lifescience Database Archive (English)

    Full Text Available Oth.Lar.20.nhr-237.AllCell ce10 TFs and others nhr-237 Larvae SRX331182,SRX331176,S...RX331178,SRX331174,SRX331184,SRX331180 http://dbarchive.biosciencedbc.jp/kyushu-u/ce10/assembled/Oth.Lar.20.nhr-237.AllCell.bed ...

  3. 48 CFR 352.237-71 - Crime Control Act-reporting of child abuse.

    Science.gov (United States)

    2010-10-01

    ...-reporting of child abuse. 352.237-71 Section 352.237-71 Federal Acquisition Regulations System HEALTH AND... Clauses 352.237-71 Crime Control Act—reporting of child abuse. As prescribed in 337.103-70(b), the Contracting Officer shall insert the following clause: Crime Control Act of 1990—Reporting of Child...

  4. MARIOS: Irradiation of UO{sub 2} containing 15% americium at well defined temperature

    Energy Technology Data Exchange (ETDEWEB)

    D' Agata, E., E-mail: elio.dagata@ec.europa.eu [European Commission, Joint Research Centre, Institute for Energy - P.O. Box 2, 1755 ZG Petten (Netherlands); Hania, P.R. [Nuclear Research and Consultancy Group, P.O. Box 25, 1755 ZG Petten (Netherlands); Bejaoui, S. [Commissariat a l' Energie Atomique, DEC CEA-Cadarache, 13108 St. Paul lez Durance Cedex (France); Sciolla, C.; Wyatt, T.; Hannink, M.H.C. [Nuclear Research and Consultancy Group, P.O. Box 25, 1755 ZG Petten (Netherlands); Herlet, N.; Jankowiak, A. [Commissariat a l' Energie Atomique DTEC CEA Marcoule, 30207 Bagnols sur Ceze Cedex (France); Klaassen, F.C. [Nuclear Research and Consultancy Group, P.O. Box 25, 1755 ZG Petten (Netherlands); Bonnerot, J.-M. [Commissariat a l' Energie Atomique, DEC CEA-Cadarache, 13108 St. Paul lez Durance Cedex (France)

    2012-01-15

    Highlights: Black-Right-Pointing-Pointer MARIOS is designed to check the behaviour of Minor Actinide Blanket Module concept. Black-Right-Pointing-Pointer Main requirement of the experiment is an accurate control of the temperature. Black-Right-Pointing-Pointer The swelling and the helium release will be the main output of the experiment. Black-Right-Pointing-Pointer A complementary experiment (DIAMINO), will be performed in the next future. - Abstract: Americium is a strong contributor to the long term radiotoxicity of high activity nuclear waste. Transmutation by irradiation in nuclear reactors of long-lived nuclides like {sup 241}Am is, therefore, an option for the reduction of radiotoxicity and residual power packages as well as the repository area. The MARIOS irradiation experiment is the latest of a series of experiments on americium transmutation (e.g. EFTTRA-T4, EFTTRA-T4bis, HELIOS). MARIOS experiment is carried out in the framework of the 4-year project FAIRFUELS of the EURATOM 7th Framework Programme (FP7). During the past years of experimental work in the field of transmutation and tests of innovative nuclear fuel containing americium, the release or trapping of helium as well as swelling has shown to be the key issue for the design of such kinds of target. Therefore, the main objective of the MARIOS experiment is to study the in-pile behaviour of UO{sub 2} containing minor actinides (MAs) in order to gain knowledge on the role of the microstructure and of the temperature on the gas release and on fuel swelling. The MARIOS experiment will be conducted in the HFR (high flux reactor) in Petten (The Netherlands) and will start in the beginning of 2011. It has been planned that the experiment will last 11 cycles, corresponding to 11 months. This paper covers the description of the objective of the experiment, as well as a general description of the design of the experiment.

  5. Speciation of americium in seawater and accumulation in the marine sponge Aplysina cavernicola.

    Science.gov (United States)

    Maloubier, Melody; Michel, Hervé; Solari, Pier Lorenzo; Moisy, Philippe; Tribalat, Marie-Aude; Oberhaensli, François R; Dechraoui Bottein, Marie Yasmine; Thomas, Olivier P; Monfort, Marguerite; Moulin, Christophe; Den Auwer, Christophe

    2015-12-21

    The fate of radionuclides in the environment is a cause of great concern for modern society, seen especially in 2011 after the Fukushima accident. Among the environmental compartments, seawater covers most of the earth's surface and may be directly or indirectly impacted. The interaction between radionuclides and the marine compartment is therefore essential for better understanding the transfer mechanisms from the hydrosphere to the biosphere. This information allows for the evaluation of the impact on humans via our interaction with the biotope that has been largely undocumented up to now. In this report, we attempt to make a link between the speciation of heavy elements in natural seawater and their uptake by a model marine organism. More specifically, because the interaction of actinides with marine invertebrates has been poorly studied, the accumulation in a representative member of the Mediterranean coralligenous habitat, the sponge Aplysina cavernicola, was investigated and its uptake curve exposed to a radiotracer (241)Am was estimated using a high-purity Ge gamma spectrometer. But in order to go beyond the phenomenological accumulation rate, the speciation of americium(III) in seawater must be assessed. The speciation of (241)Am (and natural europium as its chemically stable surrogate) in seawater was determined using a combination of different techniques: Time-Resolved Laser-Induced Fluorescence (TRLIF), Extended X-ray Absorption Fine Structure (EXAFS) at the LIII edge, Attenuated Total Reflectance Fourier Transform Infrared (ATR-FTIR) spectroscopy and Scanning Electron Microscopy (SEM) and the resulting data were compared with the speciation modeling. In seawater, the americium(III) complex (as well as the corresponding europium complex, although with conformational differences) was identified as a ternary sodium biscarbonato complex, whose formula can be tentatively written as NaAm(CO3)2·nH2O. It is therefore this chemical form of americium that is

  6. Plutonium and americium in arctic waters, the North Sea and Scottish and Irish coastal zones

    DEFF Research Database (Denmark)

    Hallstadius, L.; Aarkrog, Asker; Dahlgaard, Henning;

    1986-01-01

    collected from the Irish coast in 1983. Fallout is found to dominate as a source of 239+240Pu north of latitude 65°N, while for 238Pu a substantial fraction originates from European nuclear fuel reprocessing facilities. The 238Pu/239+240Pu isotope ratio provides clear evidence of the transport of effluent...... of the Irish Sea) to Spitsbergen. 241Am found in Arctic waters probably originates from the decay of fallout 241Pu and, like Pu, tentatively has a residence time of the order of several years. Americium from Sellafield has an estimated mean residence time of 4–6 months in Scottish waters....

  7. Penetration and decontamination of americium-241 ex vivo using fresh and frozen pig skin.

    Science.gov (United States)

    Tazrart, A; Bolzinger, M A; Moureau, A; Molina, T; Coudert, S; Angulo, J F; Briancon, S; Griffiths, N M

    2017-04-01

    Skin contamination is one of the most probable risks following major nuclear or radiological incidents. However, accidents involving skin contamination with radionuclides may occur in the nuclear industry, in research laboratories and in nuclear medicine departments. This work aims to measure the penetration of the radiological contaminant Americium ((241)Am) in fresh and frozen skin and to evaluate the distribution of the contamination in the skin. Decontamination tests were performed using water, Fuller's earth and diethylene triamine pentaacetic acid (DTPA), which is the recommended treatment in case of skin contamination with actinides such as plutonium or americium. To assess these parameters, we used the Franz cell diffusion system with full-thickness skin obtained from pigs' ears, representative of human skin. Solutions of (241)Am were deposited on the skin samples. The radioactivity content in each compartment and skin layers was measured after 24 h by liquid scintillation counting and alpha spectrophotometry. The Am cutaneous penetration to the receiver compartment is almost negligible in fresh and frozen skin. Multiple washings with water and DTPA recovered about 90% of the initial activity. The rest remains fixed mainly in the stratum corneum. Traces of activity were detected within the epidermis and dermis which is fixed and not accessible to the decontamination.

  8. Magnesium ionophore II as an extraction agent for trivalent europium and americium

    Energy Technology Data Exchange (ETDEWEB)

    Makrlik, Emanuel [Czech Univ. of Life Sciences, Prague (Czech Republic). Faculty of Environmental Sciences; Vanura, Petr [Univ. of Chemistry and Technology, Prague (Czech Republic). Dept. of Analytical Chemistry

    2016-11-01

    Solvent extraction of microamounts of trivalent europium and americium into nitrobenzene by using a mixture of hydrogen dicarbollylcobaltate (H{sup +}B{sup -}) and magnesium ionophore II (L) was studied. The equilibrium data were explained assuming that the species HL{sup +}, HL{sup +}{sub 2}, ML{sup 3+}{sub 2}, and ML{sup 3+}{sub 3} (M{sup 3+} = Eu{sup 3+}, Am{sup 3+}; L=magnesium, ionophore II) are extracted into the nitrobenzene phase. Extraction and stability constants of the cationic complex species in nitrobenzene saturated with water were determined and discussed. From the experimental results it is evident that this effective magnesium ionophore II receptor for the Eu{sup 3+} and Am{sup 3+} cations could be considered as a potential extraction agent for nuclear waste treatment.

  9. Imitators of plutonium and americium in a mixed uranium- plutonium nitride fuel

    Science.gov (United States)

    Nikitin, S. N.; Shornikov, D. P.; Tarasov, B. A.; Baranov, V. G.; Burlakova, M. A.

    2016-04-01

    Uranium nitride and mix uranium nitride (U-Pu)N is most popular nuclear fuel for Russian Fast Breeder Reactor. The works in hot cells associated with the radiation exposure of personnel and methodological difficulties. To know the main physical-chemical properties of uranium-plutonium nitride it necessary research to hot cells. In this paper, based on an assessment of physicochemical and thermodynamic properties of selected simulators Pu and Am. Analogues of Pu is are Ce and Y, and analogues Am - Dy. The technique of obtaining a model nitride fuel based on lanthanides nitrides and UN. Hydrogenation-dehydrogenation- nitration method of derived powders nitrides uranium, cerium, yttrium and dysprosium, held their mixing, pressing and sintering, the samples obtained model nitride fuel with plutonium and americium imitation. According to the results of structural studies have shown that all the samples are solid solution nitrides rare earth (REE) elements in UN.

  10. The Role of Colloids in the Transport of Plutonium and Americium: Implications for

    Energy Technology Data Exchange (ETDEWEB)

    Kersting, A B

    2003-09-17

    Colloids are small particulates (ranging in size from 1 to 0.001 micron) composed of inorganic and organic material and found in all natural water. Due to their small size, they have the ability to remain suspended in water and transported. Small amounts of plutonium (Pu) and americium (Am) can adsorb (attach) to colloids, and/or form colloidal-sized polymers and migrate in water. At Rocky Flats Environmental Technology Site (RFETS) sedimentation and resuspension of particulates and colloids in surface waters represent the dominant process for Pu and Am migration. The amount of Pu and Am that can be transported at RFETS has been quantified in the Pathway Analysis Report. The Pathway Analysis Report shows that the two dominant pathways for Pu and Am transport at RFETS are air and surface water. Shallow groundwater and biological pathways are minor.

  11. Standard practice for The separation of americium from plutonium by ion exchange

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2001-01-01

    1.1 This practice describes the use of an ion exchange technique to separate plutonium from solutions containing low concentrations of americium prior to measurement of the 241Am by gamma counting. 1.2 This practice covers the removal of plutonium, but not all the other radioactive isotopes that may interfere in the determination of 241Am. 1.3 This practice can be used when 241Am is to be determined in samples in which the plutonium is in the form of metal, oxide, or other solid provided that the solid is appropriately sampled and dissolved (See Test Methods C758, C759, and C1168). 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  12. 40 CFR 23.7 - Timing of Administrator's action under Safe Drinking Water Act.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 1 2010-07-01 2010-07-01 false Timing of Administrator's action under Safe Drinking Water Act. 23.7 Section 23.7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Drinking Water Act. Unless the Administrator otherwise explicitly provides in a particular...

  13. 27 CFR 24.237 - Spirits added to juice or concentrated fruit juice.

    Science.gov (United States)

    2010-04-01

    ... concentrated fruit juice. 24.237 Section 24.237 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX... concentrated fruit juice. Juice or concentrated fruit juice to which spirits have been added may not have an... fruit juice to which spirits have been added will be included in the appropriate tax class of any...

  14. 48 CFR 3452.237-70 - Identification of reports under consulting services contracts.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 7 2010-10-01 2010-10-01 false Identification of reports under consulting services contracts. 3452.237-70 Section 3452.237-70 Federal Acquisition Regulations System DEPARTMENT OF EDUCATION ACQUISITION REGULATION CLAUSES AND FORMS SOLICITATION PROVISIONS...

  15. Measurements of {sup 237}Np secondary neutron spectra

    Energy Technology Data Exchange (ETDEWEB)

    Kornilov, N.V.

    1997-03-01

    The activities carried out during the first year of the project are summarized. The main problems for Np spectra measurements arise from high intrinsic gamma-ray activity of the sample and admixture of the oxygen and iron nuclei. The inelastically scattered neutrons and the fission neutrons spectra for {sup 237}Np were measured by time-of-flight spectrometer of the IPPE at incident neutron energies {approx_equal}1.5 MeV, and {approx_equal}0.5 MeV. A solid tritium target and a Li-metallic target were used as neutron sources. The neutron scattering on C sample (C(n,n) standard reaction) was measured to normalize the Np data. The experimental data should be simulated by Monte Carlo method to correct the experimental data for oxygen and iron admixture as well as for multiple scattering of the neutrons in the sample. Therefore the response function of the spectrometer, and the neutron energy distribution from the source were investigated in detail. (author)

  16. Separation of oxidized americium from lanthanides by use of pillared metal(IV) phosphate-phosphonate hybrid materials

    Energy Technology Data Exchange (ETDEWEB)

    Burns, J.D.; Clearfield, A. [Texas A and M Univ., College Station, TX (United States). Dept. of Chemistry; Borkowski, M.; Reed, D.T. [Los Alamos National Laboratory, Carlsbad, NM (United States). Earth and Environmental Sciences Div.

    2012-07-01

    Closing the nuclear fuel cycle in the US poses many challenges, one of which is found in the waste streams, which contain both trivalent lanthanides and actinides. The separation of americium from the raffinate will dramatically reduce the long-term radiotoxicity of the waste. The sorption of americium in both the tri- and pentavalent oxidation states was observed for four M(IV) phosphate-phosphonate ion exchange materials in nitric acid at pH 2. High selectivity was observed for reduced Am(III) with K{sub d} values ca. 6 x 10{sup 5} mL/g, while the K{sub d} values for Am(V) were much lower. A new method of synthesizing and stabilizing AmO{sub 2}{sup +} to yield a lifetime of at least 24 h in acidic media using a combination of sodium persulfate and calcium hypochlorite will be described.

  17. 237例血培养阳性结果分析%Analysis of 237 positive results from blood cultures

    Institute of Scientific and Technical Information of China (English)

    陈梅莲; 邓任堂; 李柳燕; 李金洳; 付文金

    2015-01-01

    Objective To investigate the strains distribution and resistance characteristics of pathogenic bacteria isolated from blood culture and provide basis for clinical medication. Methods Blood samples were cultivated and continuously monitored by VersaTREK automated blood culture system with the matching blood culture bottles,and the positive bottles were transferred timely. The identification of bacteria and susceptibility test were performed by MicroScan A/S-4 bacterial automatic analyzer. Results A total of 237 strains of pathogenic bacteria were isolated from 2460 blood culture samples. The top five strains included CNS, Escherichia coli, Klebsiella pneumoniae, Staphylococcus aureus and Enterococcus. Positive pathogens were mainly distributed in ICU, general surgical department and respiratory medicine department. Susceptibility tests showed that Gram negative bacilli were highly sensitive to imipenem and Gram positive cocci had no resistance to vancomycin and linezolid. Conclusion It is important to comprehend the blood culture results promptly for the selection of antimicrobial agents and has great significance to improve cure rate.%目的:对血培养病原菌的种类分布和耐药情况进行回顾性分析,为临床用药提供依据。方法采用VersaTREK全自动血培养仪及配套血培养瓶连续监测培养细菌,阳性瓶及时转种。用MicroScan A/S-4微生物分析仪及配套试剂对分离菌进行鉴定和药敏试验。结果2460例血培养标本中共分离出237株病原菌,居前5位的病原菌依次为凝固酶阴性葡萄球菌、大肠埃希菌、肺炎克雷伯菌、金黄色葡萄球菌和肠球菌。临床分布以ICU、普外科及呼吸内科为主。药敏结果显示:革兰阴性杆菌对亚胺培南高度敏感,未发现耐万古霉素和利奈唑胺的革兰阳性球菌。结论及时了解血培养结果可以为临床抗菌治疗提供依据,对提高治愈率有重要的意义。

  18. Theoretical investigation of pressure-induced structural transitions in americium using GGA+U and hybrid density functional theory methods

    DEFF Research Database (Denmark)

    Verma, Ashok K.; Modak, P.; Sharma, Surinder M.;

    2013-01-01

    First-principles calculations have been performed for americium (Am) metal using the generalized gradient approximation + orbital-dependent onsite Coulomb repulsion via Hubbard interaction (GGA+U) and hybrid density functional theory (HYB-DFT) methods to investigate various ground state properties...... spectrum at ambient pressure relate, for some parameter choices, well to peak positions in the calculated density of states function of Am-I....

  19. Vertical and horizontal fluxes of plutonium and americium in the western Mediterranean and the Strait of Gibraltar.

    Science.gov (United States)

    León Vintró, L; Mitchell, P I; Condren, O M; Downes, A B; Papucci, C; Delfanti, R

    1999-09-30

    New data on the vertical distributions of plutonium and americium in the waters of the western Mediterranean and the Strait of Gibraltar are examined in terms of the processes governing their delivery to, transport in and removal from the water column within the basin. Residence times for plutonium and americium in surface waters of approximately 15 and approximately 3 years, respectively, are deduced, and it is shown that by the mid 1990s only approximately 35% of the 239,240Pu and approximately 5% of the 241Am deposited as weapons fallout still resided in the water column. Present 239,240Pu inventories in the water column and the underlying sediments are estimated to be approximately 25 TBq and approximately 40 TBq, respectively, which reconcile well with the time-integrated fallout deposition in this zone, taken to be approximately 69 TBq. The data show that there are significant net outward fluxes of plutonium and americium from the basin through the Strait of Gibraltar at the present time. These appear to be compensated by net inward fluxes of similar magnitude through the Strait of Sicily. Thus, the time-integrated fallout deposition in the western basin can be accounted for satisfactorily in terms of present water column and sediment inventories. Enhanced scavenging on the continental shelves, as evidenced by the appreciably higher transuranic concentrations in shelf sediments, supports this contention.

  20. The behaviour under irradiation of molybdenum matrix for inert matrix fuel containing americium oxide (CerMet concept)

    Science.gov (United States)

    D'Agata, E.; Knol, S.; Fedorov, A. V.; Fernandez, A.; Somers, J.; Klaassen, F.

    2015-10-01

    Americium is a strong contributor to the long term radiotoxicity of high activity nuclear waste. Transmutation by irradiation in nuclear reactors or Accelerator Driven System (ADS, subcritical reactors dedicated to transmutation) of long-lived nuclides like 241Am is therefore an option for the reduction of radiotoxicity of waste packages to be stored in a repository. In order to safely burn americium in a fast reactor or ADS, it must be incorporated in a matrix that could be metallic (CerMet target) or ceramic (CerCer target). One of the most promising matrix to incorporate Am is molybdenum. In order to address the issues (swelling, stability under irradiation, gas retention and release) of using Mo as matrix to transmute Am, two irradiation experiments have been conducted recently at the High Flux Reactor (HFR) in Petten (The Netherland) namely HELIOS and BODEX. The BODEX experiment is a separate effect test, where the molybdenum behaviour is studied without the presence of fission products using 10B to "produce" helium, the HELIOS experiment included a more representative fuel target with the presence of Am and fission product. This paper covers the results of Post Irradiation Examination (PIE) of the two irradiation experiments mentioned above where molybdenum behaviour has been deeply investigated as possible matrix to transmute americium (CerMet fuel target). The behaviour of molybdenum looks satisfying at operating temperature but at high temperature (above 1000 °C) more investigation should be performed.

  1. HELIOS: the new design of the irradiation of U-free fuels for americium transmutation

    Energy Technology Data Exchange (ETDEWEB)

    D' Agata, E. [European Commission, Joint Research Centre, Institute for Energy, P.O. Box 2, 1755 ZG Petten (Netherlands); Klaassen, F.; Sciolla, C. [Nuclear Research and Consultancy Group, Dept. Life Cycle and Innovations, P.O. Box 25 1755 ZG Petten (Netherlands); Fernandez-Carretero, A. [European Commission, Joint Research Centre, Institute for Transuranium Elements, P.O. Box 2340, 76125 Karlsruhe (Germany); Bonnerot, J.M. [Commissariat a l' Energie Atomique, DEC/SESC/LC2I CEA-Cadarache, 13108 St. Paul lez Durance Cedex (France)

    2009-06-15

    Americium is one of the radioactive elements that mostly contribute to the radiotoxicity of the nuclear spent fuel. Transmutation of long-lived nuclides like Americium is an option for the reduction of the mass, the radiotoxicity and the decay heat of nuclear waste. The HELIOS irradiation experiment is the last evolution in a series of experiments on americium transmutation. The previous experiments, EFTTRA-T4 and T4bis, have shown that the release or trapping of helium is the key issue for the design of such kind of target. In fact, the production of helium, which is characteristic of {sup 241}Am transmutation, is quite significant. The experiment is carried out in the framework of the 4-year project EUROTRANS of the EURATOM 6. Framework Programme (FP6). Therefore, the main objective of the HELIOS experiment is to study the in-pile behaviour of U-free fuels such as CerCer (Pu, Am, Zr)O{sub 2} and Am{sub 2}Zr{sub 2}O{sub 7}+MgO or CerMet (Pu, Am)O{sub 2}+Mo in order to gain knowledge on the role of the fuel microstructure and of the temperature on the gas release and on the fuel swelling. The experiment was planned to be conducted in the HFR (High Flux Reactor) in Petten (The Netherlands) starting the first quarter of 2007. Because of the innovative aspects of the fuel, the fabrication has had some delays as well as the final safety analyses of the original design showed some unexpected deviation. Besides, the HFR reactor has been unavailable since August 2008. Due to the reasons described above, the experiment has been postponed. HELIOS should start in the first quarter of 2009 and will last 300 full power days. The paper will cover the description of the new design of the irradiation experiment HELIOS. The experiment has been split in two parts (HELIOS1 and HELIOS2) which will be irradiated together. Moreover, due to the high temperature achieved in cladding and to the high amount of helium produced during transmutation the experiment previously designed for a

  2. Pigmented villonodular synovitis: a retrospective multicenter study of 237 cases.

    Directory of Open Access Journals (Sweden)

    Guo-ping Xie

    Full Text Available To review clinical characteristics of pigmented villonodular synovitis (PVNS in China.Electronic medical records (EMR of four Chinese institutes were queried for patients with histologically proven PVNS between January 2005 and February 2014. Their data were collected including gender, age at diagnosis, clinical presentation, affected site, symptom duration, comorbidities, treatment strategy, recurrence and routine laboratories.A total of 237 patients with biopsy-proven PVNS were investigated. The gender ratio was 1.35 for a female predominance (101 males and 136 females. The average age was 36 years (range, 2 to 83 years. The median delay from initial clinical symptom to diagnosis was 18 months. Main affected areas were the knee (73.84% and the hip (18.14%. Forty patients had a clear history of joint trauma. Six patients were concurrently diagnosed with PVNS and avascular necrosis (AVN. Five patients suffered from PVNS following implantation of orthopaedic devices including artificial prosthesis, plate and wire. One hundred and twenty-nine patients underwent arthroscopic synovectomy and 108 open synovectomy. Altogether 48 patients (26 males and 22 females had recurrence of disease. The relapse rate was 24% (knee and 6.98% (hip, 20.93% (open surgery and 19.44% (arthroscopy, respectively. Erythrocyte sedimentation rate (ESR and C-reactive protein (CRP rate were elevated in 45.83% and 38.41% of the patients respectively.To our knowledge, this study is the largest sample size of PVNS patients reported as well as the largest sample of PVNS with concurrent AVN reported to date. Our outcomes suggest that PVNS shows a female predominance, occurs mostly between 20-40 years and favors the knee and hip. Recurrence is frequent, particularly in the knee. Serum ESR and CRP may be elevated in some patients. Additionally, the present study supports the theory of an association between PVNS and orthopedic surgery, which is not limited to joint replacement.

  3. Estimated (n,f) cross sections for 236,236m237,238-Np, 237,237m-Pu, and 240,241,242,242m,243,244,244m-Am isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Younes, W; Becker, J; Britt, H

    2004-01-16

    Neutron-induced fission cross sections on targets of {sup 236,236m,237,238}Np, {sup 237,237m}Pu, and {sup 240,241,242,242m,243,244,244m}Am have been estimated for incident neutron energies of up to 6 MeV, using the ''surrogate'' technique and the ({sup 3}He,df) and ({sup 3}He,tf) reactions on stable targets to measure fission probabilities. In isotopes where low-lying isomeric states are known to exist, the (n,f) cross section on the corresponding isomeric targets has been estimated, using the surrogate technique. For targets of {sup 237}Np, {sup 241}Am, {sup 242m}Am, {sup 243}Am, measurements of the (n,f) cross section exist, and comparison with the surrogate-method results suggests that the (n,f) cross sections estimated by the surrogate technique are reliable to within 10% for incident neutron energies E{sub n}{approx}>2 MeV. Tabulated values of the estimated (n,f) cross sections are given in an appendix.

  4. {sup 237}Np and {sup 57}Fe Moessbauer study of NpFeGa{sub 5}

    Energy Technology Data Exchange (ETDEWEB)

    Homma, Y., E-mail: yhomma@imr.tohoku.ac.jp [Tohoku University, Institute for Materials Research (Japan); Nakada, M. [Japan Atomic Energy Research Institute, Nuclear Science and Engineering Directorate (Japan); Nakamura, A. [Japan Atomic Energy Research Institute, Advance Science Research Center (Japan); Nasu, S.; Aoki, D. [Tohoku University, Institute for Materials Research (Japan); Sakai, H.; Ikeda, S.; Yamamoto, E.; Haga, Y.; Onuki, Y. [Japan Atomic Energy Research Institute, Advance Science Research Center (Japan); Shiokawa, Y. [Tohoku University, Institute for Materials Research (Japan)

    2006-02-15

    {sup 57}Fe and {sup 237}Np Moessbauer Omeasurements have been performed for NpFeGa{sub 5}, which is one of the so-called neptunium 1-1-5 compounds. The {sup 57}Fe Moessbauer spectra below T{sub N} = 118 K show the magnetically ordered state. The magnitude of the hyperfine magnetic field at the {sup 57}Fe nucleus is determined to be 1.98 {+-} 0.05 T at 10 K. From the {sup 237}Np Moessbauer spectrum at 10 K, the hyperfine magnetic field at the {sup 237}Np nucleus is 203 T and the hyperfine coupling constant is determined to be 237 T/{mu}{sub B} using the Np atomic magnetic moment of 0.86 {mu}{sub B} determined by the neutron diffraction study.

  5. Residue Val237 is critical for the enantioselectivity of Penicillium expansum lipase.

    Science.gov (United States)

    Tang, Lianghua; Su, Min; Chi, Liying; Zhang, Junling; Zhang, Huihui; Zhu, Ling

    2014-03-01

    The shape of the hydrophobic tunnel leading to the active site of Penicillium expansum lipase (PEL) was redesigned by single-point mutations, in order to better understand enzyme enantioselectivity towards naproxen. A variant with a valine-to-glycine substitution at residue 237 exhibited almost no enantioselectivity (E = 1.1) compared with that (E = 104) of wild-type PEL. The function of the residue, Val237, in the hydrophobic tunnel was further analyzed by site-directed mutagenesis. For each of these variants a significant decrease of enantioselectivity (E < 7) was observed compared with that of wild-type enzyme. Further docking result showed that Val237 plays the most important role in stabilizing the correct orientation of (R)-naproxen. Overall, these results indicate that the residue Val237 is the key amino acid residue maintaining the enantioselectivity of the lipase.

  6. Americium and plutonium in water, biota, and sediment from the central Oregon coast

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, R. D.

    1982-06-01

    Plutonium-239, 240 and americium-241 were measured in the mussel Mytilus californianus from the region of Coos Bay, OR. The flesh of this species has a plutonium concentration of about 90 fCi/kg, and an Am-241/Pu-239, 240 ratio that is high relative to mixed fallout, ranging between two and three. Transuranic concentrations in sediment, unfiltered water, and filterable particulates were also measured; none of these materials has an Am/Pu ratio as greatly elevated as the mussels, and there is no apparent difference in the Am/Pu ratio of terrestrial runoff and coastal water. Sediment core profiles do not allow accumulation rates or depositional histories to be identified, but it does not appear that material characterized by a high Am/Pu ratio has ever been introduced to this estuary. Other bivalves (Tresus capax and Macoma nasuta) and a polychaete (Abarenicola sp.) do not have an elevated Am/Pu ratio, although the absolute activity of plutonium in the infaunal bivalves is roughly four times that in the mussels.

  7. Development and Testing of an Americium/Lanthanide Separation Flowsheet Using Sodium Bismuthate

    Energy Technology Data Exchange (ETDEWEB)

    Jack Law; Bruce Mincher; Troy Garn; Mitchell Greenhalgh; Nicholas Schmitt; Veronica Rutledge

    2014-04-01

    The separation of Am from the lanthanides and curium is a key step in proposed advanced fuel cycle scenarios. The partitioning and transmutation of Am is desirable to minimize the long-term heat load of material interred in a future high-level waste repository. A separation process amenable to process scale-up remains elusive. Given only subtle chemistry differences within and between the ions of the trivalent actinide and lanthanide series this separation is challenging ; however, higher oxidation states of americium can be prepared using sodium bismuthate and separated via solvent extraction using diamylamylphosphonate (DAAP) extraction. Among the other trivalent metals only Ce is also oxidized and extracted. Due to the long-term instability of Am(VI) , the loaded organic phase is readily selectively stripped to partition the actinide to a new acidic aqueous phase. Batch extraction distribution ratio measurements were used to design a flowsheet to accomplish this separation. Additionally, crossflow filtration was investigated as a method to filter the bismuthate solids from the feed solution prior to extraction. Results of the filtration studies, flowsheet development work and flowsheet performance testing using a centrifugal contactor are detailed.

  8. Americium-based oxides: Dense pellet fabrication from co-converted oxalates

    Energy Technology Data Exchange (ETDEWEB)

    Horlait, Denis; Lebreton, Florent [CEA, DEN, DTEC/SDTC/LEMA, 30207 Bagnols-sur-Cèze (France); Gauthé, Aurélie [CEA, DEN, DRCP/SERA/LCAR, 30207 Bagnols-sur-Cèze (France); Caisso, Marie [CEA, DEN, DTEC/SDTC/LEMA, 30207 Bagnols-sur-Cèze (France); Arab-Chapelet, Bénédicte; Picart, Sébastien [CEA, DEN, DRCP/SERA/LCAR, 30207 Bagnols-sur-Cèze (France); Delahaye, Thibaud, E-mail: thibaud.delahaye@cea.fr [CEA, DEN, DTEC/SDTC/LEMA, 30207 Bagnols-sur-Cèze (France)

    2014-01-15

    Mixed oxides are used as nuclear fuels and are notably envisaged for future fuel cycles including plutonium and minor actinide recycling. In this context, processes are being developed for the fabrication of uranium–americium mixed-oxide compounds for transmutation. The purpose of these processes is not only the compliance with fuel specifications in terms of density and homogeneity, but also the simplification of the process for its industrialization as well as lowering dust generation. In this paper, the use of a U{sub 0.85}Am{sub 0.15}O{sub 2±δ} powder synthesized by oxalate co-conversion as a precursor for dense fuel fabrications is assessed. This study notably focuses on sintering, which yielded pellets up to 96% of the theoretical density, taking advantage of the high reactivity and homogeneity of the powder. As-obtained pellets were further characterized to be compared to those obtained via processes based on the UMACS (Uranium Minor Actinide Conventional Sintering) process. This comparison highlights several advantages of co-converted powder as a precursor for simplified processes that generate little dust.

  9. In Vitro Dissolution Tests of Plutonium and Americium Containing Contamination Originating From ZPPR Fuel Plates

    Energy Technology Data Exchange (ETDEWEB)

    William F. Bauer; Brian K. Schuetz; Gary M. Huestis; Thomas B. Lints; Brian K. Harris; R. Duane Ball; Gracy Elias

    2012-09-01

    Assessing the extent of internal dose is of concern whenever workers are exposed to airborne radionuclides or other contaminants. Internal dose determinations depend upon a reasonable estimate of the expected biological half-life of the contaminants in the respiratory tract. One issue with refractory elements is determining the dissolution rate of the element. Actinides such as plutonium (Pu) and Americium (Am) tend to be very refractory and can have biological half-lives of tens of years. In the event of an exposure, the dissolution rates of the radionuclides of interest needs to be assessed in order to assign the proper internal dose estimates. During the November 2011 incident at the Idaho National Laboratory (INL) involving a ZPPR fuel plate, air filters in a constant air monitor (CAM) and a giraffe filter apparatus captured airborne particulate matter. These filters were used in dissolution rate experiments to determine the apparent dissolution half-life of Pu and Am in simulated biological fluids. This report describes these experiments and the results. The dissolution rates were found to follow a three term exponential decay equation. Differences were noted depending upon the nature of the biological fluid simulant. Overall, greater than 95% of the Pu and 93% of the Am were in a very slow dissolving component with dissolution half-lives of over 10 years.

  10. Plutonium and americium monazite materials: Solid state synthesis and X-ray diffraction study

    Energy Technology Data Exchange (ETDEWEB)

    Bregiroux, D. [DEN/DEC/SPUA, Commissariat a l' Energie Atomique, Cadarache, 13108 Saint Paul Lez Durance (France); Laboratoire Science des Procedes Ceramiques et de Traitements de Surface, UMR CNRS-Universite no. 6638, Batiment Chimie, 123 avenue Albert Thomas, 87060 Limoges (France); E-mail: damien.bregiroux@ccr.jussieu.fr; Belin, R. [DEN/DEC/SPUA, Commissariat a l' Energie Atomique, Cadarache, 13108 Saint Paul Lez Durance (France); Valenza, P. [DEN/DEC/SPUA, Commissariat a l' Energie Atomique, Cadarache, 13108 Saint Paul Lez Durance (France); Audubert, F. [DEN/DEC/SPUA, Commissariat a l' Energie Atomique, Cadarache, 13108 Saint Paul Lez Durance (France); Bernache-Assollant, D. [Ecole Nationale Superieure des Mines, 158 Cours Fauriel, 42023 Saint Etienne (France)

    2007-06-30

    High-temperature solid state syntheses of monazite powders containing plutonium (III), plutonium (IV) and americium (III) were performed. Resulting powders were characterized by X-ray diffraction. Pu{sup 3+}PO{sub 4} was readily obtained as a single phase by heating a Pu{sup 4+}O{sub 2}-NH{sub 4}H{sub 2}PO{sub 4} mixture under argon atmosphere. Traces of tetravalent plutonium phosphate Pu{sup 4+}P{sub 2}O{sub 7} were detected when synthesized under air atmosphere. The incorporation of (Pu{sup 4+},Ca{sup 2+}) in the monazite structure was investigated under air and argon atmosphere. We showed that Pu{sup 4+} is fully reduced in Pu{sup 3+} under argon atmosphere whereas, under air, the compound with the formula Pu{sub 0.4}{sup 3+}Pu{sub 0.3}{sup 4+}Ca{sub 0.3}{sup 2+}PO{sub 4} was obtained. Pure Am{sup 3+}PO{sub 4} was also synthesized under argon atmosphere. X-ray patterns revealed a complete amorphisation of the monazite structure at a relatively low cumulative alpha dose for {sup 241}AmPO{sub 4}.

  11. Mutual separation of americium(III) and europium(III) using glycolamic acid and thioglycolamic acid

    Energy Technology Data Exchange (ETDEWEB)

    Suneesh, A.S.; Venkatesan, K.A.; Syamala, K.V.; Antony, M.P.; Vasudeva Rao, P.R. [Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Fuel Chemistry Div.

    2012-07-01

    The extractants, bis(2-ethylhexyl)diglycolamicacid (HDEHDGA) and bis(2-ethylhexy)thiodiglycolamic acid (HDEHSDGA) were synthesized and characterized by {sup 1}H and {sup 13}C NMR, mass and IR spectroscopy. The extraction behaviour of {sup (152+154})Eu(III) and {sup 241}Am(III) from nitric acid medium by a solution of HDEHDGA (or HDEHSDGA) in n-dodecane (n-DD) was studied for the mutual separation of actinides and lanthanides. The effect of various parameters such as the pH, concentrations of HDEHDGA, HDEHSDGA, sodium nitrate, N,N,N',N'-tetrakis(2-pyridylmethyl)ethylenediamine (TPEN) and diethylenetriaminepentaacetic acid (DTPA) on the separation factor (SF) of americium(III) over europium(III) and vice versa was studied, and the conditions needed for the preferential separation were optimised. The results show that HDEHDGA exhibits higher extraction for {sup (152+154)}Eu(III) and HDEHSDGA shows the superior selectivity for {sup 241}Am(III). (orig.)

  12. Solution speciation of plutonium and Americium at an Australian legacy radioactive waste disposal site.

    Science.gov (United States)

    Ikeda-Ohno, Atsushi; Harrison, Jennifer J; Thiruvoth, Sangeeth; Wilsher, Kerry; Wong, Henri K Y; Johansen, Mathew P; Waite, T David; Payne, Timothy E

    2014-09-01

    During the 1960s, radioactive waste containing small amounts of plutonium (Pu) and americium (Am) was disposed in shallow trenches at the Little Forest Burial Ground (LFBG), located near the southern suburbs of Sydney, Australia. Because of periodic saturation and overflowing of the former disposal trenches, Pu and Am have been transferred from the buried wastes into the surrounding surface soils. The presence of readily detected amounts of Pu and Am in the trench waters provides a unique opportunity to study their aqueous speciation under environmentally relevant conditions. This study aims to comprehensively investigate the chemical speciation of Pu and Am in the trench water by combining fluoride coprecipitation, solvent extraction, particle size fractionation, and thermochemical modeling. The predominant oxidation states of dissolved Pu and Am species were found to be Pu(IV) and Am(III), and large proportions of both actinides (Pu, 97.7%; Am, 86.8%) were associated with mobile colloids in the submicron size range. On the basis of this information, possible management options are assessed.

  13. Phosphorylation of nucleophosmin at threonine 234/237 is associated with HCC metastasis.

    Science.gov (United States)

    Ching, Rachel Hiu Ha; Lau, Eunice Yuen Ting; Ling, Patrick Ming Tat; Lee, Joyce Man Fong; Ma, Mark Kin Fai; Cheng, Bowie Yik Ling; Lo, Regina Cheuk Lam; Ng, Irene Oi Lin; Lee, Terence Kin Wah

    2015-12-22

    Hepatocellular carcinoma (HCC) is frequently complicated by the occurrence of intrahepatic and extrahepatic metastases, leading to poor prognosis. To improve the prognosis for HCC patients, there is an urgent need to understand the molecular mechanisms of metastasis in HCC. Since protein Serine/Threonine phosphorylation emerges to be an important posttranslational modification critical in signaling process associated with cell proliferation, survival and metastasis, we employed a pair of primary tumor-derived and corresponding lung-metastatic counterparts (PLC/PRF/5-PT and PLC/PRF/5-LM) and aimed to identify these changes using CelluSpot Serine/Threonine kinase peptide array. Upon analysis, we found phosphorylated level of nucleophosmin (NPM) at Threonine 234/237 (p-NPM-Thr234/237) had remarkably high level in metastatic HCC cells (PLC-LM) than the corresponding primary HCC cell line (PLC-PT). Similar observation was observed in another match primary and their metastatic counterparts (MHCC-97L and MHCC-97H). By immunohistochemical staining, p-NPM-Thr234/237 was consistently found to be preferentially expressed in metastatic HCCs when compared with primary HCC in 28 HCC cases (p < 0.0001). By overexpressing Flag-tagged NPM and its phosphorylation site mutant (Thr234/237A) into low p-NPM-Thr234/237 expressing cells (Hep3B and Huh7) using a lentiviral based approach, we demonstrated that p-NPM-Thr234/237 is critical in invasion and migration of HCC cells, and this effect was mediated by cyclin-dependent kinase 1 (CDK1). Wild-type NPM was found to physically interact with a metastatic gene, ROCK2, and defective in Thr234/237 phosphorylation decreased its binding affinity, resulting in decrease in ROCK2 mediated signaling pathway. Identification of CDK1/p-NPM/ROCK2 signaling pathway provides a novel target for molecular therapy against HCC metastasis.

  14. Americium/Lanthanide Separations in Alkaline Solutions for Advanced Nuclear Fuel Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Goff, George S. [Los Alamos National Laboratory; Long, Kristy Marie [Los Alamos National Laboratory; Reilly, Sean D. [Los Alamos National Laboratory; Jarvinen, Gordon D. [Los Alamos National Laboratory; Runde, Wolfgang H. [Los Alamos National Laboratory

    2012-06-11

    Project goals: Can used nuclear fuel be partitioned by dissolution in alkaline aqueous solution to give a solution of uranium, neptunium, plutonium, americium and curium and a filterable solid containing nearly all of the lanthanide fission products and certain other fission products? What is the chemistry of Am/Cm/Ln in oxidative carbonate solutions? Can higher oxidation states of Am be stabilized and exploited? Conclusions: Am(VI) is kinetically stable in 0.5-2.0 M carbonate solutions for hours. Aliquat 336 in toluene has been successfully shown to extract U(VI) and Pu(VI) from carbonate solutions. (Stepanov et al 2011). Higher carbonate concentration gives lower D, SF{sub U/Eu} for = 4 in 1 M K{sub 2}CO{sub 3}. Experiments with Am(VI) were unsuccessful due to reduction by the organics. Multiple sources of reducing organics...more optimization. Reduction experiments of Am(VI) in dodecane/octanol/Aliquat 336 show that after 5 minutes of contact, only 30-40% of the Am(VI) has been reduced. Long enough to perform an extraction. Shorter contact times, lower T, and lower Aliquat 336 concentration still did not result in any significant extraction of Am. Anion exchange experiments using a strong base anion exchanger show uptake of U(VI) with minimal uptake of Nd(III). Experiments with Am(VI) indicate Am sorption with a Kd of 9 (10 minute contact) but sorption mechanism is not yet understood. SF{sub U/Nd} for = 7 and SF{sub U/Eu} for = 19 after 24 hours in 1 M K{sub 2}CO{sub 3}.

  15. Concentrations of plutonium and americium in plankton from the western Mediterranean Sea

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez-Cabeza, Joan-Albert; Merino, Juan; Masque, Pere [Insitut de Ciencia i Tecnologia Ambiental-Departament de Fisica, Universitat Autonoma de Barcelona, 08193 Bellaterra, Barcelona (Spain); Mitchell, Peter I.; Vintro, L. Leon [Department of Experimental Physics, University College Dublin, Dublin 4 (Ireland); Schell, William R. [Graduate School of Public Health, University of Pittsburgh, Pittsburgh, PA 15261 (United States); Cross, Lluisa; Calbet, Albert [Institut de Ciencies del Mar, Pg. Maritim Barceloneta, 37-49 08003, Barcelona (Spain)

    2003-07-20

    Understanding the transfer of radionuclides through the food chain leading to man and in particular, the uptake of transuranic nuclides by plankton, is basic to assess the potential radiological risk of the consumption of marine products by man. The main sources of transuranic elements in the Mediterranean Sea in the past were global fallout and the Palomares accident, although at present smaller amounts are released from nuclear establishments in the northwestern region. Plankton from the western Mediterranean Sea was collected and analyzed for plutonium and americium in order to study their biological uptake. The microplankton fractions accounted for approximately 50% of the total plutonium contents in particulate form. At Garrucha (Palomares area), microplankton showed much higher {sup 239,240}Pu activity, indicating the contamination with plutonium from the bottom sediments. Concentration factors were within the range of the values recommended by the International Atomic Energy Agency. Continental shelf mesoplankton was observed to efficiently concentrate transuranics. In open seawaters, concentrations were much lower. We speculate that sediments might play a role in the transfer of transuranics to mesoplankton in coastal waters, although we cannot discard that the difference in species composition may also play a role. In Palomares, both {sup 239,240}Pu and {sup 241}Am showed activities five times higher than the mean values observed in continental shelf mesoplankton. As the plutonium isotopic ratios in the contaminated sample were similar to those found in material related to the accident, the contamination was attributed to bomb debris from the Palomares accident. Concentration factors in mesoplankton were also in relatively good agreement with the ranges recommended by IAEA. In the Palomares station the highest concentration factor was observed in the sample that showed predominance of the dynoflagellate Ceratium spp. Mean values of the enrichment factors

  16. Role of ser-237 in the substrate specificity of the carbapenem-hydrolyzing class A beta-lactamase Sme-1.

    Science.gov (United States)

    Sougakoff, W; Naas, T; Nordmann, P; Collatz, E; Jarlier, V

    1999-08-17

    The role of the serine residue found at position 237 in the carbapenemase Sme-1 has been investigated by constructing a mutant in which Ser-237 was replaced by an alanine. The S237A mutant showed a catalytic behavior against penicillins and aztreonam very similar to that of Sme-1. By contrast, S237A was characterized by a reduced catalytic efficiency against cephems, such as cephalothin and cephaloridine. In addition, the weak activity of Sme-1 against the cephamycin cefoxitin was hardly detectable with the mutant enzyme. Finally, the Ser-237-->Ala mutation resulted in a marked decrease in catalytic activity against imipenem, showing that Ser-237 contributes to the carbapenemase activity of the class A beta-lactamase Sme-1.

  17. Half-life measurement of neutron-rich isotope 237Th

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    60 MeV/u 18O ions were used to bombard natural uranium targets, and the heavy neutron-rich isotope 237Th was produced via multi-nucleon transfer reaction and dissipative fragmentation of the heavy target. A relatively fast radiochcmical procedure was used to separate thorium from the mixture of uranium and complex reaction products. The chemically separated thorium fractions were studied by the γ-ray spectroscopic method. The behaviors of the growth and decay of 853.7 and 865.0 keV γ rays of 237pa decay were observed. Thc half-life of 237Th was determined to be 4.69±0.60 min.

  18. Analysis of Np-237 ENDF for the theortical interpretation of critical assembly experiments.

    Energy Technology Data Exchange (ETDEWEB)

    Mihaila, B. (Bogdan); Chadwick, M. B. (Mark B.); MacFarlane, R. E. (Robert E.); Kawano, T. (Toshihiko)

    2004-01-01

    We report on the present status of our effort toward an improved Np-237 evaluated nuclear data file (ENDF). The aim here is to bridge the gap between calculated and observed k-eff values, as measured at the Np-U critical assembly at LANL, TA-18. As such, we perform a critical analysis of the existing body of experimental data and recommended evaluations. We are targeting in principal the fission nu-bar and cross section in Np-237, as well as the inelastic scattering which is particularly important since Np-237 is a threshold fissioner. This analysis will be employed in a future sensitivity study of the calculated k-eff with respect to variations of the afore mentioned nuclear data.

  19. In situ characterization of uranium and americium oxide solid solution formation for CRMP process: first combination of in situ XRD and XANES measurements.

    Science.gov (United States)

    Caisso, Marie; Picart, Sébastien; Belin, Renaud C; Lebreton, Florent; Martin, Philippe M; Dardenne, Kathy; Rothe, Jörg; Neuville, Daniel R; Delahaye, Thibaud; Ayral, André

    2015-04-14

    Transmutation of americium in heterogeneous mode through the use of U1-xAmxO2±δ ceramic pellets, also known as Americium Bearing Blankets (AmBB), has become a major research axis. Nevertheless, in order to consider future large-scale deployment, the processes involved in AmBB fabrication have to minimize fine particle dissemination, due to the presence of americium, which considerably increases the risk of contamination. New synthesis routes avoiding the use of pulverulent precursors are thus currently under development, such as the Calcined Resin Microsphere Pelletization (CRMP) process. It is based on the use of weak-acid resin (WAR) microspheres as precursors, loaded with actinide cations. After two specific calcinations under controlled atmospheres, resin microspheres are converted into oxide microspheres composed of a monophasic U1-xAmxO2±δ phase. Understanding the different mechanisms during thermal conversion, that lead to the release of organic matter and the formation of a solid solution, appear essential. By combining in situ techniques such as XRD and XAS, it has become possible to identify the key temperatures for oxide formation, and the corresponding oxidation states taken by uranium and americium during mineralization. This paper thus presents the first results on the mineralization of (U,Am) loaded resin microspheres into a solid solution, through in situ XAS analysis correlated with HT-XRD.

  20. LIBS Spectral Data for a Mixed Actinide Fuel Pellet Containing Uranium, Plutonium, Neptunium and Americium

    Energy Technology Data Exchange (ETDEWEB)

    Judge, Elizabeth J. [Los Alamos National Laboratory; Berg, John M. [Los Alamos National Laboratory; Le, Loan A. [Los Alamos National Laboratory; Lopez, Leon N. [Los Alamos National Laboratory; Barefield, James E. [Los Alamos National Laboratory

    2012-06-18

    Laser-induced breakdown spectroscopy (LIBS) was used to analyze a mixed actinide fuel pellet containing 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2}. The preliminary data shown here is the first report of LIBS analysis of a mixed actinide fuel pellet, to the authors knowledge. The LIBS spectral data was acquired in a plutonium facility at Los Alamos National Laboratory where the sample was contained within a glove box. The initial installation of the glove box was not intended for complete ultraviolet (UV), visible (VIS) and near infrared (NIR) transmission, therefore the LIBS spectrum is truncated in the UV and NIR regions due to the optical transmission of the window port and filters that were installed. The optical collection of the emission from the LIBS plasma will be optimized in the future. However, the preliminary LIBS data acquired is worth reporting due to the uniqueness of the sample and spectral data. The analysis of several actinides in the presence of each other is an important feature of this analysis since traditional methods must chemically separate uranium, plutonium, neptunium, and americium prior to analysis. Due to the historic nature of the sample fuel pellet analyzed, the provided sample composition of 75% UO{sub 2}/20% PuO{sub 2}/3% AmO{sub 2}/2% NpO{sub 2} cannot be confirm without further analytical processing. Uranium, plutonium, and americium emission lines were abundant and easily assigned while neptunium was more difficult to identify. There may be several reasons for this observation, other than knowing the exact sample composition of the fuel pellet. First, the atomic emission wavelength resources for neptunium are limited and such techniques as hollow cathode discharge lamp have different dynamics than the plasma used in LIBS which results in different emission spectra. Secondly, due to the complex sample of four actinide elements, which all have very dense electronic energy levels, there may be reactions and

  1. 50 CFR 23.7 - What office do I contact for CITES information?

    Science.gov (United States)

    2010-10-01

    ... IMPORTATION OF WILDLIFE AND PLANTS (CONTINUED) CONVENTION ON INTERNATIONAL TRADE IN ENDANGERED SPECIES OF WILD FAUNA AND FLORA (CITES) Introduction § 23.7 What office do I contact for CITES information? Contact the... reservations (2) Information on the CoP (3) List of CITES species (4) Names and addresses of other...

  2. Reliable determination of 237Np in environmental solid samples using 242Pu as a potential tracer

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hou, Xiaolin; Roos, Per;

    2011-01-01

    onto various AG 1-type anion exchangers; suitability of 242Pu as a tracer for 237Np determination in environmental solid samples; and long-term chemical stability of tetravalent Np. Experimental results revealed that the degree of resin cross-linking has a significant influence on the separation...

  3. LOFT CIS analysis 4''-WH-237-E inside containment penetration S-17B

    Energy Technology Data Exchange (ETDEWEB)

    Nitzel, M.E.

    1978-10-30

    The stress analysis performed on the 4''-WH-237-E piping system inside containment penetration S-17B is presented. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject piping system will meet ASME Code, Section III, Class 2 requirements.

  4. 48 CFR 352.237-72 - Crime Control Act-requirement for background checks.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 4 2010-10-01 2010-10-01 false Crime Control Act... and Clauses 352.237-72 Crime Control Act—requirement for background checks. As prescribed in 337.103-70(c), the Contracting Officer shall insert the following clause: Crime Control Act of...

  5. 29 CFR 779.237 - Enterprise engaged in commerce or in the production of goods for commerce.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Enterprise engaged in commerce or in the production of goods for commerce. 779.237 Section 779.237 Labor Regulations Relating to Labor (Continued) WAGE AND... commerce or in the production of goods for commerce. Under section 3(s) the “enterprise” to be covered...

