WorldWideScience

Sample records for u2 small nuclear

  1. Yeast endoribonuclease stimulated by Novikoff Hepatoma small nuclear RNAS U1 and U2

    International Nuclear Information System (INIS)

    Stevens, A.

    1982-01-01

    Using [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) from yeast as a substrate, an endoribonuclease has been detected in enzyme fractions derived from a high salt wash of ribonucleoprotein particles of Saccharomyces cerevisiae. The [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) seems to be a preferred substrate since other polyribonucleotides are hydrolyzed more slowly, if at all. The enzyme is inhibited by ethidium bromide, but fully double-stranded polyribonucleotides are not hydrolyzed. The hydrolysis of [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) is stimulated about 2.5-fold by the addition of small nuclear RNAs U1 and U2 of Novikoff hepatoma cells. Results show that the stimulation involves an interaction of the labeled RNA with the small nuclear RNA

  2. A yeast endoribonuclease stimulated by Novikoff hepatoma small nuclear RNAs U1 and U2

    International Nuclear Information System (INIS)

    Stevens, A.

    1982-01-01

    Using [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) from yeast as a substrate, an endoribonuclease has been detected in enzyme fractions derived from a high salt wash of ribonucleoprotein particles of Saccharomyces cerevisiae. The [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) seems to be a preferred substrate since other polyribonucleotides are hydrolyzed more slowly, if at all. The enzyme is inhibited by ethidium bromide, but fully double-stranded polyribonucleotides are not hydrolyzed. The hydrolysis of [ 3 H]m 7 Gppp[ 14 C]RNA-poly(A) is stimulated about 2.5-fold by the addition of small nuclear RNAs U1 and U2 of Novikoff hepatoma cells. Results show that the stimulation involves an interaction of the labeled RNA with the small nuclear RNA

  3. Ancient Origin of the U2 Small Nuclear RNA Gene-Targeting Non-LTR Retrotransposons Utopia.

    Science.gov (United States)

    Kojima, Kenji K; Jurka, Jerzy

    2015-01-01

    Most non-long terminal repeat (non-LTR) retrotransposons encoding a restriction-like endonuclease show target-specific integration into repetitive sequences such as ribosomal RNA genes and microsatellites. However, only a few target-specific lineages of non-LTR retrotransposons are distributed widely and no lineage is found across the eukaryotic kingdoms. Here we report the most widely distributed lineage of target sequence-specific non-LTR retrotransposons, designated Utopia. Utopia is found in three supergroups of eukaryotes: Amoebozoa, SAR, and Opisthokonta. Utopia is inserted into a specific site of U2 small nuclear RNA genes with different strength of specificity for each family. Utopia families from oomycetes and wasps show strong target specificity while only a small number of Utopia copies from reptiles are flanked with U2 snRNA genes. Oomycete Utopia families contain an "archaeal" RNase H domain upstream of reverse transcriptase (RT), which likely originated from a plant RNase H gene. Analysis of Utopia from oomycetes indicates that multiple lineages of Utopia have been maintained inside of U2 genes with few copy numbers. Phylogenetic analysis of RT suggests the monophyly of Utopia, and it likely dates back to the early evolution of eukaryotes.

  4. Ribonucleoprotein organization of eukaryotic RNA. XXXII. U2 small nuclear RNA precursors and their accurate 3' processing in vitro as ribonucleoprotein particles.

    Science.gov (United States)

    Wieben, E D; Nenninger, J M; Pederson, T

    1985-05-05

    Biosynthetic precursors of U2 small nuclear RNA have been identified in cultured human cells by hybrid-selection of pulse-labeled RNA with cloned U2 DNA. These precursor molecules are one to approximately 16 nucleotides longer than mature U2 RNA and contain 2,2,7-trimethylguanosine "caps". The U2 RNA precursors are associated with proteins that react with a monoclonal antibody for antigens characteristic of small nuclear ribonucleoprotein particles. Like previously described precursors of U1 and U4 small nuclear RNAs, the pre-U2 RNAs are recovered in cytoplasmic fractions, although it is not known if this is their location in vivo. The precursors are processed to mature-size U2 RNA when cytoplasmic extracts are incubated in vitro at 37 degrees C. Mg2+ is required but ATP is not. The ribonucleoprotein structure of the pre-U2 RNA is maintained during the processing reaction in vitro, as are the 2,2,7-trimethylguanosine caps. The ribonucleoprotein organization is of major importance, as exogenous, protein-free U2 RNA precursors are degraded rapidly in the in vitro system. Two lines of evidence indicate that the conversion of U2 precursors to mature-size U2 RNA involves a 3' processing reaction. First, the reaction is unaffected by a large excess of mature U2 small nuclear RNP, whose 5' trimethylguanosine caps would be expected to compete for a 5' processing activity. Second, when pre-U2 RNA precursors are first stoichiometrically decorated with an antibody specific for 2,2,7-trimethylguanosine, the extent of subsequent processing in vitro is unaffected. These results provide the first demonstration of a eukaryotic RNA processing reaction in vitro occurring within a ribonucleoprotein particle.

  5. Circulating U2 small nuclear RNA fragments as a novel diagnostic biomarker for pancreatic and colorectal adenocarcinoma

    DEFF Research Database (Denmark)

    Baraniskin, Alexander; Nöpel-Dünnebacke, Stefanie; Ahrens, Maike

    2013-01-01

    Improved non-invasive strategies for early cancer detection are urgently needed to reduce morbidity and mortality. Non-coding RNAs, such as microRNAs and small nucleolar RNAs, have been proposed as biomarkers for non-invasive cancer diagnosis. Analyzing serum derived from nude mice implanted...... with primary human pancreatic ductal adenocarcinoma (PDAC), we identified 15 diagnostic microRNA candidates. Of those miR-1246 was selected based on its high abundance in serum of tumor carrying mice. Subsequently, we noted a cross reactivity of the established miR-1246 assays with RNA fragments derived from U...... that hsa-miR-1246 is likely a pseudo microRNA. In a next step, RNU2-1f was measured by qRT-PCR and normalized to cel-54 in 191 serum/plasma samples from PDAC and colorectal carcinoma (CRC) patients. In comparison to 129 controls, we were able to classify samples as cancerous with a sensitivity...

  6. Analysis of U2 small nuclear RNA fragments in the bile differentiates cholangiocarcinoma from primary sclerosing cholangitis and other benign biliary disorders.

    Science.gov (United States)

    Baraniskin, Alexander; Nöpel-Dünnebacke, Stefanie; Schumacher, Brigitte; Gerges, Christian; Bracht, Thilo; Sitek, Barbara; Meyer, Helmut E; Gerken, Guido; Dechene, Alexander; Schlaak, Jörg F; Schroers, Roland; Pox, Christian; Schmiegel, Wolff; Hahn, Stephan A

    2014-07-01

    Up to now the diagnosis of early stage cholangiocarcinoma (CC) has remained difficult, with low sensitivities reported for current diagnostic methods. Based on recent promising findings about circulating U2 small nuclear RNA fragments (RNU2-1f) as novel blood-based biomarkers for pancreatic and colorectal adenocarcinoma, we studied the utility of RNU2-1f as a diagnostic marker of CC in bile fluid. Bile fluid was collected from patients with CC (n = 12), controls (patients with choledocholithiasis) (n = 11) and with primary sclerosing cholangitis (PSC; n = 11). RNU2-1f levels were measured by real-time polymerase chain reaction normalized to cel-54. Measurement of RNU2-1f levels in bile fluids enabled the differentiation of patients with CC from controls in all cases. Furthermore, RNU2-1f levels in bile fluids of patients with CC were significantly higher than in patients with PSC, resulting in a receiver-operating characteristic curve area of 0.856, with sensitivity of 67 % and specificity of 91 %. Our data suggest that the measurement of RNU2-1 fragments detected in the bile fluid can be used as a diagnostic marker for CC and should be included in future prospective diagnostic studies for this disease entity.

  7. Analysis of a cDNA clone expressing a human autoimmune antigen: full-length sequence of the U2 small nuclear RNA-associated B antigen

    International Nuclear Information System (INIS)

    Habets, W.J.; Sillekens, P.T.G.; Hoet, M.H.; Schalken, J.A.; Roebroek, A.J.M.; Leunissen, J.A.M.; Van de Ven, W.J.M.; Van Venrooij, W.J.

    1987-01-01

    A U2 small nuclear RNA-associated protein, designated B'', was recently identified as the target antigen for autoimmune sera from certain patients with systemic lupus erythematosus and other rheumatic diseases. Such antibodies enabled them to isolate cDNA clone λHB''-1 from a phage λgt11 expression library. This clone appeared to code for the B'' protein as established by in vitro translation of hybrid-selected mRNA. The identity of clone λHB''-1 was further confirmed by partial peptide mapping and analysis of the reactivity of the recombinant antigen with monospecific and monoclonal antibodies. Analysis of the nucleotide sequence of the 1015-base-pair cDNA insert of clone λHB''-1 revealed a large open reading frame of 800 nucleotides containing the coding sequence for a polypeptide of 25,457 daltons. In vitro transcription of the λHB''-1 cDNA insert and subsequent translation resulted in a protein product with the molecular size of the B'' protein. These data demonstrate that clone λHB''-1 contains the complete coding sequence of this antigen. The deduced polypeptide sequence contains three very hydrophilic regions that might constitute RNA binding sites and/or antigenic determinants. These findings might have implications both for the understanding of the pathogenesis of rheumatic diseases as well as for the elucidation of the biological function of autoimmune antigens

  8. Concerted evolution of the tandemly repeated genes encoding primate U2 small nuclear RNA (the RNU2 locus) does not prevent rapid diversification of the (CT){sub n} {center_dot} (GA){sub n} microsatellite embedded within the U2 repeat unit

    Energy Technology Data Exchange (ETDEWEB)

    Liao, D.; Weiner, A.M. [Yale Univ., New Haven, CT (United States)

    1995-12-10

    The RNU2 locus encoding human U2 small nuclear RNA (snRNA) is organized as a nearly perfect tandem array containing 5 to 22 copies of a 5.8-kb repeat unit. Just downstream of the U2 snRNA gene in each 5.8-kb repeat unit lies a large (CT){sub n}{center_dot}(GA){sub n} dinucleotide repeat (n {approx} 70). This form of genomic organization, in which one repeat is embedded within another, provides an unusual opportunity to study the balance of forces maintaining the homogeneity of both kinds of repeats. Using a combination of field inversion gel electrophoresis and polymerase chain reaction, we have been able to study the CT microsatellites within individual U2 tandem arrays. We find that the CT microsatellites within an RNU2 allele exhibit significant length polymorphism, despite the remarkable homogeneity of the surrounding U2 repeat units. Length polymorphism is due primarily to loss or gain of CT dinucleotide repeats, but other types of deletions, insertions, and substitutions are also frequent. Polymorphism is greatly reduced in regions where pure (CT){sub n} tracts are interrupted by occasional G residues, suggesting that irregularities stabilize both the length and the sequence of the dinucleotide repeat. We further show that the RNU2 loci of other catarrhine primates (gorilla, chimpanzee, ogangutan, and baboon) contain orthologous CT microsatellites; these also exhibit length polymorphism, but are highly divergent from each other. Thus, although the CT microsatellite is evolving far more rapidly than the rest of the U2 repeat unit, it has persisted through multiple speciation events spanning >35 Myr. The persistence of the CT microsatellite, despite polymorphism and rapid evolution, suggests that it might play a functional role in concerted evolution of the RNU2 loci, perhaps as an initiation site for recombination and/or gene conversion. 70 refs., 5 figs.

  9. Human regulator of telomere elongation helicase 1 (RTEL1) is required for the nuclear and cytoplasmic trafficking of pre-U2 RNA.

    Science.gov (United States)

    Schertzer, Michael; Jouravleva, Karina; Perderiset, Mylene; Dingli, Florent; Loew, Damarys; Le Guen, Tangui; Bardoni, Barbara; de Villartay, Jean-Pierre; Revy, Patrick; Londoño-Vallejo, Arturo

    2015-02-18

    Hoyeraal-Hreidarsson syndrome (HHS) is a severe form of Dyskeratosis congenita characterized by developmental defects, bone marrow failure and immunodeficiency and has been associated with telomere dysfunction. Recently, mutations in Regulator of Telomere ELongation helicase 1 (RTEL1), a helicase first identified in Mus musculus as being responsible for the maintenance of long telomeres, have been identified in several HHS patients. Here we show that RTEL1 is required for the export and the correct cytoplasmic trafficking of the small nuclear (sn) RNA pre-U2, a component of the major spliceosome complex. RTEL1-HHS cells show abnormal subcellular partitioning of pre-U2, defects in the recycling of ribonucleotide proteins (RNP) in the cytoplasm and splicing defects. While most of these phenotypes can be suppressed by re-expressing the wild-type protein in RTEL1-HHS cells, expression of RTEL1 mutated variants in immortalized cells provokes cytoplasmic mislocalizations of pre-U2 and other RNP components, as well as splicing defects, thus phenocopying RTEL1-HHS cellular defects. Strikingly, expression of a cytoplasmic form of RTEL1 is sufficient to correct RNP mislocalizations both in RTEL1-HHS cells and in cells expressing nuclear mutated forms of RTEL1. This work unravels completely unanticipated roles for RTEL1 in RNP trafficking and strongly suggests that defects in RNP biogenesis pathways contribute to the pathology of HHS. © The Author(s) 2015. Published by Oxford University Press on behalf of Nucleic Acids Research.

  10. Induction of polyploidy by nuclear fusion mechanism upon decreased expression of the nuclear envelope protein LAP2β in the human osteosarcoma cell line U2OS.

    Science.gov (United States)

    Ben-Shoshan, Shirley Oren; Simon, Amos J; Jacob-Hirsch, Jasmine; Shaklai, Sigal; Paz-Yaacov, Nurit; Amariglio, Ninette; Rechavi, Gideon; Trakhtenbrot, Luba

    2014-01-28

    Polyploidy has been recognized for many years as an important hallmark of cancer cells. Polyploid cells can arise through cell fusion, endoreplication and abortive cell cycle. The inner nuclear membrane protein LAP2β plays key roles in nuclear envelope breakdown and reassembly during mitosis, initiation of replication and transcriptional repression. Here we studied the function of LAP2β in the maintenance of cell ploidy state, a role which has not yet been assigned to this protein. By knocking down the expression of LAP2β, using both viral and non-viral RNAi approaches in osteosarcoma derived U2OS cells, we detected enlarged nuclear size, nearly doubling of DNA content and chromosomal duplications, as analyzed by fluorescent in situ hybridization and spectral karyotyping methodologies. Spectral karyotyping analyses revealed that near-hexaploid karyotypes of LAP2β knocked down cells consisted of not only seven duplicated chromosomal markers, as could be anticipated by genome duplication mechanism, but also of four single chromosomal markers. Furthermore, spectral karyotyping analysis revealed that both of two near-triploid U2OS sub-clones contained the seven markers that were duplicated in LAP2β knocked down cells, whereas the four single chromosomal markers were detected only in one of them. Gene expression profiling of LAP2β knocked down cells revealed that up to a third of the genes exhibiting significant changes in their expression are involved in cancer progression. Our results suggest that nuclear fusion mechanism underlies the polyploidization induction upon LAP2β reduced expression. Our study implies on a novel role of LAP2β in the maintenance of cell ploidy status. LAP2β depleted U2OS cells can serve as a model to investigate polyploidy and aneuploidy formation by nuclear fusion mechanism and its involvement in cancerogenesis.

  11. The new NCPSS BL19U2 beamline at the SSRF for small-angle X-ray scattering from biological macromolecules in solution.

    Science.gov (United States)

    Li, Na; Li, Xiuhong; Wang, Yuzhu; Liu, Guangfeng; Zhou, Ping; Wu, Hongjin; Hong, Chunxia; Bian, Fenggang; Zhang, Rongguang

    2016-10-01

    The beamline BL19U2 is located in the Shanghai Synchrotron Radiation Facility (SSRF) and is its first beamline dedicated to biological material small-angle X-ray scattering (BioSAXS). The electrons come from an undulator which can provide high brilliance for the BL19U2 end stations. A double flat silicon crystal (111) monochromator is used in BL19U2, with a tunable monochromatic photon energy ranging from 7 to 15 keV. To meet the rapidly growing demands of crystallographers, biochemists and structural biologists, the BioSAXS beamline allows manual and automatic sample loading/unloading. A Pilatus 1M detector (Dectris) is employed for data collection, characterized by a high dynamic range and a short readout time. The highly automated data processing pipeline SASFLOW was integrated into BL19U2, with help from the BioSAXS group of the European Molecular Biology Laboratory (EMBL, Hamburg), which provides a user-friendly interface for data processing. The BL19U2 beamline was officially opened to users in March 2015. To date, feedback from users has been positive and the number of experimental proposals at BL19U2 is increasing. A description of the new BioSAXS beamline and the setup characteristics is given, together with examples of data obtained.

  12. Small nuclear reactors for desalination

    International Nuclear Information System (INIS)

    Goldsmith, K.

    1978-01-01

    Small nuclear reactors are considered to have an output of not more than 400MW thermal. Since they can produce steam at much higher conditions than needed by the brine heater of a multi-flash desalination unit, it may be economically advantageous to use small reactors for a dual-purpose installation of appropriate size, producing both electricity and desalted water, rather than for a single-purpose desalination plant only. Different combinations of dual-purpose arrangements are possible depending principally on the ratio of electricity to water output required. The costs of the installation as well as of the products are critically dependent on this ratio. For minimum investment costs, the components of the dual-purpose installation should be of a standardised design based on normal commercial power plant practice. This then imposes some restrictions on the plant arrangement but, on the other hand, it facilitates selection of the components. Depending on the electricity to water ratio to be achieved, the conventional part of the installation - essentially the turbines - will form a combination of back-pressure and condensing machines. Each ratio will probably lead to an optimum combination. In the economic evaluation of this arrangement, a distinction must be made between single-purpose and dual-purpose installations. The relationship between output and unit costs of electricity and water will be different for the two cases, but the relation can be expressed in general terms to provide guidelines for selecting the best dimensions for the plant. (author)

  13. Development and characterization of monolithic fuel miniplate alloy U-2.5Zr-7.5Nb, coated in zircaloy; Desenvolvimento e caracterizacao do combustivel nuclear tipo placa monolitico da liga U-2,5Zr-7,5Nb revestido em zircaloy

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Geraldo Correa

    2014-06-01

    The autocthonal production of nuclear fuel in Brazil for test and research reactors is restricted to MTR (Material Test Reactor) fuel type dispersion plate, using U3Si2 alloy, coated and dispersed in aluminum, developed by IPEN-SP for use in IEA-R1 reactor. Moreover, the UO{sub 2} fuel rod type for power reactors is manufactured by Rezende (RJ) with a German technology by INB under license. Currently, Brazil is performing two programs of developing reactors. Currently, Brazil is developing two reactors. One of them is the development, by CNEN, the Brazilian Multipurpose Reactor (RMB), for testing, research and radioisotope production. The other one is the development a power reactor for naval propulsion, conducted by the Brazilian Navy. This dissertation presents the development and characterization of monolithic fuel miniplate alloy U-2.5Zr-7.5Nb, coated in zircaloy (ZRY), on a laboratory scale. Due to its innovative features and properties, this fuel can be used as fuel in both test reactors, research and producing radioisotopes for power reactors as small and medium sizes. Thus, this high potential fuel can be used in domestic reactors currently under development. The development of monolithic fuel plate type is made using the technique called 'picture-frame' where a sandwich composed of a monolith alloy U-2.5Zr- 7.5Nb coupled to a frame and coated sheets of Zry is obtained. The alloy U-2.5Zr-7.5Nb was obtained by melting in an induction furnace and then was cast into rectangular ingots of graphite, thus achieving an ingot with approximate dimensions of 170 x 50 x 60 mm. The obtained ingot was hot rolled at 850 ºC, with a 50 % reduction in thickness, in order to refine the raw structure of fusion. Samples cut from the alloy U-2.5Zr-7.5Nb, with dimensions 20 x 20 x 6 mm were placed in frames and plates Zry and joined by TIG (Tungsten Inert Gas) under an atmosphere of argon, obtaining a set of 10 mm thick, 45 mm wide and 100 mm long. The sandwiches were

  14. Primary and secondary structure of U8 small nuclear RNA

    International Nuclear Information System (INIS)

    Reddy, R.; Henning, D.; Busch, H.

    1985-01-01

    U8 small nuclear RNA is a new, capped, 140 nucleotides long RNA species found in Novikoff hepatoma cells. Its sequence is: m3GpppAmUmCGUCAGGA GGUUAAUCCU UACCUGUCCC UCCUUUCGGA GGGCAGAUAG AAAAUGAUGA UUGGAGCUUG CAUGAUCUGC UGAUUAUAGC AUUUCCGUGU AAUCAGGACC UGACAACAUC CUGAUUGCUU CUAUCUGAUUOH. This RNA is present in approximately 25,000 copies/cell, and it is enriched in nucleolar preparations. Like U1, U2, U4/U6, and U5 RNAs, U8 RNA was also present as a ribonucleoprotein associated with the Sm antigen. The rat U8 RNA was highly homologous (greater than 90%) to a recently characterized 5.4 S RNA from mouse cells infected with spleen focus-forming virus. In addition to the U8 RNA, three other U small nuclear RNAs were found in anti-Sm antibody immunoprecipitates from labeled rat and HeLa cells. Each of these contained a m3GpppAm cap structure; their apparent chain lengths were 60, 130, and 65 nucleotides. These U small nuclear RNAs are designated U7, U9, and U10 RNAs, respectively

  15. Nuclear physics at small distances

    Indian Academy of Sciences (India)

    We report on the study of meson and resonance production in nuclear collisions near the threshold. Because of the large momentum transfer, these reactions occur at length scales less than the size of the hadrons. We explore whether they are best described in terms of the quark–gluon picture or the meson-exchange ...

  16. Study of phase transformation of U-2,5Zr-7,5Nb e U-3Zr-9Nb alloys for application in advanced nuclear fuel

    International Nuclear Information System (INIS)

    Pais, Rafael Witter Dias

    2015-01-01

    Metal fuels are relevant in the nuclear area due to the versatility of its use in the nuclear fuel cycle. Among the alloys of uranium investigated with high potential for use in nuclear power reactors, U-Zr-Nb alloys appear as an important alternative because of their superior physico-chemical and metallurgical properties. These alloys have also potential for use in nuclear testing, research and production radioisotopes of high performance nuclear reactors. Therefore, the development of these alloys is strategic since they are planned to be used in national reactors as RMB (Brazilian Multipurpose Reactor) and LABGENE (Electrical Generation Core Laboratory), currently under development in Brazil. In this work it was realized a extensive study in the scope of the manufacturing, heat treatment and phase transformations of U-2,5Zr-7,5Nb (m/m%) and U-3ZR-9NB (m/m%) fuel alloys. Ingots of both alloys were produced employing a specific methodology developed in this study. This methodology comprised the melting process in a vacuum induction furnace at high temperatures (1500 °C) and thermal-mechanical processing to break the as-cast structure. Samples with typical dimensions (17 x 7 x 2.5 mm) free from macrostructural defects were homogenized at 1000 °C in vacuum of 10 -5 torr for 17.5 hours with a 10°C/min cooling rate until to 820 °C and, subsequently, quenched in water. The samples, randomly selected, were subjected to isothermal treatment tests under different conditions of time and temperature. Isothermal treatments for transformation and retention phases were carried out in a special assembly designed for this work. After the tests, the samples were characterized by the usual phase characterization techniques with particular emphasis for the X-ray diffraction technique. In this way, the Rietveld refinement method was applied. In the case of uranium based alloys it is quite challenging due to the lack of data in the literature. In this work a strategy for the

  17. Small reactors and the 'second nuclear era'

    International Nuclear Information System (INIS)

    Egan, J.R.

    1984-01-01

    Predictions of the nuclear industry's demise are premature and distort both history and politics. The industry is reemerging in a form commensurate with the priorities of those people and nations controlling the global forces of production. The current lull in plant orders is due primarily to the world recession and to factors related specifically to reactor size. Traditional economies of scale for nuclear plants have been greatly exaggerated. Reactor vendors and governments in Great Britain, France, West Germany, Japan, the United States, Sweden, Canada, and the Soviet Union are developing small reactors for both domestic applications and export to the Third World. The prefabricated, factory-assembled plants under 500 MWe may alleviate many of the existing socioeconomic constraints on nuclear manufacturing, construction, and operation. In the industrialized world, small reactors could furnish a qualitatively new energy option for utilities. But developing nations hold the largest potential market for small reactors due to the modest size of their electrical systems. These units could double or triple the market potential for nuclear power in this century. Small reactors will both qualitatively and quantitatively change the nature of nuclear technology transfers, offering unique advantages and problems vis-a-vis conventional arrangements. (author)

  18. A trend to small nuclear power plants?

    International Nuclear Information System (INIS)

    Lameira, Fernando Soares

    2000-01-01

    The release of fossil fuel greenhouse gases and the depletion of cheap oil reserves outside the Persic Gulf suggest a promising scenario for the future of nuclear power. But the end of the Cold War, the crisis of the state, axiological questions and globalization may lead to a marked for small power plants. The purpose of this paper is to analyze these factors, since they are not always considered all together in the future scenarios for nuclear power. It is concluded that the current evolutionary trend of nuclear power projects toward big plants may become one of the main barriers for the introduction of new plants in the future. It is suggested that a combination of fission reactors with technologies unavailable in the 1950's, when the design characteristics of the current nuclear power plants were established, could be considered to overcome this barrier. (author)

  19. Small Nuclear Technology and Market Entry

    International Nuclear Information System (INIS)

    Stewart, J S; Schock, R N; Brown, N W; Smith, C F

    2002-01-01

    An overview of energy-system projections into the new century leads to the conclusion that nuclear power will play a significant role. How significant a role will be determined by the marketplace. Within the range of nuclear-power technologies available, small nuclear-power plants of innovative design appear to fit the needs of a number of developing nations and states. Under similar financing options used by the airline industry and others, the capital requirement barrier that puts the nuclear industry at a disadvantage in deregulated markets could be reduced. These plants have the potential advantage of modularity, are proliferation-resistant, incorporate passive safety features, minimize waste, and could be cost-competitive with fossil-fuel plants

  20. Study of phase transformation of U-2,5Zr-7,5Nb e U-3Zr-9Nb alloys for application in advanced nuclear fuel; Estudo das transformacoes de fases nas ligas U-2,5Zr-7,5Nb e U-3Zr-9Nb para aplicacao em combustivel nuclear avancado

    Energy Technology Data Exchange (ETDEWEB)

    Pais, Rafael Witter Dias

    2015-07-01

    Metal fuels are relevant in the nuclear area due to the versatility of its use in the nuclear fuel cycle. Among the alloys of uranium investigated with high potential for use in nuclear power reactors, U-Zr-Nb alloys appear as an important alternative because of their superior physico-chemical and metallurgical properties. These alloys have also potential for use in nuclear testing, research and production radioisotopes of high performance nuclear reactors. Therefore, the development of these alloys is strategic since they are planned to be used in national reactors as RMB (Brazilian Multipurpose Reactor) and LABGENE (Electrical Generation Core Laboratory), currently under development in Brazil. In this work it was realized a extensive study in the scope of the manufacturing, heat treatment and phase transformations of U-2,5Zr-7,5Nb (m/m%) and U-3ZR-9NB (m/m%) fuel alloys. Ingots of both alloys were produced employing a specific methodology developed in this study. This methodology comprised the melting process in a vacuum induction furnace at high temperatures (1500 °C) and thermal-mechanical processing to break the as-cast structure. Samples with typical dimensions (17 x 7 x 2.5 mm) free from macrostructural defects were homogenized at 1000 °C in vacuum of 10{sup -5} torr for 17.5 hours with a 10°C/min cooling rate until to 820 °C and, subsequently, quenched in water. The samples, randomly selected, were subjected to isothermal treatment tests under different conditions of time and temperature. Isothermal treatments for transformation and retention phases were carried out in a special assembly designed for this work. After the tests, the samples were characterized by the usual phase characterization techniques with particular emphasis for the X-ray diffraction technique. In this way, the Rietveld refinement method was applied. In the case of uranium based alloys it is quite challenging due to the lack of data in the literature. In this work a strategy for the

  1. Integral design small nuclear power plant UNITHERM

    International Nuclear Information System (INIS)

    Adamovich, L. A.; Grechko, G. I.; Ulasevich, V. K.; Shishkin, V. A.

    1995-01-01

    The need to erect expensive energy transmission lines to these places demands to use independent local energy sources. Therefore, a reasonable alternative to the plants fired fossil fuel, mostly hydrocarbon fuel, may come from the nuclear power plants (NPP) of relatively small capacity which are nonattended, shipped to the site by large-assembled modules and completely withdrawable from the site during decommissioning. Application of NPPs for power and heat supply may prove to be cost-efficient and rather positive from social and ecological point of view. UNITHERM NPP belongs to such energy sources and may be used for heat and power supply. Heat can be provided both as hot water and superheated steam. The consumers are able to specify heat/energy supply ratio. NPP design provides for independent energy supply to the consumers and the possibility to disconnect each of them without disruption of operation of the others. Thermal hydraulic diagram of UNITHERM NPP provides for the use of three interconnected, process circuits. The consumers of thermal energy (turbogenerator unit and boilers of the central heating unit) are arranged in the last circuit

  2. Crystallization and preliminary X-ray analysis of a U2AF65 variant in complex with a polypyrimidine-tract analogue by use of protein engineering

    International Nuclear Information System (INIS)

    Sickmier, E. Allen; Frato, Katherine E.; Kielkopf, Clara L.

    2006-01-01

    A complex of the essential splicing factor U2AF 65 and a deoxyuridine oligonucleotide has been crystallized by modification of an interdomain linker. The large subunit of the essential pre-mRNA splicing factor U2 auxiliary factor (U2AF 65 ) binds the polypyrimidine tract near the 3′ splice site of pre-mRNA introns and directs the association of the U2 small nuclear ribonucleoprotein particle (U2 snRNP) of the spliceosome with the pre-mRNA. Protein engineering, in which the flexible linker region connecting tandem RNA-recognition motifs (RRMs) within the U2AF 65 RNA-binding domain was partially deleted, allowed successful crystallization of the protein–nucleic acid complex. Cocrystals of a U2AF 65 variant with a deoxyuridine dodecamer diffract X-rays to 2.9 Å resolution and contain one complex per asymmetric unit

  3. Transcription on lampbrush chromosome loops in the absence of U2 snRNA.

    OpenAIRE

    Tsvetkov, A; Jantsch, M; Wu, Z; Murphy, C; Gall, J G

    1992-01-01

    The five small nuclear RNAs (snRNAs) involved in splicing occur on the loops of amphibian lampbrush chromosomes and in hundreds to thousands of extrachromosomal granules called B snurposomes. To assess the role of these snRNAs during transcription and to explore possible relationships between the loops and B snurposomes, we injected single-stranded antisense oligodeoxynucleotides (oligos) against U1 and U2 snRNA into toad and newt oocytes. As shown before, antisense U1 and U2 oligos caused tr...

  4. Small and medium size nuclear reactors

    International Nuclear Information System (INIS)

    Al-Mugrabi, M.A.