  6. Role of once-daily glycopyrronium bromide (NVA237 in the management of COPD

    Directory of Open Access Journals (Sweden)

    D’Urzo A

    2013-08-01

    Full Text Available Anthony D'UrzoDepartment of Family and Community Medicine, University of Toronto, Toronto, ON, CanadaAbstract: Progressive airflow limitation is a hallmark feature of chronic obstructive pulmonary disease (COPD that ultimately leads to breathlessness, impaired quality of life, and reduced exercise capacity. Pharmacotherapy is used in patients with COPD to prevent and control symptoms, reduce both the frequency and severity of exacerbations, improve health status, and increase exercise tolerance. These strategies are intended to address management issues which promote both current disease control and a reduction in the risk of disease deterioration in the future. At the present time, long-acting β2-agonists (LABAs and long-acting muscarinic antagonists (LAMAs are available for maintenance therapy in patients with persistent symptoms. Tiotropium was the first LAMA to be approved for management of COPD, and many studies have described its beneficial effects on multiple clinically relevant outcomes. Glycopyrronium bromide (NVA237, a new LAMA, has been developed and received regulatory approval for management of COPD in a number of countries around the world. Results from pivotal Phase III trials suggest that NVA237 is safe and well tolerated in patients with moderate to severe COPD, and provides rapid and sustained improvements in lung function. Further, these changes are associated with statistically and clinically meaningful improvements in dyspnea, health-related quality of life, and exercise tolerance. Treatment with NVA237 also results in a significant reduction in risk of exacerbations and the need for rescue medication, and has been comparable with tiotropium with respect to safety and efficacy outcomes. Finally, emerging data indicate that NVA237 is efficacious both as monotherapy and in combination with indacaterol.Keywords: glycopyrronium bromide, NVA237, chronic obstructive pulmonary disease, inhaled long-acting bronchodilators

  7. The clinical pathological analysis of the 237 cases of the renal biopsy%237例肾组织活检的临床病理分析

    Institute of Scientific and Technical Information of China (English)

    黄芬芬; 谢小行

    2011-01-01

    Objective: Retrospective analysis of 237 cases of renal biopsy and pathological types and clinical characteristics, relationship between the two. Methods: 237 renal biopsy patients in routine clinical features, immunopathology, light microscopy, electron microscopy of changes made pathological diagnosis. Results: The primary glomerular disease accounted for 78.1 %, mainly IgA nephropathy, mesangial proliferative glomerulone-phritis, membranous nephropathy, minimal change disease and so on. Secondary glomerulonephritis, 19.8%, mainly lupus nephritis, purpura nephritis. The average age of onset was 37. 12 years. Discussion. Primary is the more common type of kidney disease, IgA nephropathy is the main, secondary nephropathy, lupus nephritis based. The majority of patients with chronic nephritis syndrome presents a variety of pathological manifestations. Renal biopsy is of great significance.%目的:旨在通过回顾分析237例肾活检的病理类型与临床诊断,对两者的相关性进行研究总结.方法:分析237例行肾活检病人的临床诊断、免疫病理、光镜、电镜的改变,做出病理诊断.结果:原发性肾小球疾病占78.1%,主是IgA肾病、系膜增生性肾小球肾炎、膜性肾病、微小病变等.继发性肾小球肾炎占19.8%,主是狼疮性肾炎、紫疲性肾炎等.发病年龄平均为37.12岁.讨论:原发性肾病是较常见的类型,以IgA肾病为主,继发性肾病则以狼疮性肾炎为主;绝大多数的慢性肾炎综合征患者的病理表现呈现出多样化的特征,这使得肾活检意义重大.

  8. (237)Np(n,f) Cross Section: New Data and Present Status

    CERN Document Server

    Paradela, C; Carrapico, C; Eleftheriadis, C; Leeb, H; Calvino, F; Herrera-Martinez, A; Savvidis, I; Vlachoudis, V; Haas, B; Vannini, G; Le Naour, C; Gramegna, F; Wiescher, M; Pigni, M T; Audouin, L; Mengoni, A; Quesada, J; Becvar, F; Plag, R; Cennini, P; Mosconi, M; Duran, I; Rauscher, T; Couture, A; Capote, R; Sarchiapone, L; Vlastou, R; Domingo-Pardo, C; Dillmann, I; Pavlopoulos, P; Karamanis, D; Krticka, M; Jericha, E; Ferrari, A; Martinez, T; Trubert, D; Oberhummer, H; Karadimos, D; Plompen, A; Isaev, S; Terlizzi, R; Kaeppeler, F; Cortes, G; Cox, J; Voss, F; Pretel, C; Colonna, N; Berthoumieux, E; Vaz, P; Heil, M; Lopes, I; Lampoudis, C; Walter, S; Calviani, M; Gonzalez-Romero, E; Embid-Segura, M; Stephan, C; Igashira, M; Papachristodoulou, C; Aerts, G; Tavora, L; Berthier, B; Rudolf, G; Andrzejewski, J; Villamarin, D; Ferreira-Marques, R; Tain, J L; O'Brien, S; Gunsing, F; Reifarth, R; Perrot, L; Lindote, A; Neves, F; Poch, A; Kerveno, M; Rubbia, C; Koehler, P; Dahlfors, M; Wisshak, K; Salgado, J; Dridi, W; Ventura, A; Andriamonje, S; Assimakopoulos, P; Santos, C; Ferrant, L; Lozano, M; Patronis, N; Chiaveri, E; Guerrero, C; Kadi, Y; Vicente, M C; Praena, J; Baumann, P; Oshima, M; Rullhusen, P; Furman, W; David, S; Marrone, S; Tassan-Got, L; Cano-Ott, D; Pavlix, A; Alvarez-Velarde, F; Massimi, C; Mastinu, P; Pancin, J; Papadopoulos, C; Tagliente, G; Haight, R; Chepel, V; Kossionides, E; Badurek, G; Marganiec, J; Lukic, S; Tarrio, D; Alvarez, H

    2011-01-01

    In this document, we present the final result obtained at the n_TOF experiment; for the neutron-induced fission cross section of the (237)Np, from the fission threshold up to 1 GeV. The method applied to get tins result is briefly discussed. n_TOF data are compared to the last experimental measurements using other TOF facilities or the surrogate method, reported experiments performed with monoenergetic sources and the FISCAL systematic, including a discussion about the existing discrepancies.

  9. Neutronic Study of Burnup, Radiotoxicity, Decay Heat and Basic Safety Parameters of Mono-Recycling of Americium in French Pressurised Water Reactors

    Directory of Open Access Journals (Sweden)

    Robert Bright Mawuko Sogbadji

    2017-03-01

    Full Text Available The reprocessing of actinides with long half-life has been non-existent except for plutonium (Pu. This work looks at reducing the actinides inventory nuclear fuel waste meant for permanent disposal. The uranium oxide fuel (UOX assembly, as in the open cycle system, was designed to reach a burnup of 46GWd/T and 68GWd/T using the MURE code. The MURE code is based on the coupling of a static Monte Carlo code and the calculation of the evolution of the fuel during irradiation and cooling periods. The MURE code has been used to address two different questions concerning the mono-recycling of americium (Am in present French pressurised water reactors (PWR. These are reduction of americium in the clear fuel cycle and the safe quantity of americium that can be introduced into mixed oxide (MOX as fuel. The spent UOX was reprocessed to fabricate MOX assemblies, by the extraction of plutonium and addition of depleted uranium to reach burnups of 46GWd/T and 68GWd/T, taking into account various cooling times of the spent UOX assembly in the repository. The effect of cooling time on burnup and radiotoxicity was then ascertained. After 30 years of cooling in the repository, the spent UOX fuel required a higher concentration of Pu to be reprocessed into MOX fuel due to the decay of Pu-241. Americium, with a mean half-life of 432 years, has a high radiotoxicity level, high mid-term residual heat and is a precursor for other long-lived isotopes. An innovative strategy would be to reprocess not only the plutonium from the UOX spent fuel but also the americium isotopes, which presently dominate the radiotoxicity of waste. The mono-recycling of Am is not a definitive solution because the once-through MOX cycle transmutation of Am in a PWR is not enough to destroy all americium. The main objective is to propose a ‘waiting strategy’ for both Am and Pu in the spent fuel so that they can be made available for further transmutation strategies. The MOX and

  10. THE FIRST ISOLATION OF AMERICIUM IN THE FORM OF PURE COMPOUNDS - THE SPECIFIC ALPHA-ACTIVITY AND HALF-LIFE OF Am241

    Energy Technology Data Exchange (ETDEWEB)

    Cunningham, B.B.; Asprey, L.B.

    1950-07-20

    The microgram scale isolation and preparation of pure compounds of americium is described. Data are presented to show that the alpha-half-life of the isotope Am{sup 241} is 490 {+-} 14 years. The absorption spectrum of Am(III) in 1M nitric acid in the range 3500-8000 mu is given. The wave lengths of 10 of the most prominent lines in the copper spark emission spectrum of americium are given to the nearest 0.01 {angstrom}. Evidence is presented to show that the potential for the Am(III)-Am(IV) couple in acid solution is more negative than -2v and that the potential for the Am(II)-Am(III) couple is more positive than +0.9v.

  11. 'n Nota oor die vertaling van Jeremia 2:37 ("Met jou hande op jou hoof"

    Directory of Open Access Journals (Sweden)

    H.F. Stander

    1998-08-01

    Full Text Available A note on the translation of Jeremiah 2:37 ("With your hands on your head" In Jeremiah 2:37 God says to Israel: "You will leave that place (= Egypt with your hands upon your head". In this article various Bible translations and commentaries are scrutinized to determine how modem exegetes interpret this phrase. Thereafter the author discusses Egyptian depictions of mourners in funeral processions with their hands on their heads. He shows how an exploration of Egyptian Art can contribute to a better understanding of Jeremiah 2:37. This study also shows that the two dynamic Afrikaans translations of the Bible ("Die Lewende Bybel" and "Die Nuwe Afrikaanse Vertaling" are wide off the mark in their interpretation of the phrase "with your hands on your head". The author also argues that exegetes should not only rely on written texts when they study the ancient world in which the Scriptures originated, but that they should also explore works of art.

  12. Nuclear Resonance Fluorescence Measurements on ^237Np for Security and Safeguards Applications

    Science.gov (United States)

    Angell, C. T.; Joshi, T.; Yee, Ryan; Norman, E. B.; Kulp, W. D.; Warren, G. A.; Korbly, S.; Klimenko, A.; Wilson, C.; Copping, R.; Shuh, D. K.

    2009-10-01

    The smuggling of nuclear material and the diversion of fissile material for covert weapon programs both present grave risks to world security. Methods are needed to detect nuclear material smuggled in cargo, and for proper material accountability in civilian fuel re-processing facilities. Nuclear resonance fluorescence (NRF) is a technique that can address both needs. It is a non-destructive active interrogation method that provides isotope-specific information. It works by using a γ-ray beam to resonantly excite levels in a nucleus and observing the γ-rays emitted whose energy and intensity are characteristic of that isotope. ^237Np presents significant safeguard challenges; it is fissile yet currently has fewer safeguard restrictions. NRF measurements on ^237Np will expand the nuclear database and will permit designing interrogation and assay systems. Measurements were made using the bremsstrahlung beam at the HVRL at MIT on a 7 g target of ^237Np with two incident electron energies of 2.8 and 3.1 MeV. Results will be presented with discussion of the relevant nuclear structure necessary to predict levels in other actinides.

  13. 237例早产相关因素的临床分析%Clinical Analysis on 237 Cases of Premature Labour

    Institute of Scientific and Technical Information of China (English)

    崔蓉; 王蕾

    2012-01-01

    Objective To analyze the dangerous factors associated with premature labor and the etiology of death in premature infants. Methods The clinical data of 237 patients with premature labour in oar hospital from January 1 ,2009 to December 3 ] ,2010 were analyzed and compared to that of 237 randomly selected cases with full term deliver. Also, neonatal asphyxia and neonatal death rate of the control group and the cases of 28 - 31+6 weeks gestation,32 - 34*' weeks gestation and 35 - 36 +6 weeks gestation were compared. Results The preceding causes of premature labour were spontaneous of premature labour for unexplained causes,premature rupture of membrane,pre-eclampsia,multiple pregnancy and pre-partum hemorrhage. It was related with premature labour that pregnant woman didn' t accept prenatal examination. -Significant difference was shown in the neonatal asphyxia and neon ale death rate between the two groups( P < 0.01). Conclusion The course of premature labour is complicated. The key issue to reduce the incidence of premature labour is to pay more attentions to the perinatal care, prevention of complications of pregnancy. Also, premature labour is the main causation of disease and death in infants. An intensive attention paid to the factors of premature labor and implementation of corresponding measures can decrease the complication and mortality in infants.%目的 分析研究早产有关的危险因素及早产儿发病及死亡的相关因素.方法 对2009年1月1 日-2010年12月31日住院分娩237例早产患者的临床资料进行回顾性分析,并随机抽取足月分娩的237例进行相关对照.比较孕28 ~31+6、32 ~34+6、35~36 +6周和足月孕龄新生儿窒息和新生儿死亡的差异.结果 不明原因早产,胎膜早破,重度子痫前期,多胎妊娠,产前出血为早产原因的前5位;早产还与孕期母亲未做产前检查相关.早产与对照组新生儿窒息和死亡发生率差异有统计学意义(P<0.01).结论 早

  14. Concordant plutonium-241-americium-241 dating of environmental samples: results from forest fire ash

    Energy Technology Data Exchange (ETDEWEB)

    Goldstein, Steven J [Los Alamos National Laboratory; Oldham, Warren J [Los Alamos National Laboratory; Murrell, Michael T [Los Alamos National Laboratory; Katzman, Danny [Los Alamos National Laboratory

    2010-12-07

    We have measured the Pu, {sup 237}Np, {sup 241}Am, and {sup 151}Sm isotopic systematics for a set of forest fire ash samples from various locations in the western U.S. including Montana, Wyoming, Idaho, and New Mexico. The goal of this study is to develop a concordant {sup 241}Pu (t{sub 1/2} = 14.4 y)-{sup 241}Am dating method for environmental collections. Environmental samples often contain mixtures of components including global fallout. There are a number of approaches for subtracting the global fallout component for such samples. One approach is to use {sup 242}/{sup 239}Pu as a normalizing isotope ratio in a three-isotope plot, where this ratio for the nonglobal fallout component can be estimated or assumed to be small. This study investigates a new, complementary method of normalization using the long-lived fission product, {sup 151}Sm (t{sub 1/2} = 90 y). We find that forest fire ash concentrates actinides and fission products with {approx}1E10 atoms {sup 239}Pu/g and {approx}1E8 atoms {sup 151}Sm/g, allowing us to measure these nuclides by mass spectrometric (MIC-TIMS) and radiometric (liquid scintillation counting) methods. The forest fire ash samples are characterized by a western U.S. regional isotopic signature representing varying mixtures of global fallout with a local component from atmospheric testing of nuclear weapons at the Nevada Test Site (NTS). Our results also show that {sup 151}Sm is well correlated with the Pu nuclides in the forest fire ash, suggesting that these nuclides have similar geochemical behavior in the environment. Results of this correlation indicate that the {sup 151}Sm/{sup 239}Pu atom ratio for global fallout is {approx}0.164, in agreement with an independent estimate of 0.165 based on {sup 137}Cs fission yields for atmospheric weapons tests at the NTS. {sup 241}Pu-{sup 241}Am dating of the non-global fallout component in the forest fire ash samples yield ages in the late 1950's-early 1960's, consistent with a peak

  15. Intramolecular sensitization of americium luminescence in solution: shining light on short-lived forbidden 5f transitions.

    Science.gov (United States)

    Sturzbecher-Hoehne, M; Yang, P; D'Aléo, A; Abergel, R J

    2016-06-14

    The photophysical properties and solution thermodynamics of water soluble trivalent americium (Am(III)) complexes formed with multidentate chromophore-bearing ligands, 3,4,3-LI(1,2-HOPO), Enterobactin, and 5-LIO(Me-3,2-HOPO), were investigated. The three chelators were shown to act as antenna chromophores for Am(III), generating sensitized luminescence emission from the metal upon complexation, with very short lifetimes ranging from 33 to 42 ns and low luminescence quantum yields (10(-3) to 10(-2)%), characteristic of Near Infra-Red emitters in similar systems. The specific emission peak of Am(III) assigned to the (5)D1 → (7)F1 f-f transition was exploited to characterize the high proton-independent stability of the complex formed with the most efficient sensitizer 3,4,3-LI(1,2-HOPO), with a log β110 = 20.4 ± 0.2 value. In addition, the optical and solution thermodynamic features of these Am(III) complexes, combined with density functional theory calculations, were used to probe the influence of electronic structure on coordination properties across the f-element series and to gain insight into ligand field effects.

  16. Response of avalanche photo-diodes of the CMS Electromagnetic Calorimeter to neutrons from an Americium-Beryllium source.

    CERN Document Server

    Deiters, Konrad; Renker, Dieter

    2010-01-01

    The response of avalanche photo-diodes (APDs) used in the CMS Electromagnetic Calorimeter to low energy neutrons from an Americium-Beryllium source is reported. Signals due to recoil protons from neutron interactions with the hydrogen nuclei in the protective epoxy layer, mainly close to the silicon surface of the APD, have been identified. These signals increase in size with the applied bias voltage more slowly than the nominal gain of the APDs, and appear to have a substantially lower effective gain at the operating voltage. The signals originating from interactions in the epoxy are mostly equivalent to signals of a few GeV in CMS, but range up to a few tens of GeV equivalent. There are also signals not attributed to reactions in the epoxy extending up to the end of the range of these measurements, a few hundreds of GeV equivalent. Signals from the x-rays from the source can also be in the GeV equivalent scale in CMS. Simulations used to describe events due to particle interactions in the APDs need to take ...

  17. Nano-cerium vanadate: a novel inorganic ion exchanger for removal of americium and uranium from simulated aqueous nuclear waste.

    Science.gov (United States)

    Banerjee, Chayan; Dudwadkar, Nilesh; Tripathi, Subhash Chandra; Gandhi, Pritam Maniklal; Grover, Vinita; Kaushik, Chetan Prakash; Tyagi, Avesh Kumar

    2014-09-15

    Cerium vanadate nanopowders were synthesized by a facile low temperature co-precipitation method. The product was characterized by X-ray diffraction and transmission electron microscopy and found to consist of ∼25 nm spherical nanoparticles. The efficiency of these nanopowders for uptake of alpha-emitting radionuclides (233)U (4.82 MeV α) and (241)Am (5.49 MeV α, 60 keV γ) has been investigated. Thermodynamically and kinetically favorable uptake of these radionuclides resulted in their complete removal within 3h from aqueous acidic feed solutions. The uptake capacity was observed to increase with increase in pH as the zeta potential value decreased with the increase in pH but effect of ionic strength was insignificant. Little influence of the ions like Sr(2+), Ru(3+), Fe(3+), etc., in the uptake process indicated CeVO4 nanopowders to be amenable for practical applications. The isotherms indicated predominant uptake of the radioactive metal ions in the solid phase of the exchanger at lower feed concentrations and linear Kielland plots with positive slopes indicated favorable exchange of the metal ions with the nanopowder. Performance comparison with the other sorbents reported indicated excellent potential of nano-cerium vanadate for removing americium and uranium from large volumes of aqueous acidic solutions.

  18. RAPID SEPARATION METHOD FOR 237NP AND PU ISOTOPES IN LARGE SOIL SAMPLES

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S.; Culligan, B.; Noyes, G.

    2010-07-26

    A new rapid method for the determination of {sup 237}Np and Pu isotopes in soil and sediment samples has been developed at the Savannah River Site Environmental Lab (Aiken, SC, USA) that can be used for large soil samples. The new soil method utilizes an acid leaching method, iron/titanium hydroxide precipitation, a lanthanum fluoride soil matrix removal step, and a rapid column separation process with TEVA Resin. The large soil matrix is removed easily and rapidly using this two simple precipitations with high chemical recoveries and effective removal of interferences. Vacuum box technology and rapid flow rates are used to reduce analytical time.

  19. Deducing the 237U(n,f) cross-section using the Surrogate Ratio Method

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J T; Bernstein, L A; Escher, J; Ahle, L; Church, J A; Dietrich, F S; Moody, K J; Norman, E B; Phair, L; Fallon, P; Clark, R M; Deleplanque, M A; Descovich, M; Cromaz, M; Lee, I Y; Macchiavelli, A O; McMahan, M A; Moretto, L G; Rodriguez-Vieitez, E; Stephens, F S; Ai, H; Beausang, C; Cridder, B

    2005-12-29

    The authors have deduced the cross section for {sup 237}U(n,f) over an equivalent neutron energy range from 0 to 20 MeV using the Surrogate Ratio method. A 55 MeV {sup 4}He beam from the 88 Inch Cyclotron at Lawrence Berkeley National Laboratory was used to induce fission in the following reactions: {sup 238}U({alpha},{alpha}{prime}f) and {sup 236}U({alpha},{alpha}{prime}f). The {sup 238}U reaction was a surrogate for {sup 237}U(n,f) and the {sup 236}U reaction was used as a surrogate for {sup 235}U(n,f). Scattered alpha particles were detected in a fully depleted segmented silicon telescope array (STARS) over an angle range of 35{sup o} to 60{sup o} with respect to the beam axis. The fission fragments were detected in a third independent silicon detector located at backward angles between 106{sup o} and 131{sup o}.

  20. Deducing the 237U(n,f) cross-section using the Surrogate Ratio Method

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J T; Bernstein, L A; Escher, J; Ahle, L; Church, J A; Dietrich, F; Moody, K J; Norman, E B; Phair, L W; Fallon, P; Clark, R; Delaplanque, M; Descovich, M; Cromaz, M; Lee, I Y; Macchiavelli, A O; McMahan, M A; Moretto, L G; Rodriguez-Vieitez, E; Stephens, F S

    2005-08-16

    The authors have deduced the {sup 237}U(n,f) cross-section over an equivalent neutron energy range of 0 to 20 MeV using the Surrogate Ratio method. A 55 MeV {sup 4}He{sup 2+} beam from the 88 Inch Cyclotron at Lawrence Berkeley National Laboratory was used to induce fission in the following reactions {sup 238}U({alpha},{alpha}'f) and {sup 236}U({alpha},{alpha}'f). The {sup 238}U reaction was a surrogate for {sup 237}U(n,f) and the {sup 236}U reaction was used as a surrogate for {sup 235}U(n,f). The energies of the scattered alpha particles were detected in a fully depleted segmented silicon telescope array (STARS) over an angle range of 35{sup o} to 60{sup o} with respect to the beam axis. The fission fragments were detected in a third independent silicon detector located at backward angles between 106{sup o} to 131{sup o}.

  1. Multi-wavelength study of the star-formation in the S237 H II region

    CERN Document Server

    Dewangan, L K; Zinchenko, I; Janardhan, P; Luna, A

    2016-01-01

    We present a detailed multi-wavelength study of observations from X-ray, near-infrared to centimeter wavelengths to probe the star formation processes in the S237 region. Multi-wavelength images trace an almost sphere-like shell morphology of the region, which is filled with the 0.5--2 keV X-ray emission. The region contains two distinct environments - a bell-shaped cavity-like structure containing the peak of 1.4 GHz emission at center, and elongated filamentary features without any radio detection at edges of the sphere-like shell - where {\\it Herschel} clumps are detected. Using the 1.4 GHz continuum and $^{12}$CO line data, the S237 region is found to be excited by a radio spectral type of B0.5V star and is associated with an expanding H{\\sc ii} region. The photoionized gas appears to be responsible for the origin of the bell-shaped structure. The majority of molecular gas is distributed toward a massive {\\it Herschel} clump (M$_{clump}$ $\\sim$260 M$_{\\odot}$), which contains the filamentary features and ...

  2. Determination by gamma-ray spectrometry of the plutonium and americium content of the Pu/Am separation scraps. Application to molten salts; Determination par spectrometrie gamma de la teneur en plutonium et en americium de produits issus de separation Pu/Am. Application aux bains de sels

    Energy Technology Data Exchange (ETDEWEB)

    Godot, A. [CEA Valduc, Dept. de Traitement des Materiaux Nucleaires, 21 - Is-sur-Tille (France); Perot, B. [CEA Cadarache, Dept. de Technologie Nucleaire, Service de Modelisation des Transferts et Mesures Nucleaires, 13 - Saint-Paul-lez-Durance (France)

    2005-07-01

    Within the framework of plutonium recycling operations in CEA Valduc (France), americium is extracted from molten plutonium metal into a molten salt during an electrolysis process. The scraps (spent salt, cathode, and crucible) contain extracted americium and a part of plutonium. Nuclear material management requires a very accurate determination of the plutonium content. Gamma-ray spectroscopy is performed on Molten Salt Extraction (MSE) scraps located inside the glove box, in order to assess the plutonium and americium contents. The measurement accuracy is influenced by the device geometry, nuclear instrumentation, screens located between the sample and the detector, counting statistics and matrix attenuation, self-absorption within the spent salt being very important. The purpose of this study is to validate the 'infinite energy extrapolation' method employed to correct for self-attenuation, and to detect any potential bias. We present a numerical study performed with the MCNP computer code to identify the most influential parameters and some suggestions to improve the measurement accuracy. A final uncertainty of approximately 40% is achieved on the plutonium mass. (authors)

  3. Transfer across the human gut of environmental plutonium, americium, cobalt, caesium and technetium: studies with cockles (Cerastoderma edule) from the Irish Sea.

    Science.gov (United States)

    Hunt, G J

    1998-06-01

    Our previous studies have indicated lower values of the gut transfer factor ('f1 values') for plutonium and americium in winkles (Littorina littorea) than adopted by ICRP. The present study was undertaken primarily to investigate whether this observation extends to other species. Samples of cockles (Carastoderma edule) from Ravenglass, Cumbria were eaten by volunteers who provided 24 h samples of urine and faeces. Urine samples indicated f1 values for cockles which were higher than for winkles; for plutonium these ranged overall up to 7 x 10(-4) with an arithmetic mean in the range (2-3) x 10(-4), and for americium up to 2.6 x 10(-4) with an arithmetic mean of 1.2 x 10(-4). Limited data based on volunteers eating cockles from the Solway suggest that f1 values for americium may be greater at distance from Sellafield. The measured values compare with 5 x 10(-4) used by the ICRP for environmental forms of both elements, which would appear to provide adequate protection when calculating doses from Cumbrian cockles. Data for other nuclides were obtained by analysing faecal samples from the volunteers who ate the Ravenglass cockles. Cobalt-60 showed an f1 value in the region of 0.2, twice the value currently used by ICRP. For 137Cs, variabilities were indicated in the range 0.08 to 0.43, within the ICRP value of f1 = 1.0. Technetium-99 gave f1 values up to about 0.6, in reasonable conformity with the ICRP value of 0.5.

  4. Transfer across the human gut of environmental plutonium, americium, cobalt, caesium and technetium: studies with cockles (Cerastoderma edule) from the Irish Sea

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, G.J. [CEFAS Laboratory, Lowestoft, Suffolk NR33 0HT (United Kingdom)

    1998-06-01

    Our previous studies have indicated lower values of the gut transfer factor ('f{sub L} values') for plutonium and americium in winkles (Littorina littorea) than adopted by ICRP. The present study was undertaken primarily to investigate whether this observation extends to other species. Samples of cockles (Cerastoderma edule) from Ravenglass, Cumbria were eaten by volunteers who provided 24 samples of urine and faeces. Urine samples indicated f{sub L} values for cockles which were higher than for winkles; for plutonium these ranged overall up to 7x10{sup -4} with an arithmetic mean in the range (2-3)x10{sup -4}, and for americium up to 2.6x10{sup -4} with an arithmetic mean of 1.2x10{sup -4}. Limited data based on volunteers eating cockles from the Solway suggest that f{sub L} values for americium may be greater at distance from Sellafield. The measured values compare with 5x10{sup -4} used by the ICRP for environmental forms of both elements, which would appear to provide adequate protection when calculating doses from Cumbrian cockles. Data for other nuclides were obtained by analysing faecal samples from the volunteers who ate the Ravenglass cockles. Cobalt-60 showed an f{sub L} value in the region of 0.2, twice the value currently used by ICRP. For {sup 137}Cs, variabilities were indicated in the range 0.08 to 0.43, within the ICRP value of f{sub L}=1.0. Technetium-99 gave f{sub L} values up to about 0.6, in reasonable conformity with the ICRP value of 0.5. (author)

  5. Nano-cerium vanadate: A novel inorganic ion exchanger for removal of americium and uranium from simulated aqueous nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Chayan; Dudwadkar, Nilesh [Fuel Reprocessing Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Tripathi, Subhash Chandra, E-mail: sctri001@gmail.com [Fuel Reprocessing Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Gandhi, Pritam Maniklal [Fuel Reprocessing Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Grover, Vinita [Waste Management Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Kaushik, Chetan Prakash [Chemistry Division, Bhabha Atomic Research Centre, Mumbai 400085 (India); Tyagi, Avesh Kumar, E-mail: aktyagi@barc.gov.in [Waste Management Division, Bhabha Atomic Research Centre, Mumbai 400085 (India)

    2014-09-15

    Highlights: • Template free, low temperature synthesis of CeVO{sub 4} nanopowders. • Thermodynamically and kinetically favourable uptake of Am(III) and U(VI) exhibited. • K{sub d} and ΔG° values for Am(III) and U(VI) uptake in pH 1–6 are reported. • Interdiffusion coefficients and zeta potential values in pH 1–6 are reported. • Possible application in low level aqueous nuclear waste remediation. - Abstract: Cerium vanadate nanopowders were synthesized by a facile low temperature co-precipitation method. The product was characterized by X-ray diffraction and transmission electron microscopy and found to consist of ∼25 nm spherical nanoparticles. The efficiency of these nanopowders for uptake of alpha-emitting radionuclides {sup 233}U (4.82 MeV α) and {sup 241}Am (5.49 MeV α, 60 keV γ) has been investigated. Thermodynamically and kinetically favorable uptake of these radionuclides resulted in their complete removal within 3 h from aqueous acidic feed solutions. The uptake capacity was observed to increase with increase in pH as the zeta potential value decreased with the increase in pH but effect of ionic strength was insignificant. Little influence of the ions like Sr{sup 2+}, Ru{sup 3+}, Fe{sup 3+}, etc., in the uptake process indicated CeVO{sub 4} nanopowders to be amenable for practical applications. The isotherms indicated predominant uptake of the radioactive metal ions in the solid phase of the exchanger at lower feed concentrations and linear Kielland plots with positive slopes indicated favorable exchange of the metal ions with the nanopowder. Performance comparison with the other sorbents reported indicated excellent potential of nano-cerium vanadate for removing americium and uranium from large volumes of aqueous acidic solutions.

  6. Plutonium, americium and radiocaesium in the marine environment close to the Vandellos I nuclear power plant before decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Sanchez-Cabeza, J.A. E-mail: joanalbert.sanchez@uab.es; Molero, J

    2000-11-01

    The Vandellos nuclear power plant (NPP), releasing low-level radioactive liquid waste to the Mediterranean Sea, is the first to be decommissioned in Spain, after an incident which occurred in 1989. The presence, distribution and uptake of various artificial radionuclides (radiocaesium, plutonium and americium) in the environment close to the plant were studied in seawater, bottom sediments and biota, including Posidonia oceanica, fish, crustaceans and molluscs. Seawater, sediments and Posidonia oceanica showed enhanced levels in the close vicinity of the NPP, although the effect was restricted to its near environment. Maximum concentrations in seawater were 11.6{+-}0.5 Bq m{sup -3} and 16.9{+-}1.2 mBq m{sup -3} for {sup 137}Cs and {sup 239,240}Pu, respectively. When sediment concentrations were normalized to excess {sup 210}Pb, they showed both the short-distance transport of artificial radionuclides from the Vandellos plant and the long-distance transport of {sup 137}Cs from the Asco NPP. Posidonia oceanica showed the presence of various gamma-emitters attributed to the impact of the Chernobyl accident, on which the effect of the NPP was superimposed. Seawater, sediment and Posidonia oceanica collected near the plant also showed an enhancement of the plutonium isotopic ratio above the fallout value. The uptake of these radionuclides by marine organisms was detectable but limited. Pelagic fish showed relatively higher {sup 137}Cs concentrations and only in the case of demersal fish was the plutonium isotopic ratio increased. The reported levels constitute a set of baseline values against which the impact of the decommissioning operations of the Vandellos I NPP can be studied.

  7. Moessbauer Spectroscopic Studies of {sup 237}Np in frozen nitric acid solution

    Energy Technology Data Exchange (ETDEWEB)

    Nakada, M; Wang, J; Kitazawa, T; Takahashi, M; Takeda, M; Masaki, N M; Yamashita, T [Department of Materials Science, Japan Atomic Energy Research Institute (JAERI, present JAEA: Japan Atomic Energy Agency), Tokai, Naka, Ibaraki 319-1195 (Japan); Tsutsui, S, E-mail: wangjh@dicp.ac.c [Advanced Science Research Center, JAERI, Tokai, Naka, Ibaraki 319-1195 (Japan)

    2010-03-01

    We applied Moessbauer spectroscopy to {sup 237}Np in nitric acid solutions to study chemical states. Sample solutions were adjusted to 50 mg/ml of Np(V) and Np(VI) concentration in 0.6 M nitric acid solutions. These solutions were put into original designed containers for samples and mounted to sample holders. The values of isomer shift (IS, relative to NpAl{sub 2}) of Np(V) and Np(VI) in 0.6 M nitric acid were -17.4(1) and -37.2(3) mm/s at about 10 K, respectively. It was found that Np(V) had 7 coordination number and Np(VI) had 8 in nitric acid solutions from values of IS.

  8. Identification of Nilsson orbitals in the superdeformed minimum of {sup 237}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, Thomas James

    2008-03-31

    In this thesis, a spectroscopy experiment in the second minimum of the double humped fission barrier of {sup 237}Pu is presented, in which, for the first time, single - particle states for a neutron - rich shape isomer with odd neutron number were identified and characterised by their Nilsson quantum numbers. While rotational ({sup 236f}U and {sup 240f}Pu) and vibrational excitations ({sup 240f}Pu) had already been identified earlier in the even-even neighbouring nuclei, now the fission isomers in {sup 237}Pu (t{sub 1/2}=115 ns/1.12 {mu}s) were investigated in a {gamma}-spectroscopy experiment at the Cologne Tandem accelerator. Using the {sup 235}U({alpha},2n) reaction with a pulsed R beam, states in the second minimum were populated. Following the prompt decay of excited states into the ground states of the two shape isomers, the nucleus decays with its halflife, the resulting fission fragments were detected in a specially built 4{pi} parallel plate detector. The extremely rare isomeric {gamma} decays were measured in coincidence with the fission fragments using the highly efficient MINIBALL spectrometer. The background-subtracted {gamma}-ray spectrum was disentangled into contributions from the two shape isomers and 9 excited rotational bands were identified built on the ground states of the two isomers. The ground state spins of the two shape isomers were determined to be I=5/2 (115 ns isomer) and I=9/2 (1120 ns isomer). From the 149 identified {gamma} transitions, independent level schemes were constructed for the two fission isomers in {sup 237}Pu. The consistency of these level schemes was supported by the connecting {gamma} transitions between rotational bands. Furthermore, both level schemes could be combined to a common level scheme, in which the ground state of the long-lived 9/2 isomer was placed 54.0(3) keV above the ground state of the short-lived 5/2 isomer. The resulting level scheme was compared to Hartree-Fock-Bogolyubov single

  9. Measurements of fast neutron-induced fission data of Np-237

    Energy Technology Data Exchange (ETDEWEB)

    Win, Than; Saito, Keiichiro; Baba, Mamoru; Iwasaki, Tomohiko; Ibaraki, Masanobu; Miura, Takako; Sanami, Toshiya; Nauchi, Yasushi; Hirakawa, Naohiro [Tohoku Univ., Sendai (Japan). Faculty of Engineering

    1998-03-01

    We have performed the following measurements for {sup 237}Np using the 4.5 MV Dynamitron accelerator of Tohoku University as the pulsed neutron source: (1) Prompt fission neutron spectrum for 0.62 MeV incident neutrons, and (2) Neutron-Induced fission cross-section between 10 and 100 keV. The prompt fission neutron spectrum was measured using TOF method with a heavily shielded NE213 scintillation detector. The Maxwellian temperature T{sub m} derived is 1.28 MeV, which is lower than that of 1.38 MeV in JENDL-3.2. The fission cross sections were measured between 10 - 100 keV. The results are between JENDL-3.2 and ENDF/B-VI. (author)

  10. Persistence of Clostridium difficile RT 237 infection in a Western Australian piggery.

    Science.gov (United States)

    Moono, Peter; Putsathit, Papanin; Knight, Daniel R; Squire, Michele M; Hampson, David J; Foster, Niki F; Riley, Thomas V

    2016-02-01

    Clostridium difficile is commonly associated with healthcare-related infections in humans, and is an emerging pathogen in food animal species. There is potential for transmission of C. difficile from animals or animal products to humans. This study aimed to determine if C. difficile RT 237 had persisted in a Western Australian piggery or if there had been a temporal change in C. difficile diversity. C. difficile carriage in litters with and without diarrhea was investigated, as was the acquisition of C. difficile over time using cohort surveys. Rectal swabs were obtained from piglets aged 1-10 days to determine prevalence of C. difficile carriage and samples were obtained from 20 piglets on days 1, 7, 13, 20, and 42 of life to determine duration of shedding. Isolation of C. difficile from feces was achieved by selective enrichment culture. All isolates were characterized by standard molecular typing. Antimicrobial susceptibility testing was performed on selected isolates (n = 29). Diarrheic piglets were more likely to shed C. difficile than the non-diseased (p = 0.0124, χ2). In the cohort study, C. difficile was isolated from 40% samples on day 1, 50% on day 7, 20% on day 13, and 0% on days 20 and 42. All isolates were RT 237 and no antimicrobial resistance was detected. The decline of shedding of C. difficile to zero has public health implications because slaughter age pigs have a low likelihood of spreading C. difficile to consumers via pig meat.

  11. 49 CFR Appendix A to Part 237 - Supplemental Statement of Agency Policy on the Safety of Railroad Bridges

    Science.gov (United States)

    2010-10-01

    ... Safety of Railroad Bridges A Appendix A to Part 237 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD ADMINISTRATION, DEPARTMENT OF TRANSPORTATION BRIDGE SAFETY STANDARDS... Railroad Bridges A Statement of Agency Policy on the Safety of Railroad Bridges was originally published...

  12. DETERMINATION OF 237NP AND PU ISOTOPES IN LARGE SOIL SAMPLES BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S.

    2010-07-26

    A new method for the determination of {sup 237}Np and Pu isotopes in large soil samples has been developed that provides enhanced uranium removal to facilitate assay by inductively coupled plasma mass spectrometry (ICP-MS). This method allows rapid preconcentration and separation of plutonium and neptunium in large soil samples for the measurement of {sup 237}Np and Pu isotopes by ICP-MS. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via {sup 238}U peak tailing. The method provides enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then transferring Pu to DGA resin for additional purification. The decontamination factor for removal of uranium from plutonium for this method is greater than 1 x 10{sup 6}. Alpha spectrometry can also be applied so that the shorter-lived {sup 238}Pu isotope can be measured successfully. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu and {sup 238}Pu were measured by alpha spectrometry.

  13. Determination of traces of 237Np in environmental samples by ICP-MS after separation using TOA extraction chromatography.

    Science.gov (United States)

    Ji, Y Q; Li, J Y; Luo, S G; Wu, T; Liu, J L

    2001-09-01

    A simple, rapid, cost-efficient, and robust method for separation of 237Np with an extraction chromatographic column (TOA: tri-n-octylamine on Teflon powder) is outlined in detail and further improved for direct ICP-MS analysis. The column efficiently retained 237Np in 2 mol L(-1) HNO3 medium and all of the 237Np was easily eluted with 0.02 mol L(-1) oxalic acid in 0.16 mol L(-1) HNO3 at 95 degrees C. The separated solutions were free from most matrix elements and were aspirated into the ICP-MS directly. The decontamination factor for 238U is more than 10(4). The instrumental detection limit for 237Np was 0.46 pg mL(-1), which corresponds to 1.2 x 10(-5) Bq mL(-1). The method is more rapid than traditional radiometric techniques. It is also considered to be more suitable for environmental monitoring than existing methods based on TOA.

  14. Development of ionization technique for measurement of fast neutron induced fission products yields of {sup 237}Np

    Energy Technology Data Exchange (ETDEWEB)

    Goverdovski, A.A.; Khryachkov, V.A.; Ketlerov, V.V.; Mitrofanov, V.F.; Ostapenko, Yu.B.; Semenova, N.N.; Fomichev, A.N.; Rodina, L.F. [Institute of Physics and Power Engineering, Obninsk (Russian Federation)

    1997-03-01

    Twin gridded ionization chamber and corresponding software was designed for measurements of masses, kinetic energies and nuclear charges of fission fragments from fast neutron induced fission of {sup 237}Np. The ionization detector design, electronics, data acquisition and processing system and the test results are presented in this paper. (J.P.N.)

  15. Once-daily NVA237 improves exercise tolerance from the first dose in patients with COPD: the GLOW3 trial

    Directory of Open Access Journals (Sweden)

    Beeh KM

    2012-07-01

    Full Text Available Kai M Beeh,1 Dave Singh,2 Lilla Di Scala,3 Anton Drollmann31insaf Respiratory Research Institute, Wiesbaden, Germany; 2University Of Manchester, Medicines Evaluation Unit, University Hospital of South Manchester, Manchester, UK; 3Novartis Pharma AG, Basel, SwitzerlandIntroduction: Exercise limitation, dynamic hyperinflation, and exertional dyspnea are key features of symptomatic chronic obstructive pulmonary disease (COPD. We assessed the effects of glycopyrronium bromide (NVA237, a once-daily, long-acting muscarinic antagonist, on exercise tolerance in patients with moderate to severe COPD.Methods: Patients were randomized to a cross-over design of once-daily NVA237 50 µg or placebo for 3 weeks, with a 14-day washout. Exercise endurance, inspiratory capacity (IC during exercise, IC and expiratory volumes from spirometry, plethysmographic lung volumes, leg discomfort and dyspnea under exercise (Borg scales, and transition dyspnea index were measured on Days 1 and 21 of treatment. The primary endpoint was endurance time during a submaximal constant-load cycle ergometry test on Day 21.Results: A total of 108 patients were randomized to different treatment groups (mean age, 60.5 years; mean post-bronchodilator, forced expiratory volume in 1 second [FEV1] 57.1% predicted. Ninety-five patients completed the study. On Day 21, a 21% difference in endurance time was observed between patients treated with NVA237 and those treated with placebo (P < 0.001; the effect was also significant from Day 1, with an increase of 10%. Dynamic IC at exercise isotime and trough FEV1 showed significant and clinically relevant improvements from Day 1 of treatment that were maintained throughout the study. This was accompanied by inverse decreases in residual volume and functional residual capacity. NVA237 was superior to placebo (P < 0.05 in decreasing leg discomfort (Borg CR10 scale on Day 21 and exertional dyspnea on Days 1 and 21 (transition dyspnea index and Borg CR

  16. Production of plutonium tracers in Np-237 nuclear reactions with He-3-ions in the energy range from 26 to 60 MeV

    NARCIS (Netherlands)

    Aaltonen, J; Dendooven, P; Gromova, EA; Jakovlev, VA; Trzaska, WH

    1998-01-01

    Cross-sections for the reaction Np-237 + He-3 --> Pu-236,Pu-237,Pu-238 at He-3 bombarding energies from 26 to 60 MeV were measured. Thick-target yields, based on the measured and previously known cross-sections were constructed. The results are discussed and compared with Ether reactions leading to

  17. Post-Irradiation Examination of 237Np Targets for 238Pu Production

    Energy Technology Data Exchange (ETDEWEB)

    Morris, Robert Noel [ORNL; Baldwin, Charles A [ORNL; Hobbs, Randy W [ORNL; Schmidlin, Joshua E [ORNL

    2015-01-01

    Oak Ridge National Laboratory is recovering the US 238Pu production capability and the first step in the process has been to evaluate the performance of a 237Np target cermet pellet encased in an aluminum clad. The process proceeded in 3 steps; the first step was to irradiate capsules of single pellets composed of NpO2 and aluminum power to examine their shrinkage and gas release. These pellets were formed by compressing sintered NpO2 and aluminum powder in a die at high pressure followed by sintering in a vacuum furnace. Three temperatures were chosen for sintering the solution precipitated NpO2 power used for pellet fabrication. The second step was to irradiate partial targets composed of 8 pellets in a semi-prototypical arrangement at the two best performing sintering temperatures to determine which temperature gave a pellet that performed the best under the actual planned irradiation conditions. The third step was to irradiate ~50 pellets in an actual target configuration at design irradiation conditions to assess pellet shrinkage and gas release, target heat transfer, and dimensional stability. The higher sintering temperature appeared to offer the best performance after one cycle of irradiation by having the least shrinkage, thus keeping the heat transfer gap between the pellets and clad small minimizing the pellet operating temperature. The final result of the testing was a target that can meet the initial production goals, satisfy the reactor safety requirements, and can be fabricated in production quantities. The current focus of the program is to verify that the target can be remotely dissembled, the pellets dissolved, and the 238Pu recovered. Tests are being conducted to examine these concerns and to compare results to code predictions. Once the performance of the full length targets has been quantified, the pellet 237Np loading will be revisited to determine if it can be

  18. Fission mode analysis of the reaction {sup 237}Np(n,f) - possibilities and perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Siegler, P. [Joint Research Centre, Geel (Belgium). Geel Establishment

    1996-03-01

    Fission fragment properties for the reaction {sup 237}Np(n,f) have been measured at the Van de Graaff Laboratory of the IRMM. Using a double gridded ionization chamber the mass, kinetic energy and the angular distribution for both fission fragments could be determined simultaneously for an incident neutron energy range from E{sub n}=0.3 MeV upto E{sub n}=5.5 MeV. Complete datasets have been acquired for 13 different neutron energies covering sub barrier fission as well as fission in the plateau region. A detailed analysis of the fragment distributions and the respective momenta has been carried out, checking the coherence against the excitation energy of the compound nucleus. The consideration of multi-modal fission offers an improved possibility for the description of the fragment distributions backed up by theoretical calculations on the basis of the multi-model random-neck rupture model of Brosa, Grossmann and Mueller. The changes of the fission fragment properties under investigation are completely described and an interpretation of the findings is presented. (author)

  19. K0.53Mn2.37Fe1.24(PO43

    Directory of Open Access Journals (Sweden)

    Mongi Ben Amara

    2011-01-01

    Full Text Available During an attempt to crystallize potassium manganese diiron phosphate KMnFe2(PO43 by the flux method, a new phase, potassium dimanganese iron triphosphate, K0.53Mn2.37Fe1.24(PO43, was isolated. This phase, whose composition was confirmed by ICP analysis, is isotypic with the alluaudite-like phosphates, thus it exhibits the (A2(A′2(A1(A′1(A′′1(M1(M22(PO43 general formula. The site occupancies led to the following cation distribution: 0.53 K on A′2 (site symmetry 2, 0.31 Mn on A′′1, 1.0 Mn on M1 (site symmetry 2 and (0.62 Fe + 0.38 Mn on M2. The structure is built up from infinite chains of edge-sharing M1O6 and M2O6 octahedra. These chains run along [10overline{1}] and are connected by two different PO4 tetrahedra, one of which exhibits 2 symmetry. The resulting three-dimensional framework delimits large tunnels parallel to [001], which are partially occupied by the K+ and Mn2+ cations.

  20. The structures of CyMe4-BTBP complexes of americium(iii) and europium(iii) in solvents used in solvent extraction, explaining their separation properties.

    Science.gov (United States)

    Ekberg, Christian; Löfström-Engdahl, Elin; Aneheim, Emma; Foreman, Mark R StJ; Geist, Andreas; Lundberg, Daniel; Denecke, Melissa; Persson, Ingmar

    2015-11-14

    Separation of trivalent actinoid (An(iii)) and lanthanoid (Ln(iii)) ions is extremely challenging due to their similar ionic radii and chemical properties. Poly-aromatic nitrogen compounds acting as tetradentate chelating ligands to the metal ions in the extraction, have the ability to sufficiently separate An(iii) from Ln(iii). One of these compounds, 6,6'-bis(5,5,8,8-tetramethyl-5,6,7,8-tetrahydro-benzol[1,2,4]triazin-3-yl)[2,2]bipyridine, CyMe4-BTBP, has proven to be resistant towards acidic environments and strong radiation from radioactive decomposition. EXAFS studies of the dicomplexes of CyMe4-BTBP with americium(iii) and europium(iii) in nitrobenzene, cyclohexanone, 1-hexanol, 1-octanol and malonamide (DMDOHEMA) in 1-octanol have been carried out to get a deeper understanding of the parameters responsible for the separation. The predominating complexes independent of solvent used are [Am(CyMe4-BTBP)2(NO3)](2+) and [Eu(CyMe4-BTBP)2](3+), respectively, which are present as outer-sphere ion-pairs with nitrate ions in the studied solvents with low relative permittivity. The presence of a nitrate ion in the first coordination sphere of the americium(iii) complex compensates the charge density of the complex considerably in comparison when only outer-sphere ion-pairs are formed as for the [Eu(CyMe4-BTBP)2](3+) complex. The stability and solubility of a complex in a solvent with low relative permittivity increase with decreasing charge density. The [Am(CyMe4-BTBP)2(NO3)](2+) complex will therefore be increasingly soluble and stabilized over the [Eu(CyMe4-BTBP)2](3+) complex in solvents with decreasing relative permittivity of the solvent. The separation of americium(iii) from europium(iii) with CyMe4-BTBP as extraction agent will increase with decreasing relative permittivity of the solvent, and thereby also with decreasing solubility of CyMe4-BTBP. The choice of solvent is therefore a balance of a high separation factor and sufficient solubility of the CyMe4-BTBP

  1. New experimental determination of the neutronic resonance parameters of {sup 237}Np below 500 eV; Nouvelle determination experimentale des parametres de resonances neutroniques de {sup 237}Np en dessous de 500 eV

    Energy Technology Data Exchange (ETDEWEB)

    Gressier, V

    1999-10-01

    For studies of future nuclear reactors dedicated to nuclear waste transmutation, an improvement of the accuracy of the neutron radiative capture cross section of {sup 237}Np appears necessary. In the framework of a collaboration between the Commissariat a l'Energie atomique (CEA) and Institute for Reference Materials and Measurement (IRMM, Geel, Bergium), a new determination of the resonance parameters of {sup 237}Np has been performed. Two types of experiments are carried out at GELINA, the IRMM pulsed neutron source, using the time of flight method: a transmission experiment which is related to the neutron total cross section and a capture experiment which gives the neutron radiative capture cross section. The resonance parameters presented in this work are extracted from the transmission data between 0 and 500 eV with the least square code REFIT, using the Reich-Moore formalism. In parallel, the Doppler effect is investigated. The commonly used free gas model appears inadequate below 20 eV for neptunium dioxide at room temperature. By the use of the program DOPUSH, which calculates the Doppler broadening with a harmonic crystal model according to Lamb's theory, we are able to produce abetter fit of the experimental data for the resonances of {sup 237}Np in NpO{sub 2} at low energy or temperatures. In addition to the resonance parameters, a study of their mean value and distribution is included in this work. (authors)

  2. Determination of Atto- to Femtogram Levels of Americium and Curium Isotopes in Large-Volume Urine Samples by Compact Accelerator Mass Spectrometry.

    Science.gov (United States)

    Dai, Xiongxin; Christl, Marcus; Kramer-Tremblay, Sheila; Synal, Hans-Arno

    2016-03-01

    Ultralow level analysis of actinides in urine samples may be required for dose assessment in the event of internal exposures to these radionuclides at nuclear facilities and nuclear power plants. A new bioassay method for analysis of sub-femtogram levels of Am and Cm in large-volume urine samples was developed. Americium and curium were co-precipitated with hydrous titanium oxide from the urine matrix and purified by column chromatography separation. After target preparation using mixed titanium/iron oxides, the final sample was measured by compact accelerator mass spectrometry. Urine samples spiked with known quantities of Am and Cm isotopes in the range of attogram to femtogram levels were measured for method evaluation. The results are in good agreement with the expected values, demonstrating the feasibility of compact accelerator mass spectrometry (AMS) for the determination of minor actinides at the levels of attogram/liter in urine samples to meet stringent sensitivity requirements for internal dosimetry assessment.

  3. Artificial radionuclides in the Northern European Marine Environment. Distribution of radiocaesium, plutonium and americium in sea water and sediments in 1995

    Energy Technology Data Exchange (ETDEWEB)

    Groettheim, Siri

    2000-07-01

    This study considers the distribution of radiocaesium, plutonium and americium in the northern marine environment. The highest radiocaesium activity in sea water was observed in Skagerrak, 26 Bq/m{sub 3}, and in surface sediments in the Norwegian Sea, 60 Bq/kg. These enhanced levels were related to Chernobyl. The highest 239,240Pu activity in surface water was measured in the western North Sea, 66 mBq/m{sub 3}. In sea water, sub-surface maxima were observed at several locations with an 239,240Pu activity up to 160 mBq/m{sub 3}, and were related to Sellafield. With the exception to the North Sea, surface sediments reflected Pu from global fallout from weapons tests only. (author)

  4. Development of an automatic method for americium and plutonium separation and preconcentration using an multisyringe flow injection analysis-multipumping flow system.