    1996-01-01

    The purpose of this appendix is to provide up-to-date technical information relevant to the deployment of small and medium reactors (SMRs). It summarizes the status of SMRs and discusses areas of relevance to their utilization, including seawater desalination; and in particular their simplicity, their flexibility for a variety of applications and the use of passive safety features as fundamental to most of these designs. In response to important commercial developments, the energy range of small and medium reactors is now taken as being up to around 700 MW(e). Detailed information on SMR designs can be found in the IAEA report on The Design and Development Status of Small and Medium Reactor Systems 1995. 5 refs, 2 figs, 1 tab

  5. Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2

    International Nuclear Information System (INIS)

    Tijerina S, F.

    2008-01-01

    The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

  6. The decommissioning of a small nuclear reactor

    International Nuclear Information System (INIS)

    Neset, K.; Christensen, G.C.; Lundby, J.E.; Roenneberg, G.A.

    1990-02-01

    The JEEP II reactor at Kjeller, Norway has been used as a model for a study of the decommissioning of a small research reactor. A radiological survey is given and a plan for volume reducing, packaging, certifying, classifying and shipping of the radioactive waste is described. 23 refs., 4 figs

  7. Small and medium-sized nuclear power plants

    International Nuclear Information System (INIS)

    Schmidt, R.

    1986-01-01

    Small and medium-sized nuclear power plants have long been under discussion as possible applications of nuclear power in countries with small transmission grid systems, in threshold countries and developing countries, and under special local supply conditions. IAEA has condensed and promoted this interest and tried to establish the demand, and possibilities of meeting it, in special events and campaigns. In recent years, considerable interest was registered even in industrialized countries, but here specially for heating and process heat generation applications and for special purposes and, in medium-sized units, also for combined supplies of electricity and heat. This corresponds to special reactor and plant concepts, some of which have already been developed to a stage at which construction work could begin. The analysis presented deals with necessary preconditions on the sides of the users and the vendors, with problems of economy, infrastructure and financing and with the market prospects of small nuclear power plants. (orig./HP) [de

  8. Nuclear DVCS at small x using color-dipole phenomenology

    International Nuclear Information System (INIS)

    Machado, Magno V.T.

    2009-01-01

    Using the high-energy color-dipole formalism, we study the coherent and incoherent nuclear DVCS process, γ * A→γX, in the small-x regime. We consider simple models for the elementary dipole-hadron scattering amplitude that capture the main features of the dependence on atomic number A, on energy and on momentum transfer t. Using the amplitudes obtained we make predictions for the nuclear DVCS cross section at the photon level in collider kinematics. (orig.)

  9. On the development of small nuclear power stations

    International Nuclear Information System (INIS)

    Goetzmann, C.A.

    1989-01-01

    There are weighty reasons for and against the building of small nuclear power stations. Factors such as specific investment costs, opportunities for and areas of application, geographical conditions as well as those relating to infrastructure, security and availability play an important role in the planning, construction and running of a nuclear power station. For the usual large power stations, the comparatively low specific investment costs and a proven technology are favorable factors which minimize the investment risk. The article presents an overview of reasons for using small power stations and also considers the difficulties which would arise in practice. (orig.) [de

  10. Radwaste Management in Small Nuclear Country - National Policy and Strategy

    International Nuclear Information System (INIS)

    Zagar, Tomaz

    2014-01-01

    The lecture will briefly present the Slovene nuclear program and its legal framework focused on the radioactive waste management policy and strategy aspect. Slovenia is an example of small EU member state with small shared nuclear power program demonstrating safe, secure and efficient management of radioactive waste. Different principles of radioactive waste management will be discoursed; among others including: minimization of waste generation, the polluter pays principle, safe storage followed by final disposal and also new findings on research and development of storage, disposal and recycling of radioactive waste. (author)

  11. Import and export of small quantities of nuclear materials

    International Nuclear Information System (INIS)

    Grenier, M.

    1986-06-01

    Administrative procedures for import export of nuclear materials are specific for each country. In France regulations are reviewed for small quantities, lower threshold, in some cases, allows a simplified procedure, however thresholds are not the same in the different texts (and for one of them, concerning proliferation, is zero). It is obvious that regulations are necessary even for small quantities but national and international threshold should be harmonized [fr

  12. Activities in the field of small nuclear power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Baranaev, Yu.D.; Dolgov, V.V.; Sergeev, Yu.A. [Physics and Power Eng. Inst., Obninsk (Russian Federation). State Res. Centre

    1997-10-01

    Considerable efforts have been undertaken for development, design, construction and operation of small nuclear power plants (SNPP) in Russia. Systematic work in this area was started in the mid-1950s. The driving force for this activity was the awareness that the use of nuclear fuel would practically solve the problem of fuel transportation. As far as the remote northern regions are concerned, this provides the key advantage of nuclear over conventional energy sources. The activity in the field of SNPP has included pre-design analytical feasibility studies and experimental research including large-scale experiments on critical assemblies, thermal and hydraulic test facilities, research and development work, construction and operation of pilot and demonstration SNPPs, and finally, construction and more than 20 years of operation of the commercial SNPP, namely Bilibino nuclear co-generation plant (NCGP) located in Chukotka autonomous district, which is one of the most remote regions in the far north-east of Russia. In recent years, studies have been carried out on the development of several new SNPP designs using advanced reactors of the new generation. Among these are the second stage of Bilibino NCGP, floating NCGP VOLNOLOM-3, designated for siting in the Arctic sea coast area, and a nuclear district heating plant for the town of Apatity, in the Murmansk region. In this paper, the background and current status of the SNPPs are given, and the problems as well as prospects of small nuclear reactors development and implementation are considered. (orig.) 20 refs.

  13. A Realistic $U(2)$ Model of Flavor arXiv

    CERN Document Server

    Linster, Matthias

    We propose a simple $U(2)$ model of flavor compatible with an $SU(5)$ GUT structure. All hierarchies in fermion masses and mixings arise from powers of two small parameters that control the $U(2)$ breaking. In contrast to previous $U(2)$ models this setup can be realized without supersymmetry and provides an excellent fit to all SM flavor observables including neutrinos. We also consider a variant of this model based on a $D_6 \\times U(1)_F$ flavor symmetry, which closely resembles the $U(2)$ structure, but allows for Majorana neutrino masses from the Weinberg operator. Remarkably, in this case one naturally obtains large mixing in the lepton sector from small mixing in the quark sector. The model also offers a natural option for addressing the Strong CP Problem and Dark Matter by identifying the Goldstone boson of the $U(1)_F$ factor as the QCD axion.

  14. Small reactors for low-temperature nuclear heat applications

    International Nuclear Information System (INIS)

    1988-06-01

    In accordance with the Member States' calls for information exchange in the field of nuclear heat application (NHA) two IAEA meetings were organized already in 1976 and 1977. After this ''promising period'', the development of relevant programmes in IAEA Member States was slowed down and therefore only after several years interruption a new Technical Committee Meeting with a Workshop was organized in late 1983, to review the status of NHA, after a few new specific plans appeared in some IAEA Member States in the early 1980's for the use of heat from existing or constructed NPPs and for developing nuclear heating plants (NHP). In June 1987 an Advisory Group Meeting was convened in Winnipeg, Canada, to discuss and formulate a state-of-the-art review on ''Small Reactors for Low Temperature Nuclear Heat Application''. Information on this subject gained up to 1987 in the Member States whose experts attended this meeting is embodied in the present Technical Report. Figs and tabs

  15. A Single Global Small-User Nuclear Repository

    International Nuclear Information System (INIS)

    Conca, J.L.; Wright, J.

    2009-01-01

    Global energy partnerships in nuclear power, proposed by France, Russia, U.S. and England, seek to address the proliferation issue by controlling fuel production and nuclear materials, removing the need for each country to develop enrichment, fabrication, recycling or disposal capabilities. Several of the large generator countries such as France, the U.S., Japan, S. Korea, Russia, the U.K., China and India, all have plans for deep geologic repositories because they anticipate sufficient waste over the next century to justify the expense of a repository. However, countries having, or planning, less than five reactors, such as Egypt, Iran, Indonesia, Brazil and about 30 other countries, will not have sufficient waste generation, or a favorable geologic site, to justify the economic and environmental issues of developing their own repository. The Salado salt formation in New Mexico, set aside for nuclear waste disposal within the 16 square-mile area by the Land Withdrawal Act of 1992, is the most optimal geologic formation for the permanent disposal of any nuclear waste and is easily able to host all of the commercial nuclear waste that will be generated in the next thousand years. The U.S. commercial nuclear waste needs presently surpass all others, and will for the foreseeable future. Hosting the relatively small amount of waste from these small-user nations will add little to U.S. waste stream while the cost/benefit analysis from the standpoint of operations, safety, geology, cost and proliferation is overwhelmingly positive for developing such a global repository. Oceanic and overland transportation, high-level disposal logistics and costs from several programs, including WIPP, have demonstrated that the operation would pay for itself from international user fees with no U.S. taxpayer dollars required and still save the world about $400 billion over 100 years. The ethical considerations alone are compelling. (authors)

  16. Financial analysis of large versus small nuclear power plants

    International Nuclear Information System (INIS)

    Louh, R.F.; Becker, M.; Wicks, F.

    1986-01-01

    There have been no new orders for nuclear plants and many nuclear plants under construction have been cancelled in recent years in the United States. Financing problems have been a major factor in this slow down of new nuclear plant activity. Meanwhile, the nuclear plants that have been completed have been operating cost effectively and yielding fossil fuel conservation and air quality benefits. Smaller plants have been designed in the past for the purpose of penetrating markets in developing countries and countries with relatively small utility systems. This paper examines the question of whether these smaller plants would be a viable option to large nuclear plants in the United States. Although the smaller plants are estimated to have a somewhat higher capital cost on a $/k W basis, they have the potential advantage of a lower total financial committment. The computational tools required for this evaluation are optimal generation planning and financial simulation programs and the corresponding generation and financial data bases for a variety of systems

  17. Ultrasonic meters in the feedwater flow to recover thermal power in the reactor of nuclear power plant of Laguna Verde U1 and U2; Medidores ultrasonicos en el flujo de agua de alimentacion para recuperar potencia termica en el reactor de la Central Nuclear Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F. [CFE, Central Laguna Verde, Km. 42.5 Carretera Cardel-Nautla, Veracruz (Mexico)]. e-mail: francisco.tijerina@cfe.gob.mx

    2008-07-01

    The engineers in nuclear power plants BWRs and PWRs based on the development of the ultrasonic technology for the measurement of the mass, volumetric flow, density and temperature in fluids, have applied this technology in two primary targets approved by the NRC: the use for the recovery of thermal power in the reactor and/or to be able to realize an increase of thermal power licensed in a 2% (MUR) by 1OCFR50 Appendix K. The present article mentions the current problem in the measurement of the feedwater flow with Venturi meters, which affects that the thermal balance of reactor BWRs or PWRs this underestimated. One in broad strokes describes the application of the ultrasonic technology for the ultrasonic measurement in the flow of the feedwater system of the reactor and power to recover thermal power of the reactor. One is to the methodology developed in CFE for a calibration of the temperature transmitters of RTD's and the methodology for a calibration of the venturi flow transmitters using ultrasonic measurement. Are show the measurements in the feedwater of reactor of the temperature with RTD's and ultrasonic measurement, as well as the flow with the venturi and the ultrasonic measurement operating the reactor to the 100% of nominal thermal power, before and after the calibration of the temperature transmitters and flow. Finally, is a plan to be able to realize a recovery of thermal power of the reactor, showing as carrying out their estimations. As a result of the application of ultrasonic technology in the feedwater of reactor BWR-5 in Laguna Verde, in the Unit 1 cycle 13 it was recover an equivalent energy to a thermal power of 25 MWt in the reactor and an exit electrical power of 6 M We in the turbogenerator. Also in the Unit 2 cycle 10 it was recover an equivalent energy to a thermal power of 40 MWt in the reactor and an exit electrical power of 16 M We in the turbogenerator. (Author)

  18. Leading twist nuclear shadowing, nuclear generalized parton distributions and nuclear DVCS at small x

    Energy Technology Data Exchange (ETDEWEB)

    Guzey, Vadim; Goeke, Klaus; Siddikov, Marat

    2009-01-01

    We generalize the leading twist theory of nuclear shadowing and calculate quark and gluon generalized parton distributions (GPDs) of spinless nuclei. We predict very large nuclear shadowing for nuclear GPDs. In the limit of the purely transverse momentum transfer, our nuclear GPDs become impact parameter dependent nuclear parton distributions (PDFs). Nuclear shadowing induces non-trivial correlations between the impact parameter $b$ and the light-cone fraction $x$. We make predictions for the deeply virtual Compton scattering (DVCS) amplitude and the DVCS cross section on $^{208}$Pb at high energies. We calculate the cross section of the Bethe-Heitler (BH) process and address the issue of the extraction of the DVCS signal from the $e A \\to e \\gamma A$ cross section. We find that the $e A \\to e \\gamma A$ differential cross section is dominated by DVCS at the momentum transfer $t$ near the minima of the nuclear form factor. We also find that nuclear shadowing leads

  19. Small nuclear reactor safety design requirements for autonomous operation

    International Nuclear Information System (INIS)

    Kozier, K.S.; Kupca, S.

    1997-01-01

    Small nuclear power reactors offer compelling safety advantages in terms of the limited consequences that can arise from major accident events and the enhanced ability to use reliable, passive means to eliminate their occurrence by design. Accordingly, for some small reactor designs featuring a high degree of safety autonomy, it may be-possible to delineate a ''safety envelope'' for a given set of reactor circumstances within which safe reactor operation can be guaranteed without outside intervention for time periods of practical significance (i.e., days or weeks). The capability to operate a small reactor without the need for highly skilled technical staff permanently present, but with continuous remote monitoring, would aid the economic case for small reactors, simplify their use in remote regions and enhance safety by limiting the potential for accidents initiated by inappropriate operator action. This paper considers some of the technical design options and issues associated with the use of small power reactors in an autonomous mode for limited periods. The focus is on systems that are suitable for a variety of applications, producing steam for electricity generation, district heating, water desalination and/or marine propulsion. Near-term prospects at low power levels favour the use of pressurized, light-water-cooled reactor designs, among which those having an integral core arrangement appear to offer cost and passive-safety advantages. Small integral pressurized water reactors have been studied in many countries, including the test operation of prototype systems. (author)

  20. Small size modular fast reactors in large scale nuclear power

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Toshinsky, G.I.; Komlev, O.G.; Dragunov, U.G.; Stepanov, V.S.; Klimov, N.N.; Kopytov, I.I.; Krushelnitsky, V.N.

    2005-01-01

    The report presents an innovative nuclear power technology (NPT) based on usage of modular type fast reactors (FR) (SVBR-75/100) with heavy liquid metal coolant (HLMC) i. e. eutectic lead-bismuth alloy mastered for Russian nuclear submarines' (NS) reactors. Use of this NPT makes it possible to eliminate a conflict between safety and economic requirements peculiar to the traditional reactors. Physical features of FRs, an integral design of the reactor and its small power (100 MWe), as well as natural properties of lead-bismuth coolant assured realization of the inherent safety properties. This made it possible to eliminate a lot of safety systems necessary for the reactor installations (RI) of operating NPPs and to design the modular NPP which technical and economical parameters are competitive not only with those of the NPP based on light water reactors (LWR) but with those of the steam-gas electric power plant. Multipurpose usage of transportable reactor modules SVBR-75/100 of entirely factory manufacture assures their production in large quantities that reduces their fabrication costs. The proposed NPT provides economically expedient change over to the closed nuclear fuel cycle (NFC). When the uranium-plutonium fuel is used, the breeding ratio is over one. Use of proposed NPT makes it possible to considerably increase the investment attractiveness of nuclear power (NP) with fast neutron reactors even today at low costs of natural uranium. (authors)

  1. Potential advantages and disadvantages of sequentially building small nuclear units instead of a large nuclear plant

    International Nuclear Information System (INIS)

    Feretic, D.; Cavlina, N.; Grgic, D.

    2008-01-01

    Renewal of nuclear power programs in countries with modest electricity consumptions and weak electrical grid interconnections has raised the question of optimal nuclear power plants sizes for such countries. The same question would be also valid for isolated or weakly connected regions within a large country. Building large size nuclear power plant could be prevented by technical or financial limits. Research programs have been initiated in the International Atomic Energy Agency and in the USA (within the framework of the Global Nuclear Energy Partnership (GNEP) program) with the aim to inspect under which circumstances small and medium reactors could be the preferred option compared to large nuclear plants. The economy of scale is a clear advantage of large plants. This paper compares, by using probabilistic methods, the net cash flow of large and medium size plants, taking as example a large nuclear plant (around 1200 MW) and four sequentially built smaller plants (300 MW). Potential advantages and disadvantageous of both options have been considered. Main advantages of the sequential construction of several identical small units could be the reduced investor risk and reduced investment costs due to the learning effect. This analysis is a part of studies for the Croatian power generating system development. (orig.)

  2. Coded Aperture Nuclear Scintigraphy: A Novel Small Animal Imaging Technique

    Directory of Open Access Journals (Sweden)

    Dawid Schellingerhout

    2002-10-01

    Full Text Available We introduce and demonstrate the utility of coded aperture (CA nuclear scintigraphy for imaging small animals. CA imaging uses multiple pinholes in a carefully designed mask pattern, mounted on a conventional gamma camera. System performance was assessed using point sources and phantoms, while several animal experiments were performed to test the usefulness of the imaging system in vivo, with commonly used radiopharmaceuticals. The sensitivity of the CA system for 99mTc was 4.2 × 103 cps/Bq (9400 cpm/μCi, compared to 4.4 × 104 cps/Bq (990 cpm/μCi for a conventional collimator system. The system resolution was 1.7 mm, as compared to 4–6 mm for the conventional imaging system (using a high-sensitivity low-energy collimator. Animal imaging demonstrated artifact-free imaging with superior resolution and image quality compared to conventional collimator images in several mouse and rat models. We conclude that: (a CA imaging is a useful nuclear imaging technique for small animal imaging. The advantage in signal-to-noise can be traded to achieve higher resolution, decreased dose or reduced imaging time. (b CA imaging works best for images where activity is concentrated in small volumes; a low count outline may be better demonstrated using conventional collimator imaging. Thus, CA imaging should be viewed as a technique to complement rather than replace traditional nuclear imaging methods. (c CA hardware and software can be readily adapted to existing gamma cameras, making their implementation a relatively inexpensive retrofit to most systems.

  3. Testing of Small Graphite Samples for Nuclear Qualification

    Energy Technology Data Exchange (ETDEWEB)

    Julie Chapman

    2010-11-01

    Accurately determining the mechanical properties of small irradiated samples is crucial to predicting the behavior of the overal irradiated graphite components within a Very High Temperature Reactor. The sample size allowed in a material test reactor, however, is limited, and this poses some difficulties with respect to mechanical testing. In the case of graphite with a larger grain size, a small sample may exhibit characteristics not representative of the bulk material, leading to inaccuracies in the data. A study to determine a potential size effect on the tensile strength was pursued under the Next Generation Nuclear Plant program. It focuses first on optimizing the tensile testing procedure identified in the American Society for Testing and Materials (ASTM) Standard C 781-08. Once the testing procedure was verified, a size effect was assessed by gradually reducing the diameter of the specimens. By monitoring the material response, a size effect was successfully identified.

  4. Spent Fuel Challenges Facing Small and New Nuclear Programmes

    International Nuclear Information System (INIS)

    McCombie, C.

    2015-01-01

    In order to ensure that the radioactive wastes in any country are managed safely, it is necessary to have an established legislative and regulatory framework and also to create the necessary organizations for implementation and for oversight of waste management operations and facility development. Guidance on these issues is given in the Joint Convention and a number of other IAEA documents. The IAEA, and also the EC, have in addition published key overarching strategic advisory documents for new nuclear programmes. These tend to imply that all nuclear programmes, however large or small, should be pressing ahead urgently towards early implementation of geological repositories. In practice, however, in small programmes there are neither economic nor technical drivers for early implementation of deep geological repositories; constructing simpler facilities for the disposal of the larger volume of low-level waste has higher priority. Nevertheless, in all countries political decisions have to be taken and policies set in place to ensure that geological disposal will implemented without unjustified delay. This paper distils out a set of key messages for small programmes. Amongst the most critical are the following. Even if disposal is far off, planning and organization should begin at the initiation of the programme; this can help with technical and economic optimization and (importantly) also with public and political acceptance. Important lessons can be learned from advanced programmes — but these must be adapted to allow for the different boundary conditions of new and small programmes. The key differences relate to the timescales involved, and the resources available. There is a range of waste management and waste disposal options open to new programmes. It is not necessary to choose definitive solutions at the outset; options can be kept open, but a minimum level of engagement is required for all open options. (author)

  5. Fractionation of HeLa cell nuclear extracts reveals minor small nuclear ribonucleoprotein particles

    International Nuclear Information System (INIS)

    Kroemer, A.

    1987-01-01

    Upon chromatographic fractionation of HeLa cell nuclear extracts, small RNAs of 145 and 66/65 nucleotides, respectively, were detected that are distinct from the abundant small RNAs present in the extract. These RNAs are precipitated by antibodies directed against the trimethylguanosine cap structure, characteristic for small nuclear RNAs (snRNAs) of the U type. The RNAs of 145 and 66/65 nucleotides appear to be associated with at least one of the proteins common to the major small nuclear ribonucleoprotein particles U1 to U6, since they are specifically bound by anti-Sm antibodies. These criteria characterize the RNAs that are 145 and 66/65 nucleotides in length as U-type snRNAs. Upon gel filtration, the RNAs are found within particles of molecular weights ≅ 150,000 and 115,000 respectively. The RNA of 145 nucleotides represents a different minor snRNA, designated U11, whereas the RNA of 66/65 nucleotides may correspond to either mammalian U7 or U10 RNA

  6. Spliceosomal small nuclear RNAs of Tetrahymena thermophila and some possible snRNA-snRNA base-pairing interactions

    DEFF Research Database (Denmark)

    Orum, H; Nielsen, Henrik; Engberg, J

    1991-01-01

    We have identified and characterized the full set of spliceosomal small nuclear RNAs (snRNAs; U1, U2, U4, U5 and U6) from the ciliated protozoan Tetrahymena thermophila. With the exception of U4 snRNA, the sizes of the T. thermophila snRNAs are closely similar to their metazoan homologues. The T....... thermophila snRNAs all have unique 5' ends, which start with an adenine residue. In contrast, with the exception of U6, their 3' ends show some size heterogeneity. The primary sequences of the T. thermophila snRNAs contain the sequence motifs shown, or proposed, to be of functional importance in other...

  7. Small Nuclear Co-generation Plants Based on Shipbuilding Technology

    International Nuclear Information System (INIS)

    Vasyukov, V. I.; Veshnyakov, K. B.; Goryunov, E. V.; Zalugin, V. I.; Panov, Yu. K.; Polunichev, V. I.

    2002-01-01

    The development of nuclear cogeneration plants and power desalination complexes of relatively small power, using proven shipbuilding technology, becomes more and more attractive for solving the power supply problems of remote districts of the Extreme North and the Far East with small and medium power grids and for removing the shortage of fresh water in different world regions. The idea of transportation of the power unit with high degree of readiness to the place of its location with minimum construction and mounting activities at the site is very attractive. Compactness typical of RP based on shipbuilding technology allows to develop floating or ground-based plants at minimum use of water area and territory. Small construction scope at the site under conditions of minimum anthropogenic loads and high ecological indices are important arguments in favor of floating nuclear cogeneration plant based on ship power units against the alternative fossil sources. At present, the activities on floating nuclear cogeneration plant design, which is developed on the basis of floating power unit with two KLT-40S reactor plant, which is a modified option of standard KLT-40-type ship plant for icebreaker fleet in Russia are the most advanced. To date, a detailed design of reactor plant has been developed and approved, design activities on floating power unit are in the stage of completion, the site for its location has been selected and licensing by GAN, Russia, is in progress. Besides OKBM has developed some designs of nuclear cogeneration plants of different power on the basis of integral reactor plants, using the experience of transport and stationary power plants designing. Nuclear cogeneration plant investment analysis showed acceptable social and economical efficiency of the design that creates conditions for commercial construction of floating power units with KLT-40S reactor plan. At the same time the reduction of the design recovering terms, increase of budget income and

  8. New advanced small and medium nuclear power reactors: possible nuclear power plants for Australia

    International Nuclear Information System (INIS)

    Dussol, R.J.

    2003-01-01

    In recent years interest has increased in small and medium sized nuclear power reactors for generating electricity and process heat. This interest has been driven by a desire to reduce capital costs, construction times and interest during construction, service remote sites and ease integration into small grids. The IAEA has recommended that the term 'small' be applied to reactors with a net electrical output less than 300 MWe and the term 'medium' to 300-700 MWe. A large amount of experience has been gained over 50 years in the design, construction and operation of small and medium nuclear power reactors. Historically, 100% of commercial reactors were in these categories in 1951-1960, reducing to 21% in 1991-2000. The technologies involved include pressurised water reactors, boiling water reactors, high temperature gas-cooled reactors, liquid metal reactors and molten salt reactors. Details will be provided of two of the most promising new designs, the South African Pebble Bed Modular Reactor (PBMR) of about 110 MWe, and the IRIS (International Reactor Innovative and Secure) reactor of about 335 MWe. Their construction costs are estimated to be about US$l,000/kWe with a generating cost for the PBMR of about US1.6c/kWh. These costs are lower than estimated for the latest designs of large reactors such as the European Pressurised Reactor (EPR) designed for 1,600 MWe for use in Europe in the next decade. It is concluded that a small or medium nuclear power reactor system built in modules to follow an increasing demand could be attractive for generating low cost electricity in many Australian states and reduce problems arising from air pollution and greenhouse gas emissions from burning fossil fuels

  9. Small Punch Tests applied to the nuclear industry

    International Nuclear Information System (INIS)

    Moreno, M.; Gongora, P.; Bertolino, G; Yawny, A.

    2012-01-01

    The interest on miniaturized specimen techniques for the characterization of the mechanical behavior of materials was strongly motivated in the early eighties by the different programs associated with the development of fusion reactor technology. The importance of such developments is obvious in the case of the nuclear industry where the limited space available, the presence of fluence gradients in large specimens, the concern about gamma heating and dose to personnel in post-irradiation testing have all been motivations for reducing specimen size. Testing of miniature specimen includes a wide spectrum of techniques such as tensile, instrumented micro-hardness, small punch, bend, fracture, impact and fatigue. Small Punch Testing (SPT) techniques use a spherical penetrator which deforms to failure a miniature disc shaped flat specimen (typically, 3-10 mm in diameter and 0.25-0.50 mm in thickness) supported on its outer rim. Analysis of load-displacement data recorded along the test is performed for the determination of the property of interest. The present work focuses on the characterization of the elastoplastic response of pure Al, ADN 420 structural steel and AISI 304L using SPT and its correlation with the associated standard uniaxial testing behavior. In addition, the sensitivity of the technique to the specific material under study and to different experimental parameters, i.e. specimen diameter and thickness, clearance or clamping force and friction between disc and dies have been assessed both experimentally and by performing simulations using the finite element method (author)

  10. University centres of nuclear competence as TSO's in small non-nuclear countries

    International Nuclear Information System (INIS)

    Jovanovic, Slobodan

    2010-01-01

    Montenegro is small, developing 'non-nuclear' country, the use of radiation sources being modest and limited to ordinary medical and industrial applications. Even though - and taking into account current and near-future status of the field - there is (or will be) significant need in nuclear knowledge. It goes about the following areas: (i) medical applications (diagnostics, radiotherapy, palliation, sterilization of equipment, consumables, blood products, etc.), (ii) environmental protection (radioecology, low and medium activity radioactive waste management, analytical and monitoring services, etc.), (iii) industrial, geological, hydrological, agricultural, biochemical and archaeological applications (non-destructive testing, various gauges, radioisotope labeling, etc.), (iv) scientific and educational applications, (v) radiation protection, emphasizing safety and security of radiation sources, (vi) legislative and regulatory aspects, including complying to international safety/ security norms and joining international conventions in the field, (vii) preparedness and response to radiological and nuclear emergency situations, (viii) combating illicit trafficking of nuclear and radioactive materials, (ix) forensic applications, (x) security systems based on X-ray and other nuclear methods, (xi) introduction of some future topics (e.g. nuclear power for electricity generation and sea water desalination) and (xii) information and communication with media. At present, there is clear a shortage in NK in the country, resulting i.a. from long lasting poor interest of young students for the subject University of Montenegro - the only state university in the country - effectuates practically complete high education in natural and technical sciences. At the Faculty of Natural Sciences and Mathematics, Department of Physics, there is a basic education in nuclear physics, while some post-graduate curricula offer topics in radioecology, medical physics and radiation protection

  11. Habitats of small mammals at Whiteshell Nuclear Research Establishment

    Energy Technology Data Exchange (ETDEWEB)

    Iverson, S L; Turner, B N

    1973-12-01

    The small mammals in the area around the Whiteshell Nuclear Research Establishment in southeastern Manitoba were sampled by approximately 110,000 snap- trap nights in a 5 year period. Habitats trapped were divided into major types on the basis of the tree species present, and occurrences of the different species of shrubs and herbs in each habitat type were noted. The major habitats were mixed deciduous, aspen, ash, mixed coniferous, The small mammal component of the mixed deciduous forest was dominated by Peromyscus maniculatus and Clethrionomys gapperi but all of the other species included in this study were also present. In both aspen and ash forests, Microtus pennsylvanicus and C. gapperi were the most numerous species, with Sorex arcticus reaching its greatest abundance in the latter. In the open field, M. pennsylvanicus was most abundant, followed by Zapus hudsonius, C. gapperi, M. pennsylvanicus and Sorex cinereus were the most numerous mammals in the black spruce bog community, and also extended into the black spruce forest. All of the species studied, except Napaeozapus insignis and S. arcticus, were present in the mixed coniferous forest. S. arcticus and S. cinereus, although captured in habitats ranging from heavy forest to open field, appeared to be most numerous in young forests and other intermediate habitats. Blarina brevicauda was most numerous in older forests. P. maniculatus and N. insignis were most common in the mixed deciduous forest, but P. maniculatus occurred more frequently than N. insignis in the younger forests. P. maniculatus showed a significant positive relationship with large tree diameter and low percentages of ground cover. C. gapperi was captured in highest numbers in the mixed deciduous and coniferous forests, but was also found in the other types of forest in greater numbers than P. maniculaius. M. pennsylvanicus and Zapus hudsonius were most common in the open field, but both species were present in the forests. Analysis of data

  12. Westinghouse Small Modular Reactor nuclear steam supply system design

    Energy Technology Data Exchange (ETDEWEB)

    Memmott, M. J.; Harkness, A. W.; Van Wyk, J. [Westinghouse Electric Company LLC, 600 Cranberry Woods Drive, Cranberry Twp. PA 16066 (United States)

    2012-07-01

    The Westinghouse Small Modular Reactor (SMR) is an 800 MWt (>225 MWe) integral pressurized water reactor (iPWR), in which all of the components typically associated with the nuclear steam supply system (NSSS) of a nuclear power plant are incorporated within a single reactor pressure vessel. This paper is the first in a series of four papers which describe the design and functionality of the Westinghouse SMR. Also described in this series are the key drivers influencing the design of the Westinghouse SMR and the unique passive safety features of the Westinghouse SMR. Several critical motivators contributed to the development and integration of the Westinghouse SMR design. These design driving motivators dictated the final configuration of the Westinghouse SMR to varying degrees, depending on the specific features under consideration. These design drivers include safety, economics, AP1000{sup R} reactor expertise and experience, research and development requirements, functionality of systems and components, size of the systems and vessels, simplicity of design, and licensing requirements. The Westinghouse SMR NSSS consists of an integral reactor vessel within a compact containment vessel. The core is located in the bottom of the reactor vessel and is composed of 89 modified Westinghouse 17x17 Robust Fuel Assemblies (RFA). These modified fuel assemblies have an active core length of only 2.4 m (8 ft) long, and the entirety of the core is encompassed by a radial reflector. The Westinghouse SMR core operates on a 24 month fuel cycle. The reactor vessel is approximately 24.4 m (80 ft) long and 3.7 m (12 ft) in diameter in order to facilitate standard rail shipping to the site. The reactor vessel houses hot and cold leg channels to facilitate coolant flow, control rod drive mechanisms (CRDM), instrumentation and cabling, an intermediate flange to separate flow and instrumentation and facilitate simpler refueling, a pressurizer, a straight tube, recirculating steam

  13. Nuclear policy retrospection in Brazil and forecasting for using of small nuclear power plants - SNPs - in the Brazilian electric system

    International Nuclear Information System (INIS)

    Santos, E.M. dos.