    Science.gov (United States)

    Fajardo, Yamila; Ferrer, Laura; Gómez, Enrique; Garcias, Francesca; Casas, Monserrat; Cerdà, Víctor

    2008-01-01

    A new procedure for automatic separation and preconcentration of 241Am and 239+240Pu from interfering matrixes using transuranide (TRU)-resin is proposed. Combination of the multisyringe flow injection analysis and multipumping flow system techniques with the TRU-resin allows carrying out the sampling treatment and separation in a short time using large sample volumes. Americium is eluted from the column with 4 mol L(-1) hydrochloric acid, and then plutonium is separated via on-column Pu(IV) reduction to Pu(III) with titanium(III) chloride. The corresponding alpha activities are measured off-line, with a relative standard deviation of 3% and a lower limit of detection of 0.004 Bq mL(-1), by using a multiplanchet low-background proportional counter.

  5. Recovery of Americium-241 from lightning rod by the method of chemical treatment; Recuperacion del Americio-241 provenientes de los pararrayos por el metodo de tratamiento quimico

    Energy Technology Data Exchange (ETDEWEB)

    Cruz, W.H., E-mail: wcruz@ipen.gob.pe [Instituto Peruano de Energia Nuclear (GRRA/IPEN), Lima (Peru). Division de Gestion de Residuos Radiactivos

    2013-07-01

    About 95% of the lightning rods installed in the Peruvian territory have set in their structures, pose small amounts of radioactive sources such as Americium-241 ({sup 241}Am), fewer and Radium 226 ({sup 226}Ra) these are alpha emitters and have a half life of 432 years and 1600 years respectively. In this paper describes the recovery of radioactive sources of {sup 241}Am radioactive lightning rods using the conventional chemical treatment method using agents and acids to break down the slides. The {sup 241}Am recovered was as excitation source and alpha particle generator for analysing samples by X Ray Fluorescence, for fixing the stainless steel {sup 241}Am technique was used electrodeposition. (author)

  6. Americium-241 Decorporation Model

    Science.gov (United States)

    2014-10-01

    sources when combined with beryllium. Radioactive sources are used for a number of industrial applications that range from oil well logging devices...is any exposure resulting in a 50-year whole-body committed effective dose greater than 200 mSv (Rojas- Palma 2009). Therefore, the model can also...Tracheobronchial geometry: Human, dog, rat, hamster (Report LF-53). Lovelace Foundation, Albuquerque, NM Rojas- Palma C, et al. 2009. TMT Handbook

  7. Diffusion coefficient test of {sup 237}Np in bentonite backfill materials

    Energy Technology Data Exchange (ETDEWEB)

    Cui Anxi; Fan Zhiwen; Zhang Jinsheng; Gu Cunli [China Inst. for Radiation Protection, Shanxi (China); Mukai, M.; Maeda, T.; Matsumoto, J.; Tanaka, T.; Ogawa, H. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-03-01

    This paper describes the work on diffusion coefficient test of Np in bentonite backfill materials. Due to its very low permeability, diffusion is the dominant migration mechanics in bentonite. The bentonite comes from Inner Mongolia of China. {sup 237}Np was used as tracer. The special apparatus for diffusion test was setup, the diffusion coefficient of Np in pure bentonite and sand-bentonite mixture were tested. The tracer was introduced between two bentonite columns. After a specific contacting period, the bentonite columns were taken out and cut to very thin slices. The radioactivity in bentonite slices was analyzed to give the nuclide concentration versus distance curves. The diffusion coefficient could be estimated. The diffusion coefficient of pure bentonite at different density was tested. When the density of pure bentonite samples varied from 1.1, 1.3, 1.5 to 1.7 g/ml, their diffusion coefficient were 1.36 x 10{sup -13} m{sup 2}/s 1.16 x 10{sup -13}m{sup 2}/s, 1.07 x 10{sup -13} m{sup 2}/s and 8.26 x 10{sup -14} m{sup 2}/s respectively. The diffusion coefficient of Np in sand-bentonite mixture sample was 4.13 x 10{sup -13} m{sup 2}/s. To estimate the distribution coefficient (K{sub d}) value of Np in mixture sample by diffusion method, the diffusion coefficient of Br was measured./ The concluded K{sub d} value was 77ml/g for the sand-bentonite mixture. The K{sub d} value obtained by batch test methods was 30ml/g. The reason is related with the error of Br diffusion coefficient and solid-liquid ratio. (author)

  8. RAPID DETERMINATION OF 237 NP AND PU ISOTOPES IN WATER BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY AND ALPHA SPECTROMETRY

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S.; Jones, V.; Culligan, B.; Nichols, S.; Noyes, G.

    2010-06-23

    A new method that allows rapid preconcentration and separation of plutonium and neptunium in water samples was developed for the measurement of {sup 237}Np and Pu isotopes by inductively-coupled plasma mass spectrometry (ICP-MS) and alpha spectrometry; a hybrid approach. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via peak tailing. The method provide enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then moving Pu to DGA resin for additional removal of uranium. The decontamination factor for uranium from Pu is almost 100,000 and the decontamination factor for U from Np is greater than 10,000. This method uses stacked extraction chromatography cartridges and vacuum box technology to facilitate rapid separations. Preconcentration is performed using a streamlined calcium phosphate precipitation method. Purified solutions are split between ICP-MS and alpha spectrometry so that long and short-lived Pu isotopes can be measured successfully. The method allows for simultaneous extraction of 20 samples (including QC samples) in 4 to 6 hours, and can also be used for emergency response. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu, {sup 238}Pu, and {sup 239}Pu were measured by alpha spectrometry.

  9. 242Pu as tracer for simultaneous determination of 237Np and 239,240Pu in environmental samples

    DEFF Research Database (Denmark)

    Chen, Q.J.; Dahlgaard, H.; Nielsen, S.P.;

    2002-01-01

    A procedure has been developed using Pu-242 as tracer for simultaneous determination of Np-237 and Pu-239,Pu-240 in environmental samples. The validity of the method has been demonstrated by ICPMS and alpha-spectroscopy for up to 10 gram soil and sediment, seawater up to 200 litres. The paper...... describes a suitable chemical procedure for Np and Pu including a quantitative pre-concentration of neptunium and plutonium, preparation of Np4+ and Pu4+, NP(NO3)(6)(2-) and Pu(NO3)(6)(2-), The ratio of Np-237/Pu-242 (or Np-237/Pu-239) before and after the procedure has been determined using 10 g soil (free...... from Np and Pu) R-before/R-after = 1.004 +/- 3.3% (S.D n = 20) and 1 litre seawater R-before/R-after = 1.019+/-1.9% (S.D., n = 12). Results from the intercomparison samples LAEA-135, LAEA-381 and from environmental samples are presented....

  10. Nuclear Criticality Safety of the DOT 9975 Container for237NpO2Storage, Handling, and Transport

    Energy Technology Data Exchange (ETDEWEB)

    Reed, D.A.

    2003-08-29

    Nuclear criticality safety considerations are presented to address use of the DOT 9975 shipping container for {sup 237}NpO{sub 2}. The DOT 9975 container will be used by multiple DOE sites and contractors. Various of site- and activity-specific NCS and facility safety documents are yet to be developed. For these reasons, an overall assessment of criticality safety of {sup 237}NpO{sub 2}-loaded DOT 9975 containers is considered useful to personnel involved in generating, reviewing, or approving these various documents. It is concluded that inherent container features, the loading per container (maximum of 6 kg {sup 237}Np), and the nuclear physics properties of {sup 237}NpO{sub 2} combine to preclude the potential for a nuclear criticality accident. This conclusion applies to storage, handling, and transport operations involving closed DOT 9975 packages, including credible off-normal conditions that may result in damage to packages during those operations.

  11. Actinide Oxidation State and O/M Ratio in Hypostoichiometric Uranium-Plutonium-Americium U0.750Pu0.246Am0.004O2-x Mixed Oxides.

    Science.gov (United States)

    Vauchy, Romain; Belin, Renaud C; Robisson, Anne-Charlotte; Lebreton, Florent; Aufore, Laurence; Scheinost, Andreas C; Martin, Philippe M

    2016-03-07

    Innovative americium-bearing uranium-plutonium mixed oxides U1-yPuyO2-x are envisioned as nuclear fuel for sodium-cooled fast neutron reactors (SFRs). The oxygen-to-metal (O/M) ratio, directly related to the oxidation state of cations, affects many of the fuel properties. Thus, a thorough knowledge of its variation with the sintering conditions is essential. The aim of this work is to follow the oxidation state of uranium, plutonium, and americium, and so the O/M ratio, in U0.750Pu0.246Am0.004O2-x samples sintered for 4 h at 2023 K in various Ar + 5% H2 + z vpm H2O (z = ∼ 15, ∼ 90, and ∼ 200) gas mixtures. The O/M ratios were determined by gravimetry, XAS, and XRD and evidenced a partial oxidation of the samples at room temperature. Finally, by comparing XANES and EXAFS results to that of a previous study, we demonstrate that the presence of uranium does not influence the interactions between americium and plutonium and that the differences in the O/M ratio between the investigated conditions is controlled by the reduction of plutonium. We also discuss the role of the homogeneity of cation distribution, as determined by EPMA, on the mechanisms involved in the reduction process.

  12. Extensive Prospect of Winter Triticale Zhongsi 237 for Ensilage in Xinjiang%饲草型小黑麦品种中饲237在新疆前景广阔

    Institute of Scientific and Technical Information of China (English)

    艾尼瓦尔·哈德尔; 曹连莆; 孔广超; 李诚

    2004-01-01

    中饲237是一个冬性饲草型小黑麦品种,在新疆多点试验及在石河子地区大面积试种中,表现适应性良好,适于作一年两季青贮饲料生产的第一季作物品种.该品种株高150~170 cm,在中上等肥力条件下一般单产4 200~4 800 kg/hm2.

  13. Prospects for a measurement of the 237U(n,f) cross section at the LANSCE Lujan Center

    Energy Technology Data Exchange (ETDEWEB)

    Devlin, Matthew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mocko, Michal [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gavron, Victor [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jandel, Marian [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rusev, Gencho Yordanov [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bredeweg, Todd Allen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-06-24

    A new measurement of the 237U(n, f) cross section from thermal to ≈ 100 keV is discussed, using one of the flightpaths at the LANSCE Lujan Center. Previous energy-resolved resonance-region measurements have been conducted using weapon test time-of-flight[1] and the LANSCE Lead Slowing Down Spectrometer[2], the former of which is limited in its energy range, and the latter in its energy resolution and range. We present here a proposal, based on simulations of the Lujan Center neutron flux and a hypothetical experiment, that is expected to adequately address both of these issues.

  14. Study of biosorbents application on the treatment of radioactive liquid wastes with americium-241; Estudo da aplicacao de biossorventes no tratamento de rejeitos radioativos liquidos contendo americio-241

    Energy Technology Data Exchange (ETDEWEB)

    Borba, Tania Regina de

    2010-07-01

    The use of nuclear energy for many different purposes has been intensified and highlighted by the benefits that it provides. Medical diagnosis and therapy, agriculture, industry and electricity generation are examples of its application. However, nuclear energy generates radioactive wastes that require suitable treatment ensuring life and environmental safety. Biosorption and bioaccumulation represent an emergent alternative for the treatment of radioactive liquid wastes, providing volume reduction and physical state change. This work aimed to study biosorbents for the treatment of radioactive liquid wastes contaminated with americium-241 in order to reduce the volume and change the physical state from liquid to solid. The biosorbents evaluated were Saccharomyces cerevisiae immobilized in calcium alginate beads, inactivated and free cells of Saccharomyces cerevisiae, calcium alginate beads, Bacillus subtilis, Cupriavidus metallidurans and Ochrobactrum anthropi. The results were quite satisfactory, achieving 100% in some cases. The technique presented in this work may be useful and viable for implementing at the Waste Management Laboratory of IPEN - CNEN/SP in short term, since it is an easy and low cost method. (author)

  15. Human bones obtained from routine joint replacement surgery as a tool for studies of plutonium, americium and {sup 90}Sr body-burden in general public

    Energy Technology Data Exchange (ETDEWEB)

    Mietelski, Jerzy W., E-mail: jerzy.mietelski@ifj.edu.pl [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Cracow (Poland); Golec, Edward B. [Traumatology and Orthopaedic Clinic, 5th Military Clinical Hospital and Polyclinic, Independent Public Healthcare Facility, Wroclawska 1-3, 30-901 Cracow (Poland); Orthopaedic Rehabilitation Department, Chair of Clinical Rehabilitation, Faculty of Motor of the Bronislaw Czech' s Academy of Physical Education, Cracow (Poland); Department of Physical Therapy Basics, Faculty of Physical Therapy, Administration College, Bielsko-Biala (Poland); Tomankiewicz, Ewa [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Cracow (Poland); Golec, Joanna [Orthopaedic Rehabilitation Department, Chair of Clinical Rehabilitation, Faculty of Motor of the Bronislaw Czech' s Academy of Physical Education, Cracow (Poland); Physical Therapy Department, Institute of Physical Therapy, Faculty of Heath Science, Jagiellonian University, Medical College, Cracow (Poland); Nowak, Sebastian [Traumatology and Orthopaedic Clinic, 5th Military Clinical Hospital and Polyclinic, Independent Public Healthcare Facility, Wroclawska 1-3, 30-901 Cracow (Poland); Orthopaedic Rehabilitation Department, Chair of Clinical Rehabilitation, Faculty of Motor of the Bronislaw Czech' s Academy of Physical Education, Cracow (Poland); Szczygiel, Elzbieta [Physical Therapy Department, Institute of Physical Therapy, Faculty of Heath Science, Jagiellonian University, Medical College, Cracow (Poland); Brudecki, Kamil [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Cracow (Poland)

    2011-06-15

    The paper presents a new sampling method for studying in-body radioactive contamination by bone-seeking radionuclides such as {sup 90}Sr, {sup 239+240}Pu, {sup 238}Pu, {sup 241}Am and selected gamma-emitters, in human bones. The presented results were obtained for samples retrieved from routine surgeries, namely knee or hip joints replacements with implants, performed on individuals from Southern Poland. This allowed to collect representative sets of general public samples. The applied analytical radiochemical procedure for bone matrix is described in details. Due to low concentrations of {sup 238}Pu the ratio of Pu isotopes which might be used for Pu source identification is obtained only as upper limits other then global fallout (for example Chernobyl) origin of Pu. Calculated concentrations of radioisotopes are comparable to the existing data from post-mortem studies on human bones retrieved from autopsy or exhumations. Human bones removed during knee or hip joint surgery provide a simple and ethical way for obtaining samples for plutonium, americium and {sup 90}Sr in-body contamination studies in general public. - Highlights: > Surgery for joint replacement as novel sampling method for studying in-body radioactive contamination. > Proposed way of sampling is not causing ethic doubts. > It is a convenient way of collecting human bone samples from global population. > The applied analytical radiochemical procedure for bone matrix is described in details. > The opposite patient age correlations trends were found for 90Sr (negative) and Pu, Am (positive).

  16. Exercise-induced TBC1D1 Ser237 phosphorylation and 14-3-3 protein binding capacity in human skeletal muscle

    DEFF Research Database (Denmark)

    Frøsig, Christian; Pehmøller, Christian; Birk, Jesper Bratz

    2010-01-01

    TBC1D1 is a Rab-GTPase activating protein involved in regulation of GLUT4 translocation in skeletal muscle. We here evaluated exercise-induced regulation of TBC1D1 Ser237 phosphorylation and 14-3-3 protein binding capacity in human skeletal muscle. In separate experiments healthy men performed all......-out cycle exercise lasting either 30 sec, 2 min or 20 min. After all exercise protocols, TBC1D1 Ser237 phosphorylation increased (~70 - 230%, Pprotein showed a similar pattern of regulation...... increasing 60 - 250% (Pprotein kinase (AMPK) induced both Ser237 phosphorylation and 14-3-3 binding properties on human TBC1D1 when evaluated in vitro. To further characterize the role of AMPK as an upstream kinase regulating TBC1D1, extensor digitorum longus...

  17. 以短肽K237为配体的靶向脂质体超声造影剂构建方法%Preparation of liposome ultrasonic contrast agent with ligand peptide K237

    Institute of Scientific and Technical Information of China (English)

    何洁; 杨莉; 李颖嘉; 孙学刚; 刁建新; 李传刚; 宾建平; 龚渭冰

    2011-01-01

    目的 探讨以与血管内皮生长因子(VEGF)的主要受体KDR特异性结合的短肽K237(P)为配体制备靶向脂质体超声造影剂(P-Bio-Av-Bio-Mbs)的方法. 方法 采用生物素-亲和素桥接法构建P-Bio-Av-Bio-Mbs,流式细胞术筛选最佳配体适配剂量,光镜及荧光显微镜观察靶向微泡与KDR强阳性表达的人大肠癌LOVO细胞结合情况,计算花环形成率.分别以5、50、99 ml/h速率水流冲刷,光镜观察靶向微泡与LOVO细胞结合情况. 结果 不同亲和素剂量下(0、2、6、10、30 μg),微泡表面亲和素携带率差异有统计学意义( P<0.05).Mavidin=6 μg时,携带率增长达平台期;不同短肽剂量下(0、30、40、50、60、70、100 μg),微泡表面短肽携带率差异有统计学意义( P<0.05),当MK237=50 μg时,微泡表面短肽携带率增长达平台期.光镜下KDR强阳性表达的LOVO细胞周围花环形成率高达90.52%,荧光显微镜下微泡外壳发出明亮绿色荧光.随冲刷速度增加,靶细胞周围黏附的靶向微泡减少,在99 ml/h冲刷速度下,靶细胞周围仍可见花环结构. 结论 通过生物素-亲和素桥连作用,短肽K237被有效装配在P-Bio-Av-Bio-Mbs表面,体外具有靶向特异性及一定稳定性.流式细胞术是筛选靶向微泡配体适配剂量的可靠方法.%Objective To assess preparation method of a new kind of targeted liposome ultrasonic contrast agent with small peptide K237 as the ligand which can combine specifically with KDR as the main receptor of VEGF. Methods Targeted bubbles (P-Bio-Ay-Bio-Mbs) were formed through "biotin-avidin" bridge grafting. Flow cytometry screening was performed to explore the best dose of the ligands, then targeted-bubbles were incubated respectively with LOVO and LS174T which were KDR expressed in different cells. Meanwhile, rosette formation rate was calculated. Results The bubble surface's avidin-carrying rates were significant different (P<0. 05) on different dosages of avidin(0, 2

  18. Longevity-associated NADH Dehydrogenase Subunit-2 237 Leu/Met Polymorphism Modulates the Effects of Daily Alcohol Drinking on Yearly Changes in Serum Total and LDL Cholesterol in Japanese Men

    Directory of Open Access Journals (Sweden)

    Takashima,Yutaka

    2009-12-01

    Full Text Available Reduced nicotinamide adenine dinucleotide (NADH dehydrogenase subunit 2 237 leucine/methionine (ND2-237 Leu/Met polymorphism, is reportedly associated with longevity in the Japanese population. The ND2-237Met genotype may exert resistance to atherogenic diseases, such as myocardial infarction or cerebrovascular disorders. To investigate whether ND2-237 Leu/Met polymorphism is associated with yearly changes in serum lipid levels, we conducted a longitudinal study of 107 healthy Japanese male subjects. Analysis of covariance revealed that the interaction between the ND2-237 Leu/Met genotypes and habitual drinking was significantly associated with yearly changes in serum total cholesterol (TC and low-density lipoprotein cholesterol (LDLC levels (p0.036 and p0.006, respectively. In multiple regression analysis, daily drinking was significantly and positively associated with yearly changes in serum LDLC levels in men with ND2-237Met (p0.026. After adjusting for covariates, yearly changes in serum LDLC levels were significantly lower in non-daily drinkers with ND2-237Met than in those with ND2-237Leu (p0.047. These results suggest that ND2-237Met has a beneficial impact on yearly changes in serum LDLC in non-daily drinkers but not in daily drinkers.

  19. The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium

    Energy Technology Data Exchange (ETDEWEB)

    Ketelaer, Jens

    2010-06-14

    The construction of TRIGA-TRAP and direct high-precision Penning trap mass measurements on rare-earth elements and americium: Nuclear masses are an important quantity to study nuclear structure since they reflect the sum of all nucleonic interactions. Many experimental possibilities exist to precisely measure masses, out of which the Penning trap is the tool to reach the highest precision. Moreover, absolute mass measurements can be performed using carbon, the atomic-mass standard, as a reference. The new double-Penning trap mass spectrometer TRIGA-TRAP has been installed and commissioned within this thesis work, which is the very first experimental setup of this kind located at a nuclear reactor. New technical developments have been carried out such as a reliable non-resonant laser ablation ion source for the production of carbon cluster ions and are still continued, like a non-destructive ion detection technique for single-ion measurements. Neutron-rich fission products will be available by the reactor that are important for nuclear astrophysics, especially the r-process. Prior to the on-line coupling to the reactor, TRIGA-TRAP already performed off-line mass measurements on stable and long-lived isotopes and will continue this program. The main focus within this thesis was on certain rare-earth nuclides in the well-established region of deformation around N {proportional_to} 90. Another field of interest are mass measurements on actinoids to test mass models and to provide direct links to the mass standard. Within this thesis, the mass of {sup 241}Am could be measured directly for the first time. (orig.)

  20. Draft Genome Sequence of Moraxella bovoculi Strain 237T (ATCC BAA-1259T) Isolated from a Calf with Infectious Bovine Keratoconjunctivitis.

    Science.gov (United States)

    Calcutt, Michael J; Foecking, Mark F; Martin, Neal T; Mhlanga-Mutangadura, Tendai; Reilly, Thomas J

    2014-06-26

    Moraxella bovoculi is a recently identified species, recovered from the bovine eye, which is under investigation as an etiological agent of infectious bovine keratoconjunctivitis. A draft genome sequence of the Moraxella bovoculi type strain 237(T) has been determined to identify features that may be important during host colonization.

  1. Concurrent determination of 237Np and Pu isotopes using ICP-MS: analysis of NIST environmental matrix standard reference materials 4357, 1646a, and 2702.

    Science.gov (United States)

    Matteson, Brent S; Hanson, Susan K; Miller, Jeffrey L; Oldham, Warren J

    2015-04-01

    An optimized method was developed to analyze environmental soil and sediment samples for (237)Np, (239)Pu, and (240)Pu by ICP-MS using a (242)Pu isotope dilution standard. The high yield, short time frame required for analysis, and the commercial availability of the (242)Pu tracer are significant advantages of the method. Control experiments designed to assess method uncertainty, including variation in inter-element fractionation that occurs during the purification protocol, suggest that the overall precision for measurements of (237)Np is typically on the order of ± 5%. Measurements of the (237)Np concentration in a Peruvian Soil blank (NIST SRM 4355) spiked with a known concentration of (237)Np tracer confirmed the accuracy of the method, agreeing well with the expected value. The method has been used to determine neptunium and plutonium concentrations in several environmental matrix standard reference materials available from NIST: SRM 4357 (Radioactivity Standard), SRM 1646a (Estuarine Sediment) and SRM 2702 (Inorganics in Marine Sediment).

  2. Erratum : Critical Properties of Spin-1 Antiferromagnetic Heisenberg Chains with Bond Alternation and Uniaxial Single-Ion-Type Anisotropy (vol 69, pg 237, 2000)

    OpenAIRE

    飛田, 和男

    2008-01-01

    Original Paper :Critical Properties of Spin-1 Antiferromagnetic Heisenberg Chains with Bond Alternation and Uniaxial Single-Ion-Type AnisotropyWei Chen, Kazuo Hida and Bryan Clifford Sanctuary Journal of the Physical Society of Japan 69 (2000) pp.237-241

  3. Mutation Screening of 1,237 Cancer Genes across Six Model Cell Lines of Basal-Like Breast Cancer.

    Directory of Open Access Journals (Sweden)

    Eleonor Olsson

    Full Text Available Basal-like breast cancer is an aggressive subtype generally characterized as poor prognosis and lacking the expression of the three most important clinical biomarkers, estrogen receptor, progesterone receptor, and HER2. Cell lines serve as useful model systems to study cancer biology in vitro and in vivo. We performed mutational profiling of six basal-like breast cancer cell lines (HCC38, HCC1143, HCC1187, HCC1395, HCC1954, and HCC1937 and their matched normal lymphocyte DNA using targeted capture and next-generation sequencing of 1,237 cancer-associated genes, including all exons, UTRs and upstream flanking regions. In total, 658 somatic variants were identified, of which 378 were non-silent (average 63 per cell line, range 37-146 and 315 were novel (not present in the Catalogue of Somatic Mutations in Cancer database; COSMIC. 125 novel mutations were confirmed by Sanger sequencing (59 exonic, 48 3'UTR and 10 5'UTR, 1 splicing, with a validation rate of 94% of high confidence variants. Of 36 mutations previously reported for these cell lines but not detected in our exome data, 36% could not be detected by Sanger sequencing. The base replacements C/G>A/T, C/G>G/C, C/G>T/A and A/T>G/C were significantly more frequent in the coding regions compared to the non-coding regions (OR 3.2, 95% CI 2.0-5.3, P<0.0001; OR 4.3, 95% CI 2.9-6.6, P<0.0001; OR 2.4, 95% CI 1.8-3.1, P<0.0001; OR 1.8, 95% CI 1.2-2.7, P = 0.024, respectively. The single nucleotide variants within the context of T[C]T/A[G]A and T[C]A/T[G]A were more frequent in the coding than in the non-coding regions (OR 3.7, 95% CI 2.2-6.1, P<0.0001; OR 3.8, 95% CI 2.0-7.2, P = 0.001, respectively. Copy number estimations were derived from the targeted regions and correlated well to Affymetrix SNP array copy number data (Pearson correlation 0.82 to 0.96 for all compared cell lines; P<0.0001. These mutation calls across 1,237 cancer-associated genes and identification of novel variants will aid in

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

    Energy Technology Data Exchange (ETDEWEB)

    Jeo, Kih-Soo; Song, Byung-Chul; Kim, Young-Bok; Han, Sun-Ho; Jeon, Young-Shin; Jung, Euo-Chang; Jee, Kwang-Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    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, {sup 237}Np, {sup 241}Am and {sup 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 {sup 237}Np was determined by an isotope dilution alpha(gamma) spectrometry using {sup 239}Np as a spike, and {sup 241}Am and curium isotopes were determined by alpha spectrometry using {sup 243}Am as a tracer. The content of each nuclide was compared with that by the Origen-2 code.

  5. Deducing the 236Pu(n,f) and 237Pu(n,f) cross sections via the surrogate ratio method

    Science.gov (United States)

    Hughes, R. O.; Beausang, C. W.; Ross, T. J.; Burke, J. T.; Casperson, R. J.; McCleskey, M.; Cooper, N.; Escher, J. E.; Gell, K. B.; Good, E.; Humby, P.; Saastimoinen, A.; Tarlow, T. D.

    2013-10-01

    The short half-lives associated with certain minor actinide nuclei that are relevant to stockpile stewardship pursuits and the development of next-generation nuclear reactors make direct neutron measurements very challenging. In certain cases, a stable beam and target ``surrogate reaction'' can be used in lieu of the neutron-induced reaction, and the (n,f) cross section can then be deduced indirectly. Agreement between surrogate and direct measurements for (n,f) cross sections in actinide nuclei is usually within 10%. The present work reports on the measurement of the 236Pu(n,f) and 237Pu(n,f) cross sections via 239Pu(p,tf) and 239Pu(p,df) surrogate reactions, respectively. The experiment was performed at the Texas A&M University Cyclotron Facility using a 28.5 MeV proton beam to bombard 239Pu and 235U targets. Outgoing light ions were detected in coincidence with fission fragments using the STAR-LiTe detector array. Results of the analysis will be presented. This work was supported by DoE Grant Numbers: DE-FG52-09NA29454 and DE-FG02-05ER41379 (Richmond), DE-AC52-07NA27344 (LLNL) and DE-FG52-09NA29467 (TAMU).

  6. Neutron-induced transmutation reactions in 237Np, 238Pu, and 239Pu at the massive natural uranium spallation target

    Science.gov (United States)

    Zavorka, L.; Adam, J.; Baldin, A. A.; Caloun, P.; Chilap, V. V.; Furman, W. I.; Kadykov, M. G.; Khushvaktov, J.; Pronskikh, V. S.; Solnyshkin, A. A.; Sotnikov, V.; Stegailov, V. I.; Suchopar, M.; Tsoupko-Sitnikov, V. M.; Tyutyunnikov, S. I.; Voronko, V.; Vrzalova, J.

    2015-04-01

    Transmutation reactions in the 237Np, 238Pu, and 239Pu samples were investigated in the neutron field generated inside a massive (m = 512 kg) natural uranium spallation target. The uranium target assembly QUINTA was irradiated with the deuteron beams of kinetic energy 2, 4, and 8 GeV provided by the Nuclotron accelerator at the Joint Institute for Nuclear Research (JINR) in Dubna. The neutron-induced transmutation of the actinide samples was measured off-line by implementing methods of gamma-ray spectrometry with HPGe detectors. Results of measurement are expressed in the form of both the individual reaction rates and average fission transmutation rates. For the purpose of validation of radiation transport programs, the experimental results were compared with simulations of neutron production and distribution performed by the MCNPX 2.7 and MARS15 codes employing the INCL4-ABLA physics models and LAQGSM event generator, respectively. In general, a good agreement between the experimental and calculated reaction rates was found in the whole interval of provided beam energies.

  7. Initial Estimate of the 237U(n,f) Cross Section for 0.1 (less than) En (MeV) (less than or equal to) 20

    Energy Technology Data Exchange (ETDEWEB)

    Younes, W; Britt, H C; Becker, J A; Wilhelmy, J B

    2003-06-27

    In response to a request for a {sup 237}U(n,f) cross section evaluation up to E{sub n} = 20 MeV, they have married a data set from the previous reliable estimate [1-3] of the cross section up to E{sub n} = 2.5 MeV, to an estimate of the remaining cross section up to E{sub n} = 20 MeV, deduced from simple physics arguments. This straw-man, work-in-progress estimate of the {sup 237}U(n,f) cross section is intended to be used in sensitivity-test comparisons to other evaluations of the cross section (e.g., ENDF/B-VI [4] and ENDL [5]). The simple approach used in this work to generate a consistent cross section up to E{sub n} = 20 MeV is validated using the well-known {sup 235}U(n,f) cross section as a test case (see Fig. 1). The corresponding estimate of the {sup 237}U(n,f) cross section is plotted in Fig. 2 and listed in Table I.

  8. Comment: 237 [Taxonomy Icon

    Lifescience Database Archive (English)

    Full Text Available for Life Science licensed under CC Attribution2.1 Japan 絵や写真の投稿もできます。右は、没になったティラノザウルス(目がかわいい)です。 ttamura 2008/11/11 12:11:40 2011/09/14 21:10:36 ...

  9. EURADOS action for determination of americium in skull measures in vivo and Monte Carlo simulation; Accion EURADOS para la determinacion de americio en craneo mediante medidas in-vivo y simulacion Monte Carlo

    Energy Technology Data Exchange (ETDEWEB)

    Lopez Ponte, M. A.; Navarro Amaro, J. F.; Perez Lopez, B.; Navarro Bravo, T.; Nogueira, P.; Vrba, T.

    2013-07-01

    From the Group of WG7 internal dosimetry of the EURADOS Organization (European Radiation Dosimetry group, e.V.) which It coordinates CIEMAT, international action for the vivo measurement of americium has been conducted in three mannequins type skull with detectors of Germanium by gamma spectrometry and simulation by Monte Carlo methods. Such action has been raised as two separate exercises, with the participation of institutions in Europe, America and Asia. Other actions similar precede this vivo intercomparison of measurement and modeling Monte Carlo1. The preliminary results and associated findings are presented in this work. The laboratory of the body radioactivity (CRC) of service counter of dosimetry staff internal (DPI) of the CIEMAT, it has been one of the participants in vivo measures exercise. On the other hand part, the Group of numerical dosimetry of CIEMAT is participant of the Monte Carlo2 simulation exercise. (Author)

  10. Americium behaviour in plastic vessels

    Energy Technology Data Exchange (ETDEWEB)

    Legarda, F.; Herranz, M. [Departamento de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria de Bilbao, Universidad del Pais Vasco (UPV/EHU), Alameda de Urquijo s/n, 48013 Bilbao (Spain); Idoeta, R., E-mail: raquel.idoeta@ehu.e [Departamento de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria de Bilbao, Universidad del Pais Vasco (UPV/EHU), Alameda de Urquijo s/n, 48013 Bilbao (Spain); Abelairas, A. [Departamento de Ingenieria Nuclear y Mecanica de Fluidos, Escuela Tecnica Superior de Ingenieria de Bilbao, Universidad del Pais Vasco (UPV/EHU), Alameda de Urquijo s/n, 48013 Bilbao (Spain)

    2010-07-15

    The adsorption of {sup 241}Am dissolved in water in different plastic storage vessels was determined. Three different plastics were investigated with natural and distilled waters and the retention of {sup 241}Am by these plastics was studied. The same was done by varying vessel agitation time, vessel agitation speed, surface/volume ratio of water in the vessels and water pH. Adsorptions were measured to be between 0% and 70%. The adsorption of {sup 241}Am is minimized with no water agitation, with PET or PVC plastics, and by water acidification.

  11. Emission probabilities of {gamma}-rays from {sup 238}Np and their use for determination of the thermal neutron capture cross section of {sup 237}Np

    Energy Technology Data Exchange (ETDEWEB)

    Letourneau, A. [Irfu, CEA-Saclay, 91191 Gif-sur-Yvette (France)], E-mail: aletourneau@cea.fr; Marie, F. [Irfu, CEA-Saclay, 91191 Gif-sur-Yvette (France); Mutti, P. [Institut Laue-Langevin, 38000 Grenoble (France); AlMahamid, I. [Wadsworth Center, Laboratory of Inorganic and Nuclear Chemistry, Albany, NY (United States)

    2010-03-15

    The relevant absolute {gamma}-ray emission probabilities from the {beta}-decay of {sup 238}Np were measured by means of {alpha}- and {gamma}-spectroscopic techniques. We obtained values of (25.6{+-}0.4)%, (8.9{+-}0.2)% and (18.8{+-}0.3)% for the 984.45-, 1025.87- and 1028.54-keV {gamma}-rays, respectively, in agreement with the previous measured ones. These intensities were used to deduce the thermal neutron capture cross section of {sup 237}Np for which a value of (182.2{+-}4.5) b is obtained higher by 11% than the recommended value.

  12. Selectivity of bis-triazinyl bipyridine ligands for americium(III) in Am/Eu separation by solvent extraction. Part 1. Quantum mechanical study on the structures of BTBP complexes and on the energy of the separation.

    Science.gov (United States)

    Narbutt, Jerzy; Oziminski, Wojciech P

    2012-12-21

    Theoretical studies were carried out on two pairs of americium and europium complexes formed by tetra-N-dentate lipophilic BTBP ligands, neutral [ML(NO(3))(3)] and cationic [ML(2)](3+) where M = Am(III) or Eu(III), and L = 6,6'-bis-(5,6-diethyl-1,2,4-triazin-3-yl)-2,2'-bipyridine (C2-BTBP). Molecular structures of the complexes have been optimized at the B3LYP/6-31G(d) level and total energies of the complexes in various media were estimated using single point calculations performed at the B3LYP/6-311G(d,p) and MP2/6-311G(d,p) levels of theory. In the calculations americium and europium ions were treated using pseudo-relativistic Stuttgart-Dresden effective core potentials and the accompanying basis sets. Selectivity in solvent extraction separation of two metal ions is a co-operative function of contributions from all extractable metal complexes, which depend on physico-chemical properties of each individual complex and on its relative amount in the system. Semi-quantitative analysis of BTBP selectivity in the Am/Eu separation process, based on the contributions from the two pairs of Am(III) and Eu(III) complexes, has been carried out. To calculate the energy of Am/Eu separation, a model of the extraction process was used, consisting of complex formation in water and transfer of the formed complex to the organic phase. Under the assumptions discussed in the paper, this simple two-step model results in reliable values of the calculated differences in the energy changes for each pair of the Am/Eu complexes in both steps of the process. The greater thermodynamic stability (in water) of the Am-BTBP complexes, as compared with the analogous Eu species, caused by greater covalency of the Am-N than Eu-N bonds, is most likely the main reason for BTBP selectivity in the separation of the two metal ions. The other potential reason, i.e. differences in lipophilic properties of the analogous complexes of Am and Eu, is less important with regard to this selectivity.

  13. Standard practice for the determination of 237Np, 232Th, 235U and 238U in urine by inductively coupled plasma-Mass spectrometry (ICP-MS) and gamma ray spectrometry.

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This practice covers the separation and preconcentration of neptunium-237 (237Np), thorium-232 (232Th), uranium-235 (235U) and uranium-238 (238U) from urine followed by quantitation using ICP-MS. 1.2 This practice can be used to support routine bioassay programs. The minimum detectable concentrations (MDC) for this method, taking the preconcentration factor into account, are approximately 1E-2Bq for 237Np (0.38ng), 2E-6Bq for 232Th (0.50ng), 4E-5Bq for 235U (0.50ng) and 6E-6Bq for 238U (0.48ng). 1.3 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  14. Preparation and characterisation of Kolliphor® P 188 and P 237 solid dispersion oral tablets containing the poorly water soluble drug disulfiram.

    Science.gov (United States)

    Ramadhani, Nisrina; Shabir, Mehwish; McConville, Christopher

    2014-11-20

    The oral route of administration is the most common and preferred route of drug delivery due to its ease of administration, cost-effectiveness and flexibility in design. However, limited aqueous solubility of the active pharmaceutical ingredient can result in poor bioavailability, which is a major issue for the pharmaceutical industry. Increasing numbers of new drugs are falling into class II of the Biopharmaceutical Classification System (BCS), where they have a low solubility and high tissue permeability, meaning that bioavailability is solubility dependent. Here we demonstrate the development and characterisation of solid dispersion oral tablets, containing the poorly water-soluble drug disulfiram, prepared using both the hot melt and solvent evaporation methods and manufactured from two different polymers, Kolliphor(®) P 188 and P 237, specifically designed for the manufacture of solid dispersions. This paper demonstrates that the disulfiram solid dispersions tablets have an enhanced release rate of disulfiram compared to the control tablets. The Kolliphor(®) P 188 polymer control tablets released approximately 48.8% of their disulfiram content over 8h, with the solvent evaporated tablets releasing approximately 65.8%, while the 60 and 80 °C hot melt tablets released approximately 73.2 and 100% of their disulfiram content respectively. A similar trend was seen with Kolliphor(®) P 237 as the control tablets released approximately 50.5% of their disulfiram content over 8h, while the solvent evaporated tablets released approximately 79.5% and the 60 and 80 °C hot melt tablets released 100.2 and 100.3% respectively. Depending on what method and polymer is used to manufacture the solid dispersions the disulfiram is either maintained completely or partially in its amorphous state and it is this which enhances its solubility and release rate from the tablets. The disulfiram in the Kolliphor(®) P 188 solvent evaporated and 60 °C hot melt tablets retained 50

  15. 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)

  16. VALIDACIÓN DE UN PROGRAMA EDUCATIVO PARA MEJORAR EL CONOCIMIENTO DE LAS MADRES DE FAMILIA SOBRE LA SALUD BUCAL EN LA INSTITUCIÓN EDUCATIVA INICIAL N° 237 LA RINCONADA, AYAVIRI-PUNO 2015.

    OpenAIRE

    TAPIA TAPIA, RAXONA MARY

    2016-01-01

    El presente trabajo de investigación intitulado “Validación de un programa educativo para mejorar el conocimiento de las madres de familia sobre salud bucal en la Institución Educativa Inicial N° 237 la Rinconada, Ayaviri Puno 2015”. Tuvo como objetivo identificar el conocimiento de las madres de familia de la Institución Educativa Inicial N° 237 la Rinconada sobre Salud Bucal antes del programa educativo, identificar el conocimiento de las madres de familia de la Institución E...

  17. Hydrogen Abundances in Metal Grains from the Hammadah Al Hamra (HaH) 237 Metal-rich Chondrite: A Test of the Nebular-Formation Theory

    Science.gov (United States)

    Lauretta, D. S.; Guan, Y.; Leshin, L. A.

    2005-01-01

    The Bencubbin-like (CB) chondrites are metal-rich, primitive meteorites [1,2]. Some of these chondrites (HaH 237, QUE 94411) contain compositionally zoned metal grains with near-chondritic bulk compositions. Thermodynamic modeling of the zoning patterns in these grains suggests that they were formed by condensation in a region of the solar nebula with enhanced dust/gas ratios and a total pressure of 10(exp -4) bars at temperatures between 1400 - 1500 K [3]. If these predictions are correct than the metal grains would have been exposed to abundant H2 gas, which comprises the bulk of nebular systems. Since Fe-based alloys can absorb significant quantities of H, metal grains formed in the solar nebula should contain measurable abundances of H.

  18. Sequential Injection Method for Rapid and Simultaneous Determination of 236U, 237Np, and Pu Isotopes in Seawater

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hou, Xiaolin; Steier, Peter;

    2013-01-01

    An automated analytical method implemented in a novel dual-column tandem sequential injection (SI) system was developed for simultaneous determination of 236U, 237Np, 239Pu, and 240Pu in seawater samples. A combination of TEVA and UTEVA extraction chromatography was exploited to separate and purify...... target analytes, whereupon plutonium and neptunium were simultaneously isolated and purified on TEVA, while uranium was collected on UTEVA. The separation behavior of U, Np, and Pu on TEVA–UTEVA columns was investigated in detail in order to achieve high chemical yields and complete purification...... for the radionuclides of interest. 242Pu was used as a chemical yield tracer for both plutonium and neptunium. 238U was quantified in the sample before the separation for deducing the 236U concentration from the measured 236U/238U atomic ratio in the separated uranium target using accelerator mass spectrometry...

  19. Capture and Fission rate of 232-Th, 238-U, 237-Np and 239-Pu from spallation neutrons in a huge block of lead.

    CERN Document Server

    Vlachoudis, Vasilis

    2000-01-01

    The study is centered on the research of the incineration possibility of nuclear waste, by the association of a particle accelerator with a multiplying medium of neutrons, in the project "Energy Amplifier" of C. Rubbia. It consists of the experimental determination of the rates of capture and fission of certain elements (232-Th, 238-U, 237-Np and 239-Pu) subjected to a fluence of fast spallation neutrons. These neutrons are produced by the interaction of high kinetic energy protons (several GeV) provided by the CERN-PS accelerator, on a large lead solid volume. The measurement techniques used in this work, are based on the activation of elements in the lead volume and the subsequent gamma spectroscopy of the activated elements, and also by the detection of fission fragment traces. The development, of a Monte Carlo code makes it possible, on one hand, to better understand the relevant processes, and on the other hand, to validate the code, by comparison with measurements, for the design and the construction of...

  20. Fluid dynamics simulation of highly loaded anion-exchange chromatography of Np(IV) based on adsorption isotherm determined by {sup 237+239}Np

    Energy Technology Data Exchange (ETDEWEB)

    Yamamura, T. [Institute for Materials Research, Tohoku University, Sendai, Miyagi 980-8577 (Japan)], E-mail: yamamura@imr.tohoku.ac.jp; Mitsugashira, T. [Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan); Shiokawa, Y. [Institute for Materials Research, Tohoku University, Sendai, Miyagi 980-8577 (Japan); Aoki, D.; Homma, Y. [Institute for Materials Research, Tohoku University, Oarai, Ibaraki 311-1313 (Japan)

    2007-10-11

    In order to investigate the optimum condition for anion-exchange chromatography for purification and recovery of actinide(IV) constituting transuranium elements, a convective-diffusion equation model treating mass balance and Langmuir-type kinetics in porous system, which was developed for thorium(IV) by us, was applied to neptunium(IV). Absorption isotherm of neptunium(IV) to anion-exchange (MSA-1) resin was carried out by using {sup 237+239}Np in 6N HNO{sub 3} media and hereby parameters of the Langmuir-type kinetics were determined as k{sub 0} = 2.5 x 10{sup 3} and s{sub max} = 1.0. Accompanied with the fluid dynamics parameters already determined for the column system used for {sup 227+232}Th, elution curves of neptunium(IV) at highly loaded condition were estimated by the numerical calculation. According to the result, the loading of more than 10% of resin capacity leads to rapid breakthrough and severe tailing of neptunium which lowers purity and yield in the purification procedure. This numerical calculation will serve as a valuable measure to figure out column operation conditions for purification and recovery of transuranium elements.

  1. South Equatorial Current (SEC) driven changes at DSDP Site 237, Central Indian Ocean, during the Plio-Pleistocene: Evidence from Benthic Foraminifera and Stable Isotopes

    Science.gov (United States)

    Gupta, Anil K.; Das, Moumita; Bhaskar, K.

    2006-12-01

    This study attempts to analyse paleoceanographic changes in the Central Indian Ocean (Deep Sea Drilling Project Site 237), linked to monsoon variability as well as deep-sea circulation during the Plio-Pleistocene. We used factor and cluster analyses of census data of the 34 most dominant species of benthic foraminifera that enabled us to identify five biofacies: Astrononion umbilicatulum- Uvigerina proboscidea (Au-Up), Pullenia bulloides- Bulimina striata (Pb-Bs), Globocassidulina tumida- Nuttallides umbonifera (Gt-Nu), Gyroidinoides nitidula- Cibicides wuellerstorfi (Gn-Cw) and Cassidulina carinata- Cassidulina laevigata (Cc-Cl) biofacies. Knowledge of the environmental preferences of modern deep-sea benthic foraminifera helped to interpret the results of factor and cluster analyses in combination with oxygen and carbon isotope values. The biofacies indicative of high surface productivity, resulting from a stronger South Equatorial Current (Au-Up and Pb-Bs biofacies), dominate the early Pliocene interval (5.6-4.5 Ma) of global warmth. An intense Indo-Pacific 'biogenic bloom' and strong Oxygen Minimum Zone extended to intermediate depths (˜1000-2000 m) over large parts of the Indian Ocean in the early Pliocene. Since 4.5 Ma, the food supply in the Central Indian Ocean dropped and fluctuated while deep waters were corrosive (biofacies Gt-Nu, Gn-Cw). The Pleistocene interval is characterized by an intermediate flux of organic matter (Cc-Cl biofacies).

  2. Determination of neutron resonance parameters of Neptunium 237 between 0 and 500 eV. The covariance matrices of statistical and of systematic origin, relating the resonance parameters, are also given; Determination des parametres des resonances neutroniques du neptunium 237, en dessous de 500eV, et obtention des matrices de covariances statistiques et systematiques entre les parametres de ces resonances

    Energy Technology Data Exchange (ETDEWEB)

    Lepretre, A.; Herault, N. [CEA Saclay, Dept. d' Astrophysique de Physique des Particules, de Physique Nucleaire et de l' Instrumentation Associee, 91- Gif sur Yvette (France); Brusegan, A.; Noguere, G.; Siegler, P. [Institut des Materiaux et des Metrologies - IRMM, Joint Research Centre, Gell (Belgium)

    2002-12-01

    This report is a follow up of the report CEA DAPNIA/SPHN-99-04T of Vincent Gressier. In the frame of a collaboration between the 'Commissariat a l'Energie Atomique (CEA)' and the Institute for Reference Materials and Measurement (IRMM, Geel, Belgique), the resonance parameters of neptunium 237 have been determined in the energy interval between 0 and 500 eV. These parameters have been obtained by using the Refit code in analysing simultaneously three transmission experiments. The covariance matrix of statistical origin is provided. A new method, based on various sensitivity studies is proposed for determining also the covariance matrix of systematic origin, relating the resonance parameters. From an experimental viewpoint, the study indicated that, with a large probability, the background spectrum has structure. A two dimensional profiler for the neutron density has been proved feasible. Such a profiler could, among others, demonstrate the existence of the structured background. (authors)

  3. Study of the excited levels of 233{sup P}a by the 237{sup N}p alpha decay; Estudio de los niveles excitados en el 233{sup P}a por la desintegracion alfa del 237{sup N}p

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J.; Gaeta, R.; Vano, E.; Los Arcos, J. M.

    1978-07-01

    The excited levels in 233{sup P}a following the 237{sup N}p alpha decay have been studied, by performing different experiences to complete available data and supply new information. Thus, two direct alpha spectrum measurement, one alpha-gamma bidimensional coincidence experiment, three gamma-gamma and gamma-X ray coincidences and some other measurements of the gamma spectrum, direct and coincident with alpha-particles have been made. These last experiences have allowed to obviate usual radiochemical separation methods, the 233{sup P}a radioactive descendent interferences being eliminated by means of the coincidence technic. As a result, a primary decay scheme has been elaborated, including 15 new gamma transitions and two new levels, not observed in the most recent works. (Author) 60 refs.

  4. Measurement of the Np237(n,γ) cross section from 20 meV to 500 keV with a high efficiency, highly segmented 4π BaF2 detector

    Science.gov (United States)

    Esch, E.-I.; Reifarth, R.; Bond, E. M.; Bredeweg, T. A.; Couture, A.; Glover, S. E.; Greife, U.; Haight, R. C.; Hatarik, A. M.; Hatarik, R.; Jandel, M.; Kawano, T.; Mertz, A.; O'Donnell, J. M.; Rundberg, R. S.; Schwantes, J. M.; Ullmann, J. L.; Vieira, D. J.; Wilhelmy, J. B.; Wouters, J. M.

    2008-03-01

    The Np237(n,γ)Np238 cross section has been measured in the neutron energy range from 20 meV to 500 keV using the DANCE array at the Los Alamos National Laboratory. This new facility allows experiments with submilligram samples and is therefore well suited to investigate isotopes with half-lives as low as a few hundred days. In this benchmark measurement, only 0.42 mg of Np237 was sufficient to determine differential cross sections relative to the well-known resonance at 0.5 eV. The thermal cross section was measured to σ2200m/s=177±5 barn, σkT=25.3meV=167±4 barn and the resonance integral to RI=693±6 barn.

  5. Pu236(n,f), Pu237(n,f), and Pu238(n,f) cross sections deduced from (p,t), (p,d), and (p,p') surrogate reactions

    Science.gov (United States)

    Hughes, R. O.; Beausang, C. W.; Ross, T. J.; Burke, J. T.; Casperson, R. J.; Cooper, N.; Escher, J. E.; Gell, K.; Good, E.; Humby, P.; McCleskey, M.; Saastimoinen, A.; Tarlow, T. D.; Thompson, I. J.

    2014-07-01

    The Pu236(n,f), Pu237(n,f) and Pu238(n,f) cross sections have been inferred by utilizing the surrogate ratio method. Targets of Pu239 and U235 were bombarded with 28.5-MeV protons, and the light ion recoils, as well as fission fragments, were detected using the STARS detector array at the K150 Cyclotron at the Texas A&M cyclotron facility. The (p, tf) reaction on Pu239 and U235 targets was used to deduce the σ (Pu236(n ,f))/σ(U232(n,f)) ratio, and the Pu236(n,f) cross section was subsequently determined for En=0.5-7.5 MeV. Similarly, the (p,df) reaction on the same two targets was used to deduce the σ(Pu237(n ,f))/σ(U233(n,f)) ratio, and the Pu237(n,f) cross section was extracted in the energy range En=0.5-7 MeV. The Pu238(n,f) cross section was also deduced by utilizing the (p,p') reaction channel on the same targets. There is good agreement with the recent ENDF/B-VII.1 evaluated cross section data for Pu238(n,f) in the range En=0.5-10.5 MeV and for Pu237(n,f) in the range En=0.5-7 MeV; however, the Pu236(n,f) cross section deduced in the present work is higher than the evaluation between 2 and 7 MeV.

  6. 16 CFR 23.7 - Misuse of the words “platinum,” “iridium,” “palladium,” “ruthenium,” “rhodium,” and “osmium.”

    Science.gov (United States)

    2010-01-01

    ... § 23.7 Misuse of the words “platinum,” “iridium,” “palladium,” “ruthenium,” “rhodium,” and “osmium.” (a) It is unfair or deceptive to use the words “platinum,” “iridium,” “palladium,” “ruthenium,” “rhodium... marking or description misrepresents the product's true composition. The Platinum Group Metals (PGM)...

  7. Risk Factors Associated With Complication Rates of Becker-Type Expander Implants in Relation to Implant Survival: Review of 314 Implants in 237 Patients.

    Science.gov (United States)

    Taboada-Suarez, Antonio; Brea-García, Beatriz; Magán-Muñoz, Fernando; Couto-González, Iván; González-Álvarez, Eduardo

    2015-12-01

    Although autologous tissue reconstruction is the best option for breast reconstruction, using implants is still a reliable and simple method, offering acceptable aesthetic results. Becker-type implants are permanent implants that offer a 1-stage reconstructive option. A retrospective study was carried out in our center reviewing the clinical reports of 237 patients, in whom a total of 314 Becker-type prostheses were implanted. Overall survival was calculated using a Kaplan-Meier estimate. Cox proportional hazard models were used to calculate adjusted hazard ratios. At the end of the study, 214 expanders (68.15%) presented no complications, 40 (12.47%) developed significant capsular contracture, in 27 (8.60%) infection occurred, 24 (7.64%) suffered minor complications, and 9 (2.87%) ruptured. The mean survival time of the expanders was 120.41 months (95% CI: 109.62, 131.19). Radiotherapy, chemotherapy, high Molecular Immunology Borstel, age, mastectomy performed previously to the implant, ductal carcinoma, advanced tumoral stage, experience of the surgeon, and Becker 35-type implants were significantly related to a high number of complications in relation to the survival of the implants. Cox regression analysis revealed that the main risk factors for the survival of expander implants included radiotherapy and surgeon experience. The complication hazard ratio or relative risk caused by these 2 factors was 1.976 and 1.680, respectively. One-stage reconstruction using Becker-type expanders is an appropriate, simple, and reliable option in delayed breast reconstruction in patients who have not received radiotherapy and as long as the procedure is carried out by surgeons skilled in the technique.