    1992-02-01

    This thesis highlights the nuclear energy perspectives to regain a prominent place in the world energy mix, as a competitive and safe energy source. Just considering the current international changes in the nuclear power features in the developed countries, it is assessed the suitability and feasibility of defining a new nuclear policy in Brazil, based on the development of small and medium nuclear power reactors - SMNPR. The SMNPR's may be a good nuclear strategy for Brazil to develop a national and evolutionary reactor design with several improvements in safety, by means of passive safety systems. This reactor may play a significant role in the brazilian electrical system in the long term. (author)

  14. Nuclear-Mechanical Coupling: Small Amplitude Mechanical Vibrations and High Amplitude Power Oscillations in Nuclear Reactors

    International Nuclear Information System (INIS)

    Suarez Antola, R.

    2008-11-01

    The cores of nuclear reactors, including its structural parts and cooling fluids, are complex mechanical systems able to vibrate in a set of normal modes and frequencies, if suitable perturbed. The cyclic variations in the strain state of the core materials may produce changes in density. Changes in density modify the reactivity. Changes in reactivity modify thermal power. Modifications in thermal power produce variations in temperature fields. Variations in temperature produce variations in strain due to thermal-elastic effects. If the variation of the temperature field is fast enough and if the Doppler Effect and other stabilizing prompt effects in the fuel are weak enough, a fast oscillatory instability could be produced, coupled with mechanical vibrations of small amplitude. A recently constructed, simple mathematical model of nuclear reactor kinetics, that improves the one due to A.S. Thompson, is reviewed. It was constructed in order to study, in a first approximation, the stability of the reactor: a nonlinear nuclear-thermal oscillator (that corresponds to reactor point kinetics with thermal-elastic feedback and with frozen delayed neutron effects) is coupled nonlinearly with a linear mechanical-thermal oscillator (that corresponds to the first normal mode of mechanical vibrations excited by thermo-elastic effects). This mathematical model is studied here from the standpoint of mechanical vibrations. It is shown how, under certain conditions, a suitable mechanical perturbation could elicit fast and growing oscillatory instabilities in the reactor power. Applying the asymptotic method due to Krylov, Bogoliubov and Mitropolsky, analytical formulae that may be used in the calculation of the time varying amplitude and phase of the mechanical oscillations are given, as functions of the mechanical, thermal and nuclear parameters of the reactor. The consequences for the mechanical integrity of the reactor are assessed. Some conditions, mainly, but not exclusively

  15. Analysis on Domestic Law and Management Trend Related to Small-Quantity Nuclear Material

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Beom; Lee, Kyong Woo; Shim, Hye Won; Min, Gyung Sik [National Nuclear Management and Control Agency, Daejeon (Korea, Republic of)

    2005-07-01

    International Atomic Energy Agency (IAEA) has requested Korea to establish and manage the law ruling all nuclear materials through the INFCIRC/153. Now, it has been 30 years since Korea made the agreement, INFCIRC/153, with IAEA. Korea has tried their best to accomplish the international standard in nuclear control field and it is a fact that Korea finally produced some results in the nuclear control field. Related to nuclear material control, Korea is above the common level appropriately ranked 6th in the world in terms of nuclear power. Before 2000, Korea was making the foundation secure in the nuclear control. IAEA did not urge to establish the law supervising the small-quantity nuclear material and depleted uranium (DU). In a turnaround from early IAEA moderate line to Korea, the situation was changed. Since IAEA brought up the agenda to 2000 Joint Review Meeting between Korea-IAEA, IAEA has asked Korea to establish the control system for smallquantity nuclear material and DU. In 2003, the Korean government set up a project establishing the control system about all nuclear material including small-quantity nuclear material and DU. National Nuclear Management and Control Agency (NNCA), delegating the business relating to international controlling materials from government, developed some modules in nuclear material control system and operated it. The system includes a controlling system for small-quantity nuclear material. NNCA on behalf of government has collected the information and Korea Ministry of Science and Technology (MOST) has reported the information to the IAEA. This paper introduces you the background of controlling the small-quantity nuclear material and the system of controlling nuclear material in Korea. And it will suggest the improvement of the management method in the system for small-quantity nuclear material.

  16. Analysis on Domestic Law and Management Trend Related to Small-Quantity Nuclear Material

    International Nuclear Information System (INIS)

    Park, Jae Beom; Lee, Kyong Woo; Shim, Hye Won; Min, Gyung Sik

    2005-01-01

    International Atomic Energy Agency (IAEA) has requested Korea to establish and manage the law ruling all nuclear materials through the INFCIRC/153. Now, it has been 30 years since Korea made the agreement, INFCIRC/153, with IAEA. Korea has tried their best to accomplish the international standard in nuclear control field and it is a fact that Korea finally produced some results in the nuclear control field. Related to nuclear material control, Korea is above the common level appropriately ranked 6th in the world in terms of nuclear power. Before 2000, Korea was making the foundation secure in the nuclear control. IAEA did not urge to establish the law supervising the small-quantity nuclear material and depleted uranium (DU). In a turnaround from early IAEA moderate line to Korea, the situation was changed. Since IAEA brought up the agenda to 2000 Joint Review Meeting between Korea-IAEA, IAEA has asked Korea to establish the control system for smallquantity nuclear material and DU. In 2003, the Korean government set up a project establishing the control system about all nuclear material including small-quantity nuclear material and DU. National Nuclear Management and Control Agency (NNCA), delegating the business relating to international controlling materials from government, developed some modules in nuclear material control system and operated it. The system includes a controlling system for small-quantity nuclear material. NNCA on behalf of government has collected the information and Korea Ministry of Science and Technology (MOST) has reported the information to the IAEA. This paper introduces you the background of controlling the small-quantity nuclear material and the system of controlling nuclear material in Korea. And it will suggest the improvement of the management method in the system for small-quantity nuclear material

  17. Nuclear opacity for neutrinos at small Q2

    International Nuclear Information System (INIS)

    Kopeliovich, B.Z.

    1989-01-01

    The causes of nuclear screening of the vector and the weak axial currents are quite different. The hadronic fluctuations of neutrino in the nuclear matter live much longer than in the vacuum, due to interaction with nucleons. Nuclear opacity for neutrinos calculated using Glauber-Gribov theory, differs considerably from that given by the Bell optical model. A good agreement of the theory with the recent BEBC WA59 Collaboration measurements is found. 14 refs.; 4 figs

  18. Decontamination and Decommissioning at Small Nuclear Facilities: Facilitating the Submission of Decommissioning Funding Plans

    International Nuclear Information System (INIS)

    Minor, D.A.; Grumbles, A.

    2009-01-01

    This paper describes the efforts of the Washington State Department of Health to ensure that small nuclear facilities have the tools each needs to submit Decommissioning Funding Plans. These Plans are required by both the U.S. Nuclear Regulatory Commission (NRC) and in some states - in the case of Washington state, the Washington State Department of Health is the regulator of radioactive materials. Unfortunately, the guidance documents provided by the U.S. NRC pertain to large nuclear facilities, such as nuclear fuel fabrication plants, not the small nuclear laboratory nor small nuclear laundry that may also be required to submit such Plans. These small facilities are required to submit Decommissioning Funding Plans by dint of their nuclear materials inventory, but have only a small staff, such as a Radiation Safety Officer and few authorized users. The Washington State Department of Health and Attenuation Environmental Company have been working on certain tools, such as templates and spreadsheets, that are intended to assist these small nuclear facilities prepare compliant Decommissioning Funding Plans with a minimum of experience and effort. (authors)

  19. Neutrino mass with large S U (2 )L multiplet fields

    Science.gov (United States)

    Nomura, Takaaki; Okada, Hiroshi

    2017-11-01

    We propose an extension of the standard model introducing large S U (2 )L multiplet fields which are quartet and septet scalars and quintet Majorana fermions. These multiplets can induce the neutrino masses via interactions with the S U (2 ) doublet leptons. We then find the neutrino masses are suppressed by a small vacuum expectation value of the quartet/septet and an inverse of the quintet fermion mass, relaxing the Yukawa hierarchies among the standard model fermions. We also discuss collider physics at the Large Hadron Collider, considering the production of charged particles in these multiplets, and due to the effects of violating the custodial symmetry, some specific signatures can be found. Then, we discuss the detectability of these signals.

  20. Consideration of sharing small term management under the EPC model on Nuclear power

    International Nuclear Information System (INIS)

    Yu Yong

    2012-01-01

    The special nature and importance of sharing small term under management of nuclear power EPC mode were discussed. Advantages and disadvantages of EPC mode on nuclear power.engineering is analyzed. Pointed out the management problems of owners, general contracting units, equipment suppliers and engineering construction units and other parties involved in the process of a common small term implementing. The recommendations concerning management of the owners and general contractors and subcontractors owners of nuclear power engineering inside during the management of the common aspects of sharing small term were made

  1. Small and medium size nuclear power reactors for desalination

    International Nuclear Information System (INIS)

    Raisic, N.; Goodman, E.I.

    1976-01-01

    Taking the water needs, e.g. of some of the world's major towns, as a basis, it is investigated whether nuclear energy can be utilized economically for desalination. When a certain distance for the transport of water from other regions is exceeded it is quite possible that nuclear desalination becomes economical. Taking the example of Honkong, it is shown that this method can find application for other reasons, too, e.g. if the need exceeds the possibilities there are of meeting this need from natural sources. (UA) [de

  2. Old foes, new understandings: nuclear entry of small non-enveloped DNA viruses.

    Science.gov (United States)

    Fay, Nikta; Panté, Nelly

    2015-06-01

    The nuclear import of viral genomes is an important step of the infectious cycle for viruses that replicate in the nucleus of their host cells. Although most viruses use the cellular nuclear import machinery or some components of this machinery, others have developed sophisticated ways to reach the nucleus. Some of these have been known for some time; however, recent studies have changed our understanding of how some non-enveloped DNA viruses access the nucleus. For example, parvoviruses enter the nucleus through small disruptions of the nuclear membranes and nuclear lamina, and adenovirus tugs at the nuclear pore complex, using kinesin-1, to disassemble their capsids and deliver viral proteins and genomes into the nucleus. Here we review recent findings of the nuclear import strategies of three small non-enveloped DNA viruses, including adenovirus, parvovirus, and the polyomavirus simian virus 40. Copyright © 2015 Elsevier B.V. All rights reserved.

  3. Alteration of the SETBP1 gene and splicing pathway genes SF3B1, U2AF1, and SRSF2 in childhood acute myeloid leukemia.

    Science.gov (United States)

    Choi, Hyun-Woo; Kim, Hye-Ran; Baek, Hee-Jo; Kook, Hoon; Cho, Duck; Shin, Jong-Hee; Suh, Soon-Pal; Ryang, Dong-Wook; Shin, Myung-Geun

    2015-01-01

    Recurrent somatic SET-binding protein 1 (SETBP1) and splicing pathway gene mutations have recently been found in atypical chronic myeloid leukemia and other hematologic malignancies. These mutations have been comprehensively analyzed in adult AML, but not in childhood AML. We investigated possible alteration of the SETBP1, splicing factor 3B subunit 1 (SF3B1), U2 small nuclear RNA auxiliary factor 1 (U2AF1), and serine/arginine-rich splicing factor 2 (SRSF2) genes in childhood AML. Cytogenetic and molecular analyses were performed to reveal chromosomal and genetic alterations. Sequence alterations in the SETBP1, SF3B1, U2AF1, and SRSF2 genes were examined by using direct sequencing in a cohort of 53 childhood AML patients. Childhood AML patients did not harbor any recurrent SETBP1 gene mutations, although our study did identify a synonymous mutation in one patient. None of the previously reported aberrations in the mutational hotspot of SF3B1, U2AF1, and SRSF2 were identified in any of the 53 patients. Alterations of the SETBP1 gene or SF3B1, U2AF1, and SRSF2 genes are not common genetic events in childhood AML, implying that the mutations are unlikely to exert a driver effect in myeloid leukemogenesis during childhood.

  4. Innovations on nuclear energy - what can a small country contribute?

    International Nuclear Information System (INIS)

    Smodis, B.; Cercek, M.

    2007-01-01

    The Slovenian energy policy gives priority to the use of renewable energy resources. The energy policy defined in the Resolution on the National Energy Program adopted in 2004 foresees increasing of renewable energy (RES) sources in the primary energy consumption up to 12 % in 2010. The share of electricity from RES in total electricity production in the year 2004 was 29,1%. The share of RES in the primary energy balance in the same year was 10,7 %, with about half of this coming from hydropower. The electricity power produced by co-generation is about 8 % and expected to double by 2010. However, the Krsko nuclear power plant produces about one third of electricity needed within the country. Consequently, Slovenia has long tradition in research pertaining to development and utilisation of nuclear technology. Furthermore, Slovenian scientists have long been collaborating in numerous fusion-related projects. The major equipment available include an ion-beam accelerator with material diagnostics installations, the TRIGA nuclear research reactor, high-temperature furnaces, an advanced, dedicated fully-integrated high-resolution microscope facility for investigations of nano structured materials, computer systems for simulations, structural mechanical analysis and CAD, and much more. The researchers at the Jozef Stefan Institute study the processes that occur on plasma facing materials and in the edge plasma of tokamak reactors and involve neutral hydrogen/deuterium molecules. These molecules are typically vibrationally excited that influences respective reaction cross sections. Therefore, a special experimental technique for vibrational spectroscopy of molecules was developed and an ion beam analytical technique ERDA is used for characterizing hydrogen content on and beneath the material surface. Ion beam analytical methods are also being developed for the studies of plasma wall interaction processes such as erosion, deposition, fuel retention and material migration in

  5. Evidence that C9ORF72 Dipeptide Repeat Proteins Associate with U2 snRNP to Cause Mis-splicing in ALS/FTD Patients.

    Science.gov (United States)

    Yin, Shanye; Lopez-Gonzalez, Rodrigo; Kunz, Ryan C; Gangopadhyay, Jaya; Borufka, Carl; Gygi, Steven P; Gao, Fen-Biao; Reed, Robin

    2017-06-13

    Hexanucleotide repeat expansion in the C9ORF72 gene results in production of dipeptide repeat (DPR) proteins that may disrupt pre-mRNA splicing in amyotrophic lateral sclerosis (ALS) and frontotemporal dementia (FTD) patients. At present, the mechanisms underlying this mis-splicing are not understood. Here, we show that addition of proline-arginine (PR) and glycine-arginine (GR) toxic DPR peptides to nuclear extracts blocks spliceosome assembly and splicing, but not other types of RNA processing. Proteomic and biochemical analyses identified the U2 small nuclear ribonucleoprotein particle (snRNP) as a major interactor of PR and GR peptides. In addition, U2 snRNP, but not other splicing factors, mislocalizes from the nucleus to the cytoplasm both in C9ORF72 patient induced pluripotent stem cell (iPSC)-derived motor neurons and in HeLa cells treated with the toxic peptides. Bioinformatic studies support a specific role for U2-snRNP-dependent mis-splicing in C9ORF72 patient brains. Together, our data indicate that DPR-mediated dysfunction of U2 snRNP could account for as much as ∼44% of the mis-spliced cassette exons in C9ORF72 patient brains. Copyright © 2017 The Author(s). Published by Elsevier Inc. All rights reserved.