  8. VLT AND ACS OBSERVATIONS OF RDCS J1252.9-2927: DYNAMICAL STRUCTURE AND GALAXY POPULATIONS IN A MASSIVE CLUSTER AT Z=1.237*

    Energy Technology Data Exchange (ETDEWEB)

    Demarco, R; Rosati, P; Lidman, C; Girardi, M; Nonino, M; Rettura, A; Strazzullo, V; der Wel, A v; Ford, H C; Mainieri, V; Holden, B P; Stanford, S A; Blakeslee, J P; Gobat, R; Postman, M; Tozzi, P; Overzier, R A; Zirm, A W; Benitez, N; Homeier, N L; Illingworth, G D; Infante, L; Jee, M J; Mei, S; Menanteau, F; Motta, V; Zheng, W; Clampin, M; Hartig, G

    2007-03-23

    We present results from an extensive spectroscopic survey, carried out with FORS on the ESO Very Large Telescope, and from an extensive multi-wavelength imaging data set from the Advanced Camera for Surveys and ground based facilities of the cluster of galaxies RDCS J1252.9-2927. We have spectroscopically confirmed 38 cluster members in the redshift range 1.22 < z < 1.25. The distribution in velocity of these spectroscopic members yields a cluster median redshift of z = 1.237 and a rest-frame velocity dispersion of 747{sub -84}{sup +74} km s{sup -1}. Star-forming members are observed to mainly populate the outskirts of the cluster while passive galaxies dominate the central cluster region. Using the 38 confirmed redshifts, we were able to resolve, for the first time at z > 1, kinematic structure. The velocity distribution, which is not Gaussian at the 95% confidence level, is consistent with two groups that are also responsible for the projected elongation of the cluster in the East-West direction. The groups are composed of 26 and 12 galaxies and have velocity dispersions of 486{sub -85}{sup +47} km s{sup -1} and 426{sub -105}{sup +57} km s{sup -1}, respectively. The elongation is also seen in the intracluster gas (from X-ray observations) and the dark matter distribution (from a weak lensing analysis). This leads us to conclude that RDCS J1252.9-2927 has not yet reached a final virial state. We extend the analysis of the color-magnitude diagram of spectroscopic members to more than 1 Mpc from the cluster center. The scatter and slope of non-[OII]-emitting cluster members in the near-IR red sequence is similar to that seen in clusters at lower redshift. Furthermore, none of the galaxies with luminosities greater than {approx} K*{sub s} + 1.5 show any [OII] emission feature, indicating that these more luminous, redder galaxies have stopped forming stars earlier than the fainter, bluer galaxies. Our observations provide detailed dynamical and spectrophotometric

  9. Prevalence, distribution and functional significance of the -237C to T polymorphism in the IL-12Rβ2 promoter in Indian tuberculosis patients.

    Directory of Open Access Journals (Sweden)

    Vikas Kumar Verma

    Full Text Available Cytokine/cytokine receptor gene polymorphisms related to structure/expression could impact immune response. Hence, the -237 polymorphic site in the 5' promoter region of the IL-12Rβ2 (SNP ID: rs11810249 gene associated with the AP-4 transcription motif GAGCTG, was examined. Amplicons encompassing the polymorphism were generated from 46 pulmonary tuberculosis patients, 35 family contacts and 28 miscellaneous volunteers and sequenced. The C allele predominated among patients, (93.4%, 43/46, and in all volunteers and contacts screened, but the T allele was exclusively limited to patients, (6.5%, 3/46. The functional impact of this polymorphism on transcriptional activity was assessed by Luciferase-reporter and electrophoretic mobility shift assays (EMSA. Luciferase-reporter assays showed a significant reduction in transcriptional efficiency with T compared to C allele. The reduction in transcriptional efficiency with the T allele construct (pGIL-12Rb2-T, in U-87MG, THP-1 and Jurkat cell lines, were 53, 37.6, and 49.8% respectively, compared to the C allele construct (pGIL-12Rb2-C. Similarly, densitometric analysis of the EMSA assay showed reduced binding of the AP-4 transcription factor, to T compared to the C nucleotide probe. Reduced mRNA expression in all patients (3/3 harboring the T allele was seen, whereas individuals with the C allele exhibited high mRNA expression (17/25; 68%, p = 0.05. These observations were in agreement with the in vitro assessment of the promoter activity by Luciferase-reporter and EMSA assays. The reduced expression of IL-12Rβ2 transcripts in 8 patients despite having the C allele was attributed to the predominant over expression of the suppressors (IL-4 and GATA-3 and reduced expression of enhancers (IFN-α of IL-12Rβ2 transcripts. The 17 high IL-12Rβ2 mRNA expressers had significantly elevated IFN-α mRNA levels compared to low expressers and volunteers. Notwithstanding the presence of high levels of IL-12R

  10. Delocalization and new phase in Americium: theory

    Energy Technology Data Exchange (ETDEWEB)

    Soderlind, P

    1999-04-23

    Density-functional electronic structure calculations have been used to investigate the high pressure behavior of Am. At about 80 kbar (8 GPa) calculations reveal a monoclinic phase similar to the ground state structure of plutonium ({alpha}-Pu). The experimentally suggested {alpha}-U structure is found to be substantially higher in energy. The phase transition from fcc to the low symmetry structure is shown to originate from a drastic change in the nature of the electronic structure induced by the elevated pressure. A calculated volume collapse of about 25% is associated with the transition. For the low density phase, an orbital polarization correction to the local spin density (LSD) theory was applied. Gradient terms of the electron density were included in the calculation of the exchange/correlation energy and potential, according to the generalized gradient approximation (GGA). The results are consistent with a Mott transition; the 5f electrons are delocalized and bonding on the high density side of the transition and chemically inert and non-bonding (localized) on the other. Theory compares rather well with recent experimental data which implies that electron correlation effects are reasonably modeled in our orbital polarization scheme.

  11. The proliferation potential of neptunium and americium

    Energy Technology Data Exchange (ETDEWEB)

    An, J. S.; Shin, J. S.; Kim, J. S.; Kwack, E. H.; Kim, B. K

    2000-05-01

    It is recognized that some trans-uranic elements other than plutonium, in particular Np and Am, if will be available in sufficient quantities, could be used for nuclear explosive devices. The spent fuel has been accumulating in number of nuclear power plant and operation of large scale commercial reprocessing plants. However, these materials are not covered by the definition of special fissionable material in the Agency Statute. At the time when the Statute was adopted, the availability of meaningful quantities of separated Np and Am was remote and they were not included in the definition of special fissionable material. Then, IAEA Board decided a measure for control of Np and Am on September 1999. This report contains the control method and the characteristic of Np and Am for using domestic nuclear industries, and it can be useful for understanding how to report and account of Np and Am. (author)

  12. Evaluation of neutron data for americium-241

    Energy Technology Data Exchange (ETDEWEB)

    Maslov, V.M.; Sukhovitskij, E.Sh.; Porodzinskij, Yu.V.; Klepatskij, A.B.; Morogovskij, G.B. [Radiation Physics and Chemistry Problems Inst., Minsk-Sosny (Belarus)

    1997-03-01

    The evaluation of neutron data for {sup 241}Am is made in the energy region from 10{sup -5} eV up to 20 MeV. The results of the evaluation are compiled in the ENDF/B-VI format. This work is performed under the Project Agreement CIS-03-95 with the International Science and Technology Center (Moscow). The Financing Party for the Project is Japan. The evaluation was requested by Y. Kikuchi (JAERI). (author). 60 refs.

  13. Measurement of neutron-induced fission cross-sections of Th232, U238, U233 and Np237 relative to U235 from 1 MeV to 200 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Shcherbakov, O.A.; Laptev, A.B.; Petrov, G.A. [Petersburg Nuclear Physics Inst., Gatchina, Leningrad district (Russian Federation); Fomichev, A.V.; Donets, A.Y.; Osetrov, O.I.

    1998-11-01

    The measurements of neutron-induced cross-section ratios for Th232, U238, U233 and Np237 relative to U235 have been carried out in the energy range from 1 MeV up to 200 MeV using the neutron time-of-flight spectrometer GNEIS based on 1 GeV proton synchrocyclotron. Below 20 MeV, the results of present measurements are roughly in agreement with evaluated data though there are some discrepances to be resolved. (author)

  14. Determination of trace nickel(Ⅱ) by 2,3,7-trihydroxy-9-salicyl fiuorone catalytic kinetic spectrophotometry%2,3,7-三羟基-9-水杨基荧光酮催化动力学光度法测定痕量Ni(Ⅱ)

    Institute of Scientific and Technical Information of China (English)

    王洪福; 张素兰; 苏智先; 何黎明; 廖家娥

    2011-01-01

    The fading reaction of 2,3,7-Trihydroxy-9-Salicyl Fluorone solution oxidized by H2O2can be greatly catalyzed by Nickel ( Ⅱ ) in sodium by droxide solution at 45 C. The optimum experimental condition of the reaction was studied and a new catalytic kinetic method of trace Ni ( Ⅱ ) determination was proposed based on the upper mentioned phenomenon. The absorbency difference △A between non-catalytic reaction and catalytic reaction remained good linear relationship with the mass concentration p of Nickel ( Ⅱ ) in the range of 0. 00 ~0. 15 μg/mL. The detection limit of this method was 7.63 × 10-10 g/mL and kinetic parameters were determined, which showed that the catalytic reaction was the first order reaction to Nickel ( Ⅱ ) and pseudo first order to the total reaction. The apparent rate constant of the reaction was 4. 943 × 10-4/s and the apparent activation energy was 49. 98 k J/mol. The relative standard deviation (RSD) of this method was calculated to be 1.2% according to the 11 times of determinations for 0. 1 μg Nickel ( Ⅱ ) This method was also applied to the determination of trace Nickel ( Ⅱ ) in vanadium iron and low alloy steel with recoveries rate between 100% and 104%, which fulfilled the trace analysis requirements.%基于在NaOH溶液中及45℃加热条件下,Ni(Ⅱ)对H2O2氧化2,3,7-三羟基-水杨基荧光酮溶液褪色反应具有灵敏的催化作用.研究了反应的最佳条件,建立了催化动力学光度法测定痕量Ni(Ⅱ)的光度分析方法.非催化反应与催化反应的吸光度差值△A与Ni(Ⅱ)的质量浓度P在0.00~0.15μg/mL范围内呈良好的线性关系,检出限为7.63×10(-10)g/mL.测定了动力学参数,Ni(Ⅱ)为一级反应,总反应为准一级反应.反应表观速率常数为4.943×10(-3)/s,表观活化能为49.98kJ/mol.对0.1μg Ni(Ⅱ)进行11次测定,求得相对标准偏差(RSD)为1.2%.该方法用于含钒生铁和低合金钢中痕量Ni(Ⅱ)的测定,其回收率在100%~104%

  15. 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...

  16. Wind-tunnel investigation of longitudinal and lateral-directional stability and control characteristics of a 0.237-scale model of a remotely piloted research vehicle with a thick, high-aspect-ratio supercritical wing

    Science.gov (United States)

    Byrdsong, T. A.; Brooks, C. W., Jr.

    1980-01-01

    A 0.237-scale model of a remotely piloted research vehicle equipped with a thick, high-aspect-ratio supercritical wing was tested in the Langley 8-foot transonic tunnel to provide experimental data for a prediction of the static stability and control characteristics of the research vehicle as well as to provide an estimate of vehicle flight characteristics for a computer simulation program used in the planning and execution of specific flight-research mission. Data were obtained at a Reynolds number of 16.5 x 10 to the 6th power per meter for Mach numbers up to 0.92. The results indicate regions of longitudinal instability; however, an adequate margin of longitudinal stability exists at a selected cruise condition. Satisfactory effectiveness of pitch, roll, and yaw control was also demonstrated.

  17. Investigation of Neutron Spectra and Transmutation of ^{129}I, ^{237}Np and Other Nuclides with 1.5 GeV Protons from the Dubna Nuclotron Using the Electronuclear Setup "Energy plus Transmutation"

    CERN Document Server

    Krivopustov, M I; Balabekyan, A R; Batusov, Yu A; Bielewicz, M; Brandt, R; Chaloun, P; Chultem, D; Dwivedi, K K; Elishev, A F; Fragopoulou, M; Henzl, V; Henzlová, D; Kalinnikov, V G; Kievets, M K; Krása, A; Krizek, F; Kugler, A; Manolopoulou, Metaxia; Mariin, I I; Nourreddine, A; Odoj, R; Pavliouk, A V; Pronskikh, V S; Robotham, H; Siemon, K; Szuta, M; Stegailov, V I; Solnyshkin, A A; Sosnin, A N; Stoulos, S; Tsoupko-Sitnikov, V M; Tumendelger, T; Wojecehowski, A; Wagner, V; Wan, J S; Westmeier, W; Zamani-Valasiadou, M; Kumawat, H; Kumar, V; Zaverioukha, O S; Zhuk, I V

    2004-01-01

    Experiments which are part of the scientific program "Investigations of physical aspects of electronuclear method of energy production and transmutation for radioactive waste of atomic energetics using relativistic beams from the JINR Synchrophasotron/Nuclotron" (project "Energy plus Transmutation") are described. A large lead target surrounded by a four-section uranium blanket with total weight of 206.4 kg natural uranium was irradiated with 1.5 GeV protons from the new cryogenic accelerator Nuclotron. Radiochemical sensors were exposed to the secondary particle fluences inside and on top of the target assembly. Two long-lived radioactive waste of atomic energetics sensors ^{129}I and ^{237}Np (approximately 1 g weight each) and stable nuclides ^{27}Al, ^{59}Co, ^{127}I, ^{139}La, ^{197}Au and ^{209}Bi as well as natural and enriched uranium were used. In addition, various solid state nuclear track detectors and nuclear emulsions were exposed simultaneously. The experimental results confirm the theoretical e...

  18. 双侧颈总动脉外膜交感神经网剥脱术治疗小儿脑瘫流涎237例临床效果分析%Two-sided arteria carotis communis anterior external coat periplast cross coupling neural network cracking-off technique to treat the young child brain paralysis to salivate 237 example clinical effects to analyze

    Institute of Scientific and Technical Information of China (English)

    罗晓琦; 孙成彦; 李宁

    2010-01-01

    目的:回顾性分析237例双侧颈总动脉外膜交感神经网剥脱术治疗小儿脑瘫流涎效果.方法:总结2007年2月至2010年2月所有接受双侧颈总动脉外膜交感神经网剥脱术的237例患者,均完成术后6个月随访,根据流涎分级法确定是否改善.结果:治愈75例;显效56例;有效47例;总有效率为75.11%,5岁以上总有效率60.94%,术中出血1例,2例出现Honer综合征. 结论:双侧颈总动脉外膜交感神经网剥脱术治疗小儿脑瘫总体有效率在75.11%,完全控制率31.65%,无明显不良并发症,并可有智能语言障碍、斜视、吞咽进食困难、共济失调、手足徐动等症状的改善效果,故可推广应用于小儿脑瘫流涎症状的治疗,且应提倡早期手术治疗.

  19. TMFunction data: 237 [TMFunction[Archive

    Lifescience Database Archive (English)

    Full Text Available HC. J Biol Chem. 2000 Jul 14;275(28):21017-24 mutagenesis ... affinity chromatography 1AJJ ... LDLR_HUMAN (P01130) Helix ... ligand binding site; surface exposed; acidic residue; conserved

  20. 42 CFR 413.237 - Outliers.

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  3. Reference: 237 [Arabidopsis Phenome Database[Archive

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    Full Text Available member gene family in Arabidopsis (AtFer1-4). To investigate whether iron sequestration in ferritins is a pa...tical time points 0.5 and 24 h post-infection (p.i.). The activation of AtFer1 expression observed at 24 h p...tration of the purified siderophores chrysobactin and desferrioxamine strongly increased AtFer1 transcript a...ia et al. 2005 Jul. Plant J. 43(2):262-72. Ferritins are multimeric iron storage proteins encoded by a four-...rt of an iron-withholding defense system induced in response to bacterial invasio

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  6. Study of the electrochemical oxidation of Am with lacunary heteropolyanions and silver nitrate; Etude de l'oxydation electrochimique de l'americium en presence d'heteropolyanions lacunaires et de nitrate d'argent en milieu aqueux acide

    Energy Technology Data Exchange (ETDEWEB)

    Chartier, D

    1999-07-01

    Electrochemical oxidation of Am(III) with certain lacunary heteropolyanions (LHPA {alpha}{sub 2}-P{sub 2}W{sub 17}O{sub 61}{sup 10-} or {alpha}SiW{sub 11}O{sub 39}{sup 8-}) and silver nitrate is an efficient way to prepare Am(VI). This document presents bibliographic data and an experimental study of the process. Thus, it has been established that Am(IV) is an intermediate species in the reaction and occurs in 1:1 (Amt{sup IV}LHPA) or 1:2 (Am {sup IV}(LHAP){sub 2}) complexes with the relevant LHPA. These 1:1 complexes of Am(IV) have been identified and isolated in this work whereas 1:2 complexes were known from previous studies. The reactivity of these complexes in oxidation shows that 1:1 complexes of Am(IV) are oxidised much more quickly than 1:2 complexes. Apparent stability constants of Am(III) and Am(IV) complexes with the relevant LHPA have been measured for a 1 M nitric acid medium. Thermodynamic data of the reaction are then assessed: redox potentials of Am pairs are computed for a 1 M nitric acid medium containing various amount of LHPA ligands. Those results show that the role of LHPA is to stabilize the intermediate species Am(IV) by lowering the Am(IV)/Am(III) pair potential of about 1 Volt. Nevertheless, if this stabilisation is too strong (i.e. of tungsto-silicate), the oxidation of Am(IV) requires high anodic potential (more than 2 V/ENH). Then, the faradic yield of the oxidation of americium is poor because of water oxidation. This study has also shown that the main role of silver is to catalyze the electrochemical oxidation of Am{sup IV}(LHPA){sub X} complexes. Indeed, these oxidations without silver are extremely slow. An oxygen tracer experiment has been performed during the oxidation of Am(III) in Am(VI). It has been shown that the oxygen atoms of Am(VI) (AMO{sub 2}{sup 2+}) come from water molecules of the solvent and not from the complexing oxygen atoms of the ligands. (author)

  7. Fabrication of targets for transmutation of americium : synthesis of inertial matrix by sol-gel method. Procedure study on the infiltration of a radioactive solutions; Fabricacion de blancos para la transmutacion de americio: sintesis de matrices inertes por el metodo sol-gel. Estudio del procedimiento de infiltracion de disoluciones radiactivas

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez Carretero, A. [Universidad Complutense de Madrid (Spain)

    2002-07-01

    made. In addition a new and unexpected phase formed by the reaction of americium with spinel during the high temperature synthesis process has been identified. This new phase could provide a unique menas to stabilise Am in one particular oxidation state. (Author)

  8. 241镅跟骨骨密度测定在骨质疏松症中的初步应用 ——与腰椎骨密度测定的对比研究%Preliminary application of 241-Americium calcaneus bone mineral density measurement in osteoporosis ——comparison with double X-ray densitometry of the lumber spine

    Institute of Scientific and Technical Information of China (English)

    管梁; 朱承谟; 李培勇; 王辉; 濮鸣芳; 仇季高

    2001-01-01

    Bone mineral density (BMD) of calcaneus in 54 normals, 45 Osteoporosis, 25 suspected osteoporosis and 16 other non-osteoporosis patients, a total of 140 cases were measured by HUAKE (HK-1) 241-Americium BMD absorpmetry, among them 43 were compared with that of lumber spine (L2—L4) measured by Lunar Corporation's Expert-XL absorpmeter. BMD of normal group of calcaneus was (409.8±79.4)mg/cm2. The BMD were decreased slowly with the increased age. The BMD of osteoporosis, suspected osteoporosis and non-osteoporosis group were 230.3±62.3, 395.7±57.4 and 363.3±51.9mg/cm2 respectively. The BMD of osteoporosis group was much lower than that of normal group, and also lower than that of the other two groups, among 26 patients (57.78%) had bone fracture, all was in accordance with the clinical diagnosis of osteoporosis. The BMD of suspected ospteoporosis and non-osteoporosis had no significant difference with normal group. The coefficient variation (CV) of BMD in repeated measurement in calcaneus of 4 pariticipants was less than 1.2%. The correlative coefficient (r) between BMD of calcaneus and lumber spine (L2—L4) group was 0.6824. The correlative coefficient of normal young adult-matched percentage and T value in 2 groups were 0.6863 and 0.6755 respectively, whereas aged-matched percentage, Z value were 0.4614 and 0.5009 respectively. In conclusion 241-Americium calcaneus BMD absorpmetry has the advantage of low price, easy to operate, reliable and valuable in diagnosis osteoporosis. The correlations of calcaneus and lumber spine BMD, normal young adult-matched percentagy and T value were rather good.%为评价跟骨骨密度测定在骨质疏松症中的初步临床应用及与腰椎测定结果的相关性,用国产华科(HK-1型)241镅骨密度仪测定了140例跟骨骨密度(BMD)。其中正常人组54例,骨质疏松确诊组45例,骨质疏松可疑组25例和其他非骨质疏松组16例。其中43例与美国Luner 公司的Expert-XL图像骨密度仪腰

  9. Americium separation from nuclear fuel dissolution using higher oxidation states.

    Energy Technology Data Exchange (ETDEWEB)

    Bruce J. Mincher

    2009-09-01

    Much of the complexity in current AFCI proposals is driven by the need to separate the minor actinides from the lanthanides. Partitioning and recycling Am, but not Cm, would allow for significant simplification because Am has redox chemistry that may be exploited while Cm does not. Here, we have explored methods based on higher oxidation states of Am (AmV and AmVI) to partition Am from the lanthanides. In a separate but related approach we have also initiated an investigation of the utility of TRUEX Am extraction from thiocyanate solution. The stripping of loaded TRUEX by Am oxidation or SCN- has not yet proved successful; however, the partitioning of inextractable AmV by TRUEX shows promise.

  10. Further Studies of Plutonium and Americium at Thule, Greenland

    DEFF Research Database (Denmark)

    Aarkrog, Asker; Dahlgaard, Henning; Nilsson, Karen Kristina;

    1984-01-01

    further away from the impact point and at some locations the vertical distribution indicated a downward displacement of Pu in the sediment column since 1974. Seawater and seaplants showed no evidence of the presence of Pu from sources other than fallout; but Pu in benthos varied nearly proportionally......, but in benthos 241Am/239,240Pu were two times higher than in sediments. Seaplants showed the same value of Am/Pu as seawater. There was no indication of any biomagnification of Pu or Am through the marine food chains at Thule....

  11. Property Data for Simulated Americium/Curium Glasses

    Energy Technology Data Exchange (ETDEWEB)

    Riley, B.J.; Smith, D.E.; Peeler, D.K.; Reamer, I.A.; Vienna, J.D.; Schweiger, M.J.

    1999-10-20

    The authors studied the properties of mixed lanthanide-alumino-borosilicate glasses. Fifty-five glasses were designed to augment a previous, Phase I, study by systematically varying the composition of Ln{sub 2}O{sub 3} and the concentrations of Ln{sub 2}O{sub 3}, SiO{sub 2}, B{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, and SrO in glass. These glasses were designed and fabricated at the Savannah River Technology Center and tested at the Pacific Northwest National Laboratory. The properties measured include the high-temperature viscosity ({eta}) as a function of temperature (T) and the liquidus temperature (T{sub L}) of Phase II test glasses.

  12. Plutonium and americium contamination in Rocky Flats soil, 1973

    Energy Technology Data Exchange (ETDEWEB)

    Krey, P.; Hardy, E.; Volchok, H.; Toonkel, L.; Knuth, R.; Coppes, M.; Tamura, T.

    1976-03-01

    The plutonium mass isotopic analysis and the Am-241 analysis of soil samples from Rocky Flats identify the contamination as Pu which was processed in 1958. The Am-241 activity in the soil will reach its maximum in 2033 and represent 18 percent of the Pu-239-240 activity. Nuclide ratios indicate that current operations at Rocky Flats contribute little to the airborne Pu concentrations which are due to resuspension of the contaminated soil. Root uptake of Pu or Am by vegetation is slight or shows no discrimination among the isotopes and nuclides studied. The relationship between Pu deposition contour and the area enclosed by that contour has been verified for contour values extending over 7 orders of magnitude. This gives confidence to our calculations of the quantities of Pu released on and off the Rocky Flats plant site. (auth)

  13. Biosorption of americium-241 by immobilized Rhizopus arrihizus

    Energy Technology Data Exchange (ETDEWEB)

    Liao Jiali E-mail: liaojiali@163.com; Yang Yuanyou; Luo Shunzhong; Liu Ning; Jin Jiannan; Zhang Taiming; Zhao Pengji

    2004-01-01

    Rhizopus arrihizus (R. arrihizus), a fungus, which in previous experiments had shown encouraging ability to remove {sup 241}Am from solutions, was immobilized by calcium alginate and other reagents. The various factors affecting {sup 241}Am biosorption by the immobilized R. arrihizus were investigated. The results showed that not only can immobilized R. arrihizus adsorb {sup 241}Am as efficiently as free R. arrihizus, but that also can be used repeatedly or continuously. The biosorption equilibrium was achieved within 2 h, and more than 94% of {sup 241}Am was removed from {sup 241}Am solutions of 1.08 MBq/l by immobilized R. arrihizu in the pH range 1-7. Temperature did not affect the adsorption on immobilized R. arrihizus in the range 15-45 deg. C. After repeated adsorption for 8 times, the immobilized R. arrihizus still adsorbed more than 97% of {sup 241}Am. At this time, the total adsorption of {sup 241}Am was more than 88.6 KBq/g, and had not yet reached saturation. Ninety-five percent of the adsorbed {sup 241}Am was desorbed by saturated EDTA solution and 98% by 2 mol/l HNO{sub 3}.

  14. Synthesis of 2,3,7-trihydroxy-9-Camphenal-6-Fluorone with new reagent and Its Spectrophotometric Application in Determining Ti(IV) in Alloy Steel%新试剂莰烯基荧光酮的合成及光度法测定合金钢中钛

    Institute of Scientific and Technical Information of China (English)

    鲍时安; 李先春; 王敦清

    2000-01-01

      The report in this paper is about the synthesis of 2,3,7 trihydroxy -9- camphenal -6- fluorone (CAF) with a new reagent. The result of this study shows that Ti(IV)-CAF-Triton X-l00 can form a ternary complex(1:1:1),which has the maximum absorption at 562 nm and the molar absorption coefficient is 7.5×0-4 L.mol-1.cm-1. If the new spectrophotometric method is used to determine titanium contents in alloy steel samples, the result will be comparatively satisfactory. The method will be poved to be simple and direct.%  报导2,3,7-三羟基-9-莰烯基-6-荧光酮(简称CAF)的合成及光度法测定合金钢中Ti(IV)含量.结果表明,在酸性介质中,Ti(IV)-CAF-Triton X-100形成1:1:1三元络合物.最大吸收波长为562 nm,摩尔吸光系数7.5×104 L.mol-1. cm-1,Ti(IV)浓度在0~10mg/25ml范围内符合比尔定律.方法用于合金钢中钛的测定,方法快速简便,结果较为满意.

  15. Retraction of a paper containing plagiarized material: the prognostic value of serum troponin T in unstable angina. Gökhan Cin V, Gök H, Kaptanoğlu B. Int J Cardiol. 1996 Mar;53(3):237-44.

    Science.gov (United States)

    Coats, Andrew J S

    2010-12-01

    On the 6th December 2008, in my role as Editor-in-Chief of the International Journal of Cardiology, I received an email from Professor Harold Garner of UT Southwestern Medical Center, Dallas. Professor Garner told me that using a new search engine methodology (eTBLAST) he and colleagues had identified a paper in the International Journal of Cardiology published in 1996 which had remarkable text and data similarity to an earlier paper published in 1992 in the New England Journal of Medicine. They had detected this similarity after randomly selecting citations from Medline and submitting them to the tool to find other highly similar citations as part of their NIH/R01 funded research on the ethics of publication. We have been notified that all such cases are reported in a database, Déjà Vu (http://spore.swmed.edu/dejavu/). We investigated the text of the two papers and we agreed that there was such a similarity that the later paper must have plagiarized the earlier paper, and in doing so infringed the copyright. In accordance with our previously published standards on ethical publishing in the Journal we hereby retract the paper "The prognostic value of serum troponin T in unstable angina. Gökhan Cin V, Gök H, Kaptanoğlu B. Int J Cardiol. 1996 Mar;53(3):237-44.".

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  1. Dicty_cDB: SSL237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available 00384_3475( CP000384 |pid:none) Mycobacterium sp. MCS, complete... 38 0.13 DQ418879_1( DQ418879 |pid:none) Glycine max cultivar Resni...ck senes... 37 0.28 AP007164_779( AP007164 |pid:none) Aspergillus oryzae RIB40 geno

  2. Dicty_cDB: SFI237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available N BG790353 |BG790353.1 sae68c10.y1 Gm-c1064 Glycine max cDNA clone GENOME SYSTEMS CLONE ID: Gm-c1064-3212 5...-05 1 BI315670 |BI315670.1 saf75f12.y1 Gm-c1078 Glycine max cDNA clone GENOME SYSTEMS CLONE ID: Gm-c1078-218....1 sa37e09.y1 Gm-c1004 Glycine max cDNA clone GENOME SYSTEMS CLONE ID: Gm-c1004-1...INHIBITOR. ;, mRNA sequence. 62 1e-05 1 BE800797 |BE800797.1 sq98c12.y1 Gm-c1049 Glycine max cDNA clone GENOME SYSTEMS...N INHIBITOR. ;, mRNA sequence. 62 1e-05 1 AW397479 |AW397479.1 sg79d05.y1 Gm-c1007 Glycine max cDNA clone GENOME SYSTEMS

  3. 43 CFR 23.7 - Approval of exploration plan.

    Science.gov (United States)

    2010-10-01

    ... operations to explore, test, or prospect for minerals covered by the mineral leasing acts the operator shall... measures to be taken to prevent or control fire, soil erosion, pollution of surface and ground water... operator any changes, additions, or amendments necessary to meet the requirements formulated pursuant...

  4. 30 CFR 23.7 - Specific requirements for approval.

    Science.gov (United States)

    2010-07-01

    ... reserves the right to require the attachment of wiring diagrams to the cases of telephones and signal..., the electrical design and construction of telephones and signal devices shall be such that neither... external terminals and circuits will result in electrical sparks capable of igniting explosive...

  5. Dicty_cDB: VSF237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available nxfl Translated Amino Acid sequence (All Frames) Frame A: isqchhlkpspentpsistrdst...elpsriepqklsnksssllkrswvpkmsvlitn*tns ygakvsrtfhtesvspsqeretkmktqlknytlllh*sssraskvskpkkllttkwfn*n kffnif*kk--- ---isqchhlkpspent

  6. 48 CFR 237.104 - Personal services contracts.

    Science.gov (United States)

    2010-10-01

    ... intelligence component or counter-intelligence organization of DoD; or (iii) Directly support the mission of...: (i) The services to be procured are urgent or unique; (ii) It would not be practical to obtain...

  7. Dicty_cDB: VSH237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available elium discoideum small aggregate formation ... 54 0.007 1 ( M19469 ) Dictyostelium discoideum 109 gene 3, co...tyostelium citrinum mitochondrion, complete ge... 115 2e-40 3 ( U48706 ) Dictyost

  8. Dicty_cDB: AFM237 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available pmfrc*iwqtys cvtn**yhrrsqwqsl*slpqtilfrslpssp*g*lifstwwyesrri*scrnrpr*ily rctrdiytl*r*gsqerg*rpsr*gwlr*--- ---mcfvl**vg*xctxxrf...itr*cwwcw**syqsnfn*ngwyerqexrfhhwcyq*try hrssyppsrsfrsthlhsitr...ftiscchxqglxq*ixsrqgcrfxifgskxsrfxwxrfn *nlstcl*isys*ih*kgy*ixqspsxiw*xqxgx*lcrsxtrnys*slpxsheicssfx ir**y*k

  9. 48 CFR 1252.237-72 - Prohibition on advertising.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Prohibition on advertising... Prohibition on advertising. As prescribed in (TAR) 48 CFR 1213.7101 and 1237.7003, insert the following clause: Prohibition on Advertising (JAN 1996) The contractor or its representatives (including training...

  10. Americium and plutonium separation by extraction chromatography for determination by accelerator mass spectrometry.

    Science.gov (United States)

    Kazi, Zakir H; Cornett, Jack R; Zhao, Xaiolei; Kieser, Liam

    2014-06-04

    A simple method was developed to separate Pu and Am using single column extraction chromatography employing N,N,N',N'-tetra-n-octyldiglycolamide (DGA) resin. Isotope dilution measurements of Am and Pu were performed using accelerator mass spectrometry (AMS) and alpha spectrometry. For maximum adsorption Pu was stabilized in the tetra valent oxidation state in 8M HNO3 with 0.05 M NaNO2 before loading the sample onto the resin. Am(III) was adsorbed also onto the resin from concentrated HNO3, and desorbed with 0.1 M HCl while keeping the Pu adsorbed. The on-column reduction of Pu(IV) to Pu(III) with 0.02 M TiCl3 facilitated the complete desorption of Pu. Interferences (e.g. Ca(2+), Fe(3+)) were washed off from the resin bed with excess HNO3. Using NdF3, micro-precipitates of the separated isotopes were prepared for analysis by both AMS and alpha spectrometry. The recovery was 97.7±5.3% and 95.5±4.6% for (241)Am and (242)Pu respectively in reagents without a matrix. The recoveries of the same isotopes were 99.1±6.0 and 96.8±5.3% respectively in garden soil. The robustness of the method was validated using certified reference materials (IAEA 384 and IAEA 385). The measurements agree with the certified values over a range of about 1-100 Bq kg(-1). The single column separation of Pu and Am saves reagents, separation time, and cost.

  11. Neutron capture and neutron-induced fission experiments on americium isotopes with DANCE

    Science.gov (United States)

    Jandel, M.; Bredeweg, T. A.; Stoyer, M. A.; Wu, C. Y.; Fowler, M. M.; Becker, J. A.; Bond, E. M.; Couture, A.; Haight, R. C.; Haslett, R. J.; Henderson, R. A.; Keksis, A. L.; O'Donnell, J. M.; Rundberg, R. S.; Ullmann, J. L.; Vieira, D. J.; Wilhelmy, J. B.; Wouters, J. M.

    2009-01-01

    Neutron capture cross section data on Am isotopes were measured using the Detector for Advanced Neutron Capture Experiments (DANCE) at Los Alamos National Laboratory. The neutron capture cross section was determined for 241Am for neutron energies between thermal and 320 keV. Preliminary results were also obtained for 243Am for neutron energies between 10 eV and 250 keV. The results on concurrent neutron-induced fission and neutron-capture measurements on 242mAm will be presented where the fission events were actively triggered during the experiments. In these experiments, a Parallel-Plate Avalanche Counter (PPAC) detector that surrounds the target located in the center of the DANCE array was used as a fission-tagging detector to separate (n,γ) events from (n,f) events. The first direct observation of neutron capture on 242mAm in the resonance region in between 2 and 9 eV of the neutron energy was obtained.

  12. Evaluation of the readsorption of plutonium and americium in dynamic fractionations of environmental solid samples

    DEFF Research Database (Denmark)

    Petersen, Roongrat; Hou, Xiaolin; Hansen, Elo Harald

    2008-01-01

    A dynamic extraction system exploiting sequential injection (SI) for sequential extractions incorporating a specially designed extraction column is developed to fractionate radionuclides in environmental solid samples such as soils and sediments. The extraction column can contain a large amount...... of the two radionuclides. However, the dynamic system is fully automated, eliminates manual separations, significantly reduces the operational time required, and offers detailed kinetic information....

  13. Effect of solvent on in vitro dissolution: Summary of results for uranium, americium, and cobalt aerosols

    Energy Technology Data Exchange (ETDEWEB)

    Guilmette, R.A.; Hoover, M.D.

    1995-12-01

    The revised 10 CFR Part 20 has adopted the ICRP Publication 30 method for calculating the committed effective dose equivalent from intakes of radionuclides. This dosimetry scheme requires knowledge or assumptions about the chemical form of the radionuclide, its particle size, and its known or assumed solubility. The solubility is classified as being either D (relatively soluble), W, or Y (relatively insoluble), depending on whether the material dissolves over periods of days, weeks, or years. Although Nuclear Regulatory Commission licensees may wish to take advantage of material-specific knowledge in order to adjust annual limits on intake and derived air concentrations, relatively few radioactive materials to which workers and the general population may be exposed have been adequately characterized either in terms of physicochemical form or solubility. Experimental measurement of solubility using some type of in vitro dissolution measurement system is therefore needed. However, there is currently no clear consensus regarding the appropriate design of in vitro dissolution systems, particularly when considering the range of different radionuclides to be studied, and the complexity of the biological mechanisms involved in the retention and clearance of inhaled deposited radioactive particles. The purpose of this study was to evaluate the effect of the several solvents on the dissolution of four test aerosols ({sup 57}Co{sub 3}O{sub 4}, {sup 241}AmO{sub 2}, ammonium diuranate [ADU], and U{sub 3}O{sub 8}) selected to encompass a variety of chemical and biochemical properties in vivo. The results of this study provide some guidance on the usefulness of in vitro dissolution tests for estimating the solubility of unknown radionuclide particles within the context of a simple model such as the class D, W, and Y formulation of ICRP 30.

  14. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    Witt, D.C.

    1999-11-08

    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.

  16. Functional sorbents for selective capture of plutonium, americium, uranium, and thorium in blood.

    Science.gov (United States)

    Yantasee, Wassana; Sangvanich, Thanapon; Creim, Jeffery A; Pattamakomsan, Kanda; Wiacek, Robert J; Fryxell, Glen E; Addleman, R Shane; Timchalk, Charles

    2010-09-01

    Self-assembled monolayer on mesoporous supports (SAMMS) are hybrid materials created from attachment of organic moieties onto very high surface area mesoporous silica. SAMMS with surface chemistries including three isomers of hydroxypyridinone, diphosphonic acid, acetamide phosphonic acid, glycinyl urea, and diethylenetriamine pentaacetate (DTPA) analog were evaluated for chelation of actinides ((239)Pu, (241)Am, uranium, thorium) from blood. Direct blood decorporation using sorbents does not have the toxicity or renal challenges associated with traditional chelation therapy and may have potential applications for critical exposure cases, reduction of nonspecific dose during actinide radiotherapy, and for sorbent hemoperfusion in renal insufficient patients, whose kidneys clear radionuclides at a very slow rate. Sorption affinity (K(d)), sorption rate, selectivity, and stability of SAMMS were measured in batch contact experiments. An isomer of hydroxypyridinone (3,4-HOPO) on SAMMS demonstrated the highest affinity for all four actinides from blood and plasma and greatly outperformed the DTPA analog on SAMMS and commercial resins. In batch contact, a fifty percent reduction of actinides in blood was achieved within minutes, and there was no evidence of protein fouling or material leaching in blood after 24 h. The engineered form of SAMMS (bead format) was further evaluated in a 100-fold scaled-down hemoperfusion device and showed no blood clotting after 2 h. A 0.2 g quantity of SAMMS could reduce 50 wt.% of 100 ppb uranium in 50 mL of plasma in 18 min and that of 500 dpm mL(-1) in 24 min. 3,4-HOPO-SAMMS has a long shelf-life in air and at room temperature for at least 8 y, indicating its feasibility for stockpiling in preparedness for an emergency. The excellent efficacy and stability of SAMMS materials in complex biological matrices suggest that SAMMS can also be used as orally administered drugs and for wound decontamination. By changing the organic groups of SAMMS, they can be used not only for actinides but also for other radionuclides. By using the mixture of these SAMMS materials, broad spectrum decorporation of radionuclides is very feasible.

  17. Subsurface Behavior of Plutonium and Americium at Non-Hanford Sites and Relevance to Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J.; Riley, Robert G.

    2008-02-01

    Seven sites where Pu release to the environment has raised significant environmental concerns have been reviewed. A summary of the most significant hydrologic and geochemical features, contaminant release events and transport processes relevant to Pu migration at the seven sites is presented.

  18. New Synthetic Methods and Structure-Property Relationships in Neptunium, Plutonium, and Americium Borates. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Albrecht-Schmitt, Thomas Edward

    2013-09-14

    The past three years of support by the Heavy Elements Chemistry Program have been highly productive in terms of advanced degrees awarded, currently supported graduate students, peer-reviewed publications, and presentations made at universities, national laboratories, and at international conferences. Ph.D. degrees were granted to Shuao Wang and Juan Diwu, who both went on to post-doctoral appointments at the Glenn T. Seaborg Center at Lawrence Berkeley National Laboratory with Jeff Long and Ken Raymond, respectively. Pius Adelani completed his Ph.D. with me and is now a post-doc with Peter C. Burns. Andrea Alsobrook finished her Ph.D. and is now a post-doc at Savannah River with Dave Hobbs. Anna Nelson completed her Ph.D. and is now a post-doc with Rod Ewing at the University of Michigan. As can be gleaned from this list, students supported by the Heavy Elements Chemistry grant have remained interested in actinide science after leaving my program. This follows in line with previous graduates in this program such as Richard E. Sykora, who did his post-doctoral work at Oak Ridge National Laboratory with R. G. Haire, and Amanda C. Bean, who is a staff scientist at Los Alamos National Laboratory, and Philip M. Almond and Thomas C. Shehee, who are both staff scientists at Savannah River National Laboratory, Gengbang Jin who is a staff scientist at Argonne National Lab, and Travis Bray who has been a post-doc at both LBNL and ANL. Clearly this program is serving as a pipe-line for students to enter into careers in the national laboratories. About half of my students depart the DOE complex for academia or industry. My undergraduate researchers also remain active in actinide chemistry after leaving my group. Dan Wells was a productive undergraduate of mine, and went on to pursue a Ph.D. on uranium and neptunium chalcogenides with Jim Ibers at Northwestern. After earning his Ph.D., he went directly into the nuclear industry.

  19. Plutonium and americium inventories in atmospheric fallout and sediment cores from Blelham Tarn, Cumbria (UK)

    Energy Technology Data Exchange (ETDEWEB)

    Michel, H. E-mail: herve.michel@unice.fr; Barci-Funel, G.; Dalmasso, J.; Ardisson, G.; Appleby, P.G.; Haworth, E.; El-Daoushy, F

    2002-07-01

    The objective of this paper is to report on the results of a study of {sup 238}Pu, {sup 239+240}Pu and {sup 241}Am inventories onto Blelham Tarn in Cumbria (UK). The atmospheric fallout inventory was obtained by analysing soil cores and the results are in good agreement with the literature: 101 Bq m{sup -2} for {sup 239+240}Pu; 4.5 Bq m{sup -2} for {sup 238}Pu and 37 Bq m{sup -2} for {sup 241}Am. The sediment core inventory for the whole lake is compared to the atmospheric fallout inventory. The sediment activity is 60-80% higher than the estimated fallout activity, showing a catchment area contribution and in particular the stream input.

  20. Plutonium and americium inventories in atmospheric fallout and sediment cores from Blelham Tarn, Cumbria (UK).

    Science.gov (United States)

    Michel, H; Barci-Funel, G; Dalmasso, J; Ardisson, G; Appleby, P G; Haworth, E; El-Daoushy, F

    2002-01-01

    The objective of this paper is to report on the results of a study of 238Pu, 239 + 240Pu and 241Am inventories onto Blelham Tarn in Cumbria (UK). The atmospheric fallout inventory was obtained by analysing soil cores and the results are in good agreement with the literature: 101 Bq m(-2) for 239 + 240Pu; 4.5 Bq m(-2) for 238Pu and 37 Bq m(-2) for 241Am. The sediment core inventory for the whole lake is compared to the atmospheric fallout inventory. The sediment activity is 60-80% higher than the estimated fallout activity, showing a catchment area contribution and in particular the stream input.

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

    Energy Technology Data Exchange (ETDEWEB)

    Carlton, W.H. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-12-17

    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.

  2. Fundamental chemistry and materials science of americium in selected immobilization glasses

    Energy Technology Data Exchange (ETDEWEB)

    Haire, R.G. [Oak Ridge National Lab., TN (United States); Stump, N.A. [Winston-Salem State Univ., NC (United States). Dept. of Physical Sciences

    1996-12-01

    We have pursued some of the fundamental chemistry and materials science of Am in 3 glass matrices, two being high-temperature (850 and 1400 C mp) silicate-based glasses and the third a sol-gel glass. Optical spectroscopy was the principal tool. One aspect of this work was to determine the oxidation state exhibited by Am in these matrices, as well as factors that control or may alter this state. A correlation was noted between the oxidation state of the f-elements in the two high-temperature glasses with their high-temperature oxide chemistries. One exception was Am: although AmO{sub 2} is the stable oxide encountered in air, when this dioxide was incorporated into the high-temperature glasses, only trivalent Am was found in the products. When Am(III) was used to prepare the sol-gel glasses at ambient temperature, and after these products were heated in air to 800 C, only Am(III) was observed. Potential explanations for the unexpected Am behavior is offered in the context of its basic chemistry. Experimental spectra, spectroscopic assignments, etc. are discussed.

  3. Americium, curium and neodymium analysis in ECRIX-H irradiated pellet. Sample preparation for TIMS measurements

    Energy Technology Data Exchange (ETDEWEB)

    Esbelin, E.; Buravand, E. [Commissariat a l' Energie Atomique, Bagnols-sur-Ceze (France). Centre de Marcoule; Bejaoui, S.; Lamontagne, J.; Bonnerot, J.M. [Commissariat a l' Energie Atomique, St-Paul-Lez-Durance (France). Centre de Cadarache

    2013-08-01

    This paper concerns quantitative isotopic analysis of Am, Cm and Nd contained in an irradiated AmO{sub 1.62}/MgO pellet. The complete analysis protocol is described, from dissolution of the pellets in a shielded line to the laboratory glove separation processes box for TIMS analysis. Emphasis is placed on the separation processes: by ion exchange resin in a hot cell and by HPLC in the laboratory. Intermediate measurements by X-ray fluorescence, alpha spectrometry, and ICP-AES are described. (orig.)

  4. Optimization of TRPO Process Parameters for Americium Extraction from High Level Waste

    Institute of Scientific and Technical Information of China (English)

    CHEN Jing; WANG Jianchen; SONG Chongli

    2001-01-01

    The numerical calculations for Am multistage fractional extraction by trialkyl phosphine oxide (TRPO) were verified by a hot test.1750 L/t-U high level waste (HLW) was used as the feed to the TRPO process.The analysis used the simple objective function to minimize the total waste content in the TRPO process streams.Some process parameters were optimized after other parameters were selected.The optimal process parameters for Am extraction by TRPO are:10 stages for extraction and 2 stages for scrubbing;a flow rate ratio of 0.931 for extraction and 4.42 for scrubbing;nitric acid concentration of 1.35 mol/L for the feed and 0.5 mol/L for the scrubbing solution.Finally,the nitric acid and Am concentration profiles in the optimal TRPO extraction process are given.

  5. Vertical distribution of radiocaesium, plutonium and americium in the Catalan Sea (northwestern Mediterranean)

    Energy Technology Data Exchange (ETDEWEB)

    Molero, J.; Sanchez-Cabeza, J.A.; Merino, J.; Pujol, Ll.; Vidal-Quadras, A. [Universidad Autonoma de Barcelona (Spain). Facultad de Ciencias; Mitchell, P.I. [University Coll., Dublin (Ireland). Lab. of Radiation Physics

    1995-07-01

    Caesium-137, {sup 239,240}Pu and {sup 241}Am concentration profiles (0-1000 m) have been determined in unfiltered large volume water samples collected from the Catalan Sea (northwestern Mediterranean). Results showed that radiocaesium concentration decreases quickly through the water column while the transuranic concentration increases with depth, showing a faster migration to the bottom layers. Comparing our results with those reported by other authors (1975-1980), radiocaesium input from Chernobyl releases has been identified through the profile. In addition, transuranic concentrations have decreased considerably in the different layers of the profile. (Author).

  6. Americium and plutonium separation by extraction chromatography for determination by accelerator mass spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Kazi, Zakir H. [Department of Earth Science, University of Ottawa, 140 Louis Pasteur Avenue, Ottawa K1N 6N5 (Canada); Cornett, Jack R., E-mail: jack.cornett@uottawa.ca [Department of Earth Science, University of Ottawa, 140 Louis Pasteur Avenue, Ottawa K1N 6N5 (Canada); Zhao, Xaiolei; Kieser, Liam [Department of Physics, University of Ottawa, 140 Louis Pasteur Avenue, Ottawa K1N 6N5 (Canada)

    2014-06-01

    Highlights: • Am and Pu were adsorbed and separated using a single extraction chromatography DGA column. • Pu was eluted from the column completely using on-column reduction of Pu(IV) to Pu(III). • ²⁴¹Am and 239,240Pu measurements by accelerator mass spectrometry (AMS) agree with the certified values in two SRMs. Abstract: A simple method was developed to separate Pu and Am using single column extraction chromatography employing N,N,N',N'-tetra-n-octyldiglycolamide (DGA) resin. Isotope dilution measurements of Am and Pu were performed using accelerator mass spectrometry (AMS) and alpha spectrometry. For maximum adsorption Pu was stabilized in the tetra valent oxidation state in 8 M HNO₃ with 0.05 M NaNO₂ before loading the sample onto the resin. Am(III) was adsorbed also onto the resin from concentrated HNO₃, and desorbed with 0.1 M HCl while keeping the Pu adsorbed. The on-column reduction of Pu(IV) to Pu(III) with 0.02 M TiCl₃ facilitated the complete desorption of Pu. Interferences (e.g. Ca²⁺, Fe³⁺) were washed off from the resin bed with excess HNO₃. Using NdF₃, micro-precipitates of the separated isotopes were prepared for analysis by both AMS and alpha spectrometry. The recovery was 97.7 ± 5.3% and 95.5 ± 4.6% for ²⁴¹Am and ²⁴²Pu respectively in reagents without a matrix. The recoveries of the same isotopes were 99.1 ± 6.0 and 96.8 ± 5.3% respectively in garden soil. The robustness of the method was validated using certified reference materials (IAEA 384 and IAEA 385). The measurements agree with the certified values over a range of about 1–100 Bq kg⁻¹. The single column separation of Pu and Am saves reagents, separation time, and cost.

  7. Criteria Considered in Selecting Feed Items for Americium-241 Oxide Production Operations

    Energy Technology Data Exchange (ETDEWEB)

    Schulte, Louis D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-30

    The analysis in this document serves the purpose of defining a number of attributes in selection of feed items to be utilized in recovery/recycle of Pu and also production operations of 241AmO2 material intended to meet specification requirements. This document was written in response to a specific request on the part of the 2014 annual program review which took place over the dates of October 28-29, 2014. A number of feed attributes are noted including: (1) Non-interference with existing Pu recovery operations; (2) Content of sufficient 241Am to allow process efficiency in recovery operations; (3) Absence of indications that 243Am might be mixed in with the Pu/241Am material; (4) Absence of indications that Cm might be mixed in with the Pu/241Am material; (5) Absence of indications of other chemical elements that would present difficulty in chemical separation from 241Am; (6) Feed material not expected to present difficulty in dissolution; (7) Dose issues; (8) Process efficiency; (9) Size; (10) Hazard associated with items and package configuration in the vault; (11) Within existing NEPA documentation. The analysis in this document provides a baseline of attributes considered for feed materials, but does not presume to replace the need for technical expertise and judgment on the part of individuals responsible for selecting the material feed to be processed. This document is not comprehensive as regards all attributes that could prove to be important. The value of placing a formal QA hold point on accepting feed items versus more informal management of feed items is discussed in the summation of this analysis. The existing planned QA hold points on 241AmO2 products produced and packaged may be adequate as the entire project is based on QA of the product rather than QA of the process. The probability of introduction of items that would inherently cause the241AmO2 products produced to be outside of specification requirements appears to be rather small.

  8. Pu236(n,f) , Pu237(n,f) , and Pu238(n,f) cross sections deduced from (p,t) , (p,d) , and (p,p') surrogate reactions

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, R. O. [Univ. of Richmond, VA (United States); Beausang, C. W. [Univ. of Richmond, VA (United States); Ross, T. J. [Univ. of Richmond, VA (United States); Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Casperson, R. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Cooper, N. [Yale Univ., New Haven, CT (United States); Escher, J. E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Gell, K. [Univ. of Richmond, VA (United States); Good, E. [Univ. of Richmond, VA (United States); Humby, P. [Yale Univ., New Haven, CT (United States); McCleskey, M. [Texas A & M Univ., College Station, TX (United States); Saastimoinen, A. [Texas A & M Univ., College Station, TX (United States); Tarlow, T. D. [Univ. of Richmond, VA (United States); Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-07-01

    The Pu236(n,f), Pu237(n,f) and Pu238(n,f) cross sections have been inferred by utilizing the surrogate ratio method. Targets of Pu239 and U235 were bombarded with 28.5-MeV protons, and the light ion recoils, as well as fission fragments, were detected using the STARS detector array at the K150 Cyclotron at the Texas A&M cyclotron facility. The (p, tf) reaction on Pu239 and U235 targets was used to deduce the σ (Pu236(n,f))/σ(U232(n,f)) ratio, and the Pu236(n,f) cross section was subsequently determined for En=0.5–7.5 MeV. Similarly, the (p,df) reaction on the same two targets was used to deduce the σ(Pu237(n,f))/σ(U233(n,f)) ratio, and the Pu237(n,f) cross section was extracted in the energy range En=0.5–7 MeV. The Pu238(n,f) cross section was also deduced by utilizing the (p,p') reaction channel on the same targets. There is good agreement with the recent ENDF/B-VII.1 evaluated cross section data for Pu238(n,f) in the range En=0.5–10.5 MeV and for Pu237(n,f) in the range En=0.5–7 MeV; however, the Pu236(n,f) cross section deduced in the present work is higher than the evaluation between 2 and 7 MeV.

  9. Actinide partitioning and transmutation program. Progress report, July 1--September 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Tedder, D.W.; Blomeke, J.O. (comps.)

    1978-02-01

    In Purex process modifications, two cold runs with mixer-settlers were made on the extraction and stripping of ruthenium and zirconium without the presence of uranium. Efforts in actinide recovery from solids were directed toward the determination of dissolution parameters in various reagents for /sup 241/Am and /sup 239/Pu oxide mixtures, /sup 233/U oxide, /sup 237/Np oxide, /sup 244/Cm oxide, /sup 232/Th oxide, and PuO/sub 2/. Studies in americium-curium recovery with OPIX (oxalate precipitation and ion exchange), Talspeak, and cation exchange chromatography focused on the feasibility of forming oxalate precipitates in continuous systems, the effects of zirconium on Talspeak, and methods for removing solvent degradation products of the Talspeak system. In studies of americium-curium recovery using bidentate extractants, additional distribution coefficients for actinides and other key elements between reduced synthetic LWR waste solution and 30 percent dihexyl-N, N-diethyl-carbamylmethylene phosphonate in diisopropylbenzene were measured. Studies in the americium-curium recovery using inorganic ion exchange media to determine the pH dependence of lanthanide ion affinity for niobate, titanate, and zirconate ion exchange materials have been completed. A modified flowsheet for the extraction of uranium, neptunium, plutonium, americium, and curium from high-level liquid waste is presented. Evaluation of methods for measuring actinides from incinerator ash is continuing. A preliminary evaluation of methods for treatment of salt waste and waste waters was completed. In thermal reactor transmutation studies, waste actinides from an LWR lattice containing mixed uranium-plutonium assemblies were recycled in separate target assemblies. (LK)

  10. Yeast Interacting Proteins Database: YGL237C, YLR423C [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available binding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences sufficient...riptional activator and global regulator of respiratory gene expression; contains sequences sufficient for b

  11. Yeast Interacting Proteins Database: YGL237C, YOR358W [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available binding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences sufficient...icient for both complex assembly and DNA binding Rows wi...4p/5p CCAAT-binding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences suff

  12. Yeast Interacting Proteins Database: YGL237C, YGR146C [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available binding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences sufficient...inding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences sufficient

  13. Yeast Interacting Proteins Database: YGL237C, YBL021C [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available binding complex, a transcriptional activator and global regulator of respiratory gene expression; contains sequences sufficient...y gene expression; contains sequences sufficient for both complex assembly and DN

  14. Natural Disasters and Adaptive Capacity. OECD Development Centre Working Paper No. 237

    Science.gov (United States)

    Dayton-Johnson, Jeff

    2004-01-01

    Natural disasters (droughts, earthquakes, epidemics, floods, wind storms) damage wellbeing, both in their immediate and long-term aftermath, and because the insecurity of exposure to disasters is in itself harmful to risk-averse people. As such, mitigating and coping with the risk of natural disasters is a pressing issue for economic development.…

  15. 19 CFR 10.237 - Verification and justification of claim for preferential tariff treatment.

    Science.gov (United States)

    2010-04-01

    ... RATE, ETC. United States-Caribbean Basin Trade Partnership Act Non-Textile Articles Under the United... as purchase orders, invoices, bills of lading and other shipping documents, and customs import...

  16. 40 CFR 86.237-94 - Dynamometer test run, gaseous emissions.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false Dynamometer test run, gaseous... test run, gaseous emissions. (a) The complete dynamometer test consists of a cold start drive of... terminates after the first period (505 seconds) is run. (d) The provisions of § 86.137(b) apply to...

  17. 40 CFR 86.237-08 - Dynamometer test run, gaseous emissions.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 18 2010-07-01 2010-07-01 false Dynamometer test run, gaseous... test run, gaseous emissions. (a) The complete dynamometer test consists of a cold start drive of... terminates after the first period (505 seconds) is run. (d) The dynamometer run consists of two tests, a...

  18. P2-37: Processing Affordance Information from Invisible Tool Images

    Directory of Open Access Journals (Sweden)

    Shinho Cho

    2012-10-01

    Full Text Available A recent study showed that viewing manipulable objects such as images of tools induces the neural activation of posterior parietal areas. This neural activation is observed even when visual awareness of the image is visually suppressed. (Fang and He, 2005 Nature Neuroscience 10 1380–1385; Almeida et al, 2010 Psychological Science 21 772–778. However, the specific visuomotor information in tool images that drives the activation of dorsal areas is still unclear. We measured priming effect of invisible tool prime (left or right handed orientation. Observers distinguished the orientation of target tools (appropriate for left vs right handed grip briefly presented following visually suppressed primes (Experiment1. Also we measured the suppression time of tool images whose handle direction was presented in a left- or right-handed orientation. A dynamic noise pattern was presented to one of the observer's eyes at full contrast, while images of tools (left or right handed were simultaneously presented to the left or right visual field of the other eye. The subjects were asked to respond to the appearance of any partial or full part of the test image (Experiment 2. Results showed that (1 observers responded faster in the congruent condition (the same orientation between prime and target and (2 tool images shown in the right visual field took less time to gain dominance against the dynamic noise. These results suggest that even without overt recognition of presented tools, an object's affordance can be registered and processed in the brain. A recent study showed that viewing manipulable objects such as images of tools induces the neural activation of posterior parietal areas. This neural activation is observed even when visual awareness of the image is visually suppressed (Almeida et al., 2010 Psychological Science 21 772–778; Fang and He, 2005 Nature Neuroscience 10 1380–1385. However, the specific visuomotor information in tool images that drives the activation of dorsal areas is still unclear. We measured the priming effect of invisible tool prime (left or right handed orientation. Observers distinguished the orientation of target tools (appropriate for left vs. right handed grip briefly presented following visually suppressed primes (Experiment 1. Also we measured the suppression time of tool images whose handle direction was presented in a left- or right-handed orientation. A dynamic noise pattern was presented to one of the observer's eyes at full contrast, while images of tools (left or right handed were simultaneously presented to the left or right visual field of the other eye. The subjects were asked to respond to the appearance of any partial or full part of the test image (Experiment 2. Results showed that (1 observers responded faster in the congruent condition (the same orientation between prime and target and (2 tool images shown in the right visual field took less time to gain dominance against the dynamic noise. These results suggest that even without overt recognition of presented tools, an object's affordance can be registered and processed in the brain.

  19. SU-E-J-237: Image Feature Based DRR and Portal Image Registration

    Energy Technology Data Exchange (ETDEWEB)

    Wang, X; Chang, J [NY Weill Cornell Medical Ctr, NY (United States)

    2014-06-01

    Purpose: Two-dimensional (2D) matching of the kV X-ray and digitally reconstructed radiography (DRR) images is an important setup technique for image-guided radiotherapy (IGRT). In our clinics, mutual information based methods are used for this purpose on commercial linear accelerators, but with often needs for manual corrections. This work proved the feasibility that feature based image transform can be used to register kV and DRR images. Methods: The scale invariant feature transform (SIFT) method was implemented to detect the matching image details (or key points) between the kV and DRR images. These key points represent high image intensity gradients, and thus the scale invariant features. Due to the poor image contrast from our kV image, direct application of the SIFT method yielded many detection errors. To assist the finding of key points, the center coordinates of the kV and DRR images were read from the DICOM header, and the two groups of key points with similar relative positions to their corresponding centers were paired up. Using these points, a rigid transform (with scaling, horizontal and vertical shifts) was estimated. We also artificially introduced vertical and horizontal shifts to test the accuracy of our registration method on anterior-posterior (AP) and lateral pelvic images. Results: The results provided a satisfactory overlay of the transformed kV onto the DRR image. The introduced vs. detected shifts were fit into a linear regression. In the AP image experiments, linear regression analysis showed a slope of 1.15 and 0.98 with an R2 of 0.89 and 0.99 for the horizontal and vertical shifts, respectively. The results are 1.2 and 1.3 with R2 of 0.72 and 0.82 for the lateral image shifts. Conclusion: This work provided an alternative technique for kV to DRR alignment. Further improvements in the estimation accuracy and image contrast tolerance are underway.

  20. Robert et Maya Kandel, La Catastrophe climatique, Hachette, 2009, 237 p.

    Directory of Open Access Journals (Sweden)

    Luc Semal

    2012-05-01

    Full Text Available Robert Kandel, astrophysicien et directeur de recherche émérite au CNRS, n’en est pas à son premier ouvrage sur le réchauffement climatique. Dans ce nouvel essai (co-rédigé avec sa fille Maya Kandel, il est intéressant de constater un changement de ton assez représentatif de l’inquiétude croissante des scientifiques à l’égard du bouleversement climatique en cours. Tout en rappelant qu’il a longtemps fait preuve de méfiance à l’égard des discours catastrophistes, Robert Kandel annonce dès l’i...

  1. Yeast Interacting Proteins Database: YPR148C, YDL237W [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available YPR148C - Protein of unknown function that may interact with ribosomes, based on co-purification experiments... with ribosomes, based on co-purification experiments; green fluorescent protein

  2. Yeast Interacting Proteins Database: YGL237C, YOR047C [Yeast Interacting Proteins Database

    Lifescience Database Archive (English)

    Full Text Available ene expression; interacts with protein kinase Snf1p, glucose sensors Snf3p and Rgt2p, and TATA-binding prote... expression; interacts with protein kinase Snf1p, glucose sensors Snf3p and Rgt2p, and TATA-binding protein

  3. Analysis of shape isomer yields of 237Pu in the framework of dynamical–statistical model

    Indian Academy of Sciences (India)

    Hadi Eslamizadeh

    2012-02-01

    Data on shape isomer yield for + 235U reaction at $E^{\\text{lab}}$ = 20–29 MeV are analysed in the framework of a combined dynamical–statistical model. From this analysis, information on the double humped fission barrier parameters for some Pu isotopes has been obtained and it is shown that the depth of the second potential well should be less than the results of statistical model calculations.

  4. Correction: Cocaine cardiomyopathy: A case report (2014, vol. 9, no. 3, pp. 233-237)

    OpenAIRE

    Georgijev Antonio; Zhivadinovic Julija

    2016-01-01

    In Sanamed Medical Journal, vol. 9, issue 3, in the text titled 'COCAINE CARDIOMYOPATHY-A CASE REPORT' authors made a mistake by inadequately citing parts of scientific paper, in sections Introduction and Discussion. The mistake was discovered by Center for Evaluation in Education and Science (CEON). Authors were informed from the Editorial Board of Medical Journal 'Sanamed' and the stated parts of paper were timely corrected.

  5. SU-E-J-237: Real-Time 3D Anatomy Estimation From Undersampled MR Acquisitions

    Energy Technology Data Exchange (ETDEWEB)

    Glitzner, M; Lagendijk, J; Raaymakers, B; Crijns, S [University Medical Center Utrecht, Utrecht (Netherlands); Senneville, B Denis de [University Medical Center Utrecht, Utrecht (Netherlands); Mathematical Institute of Bordeaux, University of Bordeaux, Talence Cedex (France)

    2015-06-15

    Recent developments made MRI guided radiotherapy feasible. Performing simultaneous imaging during fractions can provide information about changing anatomy by means of deformable image registration for either immediate plan adaptations or accurate dose accumulation on the changing anatomy. In 3D MRI, however, acquisition time is considerable and scales with resolution. Furthermore, intra-scan motion degrades image quality.In this work, we investigate the sensitivity of registration quality on imageresolution: potentially, by employing spatial undersampling, the acquisition timeof MR images for the purpose of deformable image registration can be reducedsignificantly.On a volunteer, 3D-MR imaging data was sampled in a navigator-gated manner, acquiring one axial volume (360×260×100mm{sup 3}) per 3s during exhale phase. A T1-weighted FFE sequence was used with an acquired voxel size of (2.5mm{sup 3}) for a duration of 17min. Deformation vector fields were evaluated for 100 imaging cycles with respect to the initial anatomy using deformable image registration based on optical flow. Subsequently, the imaging data was downsampled by a factor of 2, simulating a fourfold acquisition speed. Displacements of the downsampled volumes were then calculated by the same process.In kidneyliver boundaries and the region around stomach/duodenum, prominent organ drifts could be observed in both the original and the downsampled imaging data. An increasing displacement of approximately 2mm was observed for the kidney, while an area around the stomach showed sudden displacements of 4mm. Comparison of the motile points over time showed high reproducibility between the displacements of high-resolution and downsampled volumes: over a 17min acquisition, the componentwise RMS error was not more than 0.38mm.Based on the synthetic experiments, 3D nonrigid image registration shows little sensitivity to image resolution and the displacement information is preserved even when halving the resolution. This can be employed to greatly reduce image acquisition times for interventional applications in real-time. This work was funded by the SoRTS consortium, which includes the industry partners Elekta, Philips and Technolution.

  6. Technologic Papers of the Bureau of Standards. Number 237. Aeronautic Instruments,

    Science.gov (United States)

    2007-11-02

    the motion of the airplane or on the speed of rotation of small cup anemometers ’or air propellers. -The indicati6ns of the pressure type are pro...developed by these instruments also obeys the pv2 law. In instruments of the anemometer type the air speed is determined by the rate of revolution by a cup ...to a third sighting Huntl Aeronautitc In struments. 461 FIG. 13.-Pensuti pressure plate air-speed indicator. FIG. 14.-Morell cup anemometer air-speed

  7. Reverberation in the UV-Optical Continuum Brightness Fluctuations of MACHO Quasar 13.5962.237

    CERN Document Server

    Schild, Rudolph E; Protopapas, Pavlos

    2009-01-01

    We examine the nature of brightness fluctuations in the UV-Optical spectral region of an ordinary quasar with 881 optical brightness measurements made during the epoch 1993 - 1999. We find evidence for systematic trends having the character of a pattern of reverberations following an initial disturbance. The initial pulses have brightness increases of order 20% and pulse widths of 50 days, and the reverberations have typical amplitudes of 12% with longer mean pulse widths of order 80 days and pulse separations of order 90 days. The repeat pattern occurs over the same time scales whether the initial disturbance is a brightening or fading. The lags of the pulse trains are comparable to the lags seen previously in reverberation of the broad blue-shifted emission lines following brightness disturbances in Seyfert galaxies, when allowance is made for the mass of the central object. In addition to the burst pulse trains, we find evidence for a semi-periodicity with a time scale of 2 years. These strong patterns of ...

  8. A Review of Subsurface Behavior of Plutonium and Americium at the 200-PW-1/3/6 Operable Units

    Energy Technology Data Exchange (ETDEWEB)

    Cantrell, Kirk J.; Riley, Robert G.

    2008-01-31

    This report begins with a brief summary of the history and current status of 200-PW-1/3/6 OUs in section 2.0. This is followed by a description of our concentual model of Pu/Am migration at the 200-PW-1/3/6 OUs, during both past artificial recharge conditions and current natural recharge condictions (section 3.0). Section 4.0 discusses data gaps and information needs. The final section (section 5.0) provides recommendations for futher work to address the data gaps and information needs identified in section 4.0.

  9. Input contribution and vertical migration of plutonium, americium and cesium in lake sediments (Belham Tarn, Cumbria, UK)

    Energy Technology Data Exchange (ETDEWEB)

    Michel, H.; Barci-Funel, G.; Barci, V.; Ardisson, G. [Lab. de Radiochimie et de Radioecologie, Univ. de Nice Sophia Antipolis, Nice (France)

    2002-07-01

    The record of the global atmospheric fallout could be found in the lake sediments. A mass balance for fallout radionuclides in Blelham Tarn and its catchment is established. The sediment activity contribution is coming from direct atmospheric fallout and from indirect atmospheric fallout via the catchment. The catchement activity is conveyed to the sediment by the rivers and the direct streaming. A comparison of the fallout and the sediment inventory allows the activity estimation of these different contributions and to understand the mobility of these elements on the catchment and in the sediments. The study of activity profile in sediment core allows to characterise the different radioactive events occurred in the past. For the lake Blelham, the results show two cesium activity peaks and only one peak for transuranic activities. The deepest peaks correspond to the atmospheric nuclear test fallout in the sixties (1963) and the second peak to the Chernobyl accident (1986). The activity ratio {sup 239-240}Pu/{sup 137}Cs allows estimating the ratio between cesium activities in sediments coming from these two events. Plutonium and cesium diffusion coefficients are calculated with a simple analytical model. (orig.)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    OpenAIRE

    Higginson, Matthew A.; Thompson, Paul; Marsden, Olivia J.; Livens, Francis R.; Harwood, Laurence M.; Lewis, Frank W.; Hudson, Michael J.; Heath, Sarah L.

    2015-01-01

    In analysis of complex nuclear forensic samples\\ud containing lanthanides, actinides and matrix elements,\\ud rapid selective extraction of Am/Cm for quantification\\ud is challenging, in particular due the difficult separation\\ud of Am/Cm from lanthanides. Here we present\\ud a separation process for Am/Cm(III) which is achieved\\ud using a combination of AG1-X8 chromatography followed\\ud by Am/Cm extraction with a triazine ligand. The ligands\\ud tested in our process were CyMe4-BTPhen, CyMe4-\\u...

  12. LITERATURE REVIEW ON THE SORPTION OF PLUTONIUM, URANIUM, NEPTUNIUM, AMERICIUM AND TECHNETIUM TO CORROSION PRODUCTS ON WASTE TANK LINERS

    Energy Technology Data Exchange (ETDEWEB)

    Li, D.; Kaplan, D.

    2012-02-29

    The Savannah River Site (SRS) has conducted performance assessment (PA) calculations to determine the risk associated with closing liquid waste tanks. The PA estimates the risk associated with a number of scenarios, making various assumptions. Throughout all of these scenarios, it is assumed that the carbon-steel tank liners holding the liquid waste do not sorb the radionuclides. Tank liners have been shown to form corrosion products, such as Fe-oxyhydroxides (Wiersma and Subramanian 2002). Many corrosion products, including Fe-oxyhydroxides, at the high pH values of tank effluent, take on a very strong negative charge. Given that many radionuclides may have net positive charges, either as free ions or complexed species, it is expected that many radionuclides will sorb to corrosion products associated with tank liners. The objective of this report was to conduct a literature review to investigate whether Pu, U, Np, Am and Tc would sorb to corrosion products on tank liners after they were filled with reducing grout (cementitious material containing slag to promote reducing conditions). The approach was to evaluate radionuclides sorption literature with iron oxyhydroxide phases, such as hematite ({alpha}-Fe{sub 2}O{sub 3}), magnetite (Fe{sub 3}O{sub 4}), goethite ({alpha}-FeOOH) and ferrihydrite (Fe{sub 2}O{sub 3} {center_dot} 0.5H{sub 2}O). The primary interest was the sorption behavior under tank closure conditions where the tanks will be filled with reducing cementitious materials. Because there were no laboratory studies conducted using site specific experimental conditions, (e.g., high pH and HLW tank aqueous and solid phase chemical conditions), it was necessary to extend the literature review to lower pH studies and noncementitious conditions. Consequently, this report relied on existing lower pH trends, existing geochemical modeling, and experimental spectroscopic evidence conducted at lower pH levels. The scope did not include evaluating the appropriateness of K{sub d} values for the Fe-oxyhydroxides, but instead to evaluate whether it is a conservative assumption to exclude this sorption process of radionuclides onto tank liner corrosion products in the PA model. This may identify another source for PA conservatism since the modeling did not consider any sorption by the tank liner.

  13. Plutonium interaction with a bacterial strain isolated from the waste isolation pilot plant (WIPP) environment

    Energy Technology Data Exchange (ETDEWEB)

    Strietelmeier, B.A.; Kraus, S.M.; Leonard, P.A.; Triay, I.R. [Los Alamos National Lab., NM (United States)] [and others

    1996-12-31

    This work was conducted as part of a series of experiments to determine the association and interaction of various actinides with bacteria isolated from the WIPP site. The majority of bacteria that exist at the site are expected to be halophiles, or extreme halophiles, due to the high concentration of salt minerals at the location. Experiments were conducted to determine the toxicity of plutonium-n-239, neptunium-237 and americium-243 to several species of these halophiles and the results were reported elsewhere. As an extension of these experiments, we report an investigation of the type of association that occurs between {sup 239}Pu and the isolate WIPP-1A, isolated by staff at Brookhaven National Laboratory, when grown in a high-salt, defined medium. Using scanning electron microscopy (SEM) techniques, we demonstrate a surface association of the {sup 239}Pu with the bacterial cells.

  14. 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)

  15. 237耳蜗Coch基因的特征及其与梅尼埃病的关系

    Institute of Scientific and Technical Information of China (English)

    张民; 刘兆华

    2001-01-01

    本文综述了耳蜗Coch基因的发现、特征、鉴别和展望,论述了它和梅尼埃病之间的关系,认为Coch基因在耳蜗和前庭有高表达,可以为梅尼埃病的遗传学研究提供可靠的证据.

  16. SU-E-T-237: Deformable Image Registration and Deformed Dose Composite for Volumetric Evaluation of Multimodal Gynecological Cancer Treatments

    Energy Technology Data Exchange (ETDEWEB)

    Albani, D; Sherertz, T; Ellis, R; Podder, T [Seidman Cancer Center University Hospitals Case Medical Center, Cleveland, OH (United States); Cantley, J [Case Western Reserve University, Cleveland, OH (United States); Herrmann, K [University Hospitals Case Medical Center, Case Western Reserve University, Cleveland, OH (United States)

    2015-06-15

    Purpose: Radiotherapy plans for patients with cervical cancer treated with EBRT followed by HDR brachytherapy are optimized by constraining dose to organs at risk (OARs). Risk of treatment related toxicities is estimated based on the dose received to the hottest 2cc (D2cc) of the bladder, bowel, rectum, and sigmoid. To account for intrafractional variation in OAR volume and positioning, a dose deformation method is proposed for more accurate evaluation of dose distribution for these patients. Methods: Radiotherapy plans from five patients who received 50.4Gy pelvic EBRT followed by 30Gy in five fractions of HDR brachytherapy, using split-ring and tandem applicators, were retrospectively evaluated using MIM Software version 6.0. Dose accumulation workflows were used for initial deformation of EBRT and HDR planning CTs onto a common HDR planning CT. The Reg Refine tool was applied with user-specified local alignments to refine the deformation. Doses from the deformed images were transferred to the common planning CT. Deformed doses were scaled to the EQD2, following the linear-quadratic BED model (considered α/β ratio for tumor as 10, and 3 for rest of the tissues), and then combined to create the dose composite. MIM composite doses were compared to the clinically-reported plan assessments based upon the American Brachytherapy Society (ABS) guidelines for cervical HDR brachytherapy treatment. Results: Bladder D2cc exhibited significant reduction (−11.4%±3.85%, p< 0.02) when evaluated using MIM deformable dose composition. Differences observed for bowel, rectum, and sigmoid D2cc were not significant (−0.58±7.37%, −4.13%±13.7%, and 8.58%±4.71%, respectively and p>0.05 for all) relative to the calculated values used clinically. Conclusion: Application of deformable dose composite techniques may lead to more accurate total dose reporting and can allow for elevated dose to target structures with the assurance of not exceeding dose to OARs. Further study into deformable dose composition and correlation with clinical outcomes is warranted.

  17. Challenges to Persian Gulf Security: How Should the United States Respond? (Strategic Forum, Number 237, November 2008)

    Science.gov (United States)

    2008-11-01

    sales. The extent of their discussions with European and Asian governments is unclear, but France, Germany, and Spain have been talking with...and desertification — and need transnational solutions. Offer the GCC Expanded Security Guarantees and a Smaller Military Presence. In the face of a

  18. 48 CFR 652.237-73 - Statement of Qualifications for Preference as a U.S. Person.

    Science.gov (United States)

    2010-10-01

    ... 136 determinations of eligibility— Assets means tangible and intangible things of value conveyed or... of Section 136 determinations of eligibility— Incorporated means the state of legal recognition as an... jurisdiction or component thereof. Legally organized means the state of legal recognition that may be...

  19. Procedures for determination of 239,240Pu, 241Am, 237Np, 234,238U, 2

    DEFF Research Database (Denmark)

    Chen, Q.J.; Aarkrog, Asker; Nielsen, Sven Poul;

    2001-01-01

    Since 1987, the Department of Nuclear Safety Research, Risø National Laboratory has developed procedures for analysis of low-level amounts of radioactivity in large samples of 200 liters seawater, 10 gram sediment, soil and other environmental materials.These analytical procedures provide high ch...

  20. Rapid determination of (237)Np and plutonium isotopes in urine by inductively-coupled plasma mass spectrometry and alpha spectrometry.

    Science.gov (United States)

    Maxwell, Sherrod L; Culligan, Brian K; Jones, Vernon D; Nichols, Sheldon T; Noyes, Gary W; Bernard, Maureen A

    2011-08-01

    A new rapid separation method was developed for the measurement of plutonium and neptunium in urine samples by inductively-coupled plasma mass spectrometry (ICP-MS) and/or alpha spectrometry with enhanced uranium removal. This method allows separation and preconcentration of plutonium and neptunium in urine samples using stacked extraction chromatography cartridges and vacuum box flow rates to facilitate rapid separations. There is an increasing need to develop faster analytical methods for emergency response samples. There is also enormous benefit to having rapid bioassay methods in the event that a nuclear worker has an uptake (puncture wound, etc.) to assess the magnitude of the uptake and guide efforts to mitigate dose (e.g., tissue excision and chelation therapy). This new method focuses only on the rapid separation of plutonium and neptunium with enhanced removal of uranium. For ICP-MS, purified solutions must have low salt content and low concentration of uranium due to spectral interference of (238)U(1)H(+) on m/z 239. Uranium removal using this method is enhanced by loading plutonium and neptunium initially onto TEVA resin, then moving plutonium to DGA resin where additional purification from uranium is performed with a decontamination factor of almost 1×10(5). If UTEVA resin is added to the separation scheme, a decontamination factor of ~3 × 10(6) can be achieved.

  1. Measurements of periods, relative abundances and absolute yields of delayed neutrons from fast neutron induced fission of {sup 237}Np

    Energy Technology Data Exchange (ETDEWEB)

    Piksaikine, V. [Institute of Physics and Power Engineering, Obninsk (Russian Federation)

    1997-03-01

    The experimental method for measurements of the delayed neutron yields and period is presented. The preliminary results of the total yield, relative abundances and periods are shown comparing with the previously reported values. (J.P.N.)

  2. Investigation of the chemical explosion of an ion exchange resin column and resulting americium contamination of personnel in the 242-Z building, August 30, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-10-19

    As a result of an explosion in the Waste Treatment Facility, 242-Z Building, 200 West Area of the Hanford Reservation on August 30, 1976, the Manager of the Richland Operations Office (RL), Energy Research and Development Administration (ERDA), appointed an ERDA Committee to conduct a formal investigation and to prepare a report on their findings of this occurrence. The Committee was instructed to conduct the investigation in accordance with ERDAMC 0502, insofar as circumstances would permit, to cover and explain technical elements of the casual sequence(s) of the occurrence, and to describe management systems which should have or could have prevented the occurrence. This report is the result of the investigation and presents the conclusions of the review.

  3. Aqueous complexation of citrate with neodymium(III) and americium(III): a study by potentiometry, absorption spectrophotometry, microcalorimetry, and XAFS.

    Science.gov (United States)

    Brown, M Alex; Kropf, A Jeremy; Paulenova, Alena; Gelis, Artem V

    2014-05-07

    The aqueous complexation of Nd(III) and Am(III) with anions of citrate was studied by potentiometry, absorption spectrophotometry, microcalorimetry, and X-ray absorption fine structure (XAFS). Using potentiometric titration data fitting the metal-ligand (L) complexes that were identified for Nd(III) were NdHL, NdL, NdHL2, and NdL2; a review of trivalent metal-citrate complexes is also included. Stability constants for these complexes were calculated from potentiometric and spectrophotometric titrations. Microcalorimetric results concluded that the entropy term of complex formation is much more dominant than the enthalpy. XAFS results showed a dependence in the Debye-Waller factor that indicated Nd(iii)-citrate complexation over the pH range of 1.56-6.12.

  4. Americium(III) oxidation by copper(III) periodate in nitric acid solution as compared with the action of Bi(V) compounds of sodium, lithium, and potassium

    Energy Technology Data Exchange (ETDEWEB)

    Sinkov, Sergey I.; Lumetta, Gregg J. [Pacific Northwest National Laboratory, Radiochemical Processing Lab., Richland, WA (United States)

    2015-07-01

    The oxidative action of a Cu(III) periodate compound toward Am(III) in nitric acid was studied. The extent of oxidation of Am(III) to Am(VI) was investigated using a constant initial Cu(III)-to-Am(III) molar ratio of 10:1 and varying nitric acid concentrations from 0.25 to 3.5 mol/L. From 0.25 to 3 mol/L HNO3, more than 98% of the Am(III) was oxidized to Am(VI); however, at 3.5 mol/L HNO{sub 3}, the conversion to Am(VI) was only 80%. Increasing the Cu(III)-to-Am(III) molar ratio to 20:1 in 3.5 mol/L HNO{sub 3} resulted in 98% conversion to Am(VI). For comparison, oxidation of Am(III) with NaBiO{sub 3} was studied at 3.5 mol/L HNO{sub 3} and the same stoichiometric excess of Bi(V) oxidant over Am(III) (stoichiometric ratio of 3.33:1). With NaBiO{sub 3}, the extent of Am(III) conversion to Am(VI) was only 19%, while with the Cu(III) compound this value was found to be about 4 times higher under otherwise identical conditions. Similar results were obtained with other Bi(V) salts. These results show that the Cu(III) periodate compound is a superior oxidant to NaBiO{sub 3}, yielding rapid conversion to Am(VI) in a homogeneous acidic solution, and is, therefore, an excellent candidate for further development of Am separation systems.

  5. 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

    Energy Technology Data Exchange (ETDEWEB)

    Felmy, A.R. [Pacific Northwest National Lab., Richland, WA (US); Choppin, G. [Florida State Univ., Tallahassee, FL (US)

    1997-12-31

    '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.'

  6. Studies on the feasibility of using completely incinerable reagents for the single-cycle separation of americium(III) from simulated high-level liquid waste

    Energy Technology Data Exchange (ETDEWEB)

    Nayak, P.K.; Kumaresan, R.; Venkatesan, K.A.; Subramanian, G.G.S.; Prathibha, T.; Syamala, K.V.; Selvan, B. Robert; Rajeswari, S.; Antony, M.P.; Rao, P.R. Vasudeva [Indira Gandhi Centre for Atomic Research, Kalpakkam (India). Fuel Chemistry Div.; Chaurasia, Shivkumar; Bhanage, B.M. [Institute of Chemical Technology, Mumbai (India)

    2015-06-01

    The extraction and stripping behavior of various metal ions present in the fast reactor simulated high-level liquid waste (FR-SHLLW) was studied using a solvent phase composed of a neutral extractant, N,N,-didodecyl-N',N'-dioctyl-3-oxapentane-1,5-diamide (D{sup 3}DODGA) and an acidic extractant, di-2-ethylhexyl diglycolamic acid (HDEHDGA) in n-dodecane (n-DD). The third phase formation behavior of the solvent formulation D{sup 3}DODGA + HDEHDGA/n-DD, was studied when it was contacted with FR-SHLLW, and the concentration of neutral and acidic extractant needed to avoid the third phase formation was optimized. The distribution ratio of various metal ions present in FR-SHLLW was measured in a solution of 0.1 M D{sup 3}DODGA + 0.2 M HDEHDGA/n-DD. The extraction of Am(III) was accompanied by the co-extraction of lanthanides and unwanted metal ions such as Zr(IV), Y(III), and Pd(II). A procedure was developed to minimize the extraction of unwanted metal ions by using aqueous soluble complexing agents in FR-SHLLW. Based on those results, the counter-current mixer-settler run was performed in a 20-stage mixer-settler. Quantitative extraction of Am(III), Ln(III), Y(III), and Sr(II) in 0.1 M D{sup 3}DODGA + 0.2 M HDEHDGA/n-DD was observed. The recovery of Am(III) from the loaded organic phase was carried out by the optimized aqueous formulation composed of 0.01 M diethylenetriaminepentaacetic acid (DTPA) + 0.5 M citric acid (CA) at pH 1.5. The stripping of Am(III) was accompanied by co-stripping of some early lanthanides. However the later lanthanides (Eu(III) and beyond) were not back extracted to Am(III) product. Therefore, the studies foresee the possibility of intra-lanthanides as well as lanthanide-actinide separation in a single-processing cycle.

  7. Proceedings of the specialists' meeting on nuclear data of plutonium and americium isotopes for reactor applications. [BNL, Nov. 20-21, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Chrien, R E [ed.

    1979-05-01

    Separate abstracts were prepared for 17 of the papers in these Proceedings. The remaining six have already been cited in ERA, and can be located by referring to the entry CONF-781174-- in the Report Number Index. (RWR)

  8. PS2-37: Oral Cancer Information on the Web: Assessing the Quality and Content of English and Spanish Oral Cancer Websites

    Science.gov (United States)

    Irwin, Jeannie Y; Thyvalikakath, Thankam; Schleyer, Titus; Wali, Teena; Kerr, Ross

    2010-01-01

    Background/Aims: In the United States, about 8,000 people a year die from oral cancer and more than 30,000 new cases are diagnosed annually. A recent study showed that 80% of American adult Internet users have searched the Web for health information and 15% of those specifically searched for dental health information. Having high quality oral cancer information available via the Web is important given the significance of this health problem. The goal of this study was to evaluate the quality and content of multiple English and Spanish oral cancer websites. Methods: We developed a search strategy using the keywords: oral cancer, mouth cancer, and tongue cancer to find oral cancer sites via Medline Plus, Google, and Yahoo. We then used the translations cancer oral, cancer de la boca, and cancer de la lengua to search Medline Plus en Español, Google Español, and Yahoo Telemundo. We added sites to the datasets based on inclusion/exclusion criteria. Two native speaking raters evaluated each site within their set for quality using the modified Information Quality Tool (IQT). We then developed a survey tool to asses the content of the sites. Two native speaking oral cancer experts evaluated each site within their set using this new tool. Results: Our search strategy produced 24 English language sites and 24 Spanish language sites for evaluation. English language websites had an average IQT score of 74.7 (out of 100) and average content score of 51.5 (out of 100). Spanish-language sites had an average IQT score of 48.8 and an average content score of 25.9. Conclusions: Despite higher scores for the English language websites, our analysis showed that there was a great variation in overall quality and content with room for improvement for both language types. English sites could make the biggest improvements by providing more information about their sponsors and who controls site content as well as updated and fixing links and author credentials. The Spanish sites should focus on improving information about their agenda and overall site design. For content, both types of sites need to provide more images and information on etiology and risk factors. Both English and Spanish sites scored highest in coverage of clinical presentation, treatment and follow-up care after treatment. Overall, this study identifies several information gaps and areas for improvements for oral cancer websites. We hope our results will be used to improve online oral cancer information.

  9. Adrenocorticotropin (ACTH) and corticosterone secretion by perifused pituitary and adrenal glands from rodents exposed to 2,3,7, 8-tetrachlorodibenzo-p-dioxin (TCDD).

    Science.gov (United States)

    Pitt, J A; Buckalew, A R; House, D E; Abbott, B D

    2000-10-26

    Although in utero maternal stress has been shown to have lasting effects on rodent offspring, fetal effects of chemically-induced alterations of the maternal hypothalamic-pituitary-adrenal axis (HPA) have not been well studied. This study examined the effects of in vivo 2,3,7,8-tetrachlorodibenzo-p-dioxin (TCDD) exposure on pituitary-adrenal function in the male rat, pregnant female rat and pregnant female mouse. The secretion of adrenocorticotropin (ACTH) and corticosterone (CORT) in pituitary and adrenal glands, respectively, was assessed in ex vivo perifusion cultures. Male and pregnant female (gestation day 8) Sprague-Dawley rats were gavaged once with 10 microgram/kg TCDD, pregnant female mice once with 24 microgram/kg TCDD, and euthanized 10 days later. Hemi-pituitary (rat) or whole anterior pituitaries (mice) and right adrenal glands from the same animal were quartered, perifused under baseline and stimulated conditions. In both males and pregnant females, TCDD did not affect corticotropin releasing hormone (CRH)-stimulated ACTH secretion. Neither total pituitary ACTH nor plasma ACTH was altered in either sex or species by TCDD treatment. ACTH-stimulated CORT secretion was not affected by TCDD in either sex or species, and adrenal tissue and plasma CORT levels were unchanged in males and pregnant females by TCDD. However, the plasma ACTH:CORT ratio was decreased about 46% in male rats treated with TCDD. Plasma CORT levels were 23-fold higher and plasma ACTH levels were 1.5-fold higher in pregnant females than in male rats. In male versus female rats, adrenal CORT and anterior pituitary ACTH tissue levels were about 7.5- and 1.75-fold higher and ACTH, respectively. Female mouse adrenal tissue CORT was about 4-fold greater than female rat. The reduced plasma ACTH:CORT ratio in the male rat suggests that TCDD disturbs HPA function. Exposure of male rat to a 5-fold higher dose in earlier studies clearly demonstrated effects of TCDD on male rat HPA. The present study identified substantial HPA performance differences between male and pregnant female rats. The failure to detect a response to TCDD in pregnant female rat and mouse could be a function of both TCDD dose and the high level of secretion of both ACTH and CORT in pregnant animals. For the rat or mouse, a single exposure to TCDD during pregnancy does not appear sufficient to induce maternally-mediated developmental, reproductive and behavioral toxicity via the HPA axis.

  10. VLT and ACS observations of RDCS J1252.9-2927: dynamical structure and galaxy populations in a massive cluster at z=1.237

    CERN Document Server

    Demarco, R; Lidman, C; Girardi, M; Nonino, M; Rettura, A; Strazzullo, V; Van der Wel, A; Ford, H C; Mainieri, V; Holden, B P; Stanford, S A; Blakeslee, J P; Gobat, R; Postman, M; Tozzi, P; Overzier, R A; Zirm, A W; Benítez, N; Homeier, N L; Illingworth, G D; Infante, L; Jee, M J; Mei, S; Menanteau, F; Motta, V; Zheng, W; Clampin, M; Hartig, G

    2007-01-01

    (Abridged) We present results from an extensive spectroscopic survey, carried out with FORS on the ESO VLT, and from an extensive multi-wavelength imaging data set from the ACS and ground based facilities of the cluster of galaxies RDCS J1252.9-2927. We have spectroscopically confirmed 38 cluster members in the redshift range 1.22 1, kinematic structure. The velocity distribution, which is not Gaussian at the 95% confidence level, is consistent with two groups that are also responsible for the projected elongation of the cluster in the East-West direction. The groups are composed of 26 and 12 galaxies with velocity dispersions of 486^{+47}_{-85} km s^-1 and 426^{+57}_{-105} km s^-1, respectively. The elongation is also seen in the intracluster gas and the dark matter distribution. This leads us to conclude that RDCS J1252.9-2927 has not yet reached a final virial state. We extend the analysis of the color-magnitude diagram of spectroscopic members to more than 1 Mpc from the cluster center. The scatter and s...

  11. Salvador Bernabeu Albert, La aventura de lo imposible. Expediciones marítimas españolas, Madrid-Barcelona, Lunwerg editores, 2000, 237 p.

    OpenAIRE

    Langue, Frédérique

    2005-01-01

    Dentro de la línea editorial Ciencia y Mar, culmina con esta nueva entrega un ciclo de publicaciones dedicadas a los grandes viajes marítimos españoles de la Edad Moderna. Esta síntesis histórica abarca un período bastante amplio, desde los viajes de Colón (1492-1500) hasta las expediciones científicas de la Ilustración. Desentraña las causas y etapas de estos viajes así como el significado para el imaginario de los navegantes y de los gobernantes, más allá de las conocidas implicaciones en t...

  12. 77 FR 39170 - Safety Zone; Mississippi River, Mile Marker 230.0 to Mile Marker 237.0, in the Vicinity of Baton...

    Science.gov (United States)

    2012-07-02

    ...: If you have questions on this temporary rule, call or email Lieutenant (LT) Chris Norton, Marine Safety Unit Baton Rouge, at 225-298-5400 x230, Christopher.R.Norton@uscg.mil . If you have questions on... Norton, Marine Safety Unit Baton Rouge, at (225) 298-5400 or Christopher.R.Norton@uscg.mil ....

  13. Assessment of SFR fuel pin performance codes under advanced fuel for minor actinide transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Bouineau, V.; Lainet, M.; Chauvin, N.; Pelletier, M. [French Alternative Energies and Atomic Energy Commission - CEA, CEA Cadarache, DEN/DEC/SESC, 13108 Saint Paul lez Durance (France); Di Marcello, V.; Van Uffelen, P.; Walker, C. [European Commission, Joint Research Centre, Institute for Transuranium Elements, Hermann-von-Helmholtz-Platz 1, D- 76344 Eggenstein-Leopoldshafen (Germany)

    2013-07-01

    Americium is a strong contributor to the long term radiotoxicity of high activity nuclear waste. Transmutation by irradiation in nuclear reactors of long-lived nuclides like {sup 241}Am is, therefore, an option for the reduction of radiotoxicity and residual power packages as well as the repository area. In the SUPERFACT Experiment four different oxide fuels containing high and low concentrations of {sup 237}Np and {sup 241}Am, representing the homogeneous and heterogeneous in-pile recycling concepts, were irradiated in the PHENIX reactor. The behavior of advanced fuel materials with minor actinide needs to be fully characterized, understood and modeled in order to optimize the design of this kind of fuel elements and to evaluate its performances. This paper assesses the current predictability of fuel performance codes TRANSURANUS and GERMINAL V2 on the basis of post irradiation examinations of the SUPERFACT experiment for pins with low minor actinide content. Their predictions have been compared to measured data in terms of geometrical changes of fuel and cladding, fission gases behavior and actinide and fission product distributions. The results are in good agreement with the experimental results, although improvements are also pointed out for further studies, especially if larger content of minor actinide will be taken into account in the codes. (authors)

  14. A contribution to the physical and chemical model of long-lived radioactive wastes by clayey materials; Contribution a la modelisation physico-chimique de la retention de radioelements a vie longue par des materiaux argileux

    Energy Technology Data Exchange (ETDEWEB)

    Gorgeon, L.

    1994-11-25

    This work deals with the high-level and long-lived radioactive wastes confinement which come from the irradiated fuels reprocessing. These wastes are generally coated in a deep geological structure confinement matrix. The radiation protection of a such storage requires that the coating matrix, the technological barriers which separate the storage and the geological medium and the reception rock does not let the radioactive wastes pass. The materials used in this work for the confinement studies are clayey minerals and the retention mechanisms studies are realized on cesium 135, neptunium 237, americium 241 and uranium 233. The first part of this thesis concerns the clayey minerals retention properties towards ions in aqueous solutions. More particularly the relations between these properties and the chemical structure of these solids are investigated. In the second part are presented the experimental works which have allowed to specify the intrinsic characteristics of the studied minerals. Indeed the knowledge of these parameters is essential to quantitatively explain the results of the radionuclides retention. The adsorption mechanisms are described in a third part. (O.L.). 112 refs., 59 figs., 51 tabs.

  15. Selected radionuclides important to low-level radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

  16. Effect of spectral characterization of gaseous fuel reactors on transmutation and burning of actinides

    Energy Technology Data Exchange (ETDEWEB)

    Fung, C.; Anghaie, S. [Florida Univ., Wilmington, NC (United States)

    2007-07-01

    Gaseous Core Reactors (GCR) are fueled with stable uranium compounds in a reflected cavity. The spectral characteristics of neutrons in GCR systems could shift from one end of the spectrum to the other end by changing design parameters such as reflector material and thickness, uranium enrichment, and the average operational temperature and pressure. The rate of actinide generation, transmutation, and burnup is highly influenced by the average neutron energy in reactor core. In particular, the production rate and isotopic mix of plutonium are highly dependent on the neutron spectrum in the reactor. Other actinides of primary interest to this work are neptunium-237 and americium-241 due to their pivotal impact on high-level nuclear waste disposal. In all cavity reactors including GCR's, the reflector material and thickness are the most important design parameters in determining the core spectrum. The increase in the gaseous fuel pressure and enrichment results in relative shift of neutron population toward energies greater than 2 eV. Reflector materials considered in this study are beryllium oxide, lithium hydride, lithium deuteride, zirconium carbide, graphite, lead, and tungsten. Results of the study suggest that the beryllium oxide and tungsten reflected GCR systems set the lower (softest) and upper (hardest) limits of neutron spectra, respectively. The inventory of actinides with half-lives greater than 1000 years can be minimized by increasing neutron flux level in the reactor core. The higher the neutron flux, the lower the inventory of these actinides. The majority of the GCR designs maintained a flux level on the order of 10{sup 15} cm{sup -2}*s{sup -1} while the PWR flux is one order of magnitude lower. The inventory of the feeder isotopes to Np{sup 237} including U{sup 237}, Pu{sup 241}, and Am{sup 241} decreases with relative shift of neutron spectrum toward higher energies. This is due to increased resonance absorption in these isotopes due to higher

  17. Interaction and transport of actinides in natural clay rock with consideration of humic substances and clay organics. Characterization and quantification of the influence of clay organics on the interaction and diffusion of uranium and americium in the clay. Joint project

    Energy Technology Data Exchange (ETDEWEB)

    Bernhard, Gert [Helmholtz-Zentrum Dresden-Rossendorf e.V. (Germany). Inst. of Radiochemistry; Schmeide, Katja; Joseph, Claudia; Sachs, Susanne; Steudtner, Robin; Raditzky, Bianca; Guenther, Alix

    2011-07-01

    The objective of this project was the study of basic interaction processes in the systems actinide - clay organics - aquifer and actinide - natural clay - clay organics - aquifer. Thus, complexation, redox, sorption and diffusion studies were performed. To evaluate the influence of nitrogen, phosphorus and sulfur containing functional groups of humic acid (HA) on the complexation of actinides in comparison to carboxylic groups, the Am(III) and U(VI) complexation by model ligands was studied by UV-Vis spectroscopy and TRLFS. The results show that Am(III) is mainly coordinated via carboxylic groups, however, probably stabilized by nitrogen groups. The U(VI) complexation is dominated by carboxylic groups, whereas nitrogen and sulfur containing groups play a minor role. Phosphorus containing groups may contribute to the U(VI) complexation by HA, however, due to their low concentration in HA they play only a subordinate role compared to carboxylic groups. Applying synthetic HA with varying sulfur contents (0 to 6.9 wt.%), the role of sulfur functionalities of HA for the U(VI) complexation and Np(V) reduction was studied. The results have shown that sulfur functionalities can be involved in U(VI) humate complexation and act as redox-active sites in HA for the Np(V) reduction. However, due to the low content of sulfur in natural HA, its influence is less pronounced. In the presence of carbonate, the U(VI) complexation by HA was studied in the alkaline pH range by means of cryo-TRLFS (-120 C) and ATR FT-IR spectroscopy. The formation of the ternary UO{sub 2}(CO{sub 3}){sub 2}HA(II){sup 4-} complex was detected. The complex formation constant was determined with log {beta}{sub 0.1} M = 24.57 {+-} 0.17. For aqueous U(VI) citrate and oxalate species, luminescence emission properties were determined by cryo-TRLFS and used to determine stability constants. The existing data base could be validated. The U(VI) complexation by lactate, studied in the temperature range 7 to 65 C, was found to be endothermic and entropy-driven. In contrast, the complex stability constants determined for U(VI) humate complexation at 20 and 40 C are comparable, however, decrease at 60 C. For aqueous U(IV) citrate, succinate, mandelate and glycolate species stability constants were determined. These ligands, especially citrate, increase solubility and mobility of U(IV) in solution due to complexation. The U(VI) sorption onto crushed Opalinus Clay (OPA, Mont Terri, Switzerland) was studied in the absence and presence of HA or low molecular weight organic acids, in dependence on temperature and CO2 presence using OPA pore water as background electrolyte. Distribution coefficients (K{sub d}) were determined for the sorption of U(VI) and HA onto OPA with (0.0222 {+-} 0.0004) m{sup 3}/kg and (0.129 {+-} 0.006) m{sup 3}/kg, respectively. The U(VI) sorption is not influenced by HA ({<=}50 mg/L), however, decreased by low molecular weight organic acids ({>=} 1 x 10{sup -5} M), especially by citrate and tartrate. With increasing temperature, the U(VI) sorption increases both in the absence and in the presence of clay organics. The U(VI) diffusion in compacted OPA is not influenced by HA at 25 and 60 C. Predictions of the U(VI) diffusion show that an increase of the temperature to 60 C does not accelerate the migration of U(VI). With regard to uranium-containing waste, it is concluded that OPA is suitable as host rock for a future nuclear waste repository since OPA has a good retardation potential for U(VI). (orig.)

  18. Monitored Natural Attenuation of Inorganic Contaminants in Ground Water Volume 3 Assessment for Radionuclides IncludingTritium, Radon, Strontium, Technetium, Uranium, Iodine, Radium, Thorium, Cesium, and Plutonium-Americium

    Science.gov (United States)

    The current document represents the third volume of a set of three volumes that address the technical basis and requirements for assessing the potential applicability of MNA as part of a ground-water remedy for plumes with nonradionuclide and/or radionuclide inorganic contamina...

  19. Study of plutonium and americium contamination in agricultural area, radiological impact caused by consumption of vegetables of this area; Estudio de la contaminacion de plutonio y americio en un area agricola, impacto radiologico ocasionado por consumo de vegetales contaminados

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa, Assuncion; Aragon, Antonio; Cruz, Berta de la; Gutierrez, Jose [Centro de Investigaciones Energeticas Medioambientales y Tecnologicas, Madrid (Spain). Dept. de Impacto Ambiental de la Energia

    2001-07-01

    The transuranide concentration has been studied for 30 years in vegetable production, crops in wide extensions and in private-owned farms, all of them situated within the Pu-contaminated area of Palomares due to an air accident in 1966. Based on these studies, a preliminary estimation of the radiological risk caused by the consumption of these products by the inhabitants was possible. The results show that most of the fruits present a surface contamination, which disappears or is significantly reduced when they are washed. The contamination present in edible parts of the vegetables, as well as the contamination of other products included in the diet, has facilitated the estimation of the effective dose for ingestion and the committed effective dose for 50 years for the inhabitants. The main conclusions are: those plants, whose cultivation period is less than a year, present a low level of contamination; the green parts of the plants have a higher contamination than the fruits; the Pu soil to plant transfer factor is very low. In general, those plants that have remained in the contaminated land for several years present a high contamination level; the ingestion of products from Palomares does not represent an important risk for the population, even in the case that the products were totally consumed by a critical group.( author)

  20. Supported liquid inorganic membranes for nuclear waste separation

    Energy Technology Data Exchange (ETDEWEB)

    Bhave, Ramesh R; DeBusk, Melanie M; DelCul, Guillermo D; Delmau, Laetitia H; Narula, Chaitanya K

    2015-04-07

    A system and method for the extraction of americium from radioactive waste solutions. The method includes the transfer of highly oxidized americium from an acidic aqueous feed solution through an immobilized liquid membrane to an organic receiving solvent, for example tributyl phosphate. The immobilized liquid membrane includes porous support and separating layers loaded with tributyl phosphate. The extracted solution is subsequently stripped of americium and recycled at the immobilized liquid membrane as neat tributyl phosphate for the continuous extraction of americium. The sequestered americium can be used as a nuclear fuel, a nuclear fuel component or a radiation source, and the remaining constituent elements in the aqueous feed solution can be stored in glassified waste forms substantially free of americium.

  1. Industrial research for transmutation scenarios

    Science.gov (United States)

    Camarcat, Noel; Garzenne, Claude; Le Mer, Joël; Leroyer, Hadrien; Desroches, Estelle; Delbecq, Jean-Michel

    2011-04-01

    This article presents the results of research scenarios for americium transmutation in a 22nd century French nuclear fleet, using sodium fast breeder reactors. We benchmark the americium transmutation benefits and drawbacks with a reference case consisting of a hypothetical 60 GWe fleet of pure plutonium breeders. The fluxes in the various parts of the cycle (reactors, fabrication plants, reprocessing plants and underground disposals) are calculated using EDF's suite of codes, comparable in capabilities to those of other research facilities. We study underground thermal heat load reduction due to americium partitioning and repository area minimization. We endeavor to estimate the increased technical complexity of surface facilities to handle the americium fluxes in special fuel fabrication plants, americium fast burners, special reprocessing shops, handling equipments and transport casks between those facilities.