  6. Evidence that C9ORF72 Dipeptide Repeat Proteins Associate with U2 snRNP to Cause Mis-splicing in ALS/FTD Patients

    Directory of Open Access Journals (Sweden)

    Shanye Yin

    2017-06-01

    Full Text Available Hexanucleotide repeat expansion in the C9ORF72 gene results in production of dipeptide repeat (DPR proteins that may disrupt pre-mRNA splicing in amyotrophic lateral sclerosis (ALS and frontotemporal dementia (FTD patients. At present, the mechanisms underlying this mis-splicing are not understood. Here, we show that addition of proline-arginine (PR and glycine-arginine (GR toxic DPR peptides to nuclear extracts blocks spliceosome assembly and splicing, but not other types of RNA processing. Proteomic and biochemical analyses identified the U2 small nuclear ribonucleoprotein particle (snRNP as a major interactor of PR and GR peptides. In addition, U2 snRNP, but not other splicing factors, mislocalizes from the nucleus to the cytoplasm both in C9ORF72 patient induced pluripotent stem cell (iPSC-derived motor neurons and in HeLa cells treated with the toxic peptides. Bioinformatic studies support a specific role for U2-snRNP-dependent mis-splicing in C9ORF72 patient brains. Together, our data indicate that DPR-mediated dysfunction of U2 snRNP could account for as much as ∼44% of the mis-spliced cassette exons in C9ORF72 patient brains.

  7. The Small Nuclear Genomes of Selaginella Are Associated with a Low Rate of Genome Size Evolution.

    Science.gov (United States)

    Baniaga, Anthony E; Arrigo, Nils; Barker, Michael S

    2016-06-03

    The haploid nuclear genome size (1C DNA) of vascular land plants varies over several orders of magnitude. Much of this observed diversity in genome size is due to the proliferation and deletion of transposable elements. To date, all vascular land plant lineages with extremely small nuclear genomes represent recently derived states, having ancestors with much larger genome sizes. The Selaginellaceae represent an ancient lineage with extremely small genomes. It is unclear how small nuclear genomes evolved in Selaginella We compared the rates of nuclear genome size evolution in Selaginella and major vascular plant clades in a comparative phylogenetic framework. For the analyses, we collected 29 new flow cytometry estimates of haploid genome size in Selaginella to augment publicly available data. Selaginella possess some of the smallest known haploid nuclear genome sizes, as well as the lowest rate of genome size evolution observed across all vascular land plants included in our analyses. Additionally, our analyses provide strong support for a history of haploid nuclear genome size stasis in Selaginella Our results indicate that Selaginella, similar to other early diverging lineages of vascular land plants, has relatively low rates of genome size evolution. Further, our analyses highlight that a rapid transition to a small genome size is only one route to an extremely small genome. © The Author 2016. Published by Oxford University Press on behalf of the Society for Molecular Biology and Evolution.

  8. Potential of small nuclear reactors for future clean and safe energy sources

    International Nuclear Information System (INIS)

    Sekimoto, H.

    1992-01-01

    To cope with the various kinds of energy demands expected in the 21st century, it is necessary to explore the potential of small nuclear reactors and to find a way of promoting their introduction to society. The main goal of current research activities is 'the constitution of the self-consistent nuclear energy system'. These activities can be understood by realizing that the nuclear community is facing a turning point for its survival in the 21st century. Self-consistency can be manifested by investigating and developing the potential advantages of the nuclear fission reaction and lessening the potential disadvantages. The contributions in this volume discuss concepts of small reactors, applications of small reactors, and consistency with conventional energy supply systems

  9. Fast reactors as a solution for future small-scale nuclear energy

    International Nuclear Information System (INIS)

    Kudryavtseva, A.; Danilenko, K.; Dorofeev, K.

    2013-01-01

    Small nuclear power plants can provide a future platform for decentralized energy supply providing better levels of accessibility, safety and environmental friendliness. The optimal solution for SMR deployment is fast reactors with inherent safety. To compete alternative solutions SMRs must exhibit some evident advantages in: safety, technology, and economic. Small modular reactors with lead-bismuth coolant (SVBR-100) under development in Russia can be a prospective solution for future small and decentralized energy

  10. The Perspective of Small and Medium Size Nuclear Power Reactors in the Brazilian Isolated Electricity Grids

    International Nuclear Information System (INIS)

    Moutinho dos Santos, E.

    1998-01-01

    As a consequence of the international crisis that has shaken the nuclear industry almost all over the world during the late 1980s, new academic contributions, which could settle a new basis for the nuclear energy in Brazil, have been scarce. This paper aims to partially fulfill this gap. We discuss some perspectives for the nuclear option to regain some prominence in the Brazilian energy matrix. Recent developments in the nuclear industry, including advances in plant design, have been opening interesting markets for small and medium nuclear power reactors (SMNPRs). We access the suitability and feasibility of such new technology in the Brazilian isolated electricity grids. We conclude by saying that, although the difficulties are still huge, SMNPRs may be a good strategy for Brazil to revitalize its nuclear policy. (author)

  11. Small modulator reactors (SMRs) - the key to increased social acceptance of nuclear power?

    Energy Technology Data Exchange (ETDEWEB)

    Sam-Aggrey, H. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Small Modular Reactors (SMRs) have been touted as having the potential to spearhead a nuclear renaissance. Proponents of this view cite the relative advantages of SMRs over larger nuclear plants as reason for their optimism. Some of these merits include potential economies of mass production deriving from modular factory production, enhanced safety features, the ability to locate reactors in remote areas, and reduced requirements for technical workforces to install and maintain SMRs. Despite the optimism surrounding SMRs, nuclear power is still a contentious issue for many Canadians. The growth of nuclear power remains adversely affected by concerns over issues such as: the health and safety consequences of nuclear power generation, environmental impacts, proliferation of nuclear materials, terrorism, and radioactive waste disposal. Personal values, past nuclear accidents, and lack of trust in the industry are other factors influencing attitudes toward nuclear energy. Given that public support is pivotal to the growth of the nuclear power sector, the issues surrounding the social acceptance of SMRs should be given serious consideration. Drawing on previously published data, this paper analyses the purported qualities of SMRs with a view of determining whether these characteristics have the potential of changing public attitudes toward greater acceptance of nuclear power. (author)

  12. Small modulator reactors (SMRs) - the key to increased social acceptance of nuclear power?

    International Nuclear Information System (INIS)

    Sam-Aggrey, H.

    2014-01-01

    Small Modular Reactors (SMRs) have been touted as having the potential to spearhead a nuclear renaissance. Proponents of this view cite the relative advantages of SMRs over larger nuclear plants as reason for their optimism. Some of these merits include potential economies of mass production deriving from modular factory production, enhanced safety features, the ability to locate reactors in remote areas, and reduced requirements for technical workforces to install and maintain SMRs. Despite the optimism surrounding SMRs, nuclear power is still a contentious issue for many Canadians. The growth of nuclear power remains adversely affected by concerns over issues such as: the health and safety consequences of nuclear power generation, environmental impacts, proliferation of nuclear materials, terrorism, and radioactive waste disposal. Personal values, past nuclear accidents, and lack of trust in the industry are other factors influencing attitudes toward nuclear energy. Given that public support is pivotal to the growth of the nuclear power sector, the issues surrounding the social acceptance of SMRs should be given serious consideration. Drawing on previously published data, this paper analyses the purported qualities of SMRs with a view of determining whether these characteristics have the potential of changing public attitudes toward greater acceptance of nuclear power. (author)

  13. Concepts for Small-Scale Testing of Used Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Marschman, Steven Craig [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Philip Lon [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    This report documents a concept for a small-scale test involving between one and three Boiling Water Rector (BWR) high burnup (HBU) fuel assemblies. This test would be similar to the DOE funded High Burn-Up (HBU) Confirmatory Data Project to confirm the behavior of used high burn-up fuel under prototypic conditions, only on a smaller scale. The test concept proposed would collect data from fuel stored under prototypic dry storage conditions to mimic, as closely as possible, the conditions HBU UNF experiences during all stages of dry storage: loading, cask drying, inert gas backfilling, and transfer to an Independent Spent Fuel Storage Installation (ISFSI) for multi-year storage.

  14. Nuclear criticality safety calculational analysis for small-diameter containers

    International Nuclear Information System (INIS)

    LeTellier, M.S.; Smallwood, D.J.; Henkel, J.A.

    1995-11-01

    This report documents calculations performed to establish a technical basis for the nuclear criticality safety of favorable geometry containers, sometimes referred to as 5-inch containers, in use at the Portsmouth Gaseous Diffusion Plant. A list of containers currently used in the plant is shown in Table 1.0-1. These containers are currently used throughout the plant with no mass limits. The use of containers with geometries or material types other than those addressed in this evaluation must be bounded by this analysis or have an additional analysis performed. The following five basic container geometries were modeled and bound all container geometries in Table 1.0-1: (1) 4.32-inch-diameter by 50-inch-high polyethylene bottle; (2) 5.0-inch-diameter by 24-inch-high polyethylene bottle; (3) 5.25-inch-diameter by 24-inch-high steel can (open-quotes F-canclose quotes); (4) 5.25-inch-diameter by 15-inch-high steel can (open-quotes Z-canclose quotes); and (5) 5.0-inch-diameter by 9-inch-high polybottle (open-quotes CO-4close quotes). Each container type is evaluated using five basic reflection and interaction models that include single containers and multiple containers in normal and in credible abnormal conditions. The uranium materials evaluated are UO 2 F 2 +H 2 O and UF 4 +oil materials at 100% and 10% enrichments and U 3 O 8 , and H 2 O at 100% enrichment. The design basis safe criticality limit for the Portsmouth facility is k eff + 2σ < 0.95. The KENO study results may be used as the basis for evaluating general use of these containers in the plant

  15. Nonexistence in Thomas-Fermi-Dirac-von Weizsäcker Theory with Small Nuclear Charges

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Phan Thành, E-mail: pnam@ist.ac.at [Institute of Science and Technology Austria (Austria); Den Bosch, Hanne Van, E-mail: hannevdbosch@fis.puc.cl [Pontificia Universidad Católica de Chile, Instituto de Física (Chile)

    2017-06-15

    We study the ionization problem in the Thomas-Fermi-Dirac-von Weizsäcker theory for atoms and molecules. We prove the nonexistence of minimizers for the energy functional when the number of electrons is large and the total nuclear charge is small. This nonexistence result also applies to external potentials decaying faster than the Coulomb potential. In the case of arbitrary nuclear charges, we obtain the nonexistence of stable minimizers and radial minimizers.

  16. Dynamics of the nuclear one-body density: small amplitude regime

    International Nuclear Information System (INIS)

    Nemes, M.C.; Toledo Piza, A.F.R. de.

    1984-01-01

    A microscopic treatment for the small amplitude limite of the equations of motion for the nuclear one-body density is presented. These were derived previously by means of projection techniques, and allow for the explicit separation of mean-field and collision effects which result from the dynamics of many-body correlations. The form of the nuclear response in the presence of collision effects is derived. An illustrative application to a soluble model is discussed. (Author) [pt

  17. Machining of the nuclear tube sheet with small hole diameter

    International Nuclear Information System (INIS)

    Lin Lifeng

    2010-01-01

    Regarding the tube sheet for the heat exchanger of Qinshan Phase II extension project, its material is 00Cr19Ni10 forgings, the tube sheet thickness is 125 mm, requiring 178-φ10.35 0 +0.05 hole, the tube array shall take the shape of equilateral triangle, the center distance is 15 mm, and the tube hole roughness is Ra 3.2. The guide sleeve shall be adopted for positioning prior to machining of the high precision small hole of the thick tube sheet, and the gun drill and BTA drill shall be adopted for testing, finally BTA drilling with internal chip removal shall be adopted, this method shall overcome the disadvantage factor of BTA drilling and shall be the new approach for drilling. The diameter of BTA drill is φ10.34 mm. The machined hole diameter shall be φ10.375-φ10.355 mm. The ellipticity of the tube hole shall be less than 0.01 mm, the pipe bridge dimension shall be 4.6 mm, conforming to the requirement of the drawing. The paper presents the precautions during machining so as to provide the reference for the similar pipe hole machining in the future. (author)

  18. Proceedings of the International Conference: Nuclear option in countries with small and medium electricity grid

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    The conference of Croatian Nuclear Society ``Nuclear option in countries with small and medium electricity grid`` is based on experience from last conference of Croatian Nuclear Society in Opatija and on the same philosophy of serving the needs of small or medium present or future user countries. Session topics reflect some current emphasis, such as accommodation of Kyoto restriction on CO{sub 2} emission, or liability and insurance for nuclear damage. In order to achieve best safety and operational standards these countries with limited human and material resources must put greater emphasis on their rational and efficient use. Consequently the world wide developments on innovative reactors` systems and improved concepts for fuel utilisation and waste disposal are substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and cooperation amongst that group of countries would be of great value. As in the future of nuclear energy there will be many more countries with only small or medium nuclear systems, collecting specific experience and cooperation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships. Here is presented nine sessions: 1. Energy Options in Countries with Small and Medium Grids 2. Reactors for Small and Medium Electricity Grids 3. Operation and Maintenance Experience 4. Deterministic Safety Analysis 5. Probabilistic Safety Analysis 6. Radioactive Waste Management and Decommissioning 7. Public Relations 8. Emergency Preparedness 9. Liability and Insurance for Nuclear Damage

  19. Proceedings of the International Conference: Nuclear option in countries with small and medium electricity grid

    International Nuclear Information System (INIS)

    1998-01-01

    The conference of Croatian Nuclear Society ''Nuclear option in countries with small and medium electricity grid'' is based on experience from last conference of Croatian Nuclear Society in Opatija and on the same philosophy of serving the needs of small or medium present or future user countries. Session topics reflect some current emphasis, such as accommodation of Kyoto restriction on CO 2 emission, or liability and insurance for nuclear damage. In order to achieve best safety and operational standards these countries with limited human and material resources must put greater emphasis on their rational and efficient use. Consequently the world wide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and cooperation amongst that group of countries would be of great value. As in the future of nuclear energy there will be many more countries with only small or medium nuclear systems, collecting specific experience and cooperation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships. Here is presented nine sessions: 1. Energy Options in Countries with Small and Medium Grids 2. Reactors for Small and Medium Electricity Grids 3. Operation and Maintenance Experience 4. Deterministic Safety Analysis 5. Probabilistic Safety Analysis 6. Radioactive Waste Management and Decommissioning 7. Public Relations 8. Emergency Preparedness 9. Liability and Insurance for Nuclear Damage

  20. Examining the intersection between splicing, nuclear export and small RNA pathways.

    Science.gov (United States)

    Nabih, Amena; Sobotka, Julia A; Wu, Monica Z; Wedeles, Christopher J; Claycomb, Julie M

    2017-11-01

    Nuclear Argonaute/small RNA pathways in a variety of eukaryotic species are generally known to regulate gene expression via chromatin modulation and transcription attenuation in a process known as transcriptional gene silencing (TGS). However, recent data, including genetic screens, phylogenetic profiling, and molecular mechanistic studies, also point to a novel and emerging intersection between the splicing and nuclear export machinery with nuclear Argonaute/small RNA pathways in many organisms. In this review, we summarize the field's current understanding regarding the relationship between splicing, export and small RNA pathways, and consider the biological implications for coordinated regulation of transcripts by these pathways. We also address the importance and available approaches for understanding the RNA regulatory logic generated by the intersection of these particular pathways in the context of synthetic biology. The interactions between various eukaryotic RNA regulatory pathways, particularly splicing, nuclear export and small RNA pathways provide a type of combinatorial code that informs the identity ("self" versus "non-self") and dictates the fate of each transcript in a cell. Although the molecular mechanisms for how splicing and nuclear export impact small RNA pathways are not entirely clear at this early stage, the links between these pathways are widespread across eukaryotic phyla. The link between splicing, nuclear export, and small RNA pathways is emerging and establishes a new frontier for understanding the combinatorial logic of gene regulation across species that could someday be harnessed for therapeutic, biotechnology and agricultural applications. This article is part of a Special Issue entitled "Biochemistry of Synthetic Biology - Recent Developments" Guest Editor: Dr. Ilka Heinemann and Dr. Patrick O'Donoghue. Copyright © 2017 Elsevier B.V. All rights reserved.