  2. Chemistry research and development progress report, May-October, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Miner, F. J.

    1979-08-30

    Work in progress includes: calorimetry and thermodynamics of nuclear materials; americium recovery and purification; optimization of the cation exchange process for recovering americium and plutonium from molten salt extraction residues, photochemical separations of actinides; advanced ion exchange materials and techniques; secondary actinide recovery; removal of plutonium from lathe coolant oil; evaluation of tributyl phosphate-impregnated sorbent for plutonium-uranium separations; plutonium recovery in advance size reduction facility; plutonium peroxide precipitation; decontamination of Rocky Flats soil; soil decontamination at other Department of Energy sites; recovery of actinides from combustible wastes; induction-heated, tilt-pour furnace; vacuum melting; determination of plutonium and americium in salts and alloys by calorimetry; plutonium peroxide precipitation process; silica removal study; a comparative study of annular and Raschig ring-filled tanks; recovery of plutonium and americium from a salt cleanup alloy; and process development for recovery of americium from vacuum melt furnace crucibles.

  3. 不同感染途径艾滋病症、证分布规律的研究%Research on rules of distribution and development of traditional Chinese medicine syndromes of 2 237 HIV/AIDS cases

    Institute of Scientific and Technical Information of China (English)

    王健; 刘颖; 邹雯; 李洪娟; 何丽云; 董继鹏; 岑玉文; 邓鑫; 王莉

    2013-01-01

    HIV/AIDS patients in high prevalence areas with different routes of infection (sexually transmitted 878 cases,527 cases of intravenous drug user,paid blood donor 652 cases) were choosen for traditional Chinese medicine(TCM) syndrome investigation for one-year clinical follow-up.This paper primarily concluded the nature,location and pathogenesis of AIDS diseases.Deficiency of Yang and Yin,combining deficiency of Qi are the basic deficiency syndromes,while stagnation of dampness,toxic fire are the excess syndromes; the disease location of HIV infector is spleen,main syndrome is deficiency of spleen Qi; the disease location of AIDS patient is kidney,main syndrome is deficiency of spleen and kidney Yang.The pathogenic development tendency is from deficiency of Qi to combining stagnation of dampness and toxic fire,finally to deficiency of Qi and Yin,deficiency of Yang.%运用中医学、临床流行病学、统计学的方法,在我国艾滋病流行的主要地区,选择不同感染途径(性传播878例,静脉吸毒527例,有偿供血652例)的HIV/AIDS患者,进行中医证候学调查,对不同感染途径艾滋病症、证分布规律进行为期1年的临床随访,初步总结出不同感染途径艾滋病的病性、病位和病机等特点.3种传播途径主要病性中虚证以气虚、阴虚和阳虚为主;实证中,血液传播以痰湿为主,性传播以气滞为主,静脉吸毒以热(火)毒为主.性传播者以肝肾阴虚、肝郁气滞证为主;静脉吸毒者以气阴两虚、湿热蕴结证为主;采供血者以肝胃不和、脾虚湿盛证为主.

  4. CTD data of the Hawaii Ocean Time-series (HOT) program in the North Pacific 100 miles north of Oahu, Hawaii for cruises HOT228-237 during 2011 (NODC Accession 0101727)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — The HOT program makes repeated observations of the physics, biology and chemistry at a site approximately 100 km north of Oahu, Hawaii. Two stations are visited...

  5. The behaviour of Eu, Pu, Am radionuclide at burning radioactive graphite in an oxygen atmosphere. Computer experiments

    Directory of Open Access Journals (Sweden)

    Kolbin T.S.

    2015-01-01

    Full Text Available Be means of the method of computer thermodynamic simulation we studied the behaviour of the europium, plutonium and americium from the combustion of radioactive graphite in oxygen. Europe is in the form of condensed EuOCl, Eu2O3 and vapour EuO. Pluto is in the form of condensed vapour PuO2 and PuO2. Americium is a condensed AmO2, Am2O3 and vapour Am. The basic reactions occurring compounds with europium, plutonium and americium. Equilibrium constants of the reactions have been determined.

  6. Rubbia proposes a speedier voyage to Mars and back

    CERN Multimedia

    Abbott, A

    1999-01-01

    Carlo Rubbia has designed a propulsion engine that uses fission fragments of americium to directly heat a propulsion gas. He estimates it would allow a manned trip to Mars and back in around a year (8 paragraphs).

  7. Filgrastim (Neupogen)

    Science.gov (United States)

    ... CRC) Simulation Tools Isotopes Americium-241 (Am-241) Cesium-137 (Cs-137) Radioisotope Brief Toxicology FAQs Cobalt- ... a drug that has been used successfully for cancer patients to stimulate the growth of the white ...

  8. Literatuuronderzoek plutoniumanalyses

    NARCIS (Netherlands)

    Glastra P; Kwakman PJM; LSO

    1997-01-01

    Dit rapport beschrijft de laatste ontwikkelingen in de radiochemische bepaling van plutonium in monstermatrices zoals luchtstoffilters, regenwater, gras en bodem. De radiochemische scheiding van plutonium van storende alfastralers, zoals americium en curium, is door de recente ontwikkeling van spec

  9. Study of the properties of the Am-O system in view of the transmutation of Am 241 in fast reactors; Etude des proprietes du systeme Am-O en vue de la transmutation de l`americium 241 en reacteur a neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Casalta, S.

    1996-04-01

    To reduce the long term toxicity of Am 241 it was considered to transmute this isotope in fast reactor. The first part of this thesis is an introduction at this problem. In the second part we give the experimental techniques used for the realisation of an AmO{sub 2}-MgO target (powder metallurgy under inert, oxidizing or reducing atmosphere). The properties of the Am-O system has been analyzed by X diffraction, thermodynamic and ceramography, in the Am{sub 2}O{sub 3}-AmO{sub 2} field. In the third part we study the external exposure risk created by the manufacturing of this target and in the last part the behavior of this target in a fast reactor. 66 refs., 28 figs., 25 tabs., 1 append.

  10. Methodology for the Inventory and Assessment of Americium Contamination Level in 1987 in an Area of Palomares Contaminated with Plutonium Weapon Grade; Estimacion del Contenido de Americio Existente en el Ano 1987 en una Zona de Palomares Contaminada en 1966 por Material de Plutonio Grado Bomba

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa, A.; Aragon, A.; Cruz de la, B.

    2001-07-01

    This paper presents a methodology applied for the assessment of the ''241 Am coming from the decay of ''241 Pu isotope content in a contaminated area of Palomares, where the clean-up work done in 1966, given the negligible agricultural importance of such area at the time and its geographical characteristics, was not of the same magnitude as for the rest of the region. (Author) 4 refs.

  11. Characterization of Supernate Samples from HLW Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H

    Energy Technology Data Exchange (ETDEWEB)

    STALLINGS, MARY

    2004-07-02

    This document presents work conducted in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractor for the Salt Waste Processing Facility (SWPF). The Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) analyze and characterize supernate waste from seven selected High Level Waste (HLW) tanks to allow classification of feed to be sent to the SWPF, verification that SWPF processes will be able to meet Saltstone Waste Acceptance Criteria (WAC), and updating of the Waste Characterization System (WCS) database. This document provides characterization data of samples obtained from Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H and discusses results.Characterization of the waste tank samples involved several treatments and analysis at various stages of sample processing. These analytical stages included as-received liquid, post-dilution to 6.44 M sodium (target), post-acid digestion, post-filtration (at 3 filtration pore sizes), and after cesium removal using ammonium molybdophosphate (AMP). Results and observations obtained from testing include the following. All tanks will require cesium removal as well as treatment with Monosodium Titanate (MST) for 90Sr (Strontium) decontamination. A small filtration effect for 90Sr was observed for five of the seven tank wastes. No filtration effects were observed for Pu (Plutonium), Np (Neptunium), U (Uranium), or Tc (Technetium). 137Cs (Cesium) concentration is approximately E+09 pCi/mL for all the tank wastes. Tank 37H is significantly higher in 90Sr than the other six tanks. 237Np in the F-Area tanks(45F and 46F) are at least 1 order of magnitude less than the H-Area tank wastes. The data indicate a constant ratio of 99Tc to Cs in the seven tank wastes. This indicates the Tc remains largely soluble in Savannah River Site (SRS) waste and partition similarly with Cs. 241Am (Americium) concentration was low in the seven tank wastes. The majority of data

  12. Characterization Of Supernate Samples From High Level Waste Tanks 13H, 30H, 37H, 39H, 45F, 46F and 49H

    Energy Technology Data Exchange (ETDEWEB)

    Stallings, M. E.; Barnes, M. J.; Peters, T. B.; Diprete, D. P.; Hobbs, D. T.; Fink, S. D.

    2005-06-15

    This document presents work conducted in support of technical needs expressed, in part, by the Engineering, Procurement, and Construction Contractor for the Salt Waste Processing Facility (SWPF). The Department of Energy (DOE) requested that Savannah River National Laboratory (SRNL) analyze and characterize supernate waste from seven selected High Level Waste (HLW) tanks to allow: classification of feed to be sent to the SWPF; verification that SWPF processes will be able to meet Saltstone Waste Acceptance Criteria (WAC); and updating of the Waste Characterization System (WCS) database. This document provides characterization data of samples obtained from Tanks 13H, 30H, 37H, 39H, 45F, 46F, and 49H and discusses results. Characterization of the waste tank samples involved several treatments and analysis at various stages of sample processing. These analytical stages included as-received liquid, post-dilution to 6.44 M sodium (target), post-acid digestion, post-filtration (at 3 filtration pore sizes), and after cesium removal using ammonium molybdophosphate (AMP). All tanks will require cesium removal as well as treatment with Monosodium Titanate (MST) for {sup 90}Sr (Strontium) decontamination. A small filtration effect for 90Sr was observed for six of the seven tank wastes. No filtration effects were observed for Pu (Plutonium), Np (Neptunium), U (Uranium), or Tc (Technetium); {sup 137}Cs (Cesium) concentration is ~E+09 pCi/mL for all the tank wastes. Tank 37H is significantly higher in {sup 90}Sr than the other six tanks. {sup 237}Np in the F-area tanks (45F and 46F) are at least 1 order of magnitude less than the H-Area tank wastes. The data indicate a constant ratio of {sup 99}Tc to Cs in the seven tank wastes. This indicates the Tc remains largely soluble in Savannah River Site (SRS) waste and partitions similarly with Cs. {sup 241}Am (Americium) concentration was low in the seven tank wastes. The majority of data were detection limit values, the largest being

  13. 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

  14. AM(VI) partitioning studies. FY14 final report

    Energy Technology Data Exchange (ETDEWEB)

    Mincher, Bruce J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-10-01

    The use of higher oxidation states of americium in partitioning from the lanthanides is under continued investigation by the sigma team. This is based on the hypothesis that Am(VI) can be produced and remain stable in irradiated first cycle raffinate solution long enough to perform solvent extraction for separations. The stability of Am(VI) to autoreduction was measured using millimolar americium concentrations in a 1-cm cell with a Cary 6000 UV/Vis spectrophotometer for data acquisition. At millimolar americium concentrations, Am(VI) is stable enough against its own autoreduction for separations purposes. A second major accomplishment during FY14 was the hot test. Americium oxidation and extraction was performed using a centrifugal contactor-based test bed consisting of an extraction stage and two stripping stages. Sixty-three percent americium extraction was obtained in one extraction stage, in agreement with batch contacts. Promising electrochemical oxidation results have also been obtained, using terpyridine ligand derivatized electrodes for binding of Am(III). Approximately 50 % of the Am(III) was oxidized to Am(V) over the course of 1 hour. It is believed that this is the first demonstration of the electrolytic oxidation of americium in a non-complexing solution. Finally, an initial investigation of Am(VI) extraction using diethylhexylbutyramide (DEHBA) was performed.

  15. On the transmutation of Am in a fast lead-cooled system

    Indian Academy of Sciences (India)

    B P Kochurov; V N Konev; A Yu Kwaretzkheli

    2007-02-01

    Characteristics of the equilibrium fuel cycle for the core or a blanket of ADS having the structure of the core of a fast lead-cooled reactor of type BREST (Russian abbreviation for `Bystryy Reaktor so Svintsovym Teplonositelem') in a mode of americium transmutation are calculated. Americium loading was taken 5% of heavy atoms. Keeping the average multiplication factor the same as in a standard equilibrium cycle, reactivity swing over 1 year's microcycle is about 1%, that demands partial fuel reloading with a periodicity of about one month. For one year of operation, 61 kg of americium is destroyed, and due to increased 238Pu content, americium is mainly converted to fission products. Thus in a system of 1 GWt (thermal), 87 kg of americium can be transmuted yearly. The estimate of the reactivity void effect has shown that it increases to 0.6% almost linearly with the void fraction increasing up to 25% and reaches its maximum of 0.7% at a void fraction of about 50%. Application of similar strategy for ADS with a sub-criticality level ≈ 0.96–0.98 can essentially relax safety problems related to positive void effects.

  16. Porous metal oxide microspheres from ion exchange resin

    Science.gov (United States)

    Picart, S.; Parant, P.; Caisso, M.; Remy, E.; Mokhtari, H.; Jobelin, I.; Bayle, J. P.; Martin, C. L.; Blanchart, P.; Ayral, A.; Delahaye, T.

    2015-07-01

    This study is devoted to the synthesis and the characterization of porous metal oxide microsphere from metal loaded ion exchange resin. Their application concerns the fabrication of uranium-americium oxide pellets using the powder-free process called Calcined Resin Microsphere Pelletization (CRMP). Those mixed oxide ceramics are one of the materials envisaged for americium transmutation in sodium fast neutron reactors. The advantage of such microsphere precursor compared to classical oxide powder is the diminution of the risk of fine dissemination which can be critical for the handling of highly radioactive powders such as americium based oxides and the improvement of flowability for the filling of compaction chamber. Those millimetric oxide microspheres incorporating uranium and americium were synthesized and characterizations showed a very porous microstructure very brittle in nature which occurred to be adapted to shaping by compaction. Studies allowed to determine an optimal heat treatment with calcination temperature comprised between 700-800 °C and temperature rate lower than 2 °C/min. Oxide Precursors were die-pressed into pellets and then sintered under air to form regular ceramic pellets of 95% of theoretical density (TD) and of homogeneous microstructure. This study validated thus the scientific feasibility of the CRMP process to prepare bearing americium target in a powder free manner.

  17. Diseño del sistema de alimentación de corriente y voltaje en los visores nocturnos para ser utilizados en el avión scheweizer SA2-37B de la Fuerza Aérea Colombiana

    Directory of Open Access Journals (Sweden)

    José Antonio Beltrán Bernate

    2009-01-01

    Con las baterias tradicionales el tiempo de vuelo de la aeronave, en operación con (Lentes de Visión Nocturna L.V.N. es de 10 horas, pero con la utilización del sistema de alimentación de corriente, resultado de este trabajo, se puede prolongar más allá este límite, beneficiando el desarrollo de las operaciones aéreas.

  18. Comment on Spracklandus Hoser, 2009 (Reptilia, Serpentes, ELAPIDAE): request for confirmation of availability of the generic name and for the nomenclatural validation of the journal in which it was published (Case 3601; BZN 70:234–237; 71:30–38; 133-135,181-182 ,252-253)

    Science.gov (United States)

    Rhodin, Anders G.J.; Kaiser, Hinrich; van Dijk, Peter Paul; Wüster, Wolfgang; O’Shea, Mark; Archer, Michael; Auliya, Mark; Boitani, Luigi; Bour, Roger; Clausnitzer, Viola; Contreras-MacBeath, Topiltzin; Crother, Brian I.; Daza, Juan M.; Driscoll, Carlos A.; Flores-Villela, Oscar; Frazier, Jack; Fritz, Uwe; Gardner, Alfred L.; Gascon, Claude; Georges, Arthur; Glaw, Frank; Grazziotin, Felipe G.; Groves, Colin P.; Haszprunar, Gerhard; Havaš, Peter; Hero, Jean-Marc; Hoffmann, Michael; Hoogmoed, Marinus S.; Horne, Brian D.; Iverson, John B.; Jäch, Manfred; Jenkins, Christopher L.; Jenkins, Richard K.B.; Kiester, A. Ross; Keogh, J. Scott; Lacher, Thomas E.; Lovich, Jeffrey E.; Luiselli, Luca; Mahler, D. Luke; Mallon, David P.; Mast, Roderic; McDiarmid, Roy W.; Measey, John; Mittermeier, Russell A.; Molur, Sanjay; Mosbrugger, Volker; Murphy, Robert W.; Naish, Darren; Niekisch, Manfred; Ota, Hidetoshi; Parham, James F.; Parr, Michael J.; Pilcher, Nicolas J.; Pine, Ronald H.; Rylands, Anthony B.; Sanderson, James G.; Savage, Jay M.; Schleip, Wulf; Scrocchi, Gustavo J.; Shaffer, H. Bradley; Smith, Eric N.; Sprackland, Robert; Stuart, Simon N.; Vetter, Holger; Vitt, Laurie J.; Waller, Tomás; Webb, Grahame; Wilson, Edward O.; Zaher, Hussam; Thomson, Scott

    2015-01-01

    In Case 3601 Raymond Hoser has asked the Commission to validate for the purposes of nomenclature the name Spracklandus Hoser, 2009, and ‘the journal in which it was published,’ issue 7 of the Australasian Journal of Herpetology (AJH). We note that the entire run of AJH has been written, edited, and published solely by Hoser. Although his requests to the Commission were presented as narrow and, in his words, ‘routine matters,’ we are convinced that they represent an important tipping-point with broad implications of major concern for zoological taxonomy and nomenclature as a whole and, by extension, the greater scientific community. Since Hoser’s actions and works have failed to follow scientific best practices (e.g. Turtle Taxonomy Working Group, 2007, 2014; Kaiser et al., 2013; Kaiser, 2014) and both the Commission’s general Recommendations and Code of Ethics in Appendix A, the global herpetological community has widely rejected his taxonomic decisions and resultant nomenclature. This has unfortunately caused a confusing dual nomenclature to develop in the herpetological community, with most boycotting or ignoring Hoser’s 700+ new names coined in the AJH, while he and a few personal followers actively promote their usage. We believe that suppression of the name Spracklandus, and all issues of AJH, is the only effective way to bring this contentious and confusing issue to resolution. The plenary power available under Article 81.1 of the Code exist specifically to allow the Commission to make rulings in individual cases that disturb stability and cause confusion, whether the works are Code-compliant or not. We maintain that it is in the interest of nomenclatural stability, not only for herpetology, but for all of zoological taxonomy, that the plenary power be invoked to declare the works in AJH unavailable, regardless of any narrow interpretation of their technical Code-compliance. We present our arguments for rejection of the validity of AJH in the following commentary. In view of the wide-reaching implications of this case for all of zoology, and reflecting the deep and broad-based community concern over these issues, our contributing authors include 70 global scientific leaders and accomplished amateurs from a wide variety of zoological disciplines.

  19. Ireland's hidden diaspora - the 'abortion trail'and the making of a london-irish underground,1980-2000 Ann Rossiter Ireland's hidden diaspora - the 'abortion trail'and the making of a london-irish underground,1980-2000 Iasc (email: arossit@yahoo.com ) 237 £8+p&p 9780956178503 0956178502 [Formula: see text].

    Science.gov (United States)

    2009-12-09

    This is a passionate book about patients, politics and women supporting women. It does not make for light reading. Every year more than 5,000 women cross the Irish Sea to have an abortion in a British clinic. The emigrant journey is deeply embedded in Irish consciousness, but, as Ann Rossiter points out, the abortion-seeker rarely features in migration lore.

  20. Safety assessment of poloxamers 101, 105, 108, 122, 123, 124, 181, 182, 183, 184, 185, 188, 212, 215, 217, 231, 234, 235, 237, 238, 282, 284, 288, 331, 333, 334, 335, 338, 401, 402, 403, and 407, poloxamer 105 benzoate, and poloxamer 182 dibenzoate as used in cosmetics.

    Science.gov (United States)

    Singh-Joy, Subhashni D; McLain, Valerie C

    2008-01-01

    Poloxamers are polyoxyethlyene, polyoxypropylene block polymers. The impurities of commercial grade Poloxamer 188, as an example, include low-molecular-weight substances (aldehydes and both formic and acetic acids), as well as 1,4-dioxane and residual ethylene oxide and propylene oxide. Most Poloxamers function in cosmetics as surfactants, emulsifying agents, cleansing agents, and/or solubilizing agents, and are used in 141 cosmetic products at concentrations from 0.005% to 20%. Poloxamers injected intravenously in animals are rapidly excreted in the urine, with some accumulation in lung, liver, brain, and kidney tissue. In humans, the plasma concentration of Poloxamer 188 (given intravenously) reached a maximum at 1 h, then reached a steady state. Poloxamers generally were ineffective in wound healing, but were effective in reducing postsurgical adhesions in several test systems. Poloxamers can cause hypercholesterolemia and hypertriglyceridemia in animals, but overall, they are relatively nontoxic to animals, with LD(50) values reported from 5 to 34.6 g/kg. Short-term intravenous doses up to 4 g/kg of Poloxamer 108 produced no change in body weights, but did result in diffuse hepatocellular vacuolization, renal tubular dilation in kidneys, and dose-dependent vacuolization of epithelial cells in the proximal convoluted tubules. A short-term inhalation toxicity study of Poloxamer 101 at 97 mg/m(3) identified slight alveolitis after 2 weeks of exposure, which subsided in the 2-week postexposure observation period. A short-term dermal toxicity study of Poloxamer 184 in rabbits at doses up to 1000 mg/kg produced slight erythema and slight intradermal inflammatory response on histological examination, but no dose-dependent body weight, hematology, blood chemistry, or organ weight changes. A 6-month feeding study in rats and dogs of Poloxamer 188 at exposures up to 5% in the diet produced no adverse effects. Likewise, Poloxamer 331 (tested up to 0.5 g/kg day(-1)), Poloxamer 235 (tested up to 1.0 g/kg day(-1)), and Poloxamer 338 (at 0.2 or 1.0 g/kg day(-1)) produced no adverse effects in dogs. Poloxamer 338 (at 5.0 g/kg day(-1)) produced slight transient diarrhea in dogs. Poloxamer 188 at levels up to 7.5% in diet given to rats in a 2-year feeding study produced diarrhea at 5% and 7.5% levels, a small decrease in growth at the 7.5% level, but no change in survival. Doses up to 0.5 mg/kg day(-1) for 2 years using rats produced yellow discoloration of the serum, high serum alkaline phosphatase activity, and elevated serum glutamicpyruvic transaminase and glutamic-oxalacetic transaminase activities. Poloxamers are minimal ocular irritants, but are not dermal irritants or sensitizers in animals. Data on reproductive and developmental toxicity of Poloxamers were not found. An Ames test did not identify any mutagenic activity of Poloxamer 407, with or without metabolic activation. Several studies have suggested anticarcinogenic effects of Poloxamers. Poloxamers appear to increase the sensitivity to anticancer drugs of multidrug-resistant cancer cells. In clinical testing, Poloxamer 188 increased the hydration of feces when used in combination with a bulk laxative treatment. Compared to controls, one study of angioplasty patients receiving Poloxamer 188 found a reduced myocardial infarct size and a reduced incidence of reinfarction, with no evidence of toxicity, but two other studies found no effect. Poloxamer 188 given to patients suffering from sickle cell disease had decreased pain and decreased hospitilization, compared to controls. Clinical tests of dermal irritation and sensitization were uniformly negative. The Cosmetic Ingredient Review (CIR) Expert Panel stressed that the cosmetic industry should continue to use the necessary purification procedures to keep the levels below established limits for ethylene oxide, propylene oxide, and 1,4-dioxane. The Panel did note the absence of reproductive and developmental toxicity data, but, based on molecular weight and solubility, there should be little skin penetration and any penetration of the skin should be slow. Also, the available data demonstrate that Poloxamers that are introduced into the body via routes other than dermal exposure have a rapid clearance from the body, suggesting that there would be no risk of reproductive and/or developmental toxicity. Overall, the available data do not suggest any concern about carcinogenesis. Although there are gaps in knowledge about product use, the overall information available on the types of products in which these ingredients are used, and at what concentration, indicates a pattern of use. Based on these safety test data and the information that the manufacturing process can be controlled to limit unwanted impurities, the Panel concluded that these Poloxamers are safe as used.

  1. Corrigendum to "InAsSbP/InAs0.9Sb0.1/InAs DH photodiodes (λ 0.1 = 5.2 μm, 300 K) operating in the 77-353 K temperature range" [Infrared Phys. Technol. 73 (2015) 232-237

    Science.gov (United States)

    Brunkov, P. N.; Il'inskaya, N. D.; Karandashev, S. A.; Lavrov, A. A.; Matveev, B. A.; Remennyi, M. A.; Stus', N. M.; Usikova, A. A.

    2016-05-01

    The authors regret that the following sentence was included by mistake in the Acknowledgments:"Optical measurements (Lavrov A.A.) were carried out with the support of the Russian Science Foundation (contract No. 14-12-00255)." In fact the above sentence should be excluded from the paper text.

  2. 2,3,7,8-TCDD的短期暴露对HepG2肝癌细胞内小分子代谢产物的影响%Effects of Short-Term Exposure to 2,3,7, 8-TCDD on Low-Molecular Metabolites in HepG2 Cells

    Institute of Scientific and Technical Information of China (English)

    张保琴; 张海军; 杨常青; 陈吉平

    2012-01-01

    To investigate the mechanisms underlying metabolic toxicity and hepatotoxicity of dioxins,HepG2 cells were selected to be exposed to the most toxic dioxin,23,7,8-tetrachlorodibenz0-p-dioxin (TCDD) for 24 h,and the proliferative activity of HepG2 cells was determined by MTT assay,while low-molecular metabolites (amino acids,glucose,itrea and glycerol) were qualitatively and quantitatively analyzed by HPLC-MS/MS.Results showed that short-term TCDD exposure had little effect on the proliferative activity of HepG2 cells.Glucose consumption did not change significantly after 24 h-exposure to TCDD,but only when the concentration of TCDD increased to 1 nmol·L-1,glucose consumption showed a slight decrease.0.01 nmol·L-1 TCDD inhibited the synthesis of praline and glutamate in HepG2 cells,and the synthesis of glutamate decreased in an obvious dose-response manner.The absorbability of several amino acids (valine,tryptophan,tyrosine,methi-onine,leucine and isoleucine) was stimulated by TCDD in a dose-response manner.The productions of urea and glycerol tended to decrease with increasing TCDD concentration.After 24 h-exposure to 1 nmol·L-1TCDD,the productions of urea and glycerol decreased to 1% and 18% of that of the control group.These results demonstrated that short-term exposure to TCDD could affect low-molecular metabolites in HepG2 cells to different degrees.TCDD exerted toxicity to HepG2 cells by disturbing its metabolism.%为了研究二恶英对细胞的代谢毒性,探究其肝毒性的作用机制,以二恶英中毒性最强的2,3,7,8-四氯代二苯并-对-二恶英(TCDD)为代表污染物,以HepG2肝癌细胞为受试对象,采用四甲基偶氮唑蓝(MTT)法和高技液相色谱/串联质谱法考察了TCDD的24 h暴露对HepG2细胞的增殖活性以及细胞的葡萄糖、氨基酸、尿素和甘油等小分子代谢物的影响.结果显示,短暂的TCDD暴露对HepG2细胞的增殖活性无显著影响.24 h的TCDD暴露对细胞的葡萄糖消耗量无显著影响,但当TCDD浓度增至1 nmo1·L-1时,葡萄糖的消耗量表现出一定的降低趋势.0.01 nmol·L-1TCDD就会使细胞脯氨酸和谷氨酸的合成能力下降,且谷氨酸的变化表现出明显的剂量-效应关系;TCDD可刺激细胞对缬氨酸、苏氨酸、酪氨酸、甲硫氨酸以及亮氨酸与异亮氮酸的吸收,并具有明显的浓度依赖性.随着TCDD浓度的增加,甘油和尿素产生量的降低趋势逐渐明显,1 nmol· L-1TCDD处理24 h后,甘油和尿素的产生量仅为对照组的1%和18%.研究表明,TCDD在短时间内使HepG2细胞内的一系列小分子代谢产物发生了不同程度的改变,且呈现出一定的剂量-效应关系.可见,TCDD可通过干扰HepG2肝癌细胞的代谢过程产生毒性.

  3. Facilities for preparing actinide or fission product-based targets

    CERN Document Server

    Sors, M

    1999-01-01

    Research and development work is currently in progress in France on the feasibility of transmutation of very long-lived radionuclides such as americium, blended with an inert medium such as magnesium oxide and pelletized for irradiation in a fast neutron reactor. The process is primarily designed to produce ceramics for nuclear reactors, but could also be used to produce targets for accelerators. The Actinide Development Laboratory is part of the ATALANTE complex at Marcoule, where the CEA investigates reprocessing, liquid and solid waste treatment and vitrification processes. The laboratory produces radioactive sources; after use, their constituents are recycled, notably through R and D programs requiring such materials. Recovered americium is purified, characterized and transformed for an experiment known as ECRIX, designed to demonstrate the feasibility of fabricating americium-based ceramics and to determine the reactor transmutation coefficients.

  4. 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)

  5. Colloid formation during waste form reaction: implications for nuclear waste disposal

    Science.gov (United States)

    Bates, J. K.; Bradley, J.; Teetsov, A.; Bradley, C. R.; ten Brink, Marilyn Buchholtz

    1992-01-01

    Insoluble plutonium- and americium-bearing colloidal particles formed during simulated weathering of a high-level nuclear waste glass. Nearly 100 percent of the total plutonium and americium in test ground water was concentrated in these submicrometer particles. These results indicate that models of actinide mobility and repository integrity, which assume complete solubility of actinides in ground water, underestimate the potential for radionuclide release into the environment. A colloid-trapping mechanism may be necessary for a waste repository to meet long-term performance specifications.

  6. Analysis Of 2H-Evaporator Scale Wall [HTF-13-82] And Pot Bottom [HTF-13-77] Samples

    Energy Technology Data Exchange (ETDEWEB)

    Oji, L. N.

    2013-09-11

    obtained at two different locations within the evaporator pot the major radioactive components (on a mass basis) in the additional radionuclide analyses were Sr-90, Cs-137 Np-237, Pu-239/240 and Th-232. Small quantities of americium and curium were detected in the blanks used for Am/Cm method for these radionuclides. These trace radionuclide amounts are assumed to come from airborne contamination in the shielded cells drying or digestion oven, which has been replaced. Therefore, the Am/Cm results, as presented, may be higher than the true Am/Cm values for these samples. These results are provided so that SRR can calculate the equivalent uranium-235 concentrations for the NCSA. Results confirm that the uranium contained in the scale remains depleted with respect to natural uranium. SRNL did not calculate an equivalent U-235 enrichment, which takes into account other fissionable isotopes U-233, Pu-239 and Pu-241. The applicable method for calculation of equivalent U-235 will be determined in the NCSA. With a few exceptions, a comparison of select radionuclides measurements from this 2013 2H evaporator scale characterization (pot bottom and wall scale samples) with those measurements for the same radionuclides in the 2010 2H evaporator scale analysis shows that the radionuclide analysis for both years are fairly comparable; the analyses results are about the same order of magnitude.

  7. Radiological analysis of materials sampled on the old nuclear test site of In Ekker (Algeria); Analyses radiologiques de materiaux preleves sur l'ancien site d'essais nucleaires d'In Ekker (Algerie)

    Energy Technology Data Exchange (ETDEWEB)

    Chareyron, Bruno

    2010-02-11

    After having recalled the context of the French nuclear test campaign in Algeria between 1961 and 1966, this document reports and comments radiological measurements performed on the site of In Ekker, and also results of analysis performed in laboratory (contamination by cesium 137, americium 241, plutonium); recommendations are given

  8. Historical Review of Californium-252 Discovery and Development

    Science.gov (United States)

    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 Cf conducted at the Savannah River Plant are discussed. The evolution of radiotherapy using californium 252 is reviewed. (PLG)

  9. Determination of Am-241 in lung and bone by gamma spectrometry with semiconductor detectors LEGe; Determinacion de Am- 241 en pulmon y hueso por espectrometria gamma con detectores de semiconductor LEGe

    Energy Technology Data Exchange (ETDEWEB)

    Perez Lopez, B.

    2014-07-01

    Americium is produced from neutron absorption plutonium atoms within nuclear reactors. The work of dismantling and decontamination of the installations and radioactive waste management makes workers exposed acquire risk of internal exposure and therefore can incorporate Am-241 in his body. (Author)

  10. Experimental findings on actinide recovery utilizing oxidation by peroxydisulfate followed by ion exchange: Fuel cycle research & development

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Shehee, T. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-08-31

    Our research seeks to determine if inorganic ion-exchange materials can be exploited to provide effective minor actinide (Am, Cm) separation from lanthanides. Previous work has established that a number of inorganic and UMOF ion-exchange materials exhibit varying affinities for actinides and lanthanides, which may be exploited for effective separations. During FY15, experimental work focused on investigating methods to oxidize americium in dilute nitric and perchloric acid with subsequent ion-exchange performance measurements of ion exchangers with the oxidized americium in dilute nitric acid. Ion-exchange materials tested included a variety of alkali titanates. Americium oxidation testing sought to determine the influence that other redox active components may have on the oxidation of AmIII. Experimental findings indicated that CeIII, NpV, and RuII are oxidized by peroxydisulfate, but there are no indications that the presence of CeIII, NpV, and RuII affected the rate or extent of americium oxidation at the concentrations of peroxydisulfate being used.

  11. 10 CFR Appendix E to Part 20 - Nationally Tracked Source Thresholds

    Science.gov (United States)

    2010-01-01

    ... Category 1(TBq) Category 1(Ci) Category 2(TBq) Category 2(Ci) Actinium-227 20 540 0.2 5.4 Americium-241 60... 2 54 Strontium-90 1,000 27,000 10 270 Thorium-228 20 540 0.2 5.4 Thorium-229 20 540 0.2 5.4...

  12. Literatuuronderzoek plutoniumanalyses

    NARCIS (Netherlands)

    Glastra P; Kwakman PJM; LSO

    1997-01-01

    This report describes recent developments in the radiochemical determination of plutonium in samples from the environment such as aerosols, rainwater, grass and soil. The radiochemical separation of plutonium from interfering alpha emitters, such as americium and curium, was found to be simplified b

  13. Discovery of Isotopes of the Transuranium Elements with 93 <= Z <= 98

    CERN Document Server

    Fry, C

    2012-01-01

    One hundred and five isotopes of the transuranium elements neptunium, plutonium, americium, curium, berkelium and californium have so far been observed; the discovery of these isotopes is discussed. For each isotope a brief summary of the first refereed publication, including the production and identification method, is presented.

  14. Presence and Character of the 5f Electrons in the Actinide Metals

    DEFF Research Database (Denmark)

    Johansson, B.; Skriver, Hans Lomholt; Mårtensson, N.;

    1980-01-01

    The sensitivity of the Image level binding energy to the occupation of the 5f orbital is pointed out and used to demonstrate the presence of 5f electrons in the uranium metal. It is suggested that the valence band spectrum of uranium might contain satellites originating from excitations to locali...... and the critical separation is found to take place between plutonium and americium....

  15. Experimental findings on actinide recovery utilizing oxidation by peroxydisulfate followed by ion exchange: Fuel cycle research & development

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D. T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Shehee, T. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-08-31

    Our research seeks to determine if inorganic ion-exchange materials can be exploited to provide effective minor actinide (Am, Cm) separation from lanthanides. Previous work has established that a number of inorganic and UMOF ion-exchange materials exhibit varying affinities for actinides and lanthanides, which may be exploited for effective separations. During FY15, experimental work focused on investigating methods to oxidize americium in dilute nitric and perchloric acid with subsequent ion-exchange performance measurements of ion exchangers with the oxidized americium in dilute nitric acid. Ion-exchange materials tested included a variety of alkali titanates. Americium oxidation testing sought to determine the influence that other redox active components may have on the oxidation of AmIII. Experimental findings indicated that CeIII, NpV, and RuII are oxidized by peroxydisulfate, but there are no indications that the presence of CeIII, NpV, and RuII affected the rate or extent of americium oxidation at the concentrations of peroxydisulfate being used.

  16. The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor

    Science.gov (United States)

    Syarifah, Ratna Dewi; Suud, Zaki

    2015-09-01

    Design study of small Pressurized Water Reactors (PWRs) core loaded with uranium nitride fuel (UN) and mixed nitride fuel (UN-PuN), Pa-231 as burnable poison, and Americium has been performed. Pa-231 known as actinide material, have large capture cross section and can be converted into fissile material that can be utilized to reduce excess reactivity. Americium is one of minor actinides with long half life. The objective of adding americium is to decrease nuclear spent fuel in the world. The neutronic analysis results show that mixed nitride fuel have k-inf greater than uranium nitride fuel. It is caused by the addition of Pu-239 in mixed nitride fuel. In fuel fraction analysis, for uranium nitride fuel, the optimum volume fractions are 45% fuel fraction, 10% cladding and 45% moderator. In case of UN-PuN fuel, the optimum volume fractions are 30% fuel fraction, 10% cladding and 60% coolant/ moderator. The addition of Pa-231 as burnable poison for UN fuel, enrichment U-235 5%, with Pa-231 1.6% has k-inf more than one and excess reactivity of 14.45%. And for mixed nitride fuel, the lowest value of reactivity swing is when enrichment (U-235+Pu) 8% with Pa-231 0.4%, the excess reactivity value 13,76%. The fuel pin analyze for the addition of Americium, the excess reactivity value is lower than before, because Americium absorb the neutron. For UN fuel, enrichment U-235 8%, Pa-231 1.6% and Am 0.5%, the excess reactivity is 4.86%. And for mixed nitride fuel, when enrichment (U-235+Pu) 13%, Pa-231 0.4% and Am 0.1%, the excess reactivity is 11.94%. For core configuration, it is better to use heterogeneous than homogeneous core configuration, because the radial power distribution is better.

  17. Experimental Findings On Minor Actinide And Lanthanide Separations Using Ion Exchange

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D. T.; Shehee, T. C.; Clearfield, A.

    2013-09-17

    This project seeks to determine if inorganic or hybrid inorganic ion-exchange materials can be exploited to provide effective americium and curium separations. Specifically, we seek to understand the fundamental structural and chemical factors responsible for the selectivity of the tested ion-exchange materials for actinide and lanthanide ions. During FY13, experimental work focused in the following areas: (1) investigating methods to oxidize americium in dilute nitric acid with subsequent ion-exchange performance measurements of ion exchangers with the oxidized americium and (2) synthesis, characterization and testing of ion-exchange materials. Ion-exchange materials tested included alkali titanates, alkali titanosilicates, carbon nanotubes and group(IV) metal phosphonates. Americium oxidation testing sought to determine the influence that other redox active components may have on the oxidation of Am(III). Experimental findings indicated that Pu(IV) is oxidized to Pu(VI) by peroxydisulfate, but there are no indications that the presence of plutonium affects the rate or extent of americium oxidation at the concentrations of peroxydisulfate being used. Tests also explored the influence of nitrite on the oxidation of Am(III). Given the formation of Am(V) and Am(VI) in the presence of nitrite, it appears that nitrite is not a strong deterrent to the oxidation of Am(III), but may be limiting Am(VI) by quickly reducing Am(VI) to Am(V). Interestingly, additional absorbance peaks were observed in the UV-Vis spectra at 524 and 544 nm in both nitric acid and perchloric acid solutions when the peroxydisulfate was added as a solution. These peaks have not been previously observed and do not correspond to the expected peak locations for oxidized americium in solution. Additional studies are in progress to identify these unknown peaks. Three titanosilicate ion exchangers were synthesized using a microwave-accelerated reaction system (MARS) and determined to have high affinities

  18. 78 FR 73109 - Radio Broadcasting Services; Benjamin and Cisco, TX; De Beque, CO; Port Lions, AK; Rule and...

    Science.gov (United States)

    2013-12-05

    ... COMMISSION 47 CFR Part 73 Radio Broadcasting Services; Benjamin and Cisco, TX; De Beque, CO; Port Lions, AK... at De Beque, Colorado; Channel 237C3 at Benjamin, Texas; Channel 261C3 at Cisco, Texas; Channel 288C2..., Channel 237C3; by removing Cisco, Channel 261C3; by removing Channel 288C2 at Rule; and by...

  19. AcEST: DK953349 [AcEST

    Lifescience Database Archive (English)

    Full Text Available 41 2e-63 sp|P38980|RSSA_TRIGR 40S ribosomal protein SA OS=Tripneustes gra... 237 3e-62 sp|P50890|RSSA_CHICK ...40S ribosomal protein SA OS=Tripneustes gratilla PE=2 SV=1 Length = 316 Score = 237 bits (605), Expect = 3e-

  20. Method for Determination of Neptunium in Large-Sized Urine Samples Using Manganese Dioxide Coprecipitation and 242Pu as Yield Tracer

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hou, Xiaolin; Roos, Per

    2013-01-01

    A novel method for bioassay of large volumes of human urine samples using manganese dioxide coprecipitation for preconcentration was developed for rapid determination of 237Np. 242Pu was utilized as a nonisotopic tracer to monitor the chemical yield of 237Np. A sequential injection extraction chr...

  1. Data of evolutionary structure change: 1CTWA-1SX2A [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1CTWA-1SX2A 1CTW 1SX2 A A MNIFEMLRIDEGLRLKIYKDTEGYYTIGIGHLLTKSPSL...entryIDChain>1SX2A LRMLQ-KRWDE ure>HHHH - HHH...G CA 233 TRP CA 289 ASP CA 237 GLU CA 237 1CT...W A 1CTWA LRMLQQ...KRWDE ure>HHHHH HHHure>

  2. International Disability Educational Alliance (IDEAnet)

    Science.gov (United States)

    2011-03-23

    Professionalism. Journal of General Internal Medicine . July; 23(7): 954-957. 34 Ibid. 35 Kamel Boulous, Maged N. and Wheeler, Steve (2007). Page 11 of 57...Paradise (2008). The Intersection of Online Social Networking with Medical Professionalism. Journal of General Internal Medicine . July; 23(7): 954

  3. The Separation Method of Neptunium in Reprocessed Uranium Product by TEVA-UTEVA Column Extraction Chromatography

    Institute of Scientific and Technical Information of China (English)

    JIN; Hua; SU; Yu-lan; YING; Zhe-cong; ZHAO; Sheng-yang

    2012-01-01

    <正>237Np, as a highly toxic nuclide, is limited strictly in the final uranium product of spent nuclear fuel reprocessing plant. Due to the low concentration level of 237Np, which is lower than 2.5 μg/g U, its accurate measurement is one of the most difficult analytical works in

  4. Systematic study of anomalous fragment anisotropies in subbarrier complete fusion—fission reactions

    Institute of Scientific and Technical Information of China (English)

    ZhangHuan-Qiao; LiuZu-Hua; 等

    1997-01-01

    The complete fusion-fission is separated from the transter-induced-fission with the fragment folding angle technique.The cross sections and fragment angular distributions for the complete fusion-fission reactions of 11B+ 238U(237Np),237NP,16O+232Th(238U) and 19F+232Th at near-and sub-barrier energies have been measured.The present fusion and fission standard models can reproduces both the excitation functions and the fragment anisotropies for the systems of 11B+238U(237Np)and 12C+237Np;but fail to explain both the experimental data for the other 3 systems simultaneously,The evidence of the entrance-channel dependence of fission-fragment anisotropies is revealsed by comparison of the 11B+237NP and 16O+232Th data.Based on the observations a new version model of preequilibrium fission is put forward to explain the anomaly.

  5. TRUEX Radiolysis Testing Using the INL Radiolysis Test Loop: FY-2012 Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Dean R. Peterman; Lonnie G. Olson; Richard D. Tillotson; Rocklan G. McDowell; Jack D. Law

    2012-09-01

    The INL radiolysis test loop has been used to evaluate the affect of radiolytic degradation upon the efficacy of the strip section of the TRUEX flowsheet for the recovery of trivalent actinides and lanthanides from acidic solution. The nominal composition of the TRUEX solvent used in this study is 0.2 M CMPO and 1.4 M TBP dissolved in n-dodecane and the nominal composition of the TRUEX strip solution is 1.5 M lactic acid and 0.050 M diethylenetriaminepentaacetic acid. Gamma irradiation of a mixture of TRUEX process solvent and stripping solution in the test loop does not adversely impact flowsheet performance as measured by stripping americium ratios. The observed increase in americium stripping distribution ratios with increasing absorbed dose indicates the radiolytic production of organic soluble degradation compounds.

  6. 2014 AFCI Glovebox Event Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, Joseph Lenard [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-01-01

    One of the primary INL missions is to support development of advanced fuels with the goal of creating reactor fuels that produce less waste and are easier to store. The Advanced Fuel Cycle Initiative (AFCI) Glovebox in the Fuel Manufacturing Facility (FMF) is used for several fuel fabrication steps that involve transuranic elements, including americium. The AFCI glove box contains equipment used for fuel fabrication, including an arc melter – a small, laboratory-scale version of an electric arc furnace used to make new metal alloys for research – and an americium distillation apparatus. This overview summarizes key findings related to the investigation into the releases of airborne radioactivity that occurred in the AFCI glovebox room in late August and early September 2014. The full report (AFCI Glovebox Radiological Release – Evaluation, Corrective Actions and Testing, INL/INL-15-36996) provides details of the identified issues, corrective actions taken as well as lessons learned

  7. Technical Improvements to an Absorbing Supergel for Radiological Decontamination in Tropical Environments

    Energy Technology Data Exchange (ETDEWEB)

    Kaminski, Michael D. [Argonne National Lab. (ANL), Argonne, IL (United States); Mertz, Carol J. [Argonne National Lab. (ANL), Argonne, IL (United States); Kivenas, Nadia [Argonne National Lab. (ANL), Argonne, IL (United States); demmer, Rick [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-01-01

    Argonne National Laboratory (Argonne) developed a superabsorbing gel-based process (SuperGel) for the decontamination of cesium from concrete and other porous building materials. Here, we report on results that tested the gel decontamination technology on specific concrete and ceramic formulations from a coastal city in Southeast Asia, which may differ significantly from some U.S. sources. Results are given for the evaluation of americium and cesium sequestering agents that are commercially available at a reasonable cost; the evaluation of a new SuperGel formulation that combines the decontamination properties of cesium and americium; the variation of the contamination concentration to determine the effects on the decontamination factors with concrete, tile, and brick samples; and pilot-scale testing (0.02–0.09 m2 or 6–12 in. square coupons).

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

    Energy Technology Data Exchange (ETDEWEB)

    Koehler, S. [Institut fuer Kernchemie Universitaet Mainz, Mainz (Germany); Albus, F. [Institu fuer Physik, Universitaet Mainz, Mainz (Germany); Dibenberger, R.; Erdmann, N.; Funk, H. [Institut fuer Kernchemiess Universitaet Mainz, Mainz (Germany); Hasse, H. [Institut fuer Physik, Universitaet Mainz, Mainz (Germany); Herrmann, G. [Institut fuer Kernchemiess Universitaet Mainz, Mainz (Germany); Huber, G.; Kluge, H.; Nunnemann, M.; Passler, G. [Institut fuer Physik, Universitaet Mainz, Mainz (Germany); Rao, P.M. [Bhabha Atomic Research Centre Bombay (India); Riegel, J.; Trautmann, N. [Institut fuer Kernchemie Universitaet Mainz, Mainz (Germany); Urban, F. [Institut fuer Physik, Universitaet Mainz, Mainz (Germany)

    1995-04-01

    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{sub {ital Am}}=5.9738(2) and IP{sub {ital Cm}}=5.9913(8) eV, respectively, using only 10{sup 12} atoms of {sup 243}Am and {sup 248}Cm. The same technique was applied to thorium, neptunium, and plutonium yielding IP{sub T{sub H}}=6.3067(2), IP{sub N{sub P}}=6.2655(2), and IP{sub {ital 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. Incineration by accelerator; Incineration par accelerateur

    Energy Technology Data Exchange (ETDEWEB)

    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 {sup 15} n/cm{sup 2}.s; a chemical separation of elements burning in thermal (americium) from the elements needing a flow of fast neutrons. (N.C.). 28 refs.

  11. 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.

  12. Translations from the Soviet Journal of Atomic Energy

    Science.gov (United States)

    1962-02-15

    brain and nervous system tumors is accomplished through the use of radio- active isotopes of radon, xenon, and iodine. External irradiation techniques...production of toxic chemicals. The radioactive technique cf obtaining bexachliorane has a number of advantages over the photochemical techni- 1 13 qu. Nuclear...nuclear fuels and contains results of studies on the chemistry of ruth- enium, thorium , uranium, plutoniuin and americium. Also treated are the problems

  13. Extractant Design by Covalency

    Energy Technology Data Exchange (ETDEWEB)

    Gaunt, Andrew James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Olson, Angela Christine [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kozimor, Stosh Anthony [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cross, Justin Neil [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Batista, Enrique Ricardo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Macor, Joe [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of Illinois, Urbana-Champaign, IL (United States); Peterman, Dean R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Grimes, Travis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-01-21

    This project aims to provide an electronic structure-to-function understanding of extractants for actinide selective separation processes. The research entails a multi-disciplinary approach that integrates chemical syntheses, structural determination, K-edge X-ray Absorption Spectroscopy (XAS), and Density Functional Theory (DFT) calculations. In FY15, the project reached the final stage of testing the extraction performance of a new ligand design and preparing an americium-extractant complex for analysis.

  14. Gas-phase energies of actinide oxides -- an assessment of neutral and cationic monoxides and dioxides from thorium to curium

    Energy Technology Data Exchange (ETDEWEB)

    Marcalo, Joaquim; Gibson, John K.

    2009-08-10

    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.

  15. Bibliography of PNL publications in management of radioactive wastes, subject-indexed (alphabetically) and listed chronologically (latest issues first)

    Energy Technology Data Exchange (ETDEWEB)

    Powell, J.A. (ed.)

    1976-07-01

    The citations are arranged under: actinides, alpha particles, americium, beta particles, calcination, cements, ceramics, cesium, containers, decontamination, evaporation, fluidized bed, glass, ground release, high-level wastes, incinerators, liquid wastes, marine disposal, melting, nonradioactive waste disposal, Pu, radiation doses, radiation protection, disposal, processing, radionuclide migration, Ru, safety, separation processes, soils, solidification, solid wastes, stack disposal, temperature, thermal conductivity, transmutation, tritium, underground disposal, U, volatility, and waste disposal/management/processing/storage/transportation. (DLC)

  16. Research in radiobiology. Annual report of work in progress in the internal irradiation program

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-31

    The toxicity, retention, biological effects, distribution, decorporation and measuring techniques of radionuclides are discussed. Calculations of trabecular bone formation rates from tetracycline labeling is included. The characteristics of trabecular bone in the Rhesus monkey are discussed. Studies on the early retention and distribution of radium 224 in beagles are included. Studies on the decorporation of plutonium and americium in dogs by DTPA and salicylic acid are presented.

  17. Evaluation of the neutral comet assay for detection of alpha-particle induced DNA-double-strand-breaks; Evaluation des Comet Assays bei neutralem pH zur Detektion von α-Partikel induzierten DNA-Doppelstrangbruechen

    Energy Technology Data Exchange (ETDEWEB)

    Hofbauer, Daniela

    2010-10-20

    Aim of this study was to differentiate DNA-double-strand-breaks from DNA-single-strand-breaks on a single cell level, using the comet assay after α- and γ-irradiation. Americium-241 was used as a alpha-irradiation-source, Caesium-137 was used for γ-irradiation. Because of technical problems with both the neutral and alkaline comet assay after irradiation of gastric cancer cells and human lymphocytes, no definite differentiation of DNA-damage was possible.

  18. 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

    Energy Technology Data Exchange (ETDEWEB)

    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/sup 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.

  19. In situ radiological surveying at the Double Tracks site, Nellis Air Force Range, Tonopah, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Riedhauser, S.R.; Tipton, W.J.

    1996-04-01

    A team from the Remote Sensing Laboratory conducted a series of in situ radiological measurements at the Double Tracks site on the Nellis Air Force Range just east of Goldfield, Nevada, during the periods of April 10-13 and June 5-9, 1995. The survey team measured the terrestrial gamma radiation at the site to determine the levels of natural and man-made radiation. This site includes the areas covered by previous surveys conducted from 1962 through 1993. The main purpose of the first expedition was to assess several new techniques for characterizing sites with dispersed plutonium. The two purposes of the second expedition were to characterize the distribution of transuranic contamination (primarily plutonium) at the site by measuring the gamma rays from americium-241 and to assess the performance of the two new detector platforms. Both of the new platforms performed well, and the characterization of the americium-241 activity at the site was completed. Several plots compare these ground-based system measurements and the 1993 aerial data. The agreement is good considering the systems are characterized and calibrated through independent means. During the April expedition, several methods for measuring the depth distribution of americium-241 in the field were conducted as a way of quickly and reliably obtaining depth profiles without the need to wait for laboratory analysis. Two of the methods were not very effective, but the results of the third method appear very promising.

  20. Alkali Treatment of Acidic Solution from Hanford K Basin Sludge Dissolution

    Energy Technology Data Exchange (ETDEWEB)

    AA Bessonov; AB Yusov; AM Fedoseev; AV Gelis; AY Garnov; CH Delegard; GM Plavnik; LN Astafurova; MS Grigoriev; NA Budantseva; NN Krot; SI Nikitenko; TP Puraeva; VP Perminov; VP Shilov

    1998-12-22

    Nitric acid solutions will be created from the dissolution of Hanford K Basin sludge. These acidic dissolver solutions must be made alkaline by treatment with NaOH solution before they are disposed to ~ the Tank Waste Remediation System on the Hanford Site. During the alkali treatments, sodium diuranate, hydroxides of iron and aluminum, and radioelements (uranium, plutonium, and americium) will precipitate from the dissolver solution. Laboratory tests, discussed here, were pefiormed to provide information on these precipitates and their precipitation behavior that is important in designing the engineering flowsheet for the treatment process. Specifically, experiments were conducted to determine the optimum precipitation conditions; the completeness of uranium, plutonium, and americium precipitation; the rate of sedimentation; and the physico-chemical characteristics of the solids formed by alkali treatment of simulated acidic dissolver solutions. These experiments also determined the redistribution of uranium, plutonium, and americium flom the sodium di~ate and iron and al&inurn hydroxide precipitates upon contact with carbonate- and EDTA-bearing simulated waste solutions. Note: EDTA is the tetrasodium salt of ethylenediaminetetraacetate.

  1. Capability to Recover Plutonium-238 in H-Canyon/HB-Line - 13248

    Energy Technology Data Exchange (ETDEWEB)

    Fuller, Kenneth S. Jr.; Smith, Robert H. Jr.; Goergen, Charles R. [Savannah River Nuclear Solutions, LLC, Savannah River Site, Aiken, SC 29802 (United States)

    2013-07-01

    Plutonium-238 is used in Radioisotope Thermoelectric Generators (RTGs) to generate electrical power and in Radioisotope Heater Units (RHUs) to produce heat for electronics and environmental control for deep space missions. The domestic supply of Pu-238 consists of scrap material from previous mission production or material purchased from Russia. Currently, the United States has no significant production scale operational capability to produce and separate new Pu-238 from irradiated neptunium-237 targets. The Department of Energy - Nuclear Energy is currently evaluating and developing plans to reconstitute the United States capability to produce Pu-238 from irradiated Np-237 targets. The Savannah River Site had previously produced and/or processed all the Pu-238 utilized in Radioisotope Thermoelectric Generators (RTGs) for deep space missions up to and including the majority of the plutonium for the Cassini Mission. The previous full production cycle capabilities included: Np- 237 target fabrication, target irradiation, target dissolution and Np-237 and Pu-238 separation and purification, conversion of Np-237 and Pu-238 to oxide, scrap recovery, and Pu-238 encapsulation. The capability and equipment still exist and could be revitalized or put back into service to recover and purify Pu-238/Np-237 or broken General Purpose Heat Source (GPHS) pellets utilizing existing process equipment in HB-Line Scrap Recovery, and H-Canyon Frame Waste Recovery processes. The conversion of Np-237 and Pu-238 to oxide can be performed in the existing HB-Line Phase-2 and Phase- 3 Processes. Dissolution of irradiated Np-237 target material, and separation and purification of Np-237 and Pu-238 product streams would be possible at production rates of ∼2 kg/month of Pu-238 if the existing H-Canyon Frames Process spare equipment were re-installed. Previously, the primary H-Canyon Frames equipment was removed to be replaced: however, the replacement project was stopped. The spare equipment

  2. CAPABILITY TO RECOVER PLUTONIUM-238 IN H-CANYON/HB-LINE

    Energy Technology Data Exchange (ETDEWEB)

    Fuller, Kenneth S. Jr.; Smith, Robert H. Jr.; Goergen, Charles R.

    2013-01-09

    Plutonium-238 is used in Radioisotope Thermoelectric Generators (RTGs) to generate electrical power and in Radioisotope Heater Units (RHUs) to produce heat for electronics and environmental control for deep space missions. The domestic supply of Pu-238 consists of scrap material from previous mission production or material purchased from Russia. Currently, the United States has no significant production scale operational capability to produce and separate new Pu-238 from irradiated neptunium-237 targets. The Department of Energy - Nuclear Energy is currently evaluating and developing plans to reconstitute the United States capability to produce Pu-238 from irradiated Np-237 targets. The Savannah River Site had previously produced and/or processed all the Pu-238 utilized in Radioisotope Thermoelectric Generators (RTGs) for deep space missions up to and including the majority of the plutonium for the Cassini Mission. The previous full production cycle capabilities included: Np-237 target fabrication, target irradiation, target dissolution and Np-237 and Pu-238 separation and purification, conversion of Np-237 and Pu-238 to oxide, scrap recovery, and Pu-238 encapsulation. The capability and equipment still exist and could be revitalized or put back into service to recover and purify Pu-238/Np-237 or broken General Purpose Heat Source (GPHS) pellets utilizing existing process equipment in HB-Line Scrap Recovery, and H-anyon Frame Waste Recovery processes. The conversion of Np-237 and Pu-238 to oxide can be performed in the existing HB-Line Phase-2 and Phase-3 Processes. Dissolution of irradiated Np-237 target material, and separation and purification of Np-237 and Pu-238 product streams would be possible at production rates of ~ 2 kg/month of Pu-238 if the existing H-Canyon Frames Process spare equipment were re-installed. Previously, the primary H-Canyon Frames equipment was removed to be replaced: however, the replacement project was stopped. The spare equipment is

  3. Monazite-type ceramics for conditioning of minor actinides. Structural characterization and properties

    Energy Technology Data Exchange (ETDEWEB)

    Babelot, Carole

    2013-07-01

    The minor actinides (MA) neptunium, americium, and curium are mainly responsible for the long-term radiotoxicity of the High Active Waste (HAW) generated during the nuclear power operation. If these long-lived radionuclides are removed from the HAW by partitioning and converted by neutron fission (transmutation) into shorter-lived or stable elements, the remaining waste loses most of its long-term radiotoxicity. Thus, partitioning and transmutation (P and T) are considered as attractive options for reducing the burden on geological disposals. As an alternative, these separated MA can also be conditioned (P and C strategy) in specifically adapted ceramics to ensure their safe final disposal over long periods. At the moment, spent fuel elements are foreseen either for direct disposal in deep geological repositories or for reprocessing. The highly active liquid waste that is produced during reprocessing is conditioned industrially using a vitrification process before final disposal. Although the widely used borosilicate glasses meet most of the specifications needed, ceramic host matrices appear to be even more suitable in terms of resistance to corrosion. The development of new materials based on tailor-made highly specific ceramics with extremely stable behavior would make it possible to improve the final storage of long-lived high-level radiotoxic waste. In the framework of this PhD research project, monazite-type ceramics were chosen as promising host matrices for the conditioning of trivalent actinides. The focus on the monazite-type ceramics is justified by their properties such as high chemical durability. REPO{sub 4} ceramics are named monazite for RE = La - Gd (monoclinic symmetry) and xenotime for RE = Tb - Lu and Y (tetragonal symmetry). The objective of this study is to contribute to the understanding of the alteration behavior of such ceramics under the repository conditions. REPO{sub 4} (with RE = La, Eu) is prepared by hydrothermal synthesis at 200 C

  4. Monazite-type ceramics for conditioning of minor actinides. Structural characterization and properties

    Energy Technology Data Exchange (ETDEWEB)

    Babelot, Carole

    2013-07-01

    The minor actinides (MA) neptunium, americium, and curium are mainly responsible for the long-term radiotoxicity of the High Active Waste (HAW) generated during the nuclear power operation. If these long-lived radionuclides are removed from the HAW by partitioning and converted by neutron fission (transmutation) into shorter-lived or stable elements, the remaining waste loses most of its long-term radiotoxicity. Thus, partitioning and transmutation (P and T) are considered as attractive options for reducing the burden on geological disposals. As an alternative, these separated MA can also be conditioned (P and C strategy) in specifically adapted ceramics to ensure their safe final disposal over long periods. At the moment, spent fuel elements are foreseen either for direct disposal in deep geological repositories or for reprocessing. The highly active liquid waste that is produced during reprocessing is conditioned industrially using a vitrification process before final disposal. Although the widely used borosilicate glasses meet most of the specifications needed, ceramic host matrices appear to be even more suitable in terms of resistance to corrosion. The development of new materials based on tailor-made highly specific ceramics with extremely stable behavior would make it possible to improve the final storage of long-lived high-level radiotoxic waste. In the framework of this PhD research project, monazite-type ceramics were chosen as promising host matrices for the conditioning of trivalent actinides. The focus on the monazite-type ceramics is justified by their properties such as high chemical durability. REPO{sub 4} ceramics are named monazite for RE = La - Gd (monoclinic symmetry) and xenotime for RE = Tb - Lu and Y (tetragonal symmetry). The objective of this study is to contribute to the understanding of the alteration behavior of such ceramics under the repository conditions. REPO{sub 4} (with RE = La, Eu) is prepared by hydrothermal synthesis at 200 C

  5. Gclust Server: 189782 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available nces Link to related sequences - Sequence length 237 Representative annotation hypothetical protein Number o...) (%) 0.0 Other Bikonts (Chromalveolata, Excavata) (9species) (%) 0.0 Cyanobacteria (25species) (%) 0.0 Phot

  6. Data of evolutionary structure change: 1CETA-9LDTB [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1CETA-9LDTB 1CET 9LDT A B ----------------APKAKIVLVGSGMIGGVMATLIVQKNLG-DVVLFDIVKNMPHGKALDT...SHTNVMAYSNCKVSGSNTYDDLAGSDVVIVTAGFT-----NRLDLLPLNNKIMIEIGGHIKKNCPNAFIIVVTNPVDVMVQLLHQHSGVPKNKIIGLGGVLDT...PHE CA 409 9LDT B 9LDTB MKELADEIALV H EEE...U CA 237 9LDT B 9LDT

  7. Study on Removing Micro-neptunium From Milligramme Uranium

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>In the production of radioisotopes and neutron activation analysis, it is very important to know the fast neutron densities, so that the yields of the radioistopes can be estimated. The 238U (n, 2n) 237U reactor

  8. Time Accurate Computation of Unsteady Inlet Flows with a Dynamic Flow Adaptive Mesh.

    Science.gov (United States)

    1994-09-07

    pertaining to unsteady flow effects associated with inlets. K eep up the good work! Sincerely, John H. Gerstlc, Manager HSCT Propulsion (206)237-7571 MIS 6H-FJ sh CC: Profesor Scott McRae North Carolina University

  9. Oral Contraception: A Survey of College Women's Concerns and Experience.

    Science.gov (United States)

    Sawyer, Robin G.; Beck, Kenneth H.

    1989-01-01

    Results are reported from a study which examined attitudes, experiences, and concerns of college women (N=237) regarding oral contraception. Implications of the findings for health educators are discussed. (IAH)

  10. Gene : CBRC-MDOM-11-0008 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available ica DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.62 35% MVKANESKPKEKPLVLRERK...KERKKERRKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKEGKKERRKEGKKERKKEGKKERK...KERKKERKKEGKKERKKERKKERKKEGRKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKRKGERERGREERREERRKEEKGVTKGAKEGKKKGSDGGREERQKKKYRKRERKKKEKK ...

  11. Gene : CBRC-MDOM-01-0076 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available ca DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.042 31% MIRKEGRKKERKKKKERKKERK...KERKKERKKERKKERKKERKKERKKERKKERKKERKKEREREREKRERKKERKRERKKEREKERERKREKERKKERKKERK...KERKKERKKERERKRKREERKKERKRERKKERETERERKREKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERTKE ...

  12. Gene : CBRC-MDOM-03-0125 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available ca DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.002 28% MKGKSIILERKKERKKERK...KERKKERKKERKKERKKERKKERKKERKKERKKERKKEKERKKERKKERKKERKKERKKERKKERK...KGRKKGRKEGRKEGRKEERKEGRKKGRKEERKKGRKEERKKGRKKERKKERKKERKKERKKERKKERKKERKKERKKERKKGRKEGRKEGRKKGRKEGRKEGKKERKKERKKERERKRKMGMQEQKN ...

  13. Gene : CBRC-MDOM-01-0546 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available mestica DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.015 31% MKSGKKKEERKKERK...KERKKERKKERKKERKKERKKERKKERKREREREKEREKEREKEREKEREKERERKKERKRERKRERERERKKERK...RERERERKKERKREREKERKREREKERKREREKERKREREKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERQE ...

  14. Gene : CBRC-MDOM-07-0047 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available ca DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.023 35% MERKRKKERKKERKKERK...RERERERERERKKERKKERKKERKKERKKERKKERKKERKKERERERKKERKKERKKERKKERERKRERKKERKRERERERK...RERKKERKKERKKERKKERKKERKKERKKERKRERKKEREREKERKKEREREKERKKERKKERKKERKREREKEKERKKEERKSALYKIKHYINRNLFIDYGGFCFFMFNISLFRGSITAPQ ...

  15. Gene : CBRC-MDOM-08-0098 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available ca DNA photolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.002 28% MKERKKERKKERKKERKKERK...KERKKERKKERKKERKKERKKERKKEERERRKKERKKERKKERKKERKKERERERKKERKRERKKEREKERKKERKKERK...KERKKERKKERKKERKKERKKERKKERKKERKRKEGRKEVRKKERKKERKKERKKERKKERKKEGRREGGKEGRREGGRNMERNRRGSLSFFNNAEFRKNQKESWISCIPLNVTG ...

  16. Gene : CBRC-MDOM-08-0075 [SEVENS

    Lifescience Database Archive (English)

    Full Text Available otolyase (pOPC1), mRNA /cds=p(335,1747) /gb=NM_001032977 /gi=74136504 /ug=Mdm.237 /len=1892 0.045 25% MFSGLLSKPLCPVTKKKERKKERKKERK...KERKKERKKERKKERKKERKKERKKERKKERKKERKKERKKERKRERERERERERKREREKERKREREKERKREREKERK...REREKERKREREKERKRERKKERKKERKKERKKERKKERKKERKKERKKERKKENRRGSFGP ...

  17. A propósito de Lei de Hume

    Directory of Open Access Journals (Sweden)

    Danilo Vaz-Curado R. M. Costa

    2015-04-01

    Full Text Available O presente texto apareceu pela primeira vez, sob o título de “A proposito della <>”, in Fondazione e interpretazione della norma, Morcelliana, pp. 237-245, 1986.

  18. Scenic Splendor in Calabash Island City

    Institute of Scientific and Technical Information of China (English)

    YIFAN&WANGNAN

    2003-01-01

    The Huludao landscape is one of green hills and a blue sea.Along its 237-km-long coastline are 20 finesanded beaches lapped by gentle waves ofclear water with gently undulating hills in the background.

  19. Analysis of trace neptunium in the vicinity of underground nuclear tests at the Nevada National Security Site.

    Science.gov (United States)

    Zhao, P; Tinnacher, R M; Zavarin, M; Kersting, A B

    2014-11-01

    A high sensitivity analytical method for (237)Np analysis was developed and applied to groundwater samples from the Nevada National Security Site (NNSS) using short-lived (239)Np as a yield tracer and HR magnetic sector ICP-MS. The (237)Np concentrations in the vicinity of the Almendro, Cambric, Dalhart, Cheshire, and Chancellor underground nuclear test locations range from tritium and other non-sorbing radionuclides ((14)C, (36)Cl, (99)Tc and (129)I) as expected. Surprisingly, (237)Np and plutonium ((239,240)Pu) retardation factors are very similar. It is possible that Np(IV) exists under mildly reducing groundwater conditions and exhibits a retardation behavior that is comparable to Pu(IV). Independent of the underlying process, (237)Np is migrating downgradient from NNSS underground nuclear tests at very low but measureable concentrations.

  20. Sooaspekt ja selle keeleline ülekanne : Emil Tode Piiririik / Riita-Ilona Märka

    Index Scriptorium Estoniae

    Märka, Riita-Ilona

    2003-01-01

    "Piiririigi" tõlge inglise keelde: Õnnepalu, Tõnu. Border state : [novel] / translated from the Estonian by Madli Puhvel. Evanston [USA] : Northwestern University Press, 2000. Autorist lk. 234 (inglise k.) ja lk. 237 (vene k.)

  1. A Survey of Special Educators' Awareness of, Experiences with, and Attitudes toward Nonverbal Communication Aids in the Schools.

    Science.gov (United States)

    Shrewsbury, Rosemary G.; And Others

    1985-01-01

    Results of surveys completed by 237 special educators indicate respondents' limited awareness, understanding, and experiences with nonverbal communication aids. Results have implications for preservice and continuing education programs for special educators. (Author/CL)

  2. Palm content of production metal

    Energy Technology Data Exchange (ETDEWEB)

    Campbell, M.H.; Swift, W.H.

    1959-11-23

    Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.

  3. Russia, America, and Security in the Asia-Pacific

    Science.gov (United States)

    2007-01-01

    November 4, 2004. 7 Joseph P. Ferguson argues in “Russia’s Role on the Korean Peninsula and Great Power Relations in Northeast Asia,” NBR Analysis...throughout the region), to promote (and control) commercial activities (the International Pepper Community), to share information (the Asian Vegetable Research...Enforcement Academy, 237 International Oceanographic Commission, 240 International Pepper Community, 237 Iraq, 23, 70, 71, 72, 102, 111, 140, 157, 158

  4. BRMS1 Suppresses Breast Cancer Metastasis to Bone via Its Regulation of microRNA-125b and Downstream Attenuation of TNF-Alpha and HER2 Signaling Pathways

    Science.gov (United States)

    2014-04-01

    As shown in Figure 1 and Year 3 progress report, mutation of serine 237 to alanine (S237A) that cannot be phosphorylated leads to inhibition of...and allowed to adhere for time indicated, at which point cells were fixed and stainedwith crystal violet. Representative images for times 5, 10, 15...matrix milieu and imaged by time-lapse microscopy for 1 h or fixed and stained with crystal violet at times indicated. As shown in Figure 1C and

  5. The P-38 Lightning Aircraft: Lessons Learned for Future Weapon Systems Development

    Science.gov (United States)

    2010-04-01

    PMBOK TEL \\ u.s. WER List of ~cronyms iv Brake Horse Power Design-Build Team District of Columbia Department of Defense Department of...Management, Editor-in-Chief James S. Pennypacker, 67-88. (Sylva, NC: PMI Publications Division, 1997), 73. 64 The PMBOK defines Integration Management...impact of positive events, and decrease the probability and impact of events adverse to the project." Source: PMBOK , 237. 74 PMBOK , 237. 75 Ethan

  6. Drug: D08673 [KEGG MEDICUS

    Lifescience Database Archive (English)

    Full Text Available D08673 Drug Viloxazine (INN) C13H19NO3 237.1365 237.2949 D08673.gif Antidepressant ...:6530] [KO:K05035]; serotonin transporter inhibitor [HSA:6532] [KO:K05037] hsa04726(6532) Serotonergic synapse map07027 Antidepress...[BR:br08303] N NERVOUS SYSTEM N06 PSYCHOANALEPTICS N06A ANTIDEPRESSANTS N06AX Other antidepressants N06AX09

  7. AcEST: BP918381 [AcEST

    Lifescience Database Archive (English)

    Full Text Available Alpha tubulin OS=Picea wilsonii GN=TUA1 P... 237 4e-61 tr|A9PL21|A9PL21_GOSHI Al...7 4e-61 tr|A9SEI4|A9SEI4_PHYPA Predicted protein OS=Physcomitrella paten... 237 4e-61 tr|A9QVH4|A9QVH4_9CONI

  8. A peptide fusion protein in hibits angiogenesis and tumorgrowth by blocking VEGF binding to KDR

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    Vascular endothelial growth factor (VEGF) binding to its tyrosine kinase receptors (KDR/FLK1, Flt-1) induces angiogenesis. In search of the peptides blocking VEGF binding to its receptor KDR/FLK1 to inhibit tumor- angiogenesis and growth, we screened a phage display peptide library with KDR as target protein, and some candidate peptides were isolated. In this study, we cloned the DNA fragment coding the peptide K237 from the library, into a vector pQE42 to express fusion protein DHFR-K237 in E. coli M15. The affection of fusion protein DHFR-K237 on endothelial cell proliferation and angiogenesis was investigated. In vitro, DHFR-K237 could completely block VEGF binding to KDR and significantly inhibit the VEGF-medi- ated proliferation of the human vascular endothelial cells. In vivo, DHFR-K237 inhibited angiogenesis in chick embryo chorioa- llantoric membrane and tumor growth in nude mice. These results suggest that K237 is an effective antagonist of VEGF binding to KDR, and could be a potential agent for cancer biotherapy.

  9. Scenarios for the transmutation of actinides in CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hyland, Bronwyn, E-mail: hylandb@aecl.ca [Atomic Energy of Canada Limited, Chalk River Laboratories, Chalk River, Ontario, K0J 1J0 (Canada); Gihm, Brian, E-mail: gihmb@aecl.ca [Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga, Ontario, L5K 1B2 (Canada)

    2011-12-15

    With world stockpiles of used nuclear fuel increasing, the need to address the long-term utilization of this resource is being studied. Many of the transuranic (TRU) actinides in nuclear spent fuel produce decay heat for long durations, resulting in significant nuclear waste management challenges. These actinides can be transmuted to shorter-lived isotopes to reduce the decay heat period or consumed as fuel in a CANDU(R) reactor. Many of the design features of the CANDU reactor make it uniquely adaptable to actinide transmutation. The small, simple fuel bundle simplifies the fabrication and handling of active fuels. Online refuelling allows precise management of core reactivity and separate insertion of the actinides and fuel bundles into the core. The high neutron economy of the CANDU reactor results in high TRU destruction to fissile-loading ratio. This paper provides a summary of actinide transmutation schemes that have been studied in CANDU reactors at AECL, including the works performed in the past. The schemes studied include homogeneous scenarios in which actinides are uniformly distributed in all fuel bundles in the reactor, as well as heterogeneous scenarios in which dedicated channels in the reactor are loaded with actinide targets and the rest of the reactor is loaded with fuel. The transmutation schemes that are presented reflect several different partitioning schemes. Separation of americium, often with curium, from the other actinides enables targeted destruction of americium, which is a main contributor to the decay heat 100-1000 years after discharge from the reactor. Another scheme is group-extracted transuranic elements, in which all of the transuranic elements, plutonium (Pu), neptunium (Np), americium (Am), and curium (Cm) are extracted together and then transmuted. This paper also addresses ways of utilizing the recycled uranium, another stream from the separation of spent nuclear fuel, in order to drive the transmutation of other actinides.

  10. Cleaning up the Legacy of the Cold War: Plutonium Oxides and the Role of Synchrotron Radiation Research

    Energy Technology Data Exchange (ETDEWEB)

    Clark, David Lewis [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-01-21

    The deceptively simple binary formula of AnO2 belies an incredibly complex structural nature, and propensity to form mixed-valent, nonstoichiometric phases of composition AnO2±x. For plutonium, the very formation of PuO2+x has challenged a long-established dogma, and raised fundamental questions for long-term storage and environmental migration. This presentation covers two aspects of Los Alamos synchrotron radiation studies of plutonium oxides: (1) the structural chemistry of laboratory-prepared AnO2+x systems (An = U, Pu; 0 ≤ x ≤ 0.25) determined through a combination of x-ray absorption fine structure spectroscopy (XAFS) and x-ray scattering of laboratory prepared samples; and (2) the application of synchrotron radiation towards the decontamination and decommissioning of the Rocky Flats Environmental Technology Site. Making the case for particle transport mechanisms as the basis of plutonium and americium mobility, rather than aqueous sorption-desorption processes, established a successful scientific basis for the dominance of physical transport processes by wind and water. The scientific basis was successful because it was in agreement with general theory on insolubility of PuO2 in oxidation state IV, results of ultrafiltration analyses of field water/sediment samples, XAFS analyses of soil, sediment, and concrete samples, and was also in general agreement with on-site monitoring data. This understanding allowed Site contractors to rapidly move to application of soil erosion and sediment transport models as the means of predicting plutonium and americium transport, which led to design and application of site-wide soil erosion control technology to help control downstream concentrations of plutonium and americium in streamflow.

  11. Fabrication of uranium-based ceramics using internal gelation for the conversion of trivalent actinides; Herstellung uranbasierter Keramiken mittel interner Gelierung zur Konversion trivalenter Actinoiden

    Energy Technology Data Exchange (ETDEWEB)

    Daniels, Henrik

    2012-07-01

    Alternative to today's direct final waste disposal strategy of long-lived radionuclides, for example the minor actinides neptunium, americium, curium and californium, is their selective separation from the radioactive wastestream with subsequent transmutation by neutron irradiation. Hereby it is possible to obtain nuclides with a lower risk-potential concerning their radiotoxicity. 1 neutron irradiation can be carried out either with neutron sources or in the next generation of nuclear reactors. Before the treatment, the minor actinides need to be converted in a suitable chemical and physical form. Internal gelation offers a route through which amorphous gel-spheres can be obtained directly from a metal-salt solution. Due to the presence of different types of metal ions as well as changing pH-values in a stock solution, a complex hydrolysis behaviour of these elements before and during gelation occurs. Therefore, investigations with uranium and neodymium as a minor actinide surrogate were carried out. As a result of suitable gelation-parameters, uraniumneodymium gel-spheres were successfully synthesised. The spheres also stayed intact during the subsequent thermal treatment. Based upon these findings, uranium-plutonium and uranium-americium gels were successfully created. For theses systems, the determined parameters for the uraniumneodymium gelation could also be applied. Additionally, investigations to reduce the acidity of uranium-based stock solutions for internal gelation were carried out. The necessary amount of urea and hexamethylenetetramine to induce gelation could hereby be decreased. This lead to a general increase of the gel quality and made it possible to carry out uranium-americium gelation in the first place. To investigate the stability of urea and hexamethylenetetramine, solutions of these chemicals were irradiated with different radiation doses. These chemicals showed a high stability against radiolysis in aqueous solutions.

  12. A broken-symmetry density functional study of structures, energies, and protonation states along the catalytic O-O bond cleavage pathway in ba3 cytochrome c oxidase from Thermus thermophilus.

    Science.gov (United States)

    Han Du, Wen-Ge; Götz, Andreas W; Yang, Longhua; Walker, Ross C; Noodleman, Louis

    2016-08-21

    Broken-symmetry density functional calculations have been performed on the [Fea3, CuB] dinuclear center (DNC) of ba3 cytochrome c oxidase from Thermus thermophilus in the states of [Fea3(3+)-(HO2)(-)-CuB(2+), Tyr237(-)] and [Fea3(4+)[double bond, length as m-dash]O(2-), OH(-)-CuB(2+), Tyr237˙], using both PW91-D3 and OLYP-D3 functionals. Tyr237 is a special tyrosine cross-linked to His233, a ligand of CuB. The calculations have shown that the DNC in these states strongly favors the protonation of His376, which is above propionate-A, but not of the carboxylate group of propionate-A. The energies of the structures obtained by constrained geometry optimizations along the O-O bond cleavage pathway between [Fea3(3+)-(O-OH)(-)-CuB(2+), Tyr237(-)] and [Fea3(4+)[double bond, length as m-dash]O(2-)HO(-)-CuB(2+), Tyr237˙] have also been calculated. The transition of [Fea3(3+)-(O-OH)(-)-CuB(2+), Tyr237(-)] → [Fea3(4+)[double bond, length as m-dash]O(2-)HO(-)-CuB(2+), Tyr237˙] shows a very small barrier, which is less than 3.0/2.0 kcal mol(-1) in PW91-D3/OLYP-D3 calculations. The protonation state of His376 does not affect this O-O cleavage barrier. The rate limiting step of the transition from state A (in which O2 binds to Fea3(2+)) to state PM ([Fea3(4+)[double bond, length as m-dash]O(2-), OH(-)-CuB(2+), Tyr237˙], where the O-O bond is cleaved) in the catalytic cycle is, therefore, the proton transfer originating from Tyr237 to O-O to form the hydroperoxo [Fea3(3+)-(O-OH)(-)-CuB(2+), Tyr237(-)] state. The importance of His376 in proton uptake and the function of propionate-A/neutral-Asp372 as a gate to prevent the proton from back-flowing to the DNC are also shown.

  13. TRUEX process solvent cleanup with solid sorbents

    Energy Technology Data Exchange (ETDEWEB)

    Tse, Pui-Kwan; Reichley-Yinger, L.; Vandegrift, G.F.

    1989-01-01

    Solid sorbents, alumina, silica gel, and Amberlyst A-26 have been tested for the cleanup of degraded TRUEX-NPH solvent. A sodium carbonate scrub alone does not completely remove acidic degradation products from highly degraded solvent and cannot restore the stripping performance of the solvent. By following the carbonate scrub with either neutral alumina or Amberlyst A-26 anion exchange resin, the performance of the TRUEX-NPH is substantially restored. The degraded TRUEX-NPH was characterized before and after treatment by supercritical fluid chromatography. Its performance was evaluated by americium distribution ratios, phase-separation times, and lauric acid distribution coefficients. 17 refs., 2 figs., 5 tabs.

  14. Radionuclide concentrations in honey bees from Area G at TA-54 during 1997. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Haarmann, T.K.; Fresquez, P.R.

    1998-07-01

    Honey bees were collected from two colonies located at Los Alamos National Laboratory`s Area G, Technical Area 54, and from one control (background) colony located near Jamez Springs, NM. Samples were analyzed for the following: cesium ({sup 137}Cs), americium ({sup 241}Am), plutonium ({sup 238}Pu and {sup 239,240}Pu), tritium ({sup 3}H), total uranium, and gross gamma activity. Area G sample results from both colonies were higher than the upper (95%) level background concentration for {sup 238}Pu and {sup 3}H.

  15. Measurement of the K X-ray absorption jump ratio of erbium by attenuation of a Compton peak

    Energy Technology Data Exchange (ETDEWEB)

    Ayala, A.P.; Mainardi, R.T. [Universidad Nacional de Cordoba (Argentina). Facultad de Matematica, Astronomia y Fisica

    1996-02-01

    The X-ray absorption jump ratio of erbium was measured with a high resolution intrinsic germanium detector by attenuation, with an erbium foi, of a Compton peak produced by the scattering of the 60 keV americium 241 X-rays. Data analysis consists of a deconvolution to find the true Compton peak shape and an integration of a parameterized expression of the attenuation coefficient adjusted by least squares. Our result has an error of 1.5% and compared with calculated data shows a difference of less than 5%. PACS number(s): 32.80 Fb, 32.80 Cy. (author).

  16. The extraction behaviors of transuranic elements

    Energy Technology Data Exchange (ETDEWEB)

    Byeon, Kee Hoh; Lee, Eil Hee; Kwon, Seon Gil; Kim, Kwang Wook; Yang, Han Beom; Chung, Dong Yong; Lim, Jae Kwan; Shin, Hyun Kyoo; Kim, Soo Ho

    1999-10-01

    We have studied the distribution data between organic and aqueous phases and the related reaction data in the state of extraction equilibrium for neptunium, americium and curium of transuranic elements, and also studied the chemical properties for these chemical elements. In the results of study, distribution coefficients of transuranic elements such as Np(IV), Np(V), Np(VI) Am(III), CM(III) and the redox reactions of neptunium were rearranged numerically with the data in the published literatures. (author)

  17. 2F Evaporator CP class instrumentation uncertainties evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, E.

    1994-01-28

    There are two instrumentation systems in the 2F Evaporator facilities (bldg. 242-16F) that are classified as the Critical Protection (CP). They are the Evaporator Pot Temperature instrumentations and Steam Condensate Gamma Monitor. The pot instrumentation consists of two interrelated circuits sharing the same temperature sensor and transducer. They are the high alarm and interlock circuit and the recorder circuit. The gamma monitor instrumentation consists of four interrelated circuits sharing the same scintillation detector. They are the gamma alarm and interlock circuit, failure alarm and interlock circuit, condensate cesium activity recorder circuit, and condensate americium activity recorder circuit. The resulting uncertainties for the instrument circuits are tabulated. (GHH)

  18. Bidentate organophosphorus extractants: purification, properties and applications to removal of actinides from acidic waste solutions

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, W.W.; McIsaac, L.D.

    1977-05-01

    At both Hanford and Idaho, DHDECMP (dihexyl-N, N-diethylcarbamylmethylene phosphonate) continuous counter-current solvent extraction processes are being developed for removal of americium, plutonium, and, in some cases, other actinides from acidic wastes generated at these locations. Bench and, eventually, pilot and plant-scale testing and application of these processes have been substantially enhanced by the discovery of suitable chemical and physical methods of removing deleterious impurities from technical-grade DHDECMP. Flowsheet details, as well as various properties of purified DHDECMP extractants, are enumerated.

  19. Features of manufacturing Cd1–xZnxTe ionizing radiation detector

    Directory of Open Access Journals (Sweden)

    Tomashik Z. F.

    2013-02-01

    Full Text Available The article describes a newly-developed method of manufacturing of an operating element of the Cd1–xZnxTe-detector of ionizing radiation with high sensitivity to low-energy gamma radiation of the americium 241Am radioactive isotope. The proposed two-step method of chemical surface treatment with the use of new bromine releasing polishing etchants significantly improves the quality of the detector material and increases its specific sensitivity to ionizing radiation. This allows to use smaller Cd1–xZnxTe plates, which results in lowering of the cost of detectors.

  20. Comparison of destructive and nondestructive assay of heterogeneous salt residues

    Energy Technology Data Exchange (ETDEWEB)

    Fleissner, J.G.; Hume, M.W.

    1986-03-29

    To study problems associated with nondestructive assay (NDA) measurements of molten salt residues, a joint study was conducted by the Rocky Flats Plant, Golden, CO and Mound Laboratories, Miamisburg, OH. Extensive NDA measurements were made on nine containers of molten salt residues by both Rocky Flats and Mound followed by dissolution and solution quantification at Rocky Flats. Results of this study verify that plutonium and americium can be measured in such salt residues by a new gamma-ray spectral analysis technique coupled with calorimetry. Biases with respect to the segmented gamma-scan technique were noted.

  1. An in situ survey of Clean Slate 1, 2, and 3, Tonopah Test Range, Central Nevada. Date of survey: September--November 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    A ground-based in situ radiological survey was conducted downwind of the Clean Slate 1, 2, and 3 nuclear safety test sites at the Tonopah Test Range in central Nevada from September through November 1993. The purpose of the study was to corroborate the americium-241 ({sup 241}Am) soil concentrations that were derived from the aerial radiological survey of the Clean Slate areas, which was conducted from August through October 1993. The presence of {sup 241}Am was detected at 140 of the 190 locations, with unrecoverable or lost data accounting for fifteen (15) of the sampling points. Good agreement was obtained between the aerial and in situ results.

  2. Calculated Bulk Properties of the Actinide Metals

    DEFF Research Database (Denmark)

    Skriver, Hans Lomholt; Andersen, O. K.; Johansson, B.

    1978-01-01

    Self-consistent relativistic calculations of the electronic properties for seven actinides (Ac-Am) have been performed using the linear muffin-tin orbitals method within the atomic-sphere approximation. Exchange and correlation were included in the local spin-density scheme. The theory explains...... the variation of the atomic volume and the bulk modulus through the 5f series in terms of an increasing 5f binding up to plutonium followed by a sudden localisation (through complete spin polarisation) in americium...

  3. Analysis of nuclear materials by energy dispersive x-ray fluorescence and spectral effects of alpha decay

    Energy Technology Data Exchange (ETDEWEB)

    Worley, Christopher G [Los Alamos National Laboratory

    2009-01-01

    Energy dispersive X-ray fluorescence (EDXRF) spectra collected from alpha emitters are complicated by artifacts inherent to the alpha decay process, particularly when using portable instruments. For example, {sup 239}Pu EDXRF spectra exhibit a prominent uranium L X-ray emission peak series due to sample alpha decay rather than source-induced X-ray fluorescence. A portable EDXRF instrument was used to collect spectra from plutonium, americium, and a Pu-contaminated steel sample. The plutonium sample was also analyzed by wavelength dispersive XRF to demonstrate spectral differences observed when using these very different instruments.

  4. Dissolution of spent nuclear fuel in carbonate-peroxide solution

    Science.gov (United States)

    Soderquist, Chuck; Hanson, Brady

    2010-01-01

    This study shows that spent UO2 fuel can be completely dissolved in a room temperature carbonate-peroxide solution apparently without attacking the metallic Mo-Tc-Ru-Rh-Pd fission product phase. In parallel tests, identical samples of spent nuclear fuel were dissolved in nitric acid and in an ammonium carbonate, hydrogen peroxide solution. The resulting solutions were analyzed for strontium-90, technetium-99, cesium-137, europium-154, plutonium, and americium-241. The results were identical for all analytes except technetium, where the carbonate-peroxide dissolution had only about 25% of the technetium that the nitric acid dissolution had.

  5. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1991-07-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

  6. Technical basis for internal dosimetry at Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

    1989-04-01

    The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

  7. Radiotoxicological analyses of {sup 239+240}Pu and {sup 241}Am in biological samples by anion-exchange and extraction chromatography: a preliminary study for internal contamination evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Ridone, S.; Arginelli, D.; Bortoluzzi, S.; Canuto, G.; Montalto, M.; Nocente, M.; Vegro, M. [Italian National Agency for New Technologies, Energy and the Environment (ENEA), Research Centre of Saluggia, Radiation Protection Institute, Saluggia, VC (Italy)

    2006-07-01

    Many biological samples (urines and faeces) have been analysed by means of chromatographic extraction columns, utilising two different resins (AG 1-X2 resin chloride and T.R.U.), in order to detect the possible internal contamination of {sup 239{sup +}}{sup 240}Pu and {sup 241}Am, for some workers of a reprocessing nuclear plant in the decommissioning phase. The results obtained show on one hand the great suitability of the first resin for the determination of plutonium, and on the other the great selectivity of the second one for the determination of americium.

  8. Nitrogen macrocyclic molecules for sequestering of heavy metals; Molecules macrocycliques azotees pour la sequestration de metaux lourds

    Energy Technology Data Exchange (ETDEWEB)

    Chollet, H. [CEA Valduc, 21 - Is-sur-Tille (France); Denat, F.; Guilard, R. [Universite de Bourgogne, LIMSAG, 21 - Dijon (France)

    2006-05-15

    The tetra-aza-macrocycles and their derivatives have interesting properties in many fields, in particular for heavy metal extraction. Indeed, these ligands are able to complex many metals like uranium, plutonium, americium, cadmium, lead, etc. We describe the evolutions of design of these molecules since a score of years: simplifications of the synthesis leading to the improvement of the outputs, use of intermediate compounds facilitating the transposition at an industrial scale of the production of such molecules. The physicochemical behaviour of these ligands with respect to lanthanides and actinides, and their use within various processes of treatment are evoked. (authors)

  9. Neutron Nuclear Data Evaluation of Actinoid Nuclei for CENDL-3.1

    CERN Document Server

    Guo-Chang, Chen; Bao-Sheng, Yu; Guo-You, Tang; Zhao-Min, Shi; Xi, Tao

    2011-01-01

    New evaluations for several actinoids of the third version of China Evaluated Nuclear Data Library (CENDL-3.1) have been completed during the period between 2000 and 2005. The evaluations are for all neutron induced reactions with Uranium, Neptunium, Plutonium and Americium in the mass range A=232-241, 236-239, 236-246 and 240-244, respectively, and cover the incident neutron energy up to 20 MeV. In present evaluation, much more efforts were devoted to improve reliability of nuclide for available new measured data, especially scarce experimental data. A general description for the evaluation of several actinoids data were presented.

  10. Suitability Measurement and Analysis for El Centro Naval Air Facility OLS. Opportune Landing Site Program

    Science.gov (United States)

    2008-10-01

    radioactive source at the end of the rod and the detector at the rear of the machine housing. The source rod is extended at 50-mm (2-in.) increments...Systems Workshop Phoenix, AZ, 21–24 April 2008. Stolf, R., R. Klaus, and C. Vaz, 2005, Response to “Comments on ‘Simultaneous Measurement of Soil...americium beryllium radiation source to emit neutrons from the base of the instru- ment. The neutrons collide with water hydrogen atoms and slow. The

  11. 中国南方汉族人群高亲和度IgE受体β链 基因突变的研究%Study on mutations of β chain of high-affinity IgE receptor gene in people of Han nationality of southern China

    Institute of Scientific and Technical Information of China (English)

    汤彦; 温德良; 丁勇; 刘晓妍; 曾艺; 李月琴; 吴骎

    2001-01-01

    目的检测中国南方汉族人群高亲和度IgE受体β链基因3个突变(I181L、V183L和E237G)在支气管哮喘组和正常人群中的存在与频率。探讨这些突变与哮喘的相关性。方法利用扩增阻滞突变系统聚合酶链技术(ARMS-PCR)对60例哮喘患者Fc ε RI-β基因的编码181、183和237氨基酸位点进行分析和检测,并与65例正常人进行对照。结果在哮喘组中检测到1例I181L杂合子,被检人群中没有发现V183L突变。Glu237/Gly237在哮喘组中频率是18.3%,正常组中频率是6.2%,两者比较差异有显著性(P<0.05)。结论在中国南方汉族人群中存在E237突变,与哮喘相关。I181L突变频率很低。不存在V183L突变或频率极低。%Objective To detect mutations of β chain of high-affinity IgE receptor (Fc ε RI-β)gene and analyze the association between its mutation and asthma in people of Han nationality of southern China. Methods Amplification refractory mutation system-polymerase chain reaction technique was used to determine 3 mutations (I181L,V183L and E237G) at Fc ε RI-β gene in 60 unrelated patients with asthma and 65 healthy controls from people of Han nationality of southern China. Results (1) The mutation V183L was not detected in patient and control groups. (2) The only one heterozygous for I181/L181 was found in patient group, and no homozygous for L181/L181. (3) The frequency of Glu237/Gly237 genotype is 18.3% in patient group,and 6.2% in control group. The frequency of Gly237 gene is 9.2% in patient group,and 3.1% in control group. (4) There was a significant difference in the frequencies of Glu237/Gly237 genotype and Gly237 gene. Conclusion These results suggest that E237G mutation of Fc ε RI-β gene presents in people of Han nationality of southern China,and is correlated with asthma. There are the lack or very low frequencies of V183L and I181L mutations in people of Han nationality of southern China.

  12. Neptunium Transport Behavior in the Vicinity of Underground Nuclear Tests at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, P; Tinnacher, R M; Zavarin, M; Williams, R W; Kersting, A B

    2010-12-03

    We used short lived {sup 239}Np as a yield tracer and state of the art magnetic sector ICP-MS to measure ultra low levels of {sup 237}Np in a number of 'hot wells' at the Nevada National Security Site (NNSS), formerly known as the Nevada Test Site (NTS). The results indicate that {sup 237}Np concentrations at the Almendro, Cambric, Dalhart, Cheshire and Chancellor sites, are in the range of 3 x 10{sup -5} to 7 x 10{sup -2} pCi/L and well below the MCL for alpha emitting radionuclides (15 pCi/L) (EPA, 2009). Thus, while Np transport is believed to occur at the NNSS, activities are expected to be well below the regulatory limits for alpha-emitting radionuclides. We also compared {sup 237}Np concentration data to other radionuclides, including tritium, {sup 14}C, {sup 36}Cl, {sup 99}Tc, {sup 129}I, and plutonium, to evaluate the relative {sup 237}Np transport behavior. Based on isotope ratios relative to published unclassified Radiologic Source Terms (Bowen et al., 1999) and taking into consideration radionuclide distribution between melt glass, rubble and groundwater (IAEA, 1998), {sup 237}Np appears to be substantially less mobile than tritium and other non-sorbing radionuclides, as expected. However, this analysis also suggests that {sup 237}Np mobility is surprisingly similar to that of plutonium. The similar transport behavior of Np and Pu can be explained by one of two possibilities: (1) Np(IV) and Pu(IV) oxidation states dominate under mildly reducing NNSS groundwater conditions resulting in similar transport behavior or (2) apparent Np transport is the result of transport of its parent {sup 241}Pu and {sup 241}Am isotopes and subsequent decay to {sup 237}Np. Finally, measured {sup 237}Np concentrations were compared to recent Hydrologic Source Term (HST) models. The 237Np data collected from three wells in Frenchman Flat (RNM-1, RNM-2S, and UE-5n) are in good agreement with recent HST transport model predictions (Carle et al., 2005). The agreement

  13. Immobilization of AM-241, Formed Under Plutonium Metal Conversion into Monazite-Type Ceramics

    Energy Technology Data Exchange (ETDEWEB)

    Aloy, A S; Kovarskaya, E N; Koltsova, T I; Samoylov, S E; Rovnyi, S I; Medvedev, G M; Jardine, L J

    2001-06-06

    Lanthanum orthophosphate with the monazite structure was proposed on examinations as a suitable matrix for immobilization of future americium-containing liquid wastes, which could be formed in conversion of metallic plutonium into oxide at PA ''Mayak.'' Specimens of monazite non-active ceramics were fabricated from LaPOA powders obtained using a thin-film evaporator by either hot-pressing or cold-pressing and sintering at 900-1300 C. According to electron microprobe analysis (EMPA), scanning electron microscopy (SEM), and X-ray diffraction (XRD), which were used for characterization of produced samples, all specimens did not contain any phase other than the monoclinic monazite phase. Ceramics having the specific activity of Am-241 2.13 {center_dot}10{sup 7} Bq/g were prepared by only cold-pressing with subsequent sintering at 1300 C during 1 hour. The normalized leach rates of lanthanum and americium in distilled water at 90 C were less than 1.2. 10{sup 4} and 2.3 10{sup -4} g/m{sup 2} {center_dot} day, respectively.

  14. Waste Isolation Pilot Plant Salt Decontamination Testing

    Energy Technology Data Exchange (ETDEWEB)

    Rick Demmer; Stephen Reese

    2014-09-01

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

  15. Waste Isolation Pilot Plant Salt Decontamination Testing

    Energy Technology Data Exchange (ETDEWEB)

    Demmer, Ricky Lynn [Idaho National Laboratory; Reese, Stephen Joseph [Idaho National Laboratory

    2015-03-01

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. Several practical, easily deployable methods of decontaminating WIPP salt, using a surrogate contaminant and americium (241Am), were developed and tested. The effectiveness of the methods is evaluated qualitatively, and to the extent practical, quantitatively. Of the methods tested (dry brushing, vacuum cleaning, water washing, mechanical grinding, strippable coatings, and fixative barriers), the most practical seems to be water washing. Effectiveness is very high, and water washing is easy and rapid to deploy. The amount of wastewater produced (~2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from water washed coupons found no residual removable contamination. Thus, whatever contamination is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  16. Characterization of radiolytically generated degradation products in the strip section of a TRUEX flowsheet

    Energy Technology Data Exchange (ETDEWEB)

    Dean R. Peterman; Lonnie G. Olson; Gary S. Groenewold; Rocklan G. McDowell; Richard D. Tillotson; Jack D. Law

    2013-08-01

    This report presents a summary of the work performed to meet the FCRD level 2 milestone M3FT-13IN0302053, “Identification of TRUEX Strip Degradation.” The INL radiolysis test loop has been used to identify radiolytically generated degradation products in the strip section of the TRUEX flowsheet. These data were used to evaluate impact of the formation of radiolytic degradation products in the strip section upon the efficacy of the TRUEX flowsheet for the recovery of trivalent actinides and lanthanides from acidic solution. The nominal composition of the TRUEX solvent used in this study is 0.2 M CMPO and 1.4 M TBP dissolved in n-dodecane and the nominal composition of the TRUEX strip solution is 1.5 M lactic acid and 0.050 M diethylenetriaminepentaacetic acid. Gamma irradiation of a mixture of TRUEX process solvent and stripping solution in the test loop does not adversely impact flowsheet performance as measured by stripping americium ratios. The observed increase in americium stripping distribution ratios with increasing absorbed dose indicates the radiolytic production of organic soluble degradation compounds.

  17. A radiochemical procedure for a low-level measurement of ''241Am in environmental samples using a supported functional organo phosphorus extractant; Metodo analitico para la determinacion de ''241Am en muestras biologicas y sedimentos marinos mediante uso de una columna con extractante organico

    Energy Technology Data Exchange (ETDEWEB)

    Gasco, C.; Anton, M. P.; Alvarez, A.; Navarro, N.; Salvador, S.

    1994-07-01

    The transuranides analysis in environmental samples is carried out by CIEMAT using standardized methods based on sequential separation with ionic-exchange resins. The americium fraction is purified through a two-layer ion exchange column and lately in an anion-exchange column in nitric acid methanol medium. The technique is time consuming and the results are not completely satisfactory (low recovery and loss of a-resolution) for some samples. The chemical compound CMPO (octyl(phenyl)-N,N-diisobutyl carbomoylmethyiphosphine oxide) dissolved in TPB (tributyl phosphate) and supported on an inert substrate has been tested directly for ''241Am analysis by a large number of laboratories. A new method that combines both procedures has been developed. The details of the improved procedure are described in this paper. The advantages of its application to environmental samples (urine, faeces and sediments) are discussed. The utilization of standard samples, with americium certified concentrations confirms the reliability of our measurements. (Author) 8 refs.

  18. Eutectic reaction analysis between TRU-50%Zr alloy fuel and HT-9 cladding, and temperature prediction of eutectic reaction under steady-state

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Woan; Lee, Byoung Oon; Lee, Bong Sang; Park, Won Seok

    2001-02-01

    Blanket fuel assembly for HYPER contains a bundle of pins arrayed in triangular pitch, which has hexagonal bundle structure. The reference blanket fuel pin consists of the fuel slug of TRU-50wt%Zr alloy and the cladding material of ferritic martensite steel, HT-9. Chemical interaction between fuel slug and cladding is one of the major concerns in metallic fuel rod design. The contact of metallic fuel slug and stainless steel cladding in a fuel rod forms a complex multi-component diffusion couple at elevated temperatures. The potential problem of inter-diffusion of fuel and cladding components is essentially two-fold weakening of cladding mechanical strength due to the formation of diffusion zones in the cladding, and the formation of comparatively low melting point phases in the fuel/cladding interface to develop eutectic reaction. The main components of fuel slug are composed of zirconium alloying element in plutonium matrix, including neptunium, americium and uranium additionally. Therefore basic eutectic reaction change of Pu-Fe binary system can be assessed, while it is estimated how much other elements zirconium, uranium, americium and neptunium influence on plutonium phase stability. Afterwards it is needed that eutectic reaction is verified through experimental necessarily.

  19. Performance of a corona ion source for measurement of sulfuric acid by chemical ionization mass spectrometry

    Directory of Open Access Journals (Sweden)

    A. Kürten

    2010-11-01

    Full Text Available The performance of an ion source based on corona discharge has been studied. This source is used for the detection of gaseous sulfuric acid by chemical ionization mass spectrometry (CIMS through the reaction of NO3 ions with H2SO4. The ion source is operated under atmospheric pressure and its design is similar to the one of a radioactive (Americium 241 ion source which has been used previously. Our results show that the detection limit for the corona ion source is sufficiently good for most applications. For an integration time of one minute it is ~6 × 104 molecules of H2SO4 per cm3. In addition, only a small cross-sensitivity to SO2 has been observed for concentrations as high as 1 ppmv in the sample gas. This low sensitivity to SO2 is achieved even without the addition of an OH scavenger. When comparing the new corona ion source with the americium ion source for the same provided H2SO4 concentration, both ion sources yield almost identical values. These features make the corona ion source investigated here favorable over the more commonly used radioactive ion sources for most applications where H2SO4 is measured by CIMS.

  20. Performance of a corona ion source for measurement of sulfuric acid by chemical ionization mass spectrometry

    Directory of Open Access Journals (Sweden)

    A. Kürten

    2011-03-01

    Full Text Available The performance of an ion source based on corona discharge has been studied. This source is used for the detection of gaseous sulfuric acid by chemical ionization mass spectrometry (CIMS through the reaction of NO3 ions with H2SO4. The ion source is operated under atmospheric pressure and its design is similar to the one of a radioactive (americium-241 ion source which has been used previously. The results show that the detection limit for the corona ion source is sufficiently good for most applications. For an integration time of 1 min it is ~6 × 104 molecule cm−3 of H2SO4. In addition, only a small cross-sensitivity to SO2 has been observed for concentrations as high as 1 ppmv in the sample gas. This low sensitivity to SO2 is achieved even without the addition of an OH scavenger. When comparing the new corona ion source with the americium ion source for the same provided H2SO4 concentration, both ion sources yield almost identical values. These features make the corona ion source investigated here favorable over the more commonly used radioactive ion sources for most applications where H2SO4 is measured by CIMS.

  1. An Ion Exchange Study of Possible Hydridized 5f Bonding in theActinides

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, R.M.; Street, Jr., K.; Seaborg, G.T.