  1. Management of Small Quantity of Nuclear Material at Locations Outside Facilities in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Sik; Kim, Ki Hyun [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Small quantity of nuclear material (SQNM) is prescribed to be less than specified minimum quantities of nuclear material in a facility. SQNM is used at the locations called locations outside facilities (LOFs). LOFs are used to control the locations and installations that store nuclear materials under one effective Kg, respectively. Holders of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or neither report them to the System of Accounting for and Control of nuclear material (SSAC) under specified quantities according to the Atomic Safety Law. Well defined safeguards law is fundamental to the effective control of nuclear material, facilities and nuclear related activities. In the current nuclear safety legislation, there are some exceptive clauses. Users of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or not report them to the national authority below specified amount.

  2. Management of Small Quantity of Nuclear Material at Locations Outside Facilities in Korea

    International Nuclear Information System (INIS)

    Park, Seung Sik; Kim, Ki Hyun

    2016-01-01

    Small quantity of nuclear material (SQNM) is prescribed to be less than specified minimum quantities of nuclear material in a facility. SQNM is used at the locations called locations outside facilities (LOFs). LOFs are used to control the locations and installations that store nuclear materials under one effective Kg, respectively. Holders of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or neither report them to the System of Accounting for and Control of nuclear material (SSAC) under specified quantities according to the Atomic Safety Law. Well defined safeguards law is fundamental to the effective control of nuclear material, facilities and nuclear related activities. In the current nuclear safety legislation, there are some exceptive clauses. Users of SQNM don't need to require a license for use or possession of Uranium or Thorium exclusively for non-nuclear activities, or not report them to the national authority below specified amount

  3. Development of public acceptance and market success with very small nuclear power reactors (VSR)

    International Nuclear Information System (INIS)

    Lang, P

    2008-01-01

    This paper presents a case for public acceptance of very small nuclear reactors (VSR) as a socially welcomed, locally produced source of energy. It is argued that the subconscious associations and emotional responses that the public makes with size and appearance will often outweigh technical or economic advantages as the determining factor in their ultimate acceptance or rejection of a new power plant. The unique technical features of VSR effectively refute the three most commonly cited reasons for opposing nuclear power: cost, safety, and waste management. VSR also address the demands of environmentalists for small-scale, clean distributed energy production. (author)

  4. U2 laulusõnade tundmine lennutab Hawaile

    Index Scriptorium Estoniae

    2006-01-01

    Iiri bänd U2 algatas oma uue albumi "U2 18 Singles väljatuleku puhul internetis võistluse "Hunt The Lyric", kus fännidel on võimalus võita reis Hawaile (reisi paketis ka U2 "Vertigo" tuuri kontsert 9. dets.)

  5. Proceedings of the International conference: Nuclear option in countries with small and medium electricity grid

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The conference of Croatian Nuclear Society `Nuclear option in countries with small and medium electricity grid` was organized with intention to focus on and discuss the specific needs and interests of the countries with small or medium nuclear systems. In order to achieve best safety and operational standards these countries with limited human and material resources must put greater emphasis on their rational and efficient use. For these countries the world wide developments on innovative reactors` systems and improved concepts for fuel utilisation and waste disposal are substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and cooperation amongst that group of countries would be of great value. As in the future of nuclear energy there will be many more countries with only small or medium nuclear systems, collecting specific experience and cooperation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships.

  6. Proceedings of the International conference: Nuclear option in countries with small and medium electricity grid

    International Nuclear Information System (INIS)

    1996-01-01

    The conference of Croatian Nuclear Society 'Nuclear option in countries with small and medium electricity grid' was organized with intention to focus on and discuss the specific needs and interests of the countries with small or medium nuclear systems. In order to achieve best safety and operational standards these countries with limited human and material resources must put greater emphasis on their rational and efficient use. For these countries the world wide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and cooperation amongst that group of countries would be of great value. As in the future of nuclear energy there will be many more countries with only small or medium nuclear systems, collecting specific experience and cooperation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships

  7. Path integral for coherent states of the dynamical U2 group and U2/1 supergroup

    International Nuclear Information System (INIS)

    Kochetov, E.A.

    1992-01-01

    A part-integral formulation in the representation of coherent states for the unitary U 2 group and U 2/1 supergroup is introduced. U 2 and U 2/1 path integrals are shown to be defined on the coset spaces U 2 /U 1 xU 1 and U 2/1 /U 1/1 xU 1 , respectively. These coset appears as curved classical phase spaces. Partition functions are expressed as path integrals over these spaces. In the case when U 2 and U 2/1 are the dynamical groups, the corresponding path integrals are evaluated with the help of linear fractional transformations that appear as the group (supergroup) action in the coset space (superspace). Possible applications for quantum models are discussed. 9 refs

  8. Control and Management of Small Quantity Nuclear Material (SQNM) on Safeguards

    International Nuclear Information System (INIS)

    Park, Jae Hwan; Shin, Byung Woo; Park, Jae Beom

    2009-01-01

    Small Quantity Nuclear Material (SQNM) is defined as the nuclear material that is below the amount approved in atomic energy act. SQNM generally lists depleted uranium (DU) used as a catalyst or shielding material in exposure devices in industries. The SQNM users have a duty to report information on possessing and using SQNM regularly to the government. All nuclear materials must be included in IAEA reporting lists according to safeguards agreement and additional protocol regardless of amount. However, it is difficult to investigate the status of nuclear material possessed in industries because SQNM is excepted regulation item list in atomic energy act. Most SQNM user industries are small companies so they have some problems like the loss of nuclear material after bankruptcy. Even though the damage of radiation leakage is very low, loss or careless management of nuclear material causes confusion. Thus, developing a control and management system for SQNM is essential. This paper discusses the present condition and prospect of control and management SQNM in Korea

  9. Order in large and chaos in small components of nuclear wave functions

    International Nuclear Information System (INIS)

    Soloviev, V.G.

    1992-06-01

    An investigation of the order and chaos of the nuclear excited states has shown that there is order in the large and chaos in the small quasiparticle or phonon components of the nuclear wave functions. The order-to-chaos transition is treated as a transition from the large to the small components of the nuclear wave function. The analysis has shown that relatively large many-quasiparticle components of the wave function at an excitation energy (4-8)MeV may exist. The large many-quasiparticle components of the wave functions of the neutron resonances are responsible for enhanced E1-, M1- and E2-transition probabilities from neutron resonance to levels lying (1-2)MeV below them. (author)

  10. Analysis of near optimum design for small and medium size nuclear power plants

    International Nuclear Information System (INIS)

    Ahmed, A.A.

    1977-01-01

    Market surveys in recent years have shown that a significant market would exist among the developing nations of the world for nuclear power plants that would be classified as small to medium sized, provided that these small plants could produce electricity at a unit price comparable to that of equivalent sized fossil fired plants. Nuclear plants in the range of 100 MWe to 500 MWe would fit more effectively into the relatively smaller grids of most developing nations than would the 900 MWe to 1300 MWe units now being constructed in the large industrial nations. Worldwide re-evaluation of the worth of fossil fuels has prompted a re-examination of the competitive position of small to medium sized nuclear generating units compared to comparable fossil fired units, especially in the context of units specifically optimized for the size range of interest, rather than of designs that are simply scaled down versions of the currently available larger units. Since the absolute cost of electricity is more sensitive to external factors such as cost of money, national inflation rate and time required for licensing and construction than to details of design or perhaps even to choice of fuels, and since the cost of electricity generated in small to medium sized fossil fired units is periodically compared to that of scaled down versions of conventional large nuclear units, the point of view taken here is one of comparing the relative generating costs of smaller nuclear units of optimum design with the corresponding costs of scaled down versions of current large nuclear generating units

  11. Bridging the energy gap through small and medium sized nuclear reactors in India

    International Nuclear Information System (INIS)

    Srivastava, R.

    1987-01-01

    India is the only country in the world which is employing small sized nuclear reactors for its nuclear power programme. It has now embarked on a programme of augmenting the contribution of the nuclear power by way of employing both medium and small sized nuclear reactors in the next 15 years. This paper discusses the Indian experience and its efforts for industrial mobilisation for rapidly constructing 235/500 MWe nuclear reactor units in a period of about 8 to 9 years. The current energy situation in India and this context the near term role of nuclear power for supplementing the existing sources of commercial energy have been evaluated. Nuclear power has reached such a stage of maturity whereby it has now become a commercially viable source of electricity and it could be utilised on large scale to bridge the energy gap. At present six reactor units of 210/235 MWe capacity are in operation and eight more are in different stages of construction. While we are continuing with the construction of 235 MWe units, a programme of being pursued to construct 550 MWe capacity reactor units from midnineties onwards. This has become possible with the strengthening of regional electricity grids and simultaneous efforts undertaken for augmentation of fuel supply, heavy water production and industrial infrastructure. For a developing country like India, implementation of a sizable nuclear power programme has posed certain special challenges as major inputs are required to be made available with indigeneous efforts. This paper discusses such challenges and presents the ways and means adopted to surmount them. Other developing countries with conditions comparable to those in India could benefit from Indian experience in this regard. This paper also proposes India's willingness to cooperate with other countries for exchange of information and assistance in terms of technical knowhow. (author)

  12. New to nuclear countries: considerations for adoption of Small Modular Reactors - a guide to future adopters

    Energy Technology Data Exchange (ETDEWEB)

    Paterson, A.; Ho, M.; Storr, G., E-mail: adi.paterson@ansto.gov.au [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    2014-07-01

    Small Modular Reactors (SMRs) are under development in a number of countries. This class of reactors, with enhanced safety and security inherent to their design, can potentially offer advantages to countries adopting nuclear power for the first time. This includes countries considering expanding existing nuclear power capability using the benefits of Generation III+ and Generation IV technological advances. For example, public perceptions and engagement in relation to nuclear safety and security are important and need to be addressed. The regulation of nuclear power plants and the management of the nuclear fuel cycle are also important considerations. For some countries, an industrial strategy linked to participation in the nuclear fuel cycle could be a priority, associated with the development of a sophisticated workforce to support the design, construction, commissioning and operation of a fleet of reactors. Some countries will choose to be early adopters of SMRs. Others may prefer to wait until the technologies are more established. This paper will focus on the potential appeal of different SMR designs in relation to the considerations that new to nuclear countries must address and how this underpins effective decision making. (author)

  13. Recruitment of phosphorylated small heat shock protein Hsp27 to nuclear speckles without stress

    International Nuclear Information System (INIS)

    Bryantsev, A.L.; Chechenova, M.B.; Shelden, E.A.

    2007-01-01

    During stress, the mammalian small heat shock protein Hsp27 enters cell nuclei. The present study examines the requirements for entry of Hsp27 into nuclei of normal rat kidney (NRK) renal epithelial cells, and for its interactions with specific nuclear structures. We find that phosphorylation of Hsp27 is necessary for the efficient entry into nuclei during heat shock but not sufficient for efficient nuclear entry under control conditions. We further report that Hsp27 is recruited to an RNAse sensitive fraction of SC35 positive nuclear speckles, but not other intranuclear structures, in response to heat shock. Intriguingly, Hsp27 phosphorylation, in the absence of stress, is sufficient for recruitment to speckles found in post-anaphase stage mitotic cells. Additionally, pseudophosphorylated Hsp27 fused to a nuclear localization peptide (NLS) is recruited to nuclear speckles in unstressed interphase cells, but wildtype and nonphosphorylatable Hsp27 NLS fusion proteins are not. The expression of NLS-Hsp27 mutants does not enhance colony forming abilities of cells subjected to severe heat shock, but does regulate nuclear speckle morphology. These data demonstrate that phosphorylation, but not stress, mediates Hsp27 recruitment to an RNAse soluble fraction of nuclear speckles and support a site-specific role for Hsp27 within the nucleus

  14. Raising awareness about protection and control of nuclear materials held by 'small-scale holders'

    International Nuclear Information System (INIS)

    Ladsous, D.; Coulie, E.; Giorgio, M.

    2013-01-01

    In France, the activities carried out by the 'small-scale holders' of nuclear materials are organized by a specific regulatory system which defines in a detailed way their obligations and the means of control of the government. The first part of the article presents the legal framework relating to the use of nuclear materials by small-scale holders in civilian fields. The importance of the declaration of the nuclear material inventory is clearly emphasized and must be prepared and transmitted to the Institute for Radiological Protection and Nuclear Safety (IRSN) every year. The second part describes how this declaration is used to provide basic information for the competent Ministry and the inspectors to check the correct application of the regulatory requirements relating to physical protection and to the control of nuclear materials. Finally, the last part presents the on-site inspections carried out by sworn and accredited inspectors under the authority of the competent Authority, which provide an overall picture and allow an evaluation of the risks of theft, loss or diversion of these materials. (authors)

  15. Waste from decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    Massaut, V.

    2001-01-01

    Full text: Small nuclear facilities were often built for research or pilot purposes. It includes the research reactors of various types and various aims (physics research, nuclear research, nuclear weapons development, materials testing reactor, isotope production, pilot plant, etc.) as well as laboratories, hot cells and accelerators used for a broad spectrum of research or production purposes. These installations are characterized not only by their size (reduced footprint) but also, and even mostly, by the very diversified type of materials, products and isotopes handled within these facilities. This large variety can sometimes enhance the difficulties encountered for the dismantling of such facilities. The presence of materials like beryllium, graphite, lead, PCBs, sodium, sometimes in relatively large quantities, are also challenges to be faced by the dismantlers of such facilities, because these types of waste are either toxic or no solutions are readily available for their conditioning or long term disposal. The paper will review what is currently done in different small nuclear facilities, and what are the remaining problems and challenges for future dismantling and waste management. The question of whether Research and Development for waste handling methods and processes is needed is still pending. Even for the dismantling operation itself, important improvements can be brought in the fields of characterization, decontamination, remote handling, etc. by further developments and innovative systems. The way of funding such facilities decommissioning will be reviewed as well as the very difficult cost estimation for such facilities, often one-of-a-kind. The aspects of radioprotection optimization (ALARA principle) and classical operators safety will also be highlighted, as well as the potential solutions or improvements. In fact, small nuclear facilities encounter often, when dismantling, the same problems as the large nuclear power plants, but have in

  16. Atomistic Simulations of Small-scale Materials Tests of Nuclear Materials

    International Nuclear Information System (INIS)

    Shin, Chan Sun; Jin, Hyung Ha; Kwon, Jun Hyun

    2012-01-01

    Degradation of materials properties under neutron irradiation is one of the key issues affecting the lifetime of nuclear reactors. Evaluating the property changes of materials due to irradiations and understanding the role of microstructural changes on mechanical properties are required for ensuring reliable and safe operation of a nuclear reactor. However, high dose of neuron irradiation capabilities are rather limited and it is difficult to discriminate various factors affecting the property changes of materials. Ion beam irradiation can be used to investigate radiation damage to materials in a controlled way, but has the main limitation of small penetration depth in the length scale of micro meters. Over the past decade, the interest in the investigations of size-dependent mechanical properties has promoted the development of various small-scale materials tests, e.g. nanoindentation and micro/nano-pillar compression tests. Small-scale materials tests can address the issue of the limitation of small penetration depth of ion irradiation. In this paper, we present small-scale materials tests (experiments and simulation) which are applied to study the size and irradiation effects on mechanical properties. We have performed molecular dynamics simulations of nanoindentation and nanopillar compression tests. These atomistic simulations are expected to significantly contribute to the investigation of the fundamental deformation mechanism of small scale irradiated materials

  17. The creation of a development fund for small and intermediate enterprises in the nuclear sector

    International Nuclear Information System (INIS)

    Anon.