    1951-08-28

    A study has been made of the elution behavior of curium(III), americium(III), plutonium(III), actinium(III), plutonium(IV), neptunium(IV), uraniuM(IV), thorium(IV), neptunium(V), plutonium (VI), uranium (VI), lanthanum(III), cerium(III), europium(III), ytterbium(III), ytterium(III), strontium(II), barium(II), radium(II), cesium(I) with 3.2 M, 6.2 M, 9.3 M, and 12.2 M HCl solutions from Dowex-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. The strengths of the tripositive actinide complex ions apparently go in the order plutonium > americium> curium, although their ionic radii also decrease in this same order. To explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5f orbitals in the actinide elements.

  2. The EBR-II X501 Minor Actinide Burning Experiment

    Energy Technology Data Exchange (ETDEWEB)

    W. J. Carmack; M. K. Meyer; S. L. Hayes; H. Tsai

    2008-01-01

    The X501 experiment was conducted in EBR II as part of the Integral Fast Reactor program to demonstrate minor actinide burning through the use of a homogeneous recycle scheme. The X501 subassembly contained two metallic fuel elements loaded with relatively small quantities of americium and neptunium. Interest in the behavior of minor actinides (MA) during fuel irradiation has prompted further examination of existing X501 data and generation of new data where needed in support of the U.S. waste transmutation effort. The X501 experiment is one of the few MA bearing fuel irradiation tests conducted worldwide, and knowledge can be gained by understanding the changes in fuel behavior due to addition of MAs. Of primary interest are the effect of the MAs on fuel cladding chemical interaction and the redistribution behavior of americium. The quantity of helium gas release from the fuel and any effects of helium on fuel performance are also of interest. It must be stressed that information presented at this time is based on the limited PIE conducted in 1995–1996 and, currently, represents a set of observations rather than a complete understanding of fuel behavior. This report provides a summary of the X501 fabrication, characterization, irradiation, and post irradiation examination.

  3. The United States Transuranium and Uranium Registries. Revision 1, [Annual] report, October 1, 1990--April 1992

    Energy Technology Data Exchange (ETDEWEB)

    Kathren, R.L.

    1992-09-01

    This paper describes the history, organization, activities and recent scientific accomplishments of the United States Transuranium and Uranium Registries. Through voluntary donations of tissue obtained at autopsies, the Registries carry out studies of the concentration, distribution and biokinetics of plutonium in occupationally exposed persons. Findings from tissue analyses from more than 200 autopsies include the following: a greater proportion of the americium intake, as compared with plutonium, was found in the skeleton; the half-time of americium in liver is significantly shorter than that of plutonium; the concentration of actinide in the skeleton is inversely proportional to the calcium and ash content of the bone; only a small percentage of the total skeletal deposition of plutonium is found in the marrow, implying a smaller risk from irradiation of the marrow relative to the bone surfaces; estimates of plutonium body burden made from urinalysis typically exceed those made from autopsy data; pathologists were unable to discriminate between a group of uranium workers and persons without known occupational exposure on the basis of evaluation of microscopic kidney slides; the skeleton is an important long term depot for uranium, and that the fractional uptake by both skeleton and kidney may be greater than indicated by current models. These and other findings and current studies are discussed in depth.

  4. Magnetically assisted chemical separation (MACS) process: Preparation and optimization of particles for removal of transuranic elements

    Energy Technology Data Exchange (ETDEWEB)

    Nunez, L.; Kaminski, M.; Bradley, C.; Buchholz, B.A.; Aase, S.B.; Tuazon, H.E.; Vandegrift, G.F. [Argonne National Lab., IL (United States); Landsberger, S. [Univ. of Illinois, Urbana, IL (United States)

    1995-05-01

    The Magnetically Assisted Chemical Separation (MACS) process combines the selectivity afforded by solvent extractants with magnetic separation by using specially coated magnetic particles to provide a more efficient chemical separation of transuranic (TRU) elements, other radionuclides, and heavy metals from waste streams. Development of the MACS process uses chemical and physical techniques to elucidate the properties of particle coatings and the extent of radiolytic and chemical damage to the particles, and to optimize the stages of loading, extraction, and particle regeneration. This report describes the development of a separation process for TRU elements from various high-level waste streams. Polymer-coated ferromagnetic particles with an adsorbed layer of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) diluted with tributyl phosphate (TBP) were evaluated for use in the separation and recovery of americium and plutonium from nuclear waste solutions. Due to their chemical nature, these extractants selectively complex americium and plutonium contaminants onto the particles, which can then be recovered from the solution by using a magnet. The partition coefficients were larger than those expected based on liquid[liquid extractions, and the extraction proceeded with rapid kinetics. Extractants were stripped from the particles with alcohols and 400-fold volume reductions were achieved. Particles were more sensitive to acid hydrolysis than to radiolysis. Overall, the optimization of a suitable NMCS particle for TRU separation was achieved under simulant conditions, and a MACS unit is currently being designed for an in-lab demonstration.

  5. Waste management in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I. [Japan Atomic Energy Research Institute, Dept. of Safety Research Technical Support, Tokai-Mura, Naka-Gun, Ibaraki-Ken (Japan)

    2000-07-01

    In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)

  6. Radioecology of transuranics: characterization and behaviour of nuclear fuels particulates in soil of Palomares (Almeria); Radiecologia de transuranidos: Caracterizacion y comportamiento de particulas de combustible nuclear en suelos afectados por el accidente de Palomares

    Energy Technology Data Exchange (ETDEWEB)

    Aragon del Valle, A.

    2003-07-01

    The framework of this work is within Radioecology. Its objective is to improve our knowledge on the environmental impact of transuranic elements (plutonium and americium principally) in a Mediterranean ecosystem in SE Spain. The studies concerning the transuranide behavior in the affected area include solubility tests with contaminated soils (in physiological and aqueous solutions)and control of the evolution and effects caused by the agricultural activities. The interaction degree between plutonium and soil constituents has been studied by adapting and applying a sequential extraction procedure, based on the specificity of the reagents in the solubilization of the different mineralogical phases. The level of plutonium and americium has been determined in gastropods collected in the surroundings of Palomares, thus proving the presence of transuranides in the food chain. Autoradiographic studies show that the radioactive contamination present in soils, affected by a nuclear accident that occurred in 1966, is in particle form. In order to characterize the contamination, isolation, description and destructive and nondestructive analyses of radioactive particles have been performed and the results appear in this work. All these studies have been carried out by standard metrological procedures (field and laboratory), and by performing a huge number of radiochemical analysis and alpha and gamma spectrometric measurements. Therefore, the research work of this doctoral. Thesis will contribute to the obtention of an adequate scientific basis for the assessment of the radiological situation in radioactively-contaminates sites, as well as to the development of methods and criteria for restoration. (Author)

  7. NIST Calibration of a Neutron Spectrometer ROSPEC.

    Science.gov (United States)

    Heimbach, Craig

    2006-01-01

    A neutron spectrometer was acquired for use in the measurement of National Institute of Standards and Technology neutron fields. The spectrometer included options for the measurement of low and high energy neutrons, for a total measurement range from 0.01 eV up to 17 MeV. The spectrometer was evaluated in calibration fields and was used to determine the neutron spectrum of an Americium-Beryllium neutron source. The calibration fields used included bare and moderated (252)Cf, monoenergetic neutron fields of 2.5 MeV and 14 MeV, and a thermal-neutron beam. Using the calibration values determined in this exercise, the spectrometer gives a good approximation of the neutron spectrum, and excellent values for neutron fluence, for all NIST calibration fields. The spectrometer also measured an Americium-Beryllium neutron field in a NIST exposure facility and determined the field quite well. The spectrometer measured scattering effects in neutron spectra which previously could be determined only by calculation or integral measurements.

  8. Effects of soluble organic complexants and their degradation products on the removal of selected radionuclides from high-level waste. Part II: Distributions of Sr, Cs, Tc, and Am onto 32 absorbers from four variations of Hanford tank 101-SY simulant solution

    Energy Technology Data Exchange (ETDEWEB)

    Marsh, S.F. [Sandia National Labs., Albuquerque, NM (United States); Svitra, Z.V.; Bowen, S.M. [Los Alamos National Lab., NM (United States)

    1995-04-01

    Many of the radioactive waste storage tanks at U.S. Department of Energy facilities contain organic compounds that have been degraded by radiolysis and chemical reactions during decades of storage. In this second part of our three-part investigation of the effects of soluble organic complexants and their degradation products, we measured the sorption of strontium, cesium, technetium, and americium onto 32 absorbers that offer high sorption of these elements in the absence of organic complexants. The four solutions tested were (1) a simulant for a 3:1 dilution of Hanford Tank 101-SY contents that initially contained ethylenediaminetetraacetic acid (EDTA), (2) this simulant after gamma-irradiation to 34 Mrads, (3) the unirradiated simulant after treatment with a hydrothermal organic-destruction process, and (4) the irradiated simulant after hydrothermal processing. For each of 512 element/absorber/solution combinations, we measured distribution coefficients (Kds) twice for each period for dynamic contact periods of 30 min, 2 h, and 6 h to obtain information about sorption kinetics. On the basis of our 3,072 measured Kd values, the sorption of strontium and americium is significantly decreased by the organic components of the simulant solutions, whereas the sorption of cesium and technetium appears unaffected by the organic components of the simulant solutions.

  9. Dosimetry studies on prototype 241Am sources for brachytherapy.

    Science.gov (United States)

    Nath, R; Gray, L

    1987-06-01

    Sealed sources of 241Am emit primarily 60 keV photons which, because of multiple Compton scattering, produce dose distributions in water that are comparable to those from 226Ra or 137Cs. However, americium gamma rays can be shielded by thin layers of high atomic number materials since the half value layer thickness is only 1/8th of a mm of lead for americium gamma rays as compared to a value of 12 mm for 226Ra gamma rays. This may allow effective in vivo shielding of critical organs, for example; the bladder can be partially shielded by hypaque solution, and the rectum and sigmoid colon by barium sulfate. In addition, the exposure to medical personnel involved in intracavitary application and patient care may be reduced substantially by the use of relatively thin lead aprons and light weight, portable shields. To investigate the feasibility of 241Am sources for intracavitary irradiation, dosimetry studies on prototype 241Am sources have been performed and a computer model for the determination of dose distributions around encapsulated cylindrical sources of 241Am has been developed and tested. Results of dosimetry measurements using ionization chambers, lithium fluoride thermoluminescent dosimeters, a scanning scintillation probe, and film dosimetry, confirm theoretical predictions that these sources can deliver dose rates adequate for intracavitary irradiation. Further dosimetry measurements in simulated clinical situations using lead foils and test tubes filled with hypaque or barium sulfate, confirm the predicted effectiveness of in vivo shielding which can be readily achieved with 241Am sources.

  10. Ambient air sampling for radioactive air contaminants at Los Alamos National Laboratory: A large research and development facility

    Energy Technology Data Exchange (ETDEWEB)

    Eberhart, C.F.

    1998-09-01

    This paper describes the ambient air sampling program for collection, analysis, and reporting of radioactive air contaminants in and around Los Alamos National Laboratory (LANL). Particulate matter and water vapor are sampled continuously at more than 50 sites. These samples are collected every two weeks and then analyzed for tritium, and gross alpha, gross beta, and gamma ray radiation. The alpha, beta, and gamma measurements are used to detect unexpected radionuclide releases. Quarterly composites are analyzed for isotopes of uranium ({sup 234}U, {sup 235}U, {sup 238}U), plutonium ({sup 238}Pu, {sup 239/249}Pu), and americium ({sup 241}Am). All of the data is stored in a relational database with hard copies as the official records. Data used to determine environmental concentrations are validated and verified before being used in any calculations. This evaluation demonstrates that the sampling and analysis process can detect tritium, uranium, plutonium, and americium at levels much less than one percent of the public dose limit of 10 millirems. The isotopic results also indicate that, except for tritium, off-site concentrations of radionuclides potentially released from LANL are similar to typical background measurements.

  11. Synthesis and characterization of hybrid silicon based complexing materials: extraction of transuranic elements from high level liquid waste; Synthese et caracterisation de gels hybrides de silice a proprietes complexantes: applications a l'extraction des transuraniens des effluents aqueux

    Energy Technology Data Exchange (ETDEWEB)

    Conocar, O

    1999-07-01

    Hybrid organic/inorganic silica compounds with extractive properties have been developed under an enhanced decontamination program for radioactive aqueous nitric acid waste in nuclear facilities. The materials were obtained by the sol-gel process through hydrolysis and poly-condensation of complexing organo-tri-alkoxy-silanes with the corresponding tetra-alkoxy-silane. Hybrid silica compounds were initially synthesized and characterized from mono- and bis-silyl precursors with malonamide or ethylenediamine patterns. Solids with different specific areas and pore diameters were obtained depending on the nature of the precursor, its functionality and its concentration in the tetra-alkoxy-silane. These compounds were then considered and assessed for use in plutonium and americium extraction. Excellent results-partitioning coefficients and capacities have been obtained with malonamide hybrid silica. The comparison with silica compounds impregnated or grafted with the same type of organic group is significant in this respect. Much of the improved performance obtained with hybrid silica may be attributed to the large quantity of complexing groups that can be incorporated in these materials. The effect of the solid texture on the extraction performance was also studied. Although the capacity increased with the specific area, little effect was observed on the distribution coefficients -notably for americium- indicating that the most favorable complexation sites are found on the outer surface. Macroporous malonamide hybrid silica compounds were synthesized to study the effects of the pore diameter, but the results have been inconclusive to date because of the unexpected molecular composition of the materials. (author)

  12. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    Energy Technology Data Exchange (ETDEWEB)

    NA

    2004-11-22

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

  13. Use of Electro-spray Ionization Mass Spectrometry (ESI-MS) for the characterization of complexes 'ligand - metallic cations' in solution

    Energy Technology Data Exchange (ETDEWEB)

    Berthon, Laurence; Zorz, Nicole; Lagrave, Stephanie; Gannaz, Benoit; Hill, Clement [CEA-Marcoule DEN-DRCP-SCPS-LCSE, BP 17171, 30207 Bagnols sur Ceze cedex (France)

    2008-07-01

    In the framework of nuclear waste reprocessing, separation processes of minor actinides from fission products are developed by Cea. In order to understand the mechanisms involved in the extraction processes, the 'ligand/metallic cation' complexes, formed in the organic phases are characterized by electro-spray-mass-spectrometry (ESI-MS). This paper deals with the extraction of lanthanides (III) and americium (III) cations by an organic phase composed of a malonamide or / and a dialkyl phosphoric acid, diluted in an aliphatic diluent. For the dialkyl phosphoric acid, Ln(DEHP){sub 3}(HDEHP){sub 3} complexes are observed and in the presence of a large excess of Ln(NO{sub 3}){sub 3}, dinuclear species are also observed. For the malonamide extractant, it appears that the complexes formed in the organic phase are of the Nd(NO{sub 3}){sub 3}D{sub x} type, with 2 {<=} x {<=} 4: their distributions depend on the ratio [Ln]/[DMDOHEMA]. When the two extractants are present in the organic phase, mixed 'Ln-malonamide-dialkyl phosphoric acid' species are observed. The influence of several parameters, such as extractant concentration, solute concentration, aqueous acidity and the nature of the cations (lanthanides or americium) are studied. (authors)

  14. Isotope ratio analysis of individual sub-micrometer plutonium particles with inductively coupled plasma mass spectrometry.

    Science.gov (United States)

    Esaka, Fumitaka; Magara, Masaaki; Suzuki, Daisuke; Miyamoto, Yutaka; Lee, Chi-Gyu; Kimura, Takaumi

    2010-12-15

    Information on plutonium isotope ratios in individual particles is of great importance for nuclear safeguards, nuclear forensics and so on. Although secondary ion mass spectrometry (SIMS) is successfully utilized for the analysis of individual uranium particles, the isobaric interference of americium-241 to plutonium-241 makes difficult to obtain accurate isotope ratios in individual plutonium particles. In the present work, an analytical technique by a combination of chemical separation and inductively coupled plasma mass spectrometry (ICP-MS) is developed and applied to isotope ratio analysis of individual sub-micrometer plutonium particles. The ICP-MS results for individual plutonium particles prepared from a standard reference material (NBL SRM-947) indicate that the use of a desolvation system for sample introduction improves the precision of isotope ratios. In addition, the accuracy of the (241)Pu/(239)Pu isotope ratio is much improved, owing to the chemical separation of plutonium and americium. In conclusion, the performance of the proposed ICP-MS technique is sufficient for the analysis of individual plutonium particles.

  15. Synthesis of actinide nitrides, phosphides, sulfides and oxides

    Science.gov (United States)

    Van Der Sluys, William G.; Burns, Carol J.; Smith, David C.

    1992-01-01

    A process of preparing an actinide compound of the formula An.sub.x Z.sub.y wherein An is an actinide metal atom selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, x is selected from the group consisting of one, two or three, Z is a main group element atom selected from the group consisting of nitrogen, phosphorus, oxygen and sulfur and y is selected from the group consisting of one, two, three or four, by admixing an actinide organometallic precursor wherein said actinide is selected from the group consisting of thorium, uranium, plutonium, neptunium, and americium, a suitable solvent and a protic Lewis base selected from the group consisting of ammonia, phosphine, hydrogen sulfide and water, at temperatures and for time sufficient to form an intermediate actinide complex, heating said intermediate actinide complex at temperatures and for time sufficient to form the actinide compound, and a process of depositing a thin film of such an actinide compound, e.g., uranium mononitride, by subliming an actinide organometallic precursor, e.g., a uranium amide precursor, in the presence of an effectgive amount of a protic Lewis base, e.g., ammonia, within a reactor at temperatures and for time sufficient to form a thin film of the actinide compound, are disclosed.

  16. Excited levels of Pa-233; Niveles excitados del Pa-233

    Energy Technology Data Exchange (ETDEWEB)

    Vara Cuadrado, J. M.

    1969-07-01

    A study of Pa-233 excited levels from the alpha decay of Np-237 and from beta decay of Th-233 has been performed. The alpha decay spectrum was measured with a semiconductor spectrometer of 18 keV effective resolution (FWHM). Over 13 new lines were identified. The gamma ray spectra of Np-237 and Th-233 were obtained with a Ge-Li detector low and medium range energy lines, and with Si-Li detector for the low energy region. A continuous purification method of Np-237 from its comparatively short-lived daughter Pa-233 was applied. A high number of new lines were identified in both spectra. The gamma-gamma coincidence spectra were obtained with INa(T{sub 1}) detectors. (Author) 54 refs.

  17. Dicty_cDB: SSH236 [Dicty_cDB

    Lifescience Database Archive (English)

    Full Text Available SS (Link to library) SSH236 (Link to dictyBase) - - - Contig-U12328-1 SSH236F (Link to Original site) SSH...236F 189 - - - - - - Show SSH236 Library SS (Link to library) Clone ID SSH236 (Link to...ycdb.biol.tsukuba.ac.jp/CSM/SS/SSH2-B/SSH236Q.Seq.d/ Representative seq. ID SSH23...6F (Link to Original site) Representative DNA sequence >SSH236 (SSH236Q) /CSM/SS/SSH2-B/SSH236Q.Seq.d/ CTTTT.../VF/VFI8-C/VFI851Q.Seq.d/ 375 e-103 SSH237 (SSH237Q) /CSM/SS/SSH2-B/SSH237Q.Seq.d/ 375 e-103 SSH236 (SSH236Q) /CSM/SS/SSH2-B/SSH

  18. Photofission of heavy nuclei at energies up to 4 GeV

    CERN Document Server

    Cetina, C; Briscoe, W J; Cole, P L; Feldman, G; Heimberg, P; Murphy, L Y; Phillips, S; Sanabria, J C; Crannell, H; Longhi, A; Sober, D I; Kezerashvili, G Ya; Crannell, Hall

    2000-01-01

    Total photofission cross sections for 238U, 235U, 233U, 237Np, 232Th, and natPb have been measured simultaneously, using tagged photons in the energy range Egamma=0.17-3.84 GeV. This was the first experiment performed using the Photon Tagging Facility in Hall B at Jefferson Lab. Our results show that the photofission cross section for 238U relative to that for 237Np is about 80%, implying the presence of important processes that compete with fission. We also observe that the relative photofission cross sections do not depend strongly on the incident photon energy over this entire energy range. If we assume that for 237Np the photofission probability is equal to unity, we observe a significant shadowing effect starting below 1.5 GeV.

  19. Criticality experiments and benchmarks for cross section evaluation: the neptunium case

    Directory of Open Access Journals (Sweden)

    Duran I.

    2013-03-01

    Full Text Available The 237Np neutron-induced fission cross section has been recently measured in a large energy range (from eV to GeV at the n_TOF facility at CERN. When compared to previous measurement the n_TOF fission cross section appears to be higher by 5-7% beyond the fission threshold. To check the relevance of n_TOF data, we apply a criticality experiment performed at Los Alamos with a 6 kg sphere of 237Np, surrounded by enriched uranium 235U so as to approach criticality with fast neutrons. The multiplication factor ke f f of the calculation is in better agreement with the experiment (the deviation of 750 pcm is reduced to 250 pcm when we replace the ENDF/B-VII.0 evaluation of the 237Np fission cross section by the n_TOF data. We also explore the hypothesis of deficiencies of the inelastic cross section in 235U which has been invoked by some authors to explain the deviation of 750 pcm. With compare to inelastic large distortion calculation, it is incompatible with existing measurements. Also we show that the v of 237Np can hardly be incriminated because of the high accuracy of the existing data. Fission rate ratios or averaged fission cross sections measured in several fast neutron fields seem to give contradictory results on the validation of the 237Np cross section but at least one of the benchmark experiments, where the active deposits have been well calibrated for the number of atoms, favors the n_TOF data set. These outcomes support the hypothesis of a higher fission cross section of 237Np.

  20. Validation of Cross Sections with Criticality Experiment and Reaction Rates: the Neptunium Case

    Science.gov (United States)

    Leong, L. S.; Tassan-Got, L.; Audouin, L.; Berthier, B.; Le Naour, C.; Stéphan, C.; Paradela, C.; Tarrío, D.; Duran, I.

    2014-04-01

    The 237Np neutron-induced fission cross section has been recently measured in a large energy range (from eV to GeV) at the n_TOF facility at CERN. When compared to previous measurements the n_TOF fission cross section appears to be higher by 5-7% beyond the fission threshold. To check the relevance of the n_TOF data, we considered a criticality experiment performed at Los Alamos with a 6 kg sphere of 237Np, surrounded by uranium highly enriched in 235U so as to approach criticality with fast neutrons. The multiplication factor keff of the calculation is in better agreement with the experiment when we replace the ENDF/B-VII.0 evaluation of the 237Np fission cross section by the n_TOF data. We also explored the hypothesis of deficiencies of the inelastic cross section in 235U which has been invoked by some authors to explain the deviation of 750 pcm. The large modification needed to reduce the deviation seems to be incompatible with existing inelastic cross section measurements. Also we show that the νbar of 237Np can hardly be incriminated because of the high accuracy of the existing data. Fission rate ratios or averaged fission cross sections measured in several fast neutron fields seem to give contradictory results on the validation of the 237Np cross section but at least one of the benchmark experiments, where the active deposits have been well calibrated for the number of atoms, favors the n_TOF data set. These outcomes support the hypothesis of a higher fission cross section of 237Np.

  1. Criticality experiments and benchmarks for cross section evaluation: the neptunium case

    Science.gov (United States)

    Leong, L. S.; Tassan-Got, L.; Audouin, L.; Paradela, C.; Wilson, J. N.; Tarrio, D.; Berthier, B.; Duran, I.; Le Naour, C.; Stéphan, C.

    2013-03-01

    The 237Np neutron-induced fission cross section has been recently measured in a large energy range (from eV to GeV) at the n_TOF facility at CERN. When compared to previous measurement the n_TOF fission cross section appears to be higher by 5-7% beyond the fission threshold. To check the relevance of n_TOF data, we apply a criticality experiment performed at Los Alamos with a 6 kg sphere of 237Np, surrounded by enriched uranium 235U so as to approach criticality with fast neutrons. The multiplication factor ke f f of the calculation is in better agreement with the experiment (the deviation of 750 pcm is reduced to 250 pcm) when we replace the ENDF/B-VII.0 evaluation of the 237Np fission cross section by the n_TOF data. We also explore the hypothesis of deficiencies of the inelastic cross section in 235U which has been invoked by some authors to explain the deviation of 750 pcm. With compare to inelastic large distortion calculation, it is incompatible with existing measurements. Also we show that the v of 237Np can hardly be incriminated because of the high accuracy of the existing data. Fission rate ratios or averaged fission cross sections measured in several fast neutron fields seem to give contradictory results on the validation of the 237Np cross section but at least one of the benchmark experiments, where the active deposits have been well calibrated for the number of atoms, favors the n_TOF data set. These outcomes support the hypothesis of a higher fission cross section of 237Np.

  2. The association analysis of FcεRⅠβ with allergic asthma in a Chinese population

    Institute of Scientific and Technical Information of China (English)

    崔天盆; 王琳; 吴健民; 谢俊刚

    2003-01-01

    Objective To investigate the link between the polymorphism of -109 and Glu237 in the high-affinity IgE receptor β (FcεRⅠβ) gene and susceptibilty to allergic asthma in a Chinese population.Method Blood samples from 216 allergic asthma patients and 198 age- and sex-matched controls were studied. A-109C/T and a coding variant Glu237Gly in FcεRⅠβ were detected with polymerase chain reaction-restriction fragment length polymorphism(PCR-RFLP).Results The genotype frequencies were 0.403 for -109T/T, 0.491 for -109T/C and 0.106 for -109C/C in allergic asthma in a Chinese population. No significant difference in the distribution of -109C/T polymorphism was found between allergic asthma subjects and healthy controls, however, homozygosity for the -109T allele was associated with increased total plasma IgE levels in subjects with allergic asthma (F=4.020,P<0.05). The allele frequency of Gly237 in the patients and control was 0.236 and 0.136 respectively. There was a significant association between the Gly/Gly genotype and allergic asthma. Among allergic asthma patients Gly237 was significantly associated with high IgE levels.Conclusions These results suggest that the Gly237 variant of the FcεRⅠβ gene is involved in the development of allergic asthma. The-109C/T and Glu237Gly polymorphisms are two of the genetic factor identified thus far, which affect total plasma IgE levels of allergic asthma patients in a Chinese population.

  3. EST Table: FS823180 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS823180 E_FL_fmgV_14H20_R_0 10/09/28 33 %/237 aa ref|XP_001868268.1| thymus-specif...ic serine protease [Culex quinquefasciatus] gb|EDS26459.1| thymus-specific serine protease [Culex quinquefas...| PREDICTED: similar to thymus-specific serine protease [Tribolium castaneum] FS826745 fmgV ... ... 32 %/237 aa gnl|Amel|GB17481-PA 10/09/10 31 %/248 aa gi|91078858|ref|XP_972061.1

  4. Drug: D07283 [KEGG MEDICUS

    Lifescience Database Archive (English)

    Full Text Available D07283 Drug Esketamine (INN) C13H16ClNO 237.092 237.7252 D07283.gif Anesthetic ATC ...amine D07283 Esketamine (INN) Target-based classificatio...-aspartate receptor [HSA:2902 2903 2904 2905 2906] [KO:K05208 K05209 K05210 K05211 K05212] Esketamine [ATC:N01AX14] D07283 Esketamin... classification [BR:br08303] N NERVOUS SYSTEM N01 ANESTHETICS N01A ANESTHETICS, GENERAL N01AX Other general anesthetics N01AX14 Esket

  5. The isotope effect in H3S superconductor

    Science.gov (United States)

    Szczęśniak, R.; Durajski, A. P.

    2017-01-01

    The experimental value of H3S a isotope coefficient decreases from 2.37 to 0.31 in the pressure range from 130 GPa to 200 GPa. We have shown that the value of 0.31 is correctly reproduced in the framework of the classical Eliashberg approach in the harmonic approximation. On the other hand, the anomalously large value of the isotope coefficient (2.37) may be associated with the strong renormalization of the normal state by the electron density of states.

  6. 78 FR 42036 - Radio Broadcasting Services; Port Lions, AK, De Beque, CO, Benjamin, Cisco, Rule, and Shamrock, TX

    Science.gov (United States)

    2013-07-15

    ... From the Federal Register Online via the Government Publishing Office FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 73 Radio Broadcasting Services; Port Lions, AK, De Beque, CO, Benjamin, Cisco, Rule... 237C3; Cisco, Channel 261C3; Rule, Channel 288C2; and Shamrock, Channel 225C2. BILLING CODE 6712-01-P...

  7. The PADME experiment

    CERN Document Server

    ,

    2016-01-01

    The PADME experiment, hosted at the Laboratori Nazionali di Frascati, will search for a Dark Photon that decays in invisible channels with a mass up to $23.7\\,\\mbox{MeV}$ and coupling constant down to $10^{-3}$.

  8. The PADME experiment at Laboratori Nazionali di Frascati

    CERN Document Server

    ,

    2016-01-01

    The PADME experiment will search for the invisible decay of Dark Photons produced in interactions of positron from the DA$\\Phi$NE Linac on a target. The collaboration aims at reaching a sensitivity of $\\sim10^{-3}$ on the coupling constant for values of Dark Photon masses up to $23.7\\,\\mbox{MeV}$.

  9. Composition of ending inventory, November 1966

    Energy Technology Data Exchange (ETDEWEB)

    Budd, R.O.

    1966-12-14

    Submitted herewith are source and special nuclear material composition of ending inventory reports for the month of November 1966. The depleted uranium, enriched uranium, plutonium, enriched lithium, U-233, normal uranium, neptunium 237, plutonium 238, deuterium, tritium, and thorium compositions are all broken down.

  10. GULF WAR VETERANS: Limitations of Available Data for Accurately Determining the Incidence of Tumors.

    Science.gov (United States)

    2007-11-02

    growth, benign Brain, new growth, malignant Brain, new growth, benign Spinal cord , new growth malignant Spinal cord , new growth, benign Number...237 238 239 Total Eye Brain and other parts of nervous system Thyroid gland Other endocrine glands and related structures Hemangioma and...lymphangioma, any site Other and unspecified sites Carcinoma in situ Digestive organs Respiratory system Skin Breast and genitourinary system Other

  11. Minor Delinquency and Immigration: A Longitudinal Study among Male Adolescents

    Science.gov (United States)

    Titzmann, Peter F.; Silbereisen, Rainer K.; Mesch, Gustavo

    2014-01-01

    On the basis of general theories of delinquency and the specific situation of immigrants, this longitudinal study investigated predictors of initial levels and rates of change in delinquency among 188 male ethnic German Diaspora immigrants from the former Soviet Union (FSU) in Germany, 237 male native German adolescents, and 182 male Jewish…

  12. Teachers' Emotions and Emotion Management: Integrating Emotion Regulation Theory with Emotional Labor Research

    Science.gov (United States)

    Lee, Mikyoung; Pekrun, Reinhard; Taxer, Jamie L.; Schutz, Paul A.; Vogl, Elisabeth; Xie, Xiyao

    2016-01-01

    While the similarities between emotion regulation (Gross in "J Personal Soc Psychol" 74:224-237, 1998a) and emotional labor (Hochschild in The managed heart: commercialization of human feeling. University of California Press, Berkeley, 1983) have been theoretically discussed, empirical research on their relation is lacking. We examined…

  13. A Study of Promotion and Attrition of Mid-Grade Officers in the U.S. Marine Corps: Are Assignments a Key Factor?

    Science.gov (United States)

    2005-03-01

    Vincent Van Gogh This is not the end. It is not even the beginning of the end. But...usc_sup_01_10.html] accessed January 2005. Van Gogh , Vincent , Letter 237, The Hague, 22 October 1882 [http://www.vangoghgallery.com/letters/269_V

  14. Increasing Incidence of Juvenile Thyrotoxicosis in Denmark

    DEFF Research Database (Denmark)

    Kjær, R. H.; Andersen, M. S.; Hansen, D.

    2015-01-01

    . Additional data were collected on children diagnosed with GD in 2008-2012. Results: In total, 237 patients with juvenile thyrotoxicosis (JT) were identified. The overall IR in 1998-2012 was 1.58/100,000 person-years and has increased significantly from 0.79/100,000 person-years in 1982-1988 (p

  15. Comparing Benefit Estimation Techniques: Residential Flood Hazard Reduction Benefits in Roanoke, Virginia

    Science.gov (United States)

    1998-03-01

    Experimental Study of Insurance Decisions." Journal of Risk and Insurance . 46 (1979): 603-618. Senjem, N. and D. Freshwater, "The Capitalization of Flood...Implications: Journal of Risk and Insurance . 44 (1977): 237-258. Slovic, P., D. Griffin, and A. Tversky. "Compatibility Effects in Judgement and Choice." in

  16. Modelling the Role of Inter-Cultural Contact in the Motivation of Learning English as a Foreign Language

    Science.gov (United States)

    Csizer, Kata; Kormos, Judit

    2009-01-01

    The research reported in this paper explores the effect of direct and indirect cross-cultural contact on Hungarian school children's attitudes and motivated behaviour by means of structural equation modelling. Our data are based on a national representative survey of 1,777 13/14-year-old learners of English and German in Hungary; 237 of the…

  17. Conceptions of Pupils of the Primary on the Topic of an Electric Circuit in Three Countries (Canada, France and Morocco)

    Science.gov (United States)

    Métioui, Abdeljalil; MacWillie, Mireille Baulu; Trudel, Louis

    2016-01-01

    Qualitative research conducted with 237 pupils from Canada, France, and Morocco, between 10 and 12 years of age, on the setting and functioning of simple electric circuits, demonstrates that similar explanatory systems of the students. For this, we had given them a paper and pencil questionnaire of a sixty minutes duration. The first question was…

  18. 8 CFR 1280.6 - Bond to obtain clearance; form.

    Science.gov (United States)

    2010-01-01

    ... 8 Aliens and Nationality 1 2010-01-01 2010-01-01 false Bond to obtain clearance; form. 1280.6... IMMIGRATION REGULATIONS IMPOSITION AND COLLECTION OF FINES § 1280.6 Bond to obtain clearance; form. A bond to obtain clearance of a vessel or aircraft under section 231, 237, 239, 243, 251, 253, 254, 255, 256,...

  19. Pharmacogenetic determinants of beta-fibrinogen gene polymorphism in response to aspirin in patients with severe ischemic stroke

    Directory of Open Access Journals (Sweden)

    Kiking Ritarwan

    2014-12-01

    Conclusion: Plasma fibrinogen levels decreased after administration of either aspirin or polymorphisms according to age. Identification of stroke risk factors based on the relative risk of plasma fibrinogen levels are at higher degree in younger age. [J Exp Integr Med 2014; 4(4.000: 237-240

  20. 75 FR 25844 - Class Deviation From FAR 52.219-7, Notice of Partial Small Business Set-Aside

    Science.gov (United States)

    2010-05-10

    ... portion at a price higher than its offer price under the non-set-aside portion. The proposed revisions are... DOCUMENT. I237.06 NOTICE OF PARTIAL SMALL BUSINESS SET-ASIDE (DEVIATION) (DESC) (a) DEFINITION. Small... negotiated as to price and an evaluation will be made as though there were no set-aside. (4) For the...

  1. Analytical Method Details (MS): SE58_MS01 [Metabolonote[Archive

    Lifescience Database Archive (English)

    Full Text Available at an ionization current of 2.0 mA. The acceleration voltage was turned on after a solvent delay of 237 s. Data acquisition... was performed on a Pegasus IV TOF mass spectrometer (LECO, St. Joseph, MI, USA) with an acquisition

  2. Battle of Kursk: The Operational Art and Principles of War

    Science.gov (United States)

    2011-04-01

    midqle initial, and additional qualifiers separated by commas, e.g: Smith, Richard , Jr .. 7. PERFORMING ORGANIZATION NAME(S) . AND ADDRESS(ES). Self...fy065 2/000213 57 -d.html. 17 Mosier, John pg 236 18 Mosier, John pg 237 19 Kasdorf, Bruno pg 14 20 Rru; dorf , Bruno pg 15 · 21 ,~tte"tling

  3. Control of Supercavitating Vehicles using Transverse Jets

    Science.gov (United States)

    2016-03-15

    wind turbine blades," Wind Energy, Vol. 13, 2009, pp. 221-237. Mejia, 0. D. L. , Moser, R. D. , and Brzozowski, D.P. , "Effects of Trailing-Edge...thruster was designed to produce the greatest force possible given the tight size constraints. Because there was no restriction on the axial length of the

  4. Eesti peaminister ja pankur said kõrge tiitli / Priit Pullerits

    Index Scriptorium Estoniae

    Pullerits, Priit, 1965-

    2005-01-01

    Maailma Majandusfoorum andis Eesti peaministrile Juhan Partsile ja USA-s tegutsevale investeerimispankurile Steve Jurvetsonile, kelle vanemad on Eesti päritolu, tulevikujuhi nimetuse. Kokku sai tiitli 237 inimest 8000 kandidaadi hulgast. 1999. aastal sai eestlastest tiitli Helo Meigas, 2001. a. Indrek Neivelt, 2003. a. Kristiina Ojuland. Lisa: Tulevikujuhid

  5. Domain Modeling: NP_060562.3 [SAHG[Archive

    Lifescience Database Archive (English)

    Full Text Available NP_060562.3 chr16 Crystal Structure of the CUB1-EGF Interaction Domain of Complemen...t Protease C1s c1nzib_ chr16/NP_060562.3/NP_060562.3_holo_183-338.pdb psi-blast 197E,216K,229E,237N,276A,277

  6. Genetic basis of destruxin production in the entomopathogen Metarhizium robertsii

    Science.gov (United States)

    Destruxins are among the most exhaustively researched secondary metabolites of entomopathogenic fungi, yet definitive evidence for their roles in pathogenicity and virulence has yet to be shown. To establish the genetic bases for the biosynthesis of this family of depsipeptides, we identified a 23,7...

  7. Encouraging Reactivity to Create Robust Machines

    Science.gov (United States)

    2013-07-01

    quadruped locomotion (Clune et al., 2011), checkers board evaluation (Gauci & Stanley, 2010), and robocup soccer (Verbancsics & Stanley, 2010...Pfeifer, R. (2003). Evolving complete agents using artificial ontogeny. In (pp. 237 258). Springer Verlag. Brooks, R. (1994). Artifical life and...evolutionary computation conference. Springer . Green, C. (2003 2006). SharpNEAT homepage. http://sharp neat.sourceforge.net/. Haasdijk, E., Rusu, A

  8. Study on behavior of long-lived radionuclides in soil environment

    Energy Technology Data Exchange (ETDEWEB)

    Morita, Shigemitsu; Watanabe, Hitoshi; Katagiri, Hiromi; Akatsu, Yasuo [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

    1996-04-01

    Distribution of {sup 99}Tc, {sup 239,240}Pu and {sup 237}Np in soil in Japan was measured. Dependency of concentration on physical and chemical properties of soil was studied. High sensitivity inductively coupled plasma mass spectroscopy was applied to the quantitative analysis of long-lived radionuclides. (J.P.N.)

  9. The reaction of NADPH with bovine mitochondrial NADH:ubiquinone oxidoreductase revisited: II. Comparison of the proposed working hypothesis with literature data.

    NARCIS (Netherlands)

    Albracht, S.P.J.

    2010-01-01

    The first purification of bovine NADH:ubiquinone oxidoreductase (Complex I) was reported nearly half a century ago (Hatefi et al. J Biol Chem 237:1676-1680, 1962). The pathway of electron-transfer through the enzyme is still under debate. A major obstacle is the assignment of EPR signals to the indi

  10. Predictors of Self-Reported Likelihood of Working with Older Adults

    Science.gov (United States)

    Eshbaugh, Elaine M.; Gross, Patricia E.; Satrom, Tatum

    2010-01-01

    This study examined the self-reported likelihood of working with older adults in a future career among 237 college undergraduates at a midsized Midwestern university. Although aging anxiety was not significantly related to likelihood of working with older adults, those students who had a greater level of death anxiety were less likely than other…

  11. Gclust Server: 101161 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available 101161 HSA_9506431 Cluster Sequences - 1156 NP_061831.1 hypothetical protein LOC237...42 ; no annotation 1 1.00e+00 0.0 0.0 0.0 0.0 0.0 12.5 Show 101161 Cluster ID 101161 Sequence ID HSA_9506431

  12. A Novel Therapeutic Modality for Advanced-Stage Prostate Cancer Treatment

    Science.gov (United States)

    2015-10-01

    Figure 6: A. Picture of 25 weeks old TRAMP mice bearing prostate tumor. B. PKD1 and MTA1 protein levels in prostate tissues of TRAMP (TG) and their wild...Verras, M. and Z. Sun , Roles and regulation of Wnt signaling and beta-catenin in prostate cancer. Cancer Lett, 2006. 237(1): p. 22-32. 5. Sarkar, F.H

  13. Development of a Scale for Measuring Invasive Plant Environmentalism.

    Science.gov (United States)

    Wolfe, Edward W.; Dozier, Hallie

    2000-01-01

    Developed an instrument to measure invasive plant environmentalism (knowledge and attitudes concerning non-native plant invasions). Scaled responses of 237 plant nursery customers to a 17-item standardized interview using the partial credit model. Results indicate that the instrument measured the construct of invasive plant environmentalism…

  14. Um olhar econômico sobre a fotografia

    Directory of Open Access Journals (Sweden)

    Bruna Mayara Komarchesqui

    2010-08-01

    Full Text Available Resenha do livro Economia da arte e da cultura, organizado por César Bolaño, Cida Golin e Valério Brittos. São Paulo: Itaú Cultural; São Leopoldo: Cepos/Unisinos; Porto Alegre: PPGCOM/UFRGS; São Cristóvão: Obscom/UFS, 2010, 237 p.

  15. Supercontinuum generation from dispersion-flattened photonic crystal fiber using picosecond pulses

    Institute of Scientific and Technical Information of China (English)

    Li He; Bojun Yang; Xiaoguang Zhang; Li Yu

    2006-01-01

    We present the all-fiber system for supercontiuum (SC) generation with picosecond pulses. By launching1.6-ps pulses from pulsed erbium-doped fiber laser (EDFL) into a section of photonic crystal fiber (PCF),the spectral broadening is observed. The bandwidth of 237 nm (at 20 dB level) is achieved.

  16. Effects of Role Division, Interaction, and Shared Mental Model on Team Performance in Project-Based Learning Environment

    Science.gov (United States)

    Jo, Il-Hyun

    2011-01-01

    The purpose of this study was to investigate the cognitive mechanism of project-based learning teams of college students on the basis of the Shared Mental Model (SMM) theory. The study participants were 237 female college students in Korea organized into 51 project teams. To test the study hypotheses, a structural equation modeling was employed.…

  17. A review of opioid prescription in a teaching hospital in Colombia [Corrigendum

    Directory of Open Access Journals (Sweden)

    Moyano J

    2015-05-01

    Full Text Available Moyano J, Figueras A. J Pain Res. 2012;5:237–242.Jairo Moyano is also affiliated with Deparment de Farmacologia, Terapeutica i Toxicologia, Universitat Autonoma de Barcelona, Barcelona, Spain, which was not included in the original publication.Read the original article

  18. Drug: D04844 [KEGG MEDICUS

    Lifescience Database Archive (English)

    Full Text Available D04844 Mixture, Drug Paraformaldehyde - dibucaine hydrochloride mixt; Periodon (TN)... Paraformaldehyde [DR:D01494], Dibucaine hydrochloride [DR:D02220] Therapeutic category: 2730 Therapeutic category of dr...sics and sedatives 2730 Analgesics and sedatives D04844 Paraformaldehyde - dibucaine hydrochloride mixt CAS: 617-48-1 PubChem: 17398192 NIKKAJI: J237.180D ...

  19. Remarks abort certain species of the Anthribid genus Xylinades, Latr

    NARCIS (Netherlands)

    Ritsema Cz., C.

    1883-01-01

    1. Xylinades affinis Chevrol. in litt., judging from a typical specimen received from Mr. Chevrolat, is not a variety of Xylinades Westermanni Schönh., but identical with Dejean’s Xylinades marmoratus. described by Mr. Roelofs in the Notes from the Leyden Museum. Vol. II (1880), p. 237. 2. Xylinades

  20. Draft genome sequence of pigeonpea (Cajanus cajan), an orphan legume crop of resource-poor farmers

    DEFF Research Database (Denmark)

    Varshney, Rajeev K.; Chen, Wenbin; Li, Yupeng;

    2012-01-01

    Pigeonpea is an important legume food crop grown primarily by smallholder farmers in many semi-arid tropical regions of the world. We used the Illumina next-generation sequencing platform to generate 237.2 Gb of sequence, which along with Sanger-based bacterial artificial chromosome end sequences...

  1. Pathological psychology

    Institute of Scientific and Technical Information of China (English)

    2009-01-01

    2009258 Executive function and working memory of patients with mild cognitive impairment.GUO Cuiping(郭翠萍),et al.Neuropsychol Lab,Dept neurol,1st Hosp,Anhui Med Univ,Hefei 230022,Chin J Neurol,2009;42940:237-240.

  2. Norma kasumlikkus kahanes / Annika Matson

    Index Scriptorium Estoniae

    Matson, Annika, 1976-

    2005-01-01

    Autodele turvavöösid tootva Norma ärikasum oli kolmandas kvartalis 23,7 miljonit krooni, mis on ligi viiendiku võrra vähem kui eelmisel aastal samal ajal. Diagramm. Vt. samas: Rootsi analüütik ennustas suvel Norma ülevõtmist

  3. Folic Acid

    Science.gov (United States)

    ... damage. 10 Do I need folic acid after menopause? Yes. Women who have gone through menopause still need 400 micrograms of folic acid every ... United States: 2003–2006 . American Journal of Clinical Nutrition; 91(1): 231–237. Hamner, H.C., Cogswell, ...

  4. Assessing the Relationship between Family Mealtime Communication and Adolescent Emotional Well-Being Using the Experience Sampling Method

    Science.gov (United States)

    Offer, Shira

    2013-01-01

    While most prior research has focused on the frequency of family meals the issue of which elements of family mealtime are most salient for adolescents' well-being has remained overlooked. The current study used the experience sampling method, a unique form of time diary, and survey data drawn from the 500 Family Study (N = 237 adolescents with…

  5. Gclust Server: 36725 [Gclust Server

    Lifescience Database Archive (English)

    Full Text Available 36725 SCE_YOL110W=SHR5 Cluster Sequences - 237 Subunit of a palmitoyltransferase, composed...ve annotation Subunit of a palmitoyltransferase, composed of Shr5p and Erf2p, that adds a palmitoyl lipid mo

  6. 75 FR 7488 - National Institute of Allergy and Infectious Diseases; Notice of Closed Meetings

    Science.gov (United States)

    2010-02-19

    ... HUMAN SERVICES National Institutes of Health National Institute of Allergy and Infectious Diseases... personal privacy. Name of Committee: National Institute of Allergy and Infectious Diseases Special Emphasis..., Bethesda, MD 20892. 301-402-1464. eb237e@nih.gov . Name of Committee: National Institute of Allergy...

  7. Familial Influences on Sustained Attention and Inhibition in Preschoolers

    Science.gov (United States)

    Groot, Alexia S.; De Sonneville, Leo M. J.; Stins, John F.; Boomsma, Dorret I.

    2004-01-01

    Background: In this study several aspects of attention were studied in 237 nearly 6-year-old twin pairs. Specifically, the ability to sustain attention and inhibition were investigated using a computerized test battery (Amsterdam Neuropsychological Tasks). Furthermore, the Teacher's Report Form (TRF) was filled out by the teacher of the child and…

  8. An empirical algorithm to estimate spectral average cosine of underwater light field from remote sensing data in coastal oceanic waters.

    Digital Repository Service at National Institute of Oceanography (India)

    Talaulika, M.; Suresh, T.; Desa, E.S.; Inamdar, A.

    . 2003. Optical characteristics of two contrasting Case 2 waters and their influence on remote sensing algorithms. Cont Shelf Res. 23(3-4):237–250. Fournier, G. and Forand, J. L. 1994. Analytic phase function for ocean water. Ocean Optics XII. J. S...

  9. A Systems Analysis View of the Vietnam War: 1965-1972 Volume 7. Republic of Vietnam Armed Forces (RVNAF)

    Science.gov (United States)

    1975-02-18

    the severity of penalties increased. g Excludes desertions from CIDG, Armed Combat and National Police. Using SEM Statistical Surr•ry’" Tabla I Force...171 863 169 743 183 863 Ii Corps 359 1311 291 1266 237 1121 261 1268 ( XII Corps 372 1028 310 965 148 803 153 835 IV Corps 530 2413 307 2154 380 2004

  10. An Investigation of Personal Background Factors Related to the Civil Engineering Officers’ Satisfaction with the Air Force Way of Life.

    Science.gov (United States)

    1986-09-01

    21 and up, a shift in this value system can be caused by a significant emotional event (13:237). Jean Piaget , an expert in the area of value 7 rI...the previous thought processes. Piaget constructed a general development model summarized as follows: 1. There is an invariable order of the stages

  11. An evaluation of algorithms designed to classify the results from frequency doubling perimetry

    NARCIS (Netherlands)

    Muskens, RPHM; Heeg, GP; Jansonius, NM

    2004-01-01

    All previously published algorithms for the interpretation of frequency doubling perimetry test results were compared in full-threshold mode in a large group of glaucoma patients (n = 452) and normal subjects (n = 237). Areas under the receiver-operating characteristic (ROC) curve ranged from 0.86 t

  12. Data of evolutionary structure change: 1C4TC-1DPCA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1C4TC-1DPCA 1C4T 1DPC C A -----------ARSEKRVP----RKRVAERLLEAKNSTA...> ARG CA 109 VAL CA 154 ALA CA 140 1DPC... A 1DPCA IEEVPMTRLMQIGA GLU CA 181 1DPC A 1DPC... TYR CA 237 HIS CA 284 ASN CA 217 1DPC

  13. Diurnal Patterns of Photosynthesis, Chlorophyll Fluorescence, and PRI to Evaluate Water Stress in the Invasive Species, Elaeagnus umbellata Thunb

    Science.gov (United States)

    2010-01-01

    effective quantum yield of pho- tosystem II: DF=F0m ¼ F0m Fs =F0m 238 Trees (2010) 24:237–245 123 Leaf xylem pressure potentials (W) were...with ontogenic changes in water limited Chenopodium quinoa leaves. Photosynthetica 40:227–232 Yates ED, Levia DP Jr, Williams CL (2004) Recruitment of

  14. EST Table: NM_001173331 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available on) 10/09/29 76 %/269 aa ref|NP_001139700.1| abdominal B isoform RBL [Bombyx mori] dbj|BAH30152.1| Abdomin...al-B [Bombyx mori] 10/09/13 41 %/237 aa FBpp0281793|DpseGA11117-PA 10/08/29 low hom

  15. 20 CFR 408.809 - What happens to your SVB payments if you are removed (including deported) from the United States?

    Science.gov (United States)

    2010-04-01

    ... removed (including deported) from the United States? 408.809 Section 408.809 Employees' Benefits SOCIAL... Suspension § 408.809 What happens to your SVB payments if you are removed (including deported) from the... that you have been removed (including deported) from the United States under section 237(a) or...

  16. Latency and Accuracy Characteristics of Saccades and Corrective Saccades in Children and Adults.

    Science.gov (United States)

    Cohen, Mark E.; Ross, Leonard E.

    1978-01-01

    Examines the latency and the accuracy of adult's and children's saccades under optimal warning and no-warning conditions. Subjects were nine adults (mean age =23.7) and nine elementary school students (mean age =8.5). (Author/MP)

  17. Data of evolutionary structure change: 1BS7A-3CPMA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1BS7A-3CPMA 1BS7 3CPM A A -----SVLQVLHIPDERLRKVAKPVEEVNAEIQRIVDDM... 3CPM A 3CPMA THR CA 223 GLY CA 250 ILE CA 233 3CPM... A 3CPMA IKKYSDKLVPF ILE CA 313 ARG CA 309 GLN CA 237 3CPM

  18. Learning English Pragmatics in China: An Investigation into Chinese EFL Learners' Perceptions of Pragmatics

    Science.gov (United States)

    Yuan, Yifeng; Tangen, Donna; Mills, Kathy A.; Lidstone, John

    2015-01-01

    This paper reports the findings of a study investigating Chinese English language learners' perceptions of pragmatics in the EFL learning context in China. A total of 237 Chinese EFL first--year university students participated in the study. A questionnaire and focus group interviews were used to collect data about learners' pragmatics insights…

  19. Confirmation of Molecular Markers and Agronomic Traits Associated with Seed Phytate Content in Two Soybean RIL Populations

    Science.gov (United States)

    The concentration of phytate is an important consideration when analyzing grain for livestock feed rations. Simple sequence repeat (SSR) markers Satt237 and Satt561 were recently found to be linked to quantitative trait loci (QTL) for phytate concentration in soybean [Glycine max (L.) Merr.]. The ...

  20. Rapid and simultaneous determination of neptunium and plutonium isotopes in environmental samples by extraction chromatography using sequential injection analysis and ICP-MS

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hou, Xiaolin; Roos, Per

    2010-01-01

    This paper reports an automated analytical method for rapid and simultaneous determination of plutonium isotopes (239Pu and 240Pu) and neptunium (237Np) in environmental samples. An extraction chromatographic column packed with TrisKem TEVA® resin was incorporated in a sequential injection (SI...