    2014-01-01

    The French public bank of investment (Bpi france) has announced its new strategy of investment in small and intermediate companies in the nuclear industry in order to help them to develop and to export. Long-term Investments from 1 to 13 million euros will help to reinforce the innovation capability and competitiveness of enterprises, the purpose is to stimulate a global trend towards the emergence of bigger size enterprises. In France, nuclear industry employs 220.000 people dispatched in more than 2500 enterprises. (A.C.)

  18. Wishful thinking and real problems: Small modular reactors, planning constraints, and nuclear power in Jordan

    International Nuclear Information System (INIS)

    Ramana, M.V.; Ahmad, Ali

    2016-01-01

    Jordan plans to import two conventional gigawatt scale nuclear reactors from Russia that are expensive and too large for Jordan's current electricity grid. Jordan efforts to establish nuclear power might become easier in some ways if the country were to construct Small Modular Reactors, which might be better suited to Jordan's financial capabilities and its smaller electrical grid capacity. But, the SMR option raises new problems, including locating sites for multiple reactors, finding water to cool these reactors, and the higher cost of electricity generation. Jordan's decision has important implications for its energy planning as well as for the market for SMRs. - Highlights: •Jordan is planning to purchase two large reactors from Russia. •Large reactors would be inappropriate to Jordan's small electricity grid. •Small modular reactors would be more appropriate to Jordan's grid, but have problems. •The market for small modular reactors will be smaller than often projected. •Jordan should consider the financial impact of building a large nuclear reactor.

  19. The Westinghouse AP600 an advanced nuclear option for small or medium electricity grids

    International Nuclear Information System (INIS)

    Bruschi, H. J.; Novak, V.

    1996-01-01

    During the early days of commercial nuclear power, many countries looking to add nuclear power to their energy mix required large plants to meet the energy needs of rapidly growing populations and large industrial complexes. The majority of plants worldwide are in the range of 100 megawatts and beyond. During the 1970s, it became apparent that a smaller nuclear plants would appeal to utilities looking to add additional power capacity to existing grids, or to utilities in smaller countries which were seeking efficient, new nuclear generation capacity for the first time. For instance, the Westinghouse-designed 600 megawatt Krsko plant in Slovenia began operation in 1980, providing electricity to inhabitants of relatively small, yet industrial populations of Slovenia and Croatia. This plant design incorporated the best, proven technology available at that time, based on 20 years of Westinghouse PWR pioneering experience. Beginning in the early 1980s, Westinghouse began to build further upon that experience - in part through the advanced light water reactor programs established by the Electric Power Research institute (EPRI) and the U.S. Department of Energy (DOE) - to design a simplified, advanced nuclear reactor in the 600 megawatt range. Originally, Westinghouse's development of its AP600 (advanced, passive 600-megawatt) plants was geared towards the needs of U.S. utilities which specified smaller, simplified nuclear options for the decades ahead. It soon became evident that the small and medium sized electricity grids of international markets could benefit from this new reactor. From the earliest days of Westinghouse's AP600 development, the corporation invited members of the international nuclear community to take part in the design, development and testing of the AP600 - with the goal of designing a reactor that would meet the diverse needs of an international industry composed of countries with similar, yet different, concerns. (author)

  20. Affordable Development and Demonstration of a Small Nuclear Thermal Rocket (NTR) Engine and Stage: How Small Is Big Enough?

    Science.gov (United States)

    Borowski, Stanley K.; Sefcik, Robert J.; Fittje, James E.; McCurdy, David R.; Qualls, Arthur L.; Schnitzler, Bruce G.; Werner, James E.; Weitzberg, Abraham; Joyner, Claude R.

    2016-01-01

    The Nuclear Thermal Rocket (NTR) derives its energy from fission of uranium-235 atoms contained within fuel elements that comprise the engine's reactor core. It generates high thrust and has a specific impulse potential of approximately 900 specific impulse - a 100 percent increase over today's best chemical rockets. The Nuclear Thermal Propulsion (NTP) project, funded by NASA's Advanced Exploration Systems (AES) program, includes five key task activities: (1) Recapture, demonstration, and validation of heritage graphite composite (GC) fuel (selected as the Lead Fuel option); (2) Engine Conceptual Design; (3) Operating Requirements Definition; (4) Identification of Affordable Options for Ground Testing; and (5) Formulation of an Affordable Development Strategy. During fiscal year (FY) 2014, a preliminary Design Development Test and Evaluation (DDT&E) plan and schedule for NTP development was outlined by the NASA Glenn Research Center (GRC), Department of Energy (DOE) and industry that involved significant system-level demonstration projects that included Ground Technology Demonstration (GTD) tests at the Nevada National Security Site (NNSS), followed by a Flight Technology Demonstration (FTD) mission. To reduce cost for the GTD tests and FTD mission, small NTR engines, in either the 7.5 or 16.5 kilopound-force thrust class, were considered. Both engine options used GC fuel and a common fuel element (FE) design. The small approximately 7.5 kilopound-force criticality-limited engine produces approximately157 thermal megawatts and its core is configured with parallel rows of hexagonal-shaped FEs and tie tubes (TTs) with a FE to TT ratio of approximately 1:1. The larger approximately 16.5 kilopound-force Small Nuclear Rocket Engine (SNRE), developed by Los Alamos National Laboratory (LANL) at the end of the Rover program, produces approximately 367 thermal megawatts and has a FE to TT ratio of approximately 2:1. Although both engines use a common 35-inch (approximately

  1. Nuclear Power as an Option in Electrical Generation Planning for Small Economy and Electricity Grid

    International Nuclear Information System (INIS)

    Tomsic, Z.

    2012-01-01

    Implementing a NPP in countries with relatively small total GDP (small economy) and usually with small electricity grid face two major problems and constrains: the ability to obtain the considerable financial resources required on reasonable terms and to connect large NPP to small electricity grid. Nuclear generation financing in developing countries involves complex issues that need to be fully understood and dealt with by all the parties involved. The main topics covered by paper will be the: special circumstances related to the financing of NPP, costs and economic feasibility of NPP, conventional approaches for financing power generation projects in developing countries, alternative approaches for mobilizing financial resources. The safe and economic operation of a nuclear power plant (NPP) requires the plant to be connected to an electrical grid system that has adequate capacity for exporting the power from the NPP, and for providing a reliable electrical supply to the NPP for safe start-up, operation and normal or emergency shut-down of the plant. Connection of any large new power plant to the electrical grid system in a country may require significant modification and strengthening of the grid system, but for NPPs there may be added requirements to the structure of the grid system and the way it is controlled and maintained to ensure adequate reliability. Paper shows the comparative assesment of differrent base load technologies as an option in electrical generation planning for small economy and electricity grid.(author).

  2. Energy dependence of the Coulomb-nuclear interference at small momentum transfers

    International Nuclear Information System (INIS)

    Selyugin, O.V.

    1997-01-01

    The analyzing power of the elastic proton-proton scattering at small momentum transfers and the effect of the Coulomb-nuclear interference are examined on the basis of the available experimental data at p L from 6 up to 200 GeV/c taking account of a phenomenological analysis at p L =6 GeV/c and of the dynamic high energy spin model. The structure of the spin-dependent elastic scattering amplitude at small momentum transfers is obtained. The predictions for the analyzing power at RHIC energies are made

  3. Nuclear piping and pipe support design and operability relating to loadings and small bore piping

    International Nuclear Information System (INIS)

    Stout, D.H.; Tubbs, J.M.; Callaway, W.O.; Tang, H.T.; Van Duyne, D.A.

    1994-01-01

    The present nuclear piping system design practices for loadings, multiple support design and small bore piping evaluation are overly conservative. The paper discusses the results developed for realistic definitions of loadings and loading combinations with methodology for combining loads under various conditions for supports and multiple support design. The paper also discusses a simplified method developed for performing deadweight and thermal evaluations of small bore piping systems. Although the simplified method is oriented towards the qualification of piping in older plants, this approach is applicable to plants designed to any edition of the ASME Section III or B31.1 piping codes

  4. The Planning of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeborg, T U; Haeffner, E; Hultgren, Aa

    1963-10-15

    A shielded volume (42 m{sup 3}) in the hot laboratory at Kjeller, Norway, has been used for the installation of a small pilot plant intended for studies on nuclear fuel reprocessing. During the first period of operation (1963) a plutonium separation method (the Silex process) developed at AB Atomenergi will be studied. This document is a description of the project during the stage of technical planning and chemical process development.

  5. Percolation and nucleation approaches to nuclear fragmentation: criticality in very small systems

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, A.J. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Inst. de Fisica; Chung, K.C.

    1994-12-01

    Different criteria for criticality in very small systems are discussed in the context of percolation and nucleation approaches to nuclear fragmentation. It is shown that the probability threshold in percolation and interaction radius threshold in nucleation are very strongly dependent upon the adopted criterion. By using Monte Carlo method, similarities and dissimilarities between nucleation and percolation pictures are also pointed out. (author). 17 refs, 5 figs, 2 tabs.

  6. Percolation and nucleation approaches to nuclear fragmentation: criticality in very small systems

    International Nuclear Information System (INIS)

    Santiago, A.J.; Chung, K.C.

    1994-12-01

    Different criteria for criticality in very small systems are discussed in the context of percolation and nucleation approaches to nuclear fragmentation. It is shown that the probability threshold in percolation and interaction radius threshold in nucleation are very strongly dependent upon the adopted criterion. By using Monte Carlo method, similarities and dissimilarities between nucleation and percolation pictures are also pointed out. (author). 17 refs, 5 figs, 2 tabs

  7. Planning and management for the decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    Many research reactors and other small nuclear facilities throughout the world date from the original nuclear research programmes in the Member States. Consequently, a large number of these plants have either been retired from service or will soon reach the end of their useful lives and are likely to become significant decommissioning tasks for those Members States. In recognition of this situation and in response to considerable interest shown by Member States, the IAEA has produced this document on planning and management for the decommissioning of research reactors and other small nuclear facilities. While not directed specifically at large nuclear installations, it is likely that much of the information presented will also be of interest to those involved in the decommissioning of such facilities. Current views, information and experience on the planning and management of decommissioning projects in Member States were collected and assessed during a Technical Committee Meeting held by the IAEA in Vienna from 29 July to 2 August 1991. It was attended by 22 participants from 14 Member States and one international organization. 28 refs, 2 figs, 3 tabs

  8. Local U(2,2) Symmetry in Relativistic Quantum Mechanics

    OpenAIRE

    Finster, Felix

    1997-01-01

    Local gauge freedom in relativistic quantum mechanics is derived from a measurement principle for space and time. For the Dirac equation, one obtains local U(2,2) gauge transformations acting on the spinor index of the wave functions. This local U(2,2) symmetry allows a unified description of electrodynamics and general relativity as a classical gauge theory.

  9. Local U(2,2) symmetry in relativistic quantum mechanics

    Science.gov (United States)

    Finster, Felix

    1998-12-01

    Local gauge freedom in relativistic quantum mechanics is derived from a measurement principle for space and time. For the Dirac equation, one obtains local U(2,2) gauge transformations acting on the spinor index of the wave functions. This local U(2,2) symmetry allows a unified description of electrodynamics and general relativity as a classical gauge theory.

  10. Small Reactor Designs Suitable for Direct Nuclear Thermal Propulsion: Interim Report

    International Nuclear Information System (INIS)

    Schnitzler, Bruce G.

    2012-01-01

    open loop systems for direct nuclear thermal propulsion. Although a number of fast spectrum reactor and engine designs suitable for direct nuclear thermal propulsion were proposed and designed, none were built. This report summarizes status results of evaluations of small nuclear reactor designs suitable for direct nuclear thermal propulsion.

  11. Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

    Energy Technology Data Exchange (ETDEWEB)

    OHara J. M.; Higgins, J.; DAgostino, A.

    2012-01-17

    The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

  12. Assessment of the impact of nuclear power plant construction and operation on small regions

    International Nuclear Information System (INIS)

    Johnson, M.H. Jr.

    1977-01-01

    This study addresses the problem of the comprehensive, quantitative evaluation of the environmental, economic, and social impacts of the construction and operation of nuclear power plant on a given region. A theoretical model of the regional impacts is constructed employing input-output methods that are extended to include ecologic as well as economic effects. Thus, the regional model explicitly incorporates environmental feedback as a consequence of economic activity. The model is then employed to estimate the impact of the construction and operation of a nuclear power facility on a small region in South Carolina. Measures of economic and environmental effects include estimates of changes in output, income, employment, local government revenue and expenditure, external costs of environmental decay, pollution loads, and common-property resource usage. Results indicate that, in the South Carolina case study, significant gains in social welfare accrued to the region due to the construction and operation of the nuclear power facility. Further, the theoretical method developed herein provides a comprehensive method of objectively assessing various types of impacts on a region as small as several contiguous counties or even a single county

  13. A small floating seawater desalination plant using a nuclear heating reactor coupled with the MED process

    International Nuclear Information System (INIS)

    Dong Duo; Wu Shaorong; Zhang Dafang; Wu Zongxin

    1997-01-01

    A small floating seawater desalination plant using a nuclear heating reactor coupled with a multi-effect distillation (MED) process was designed by the Institute of Nuclear Energy Technology, Tsinghua University of China. It was intended to supply potable water to remove coastal areas or islands where both fresh water and energy are severely lacking, and also to serve as a demonstration and training facility. The design of a small floating plant coupled two proven technologies in the cogeneration mode: a nuclear heating reactor (NHR-10), with inherent, passive safety features based on NHR-5 experience, and a low temperature MED process. The secondary loop was designed as a safety barrier between the primary loop and the steam loop. With a 10 MW(th) heating reactor, the floating plant could provide 4,000 m 3 /d of potable water and 750 kW of electricity. The design concept and parameters, safety features, coupling scheme and floating plant layout are presented in the paper. (author). 3 refs, 4 figs, 3 tabs

  14. Proliferation attractiveness of nuclear material in a small modular pressure tube SCWR

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, M.; Pencer, J., E-mail: mcdonamh@aecl.ca, E-mail: pencerj@aecl.ca [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2013-07-01

    The SuperSafe© Reactor (SSR), has been recently proposed as a small modular version of the Canadian supercritical water cooled reactor (SCWR). This reactor is a heavy water moderated, pressure tube reactor using supercritical light water as coolant. The current SSR design is to generate 300 MWe taking advantage of the expected high thermal efficiency (assumed 45%). As one of the reactor types being considered by the Generation-IV International Forum, it is expected that this SCWR design will feature enhanced proliferation resistance over current generation technologies. Proliferation resistance assessments are wide-ranging, multidisciplinary efforts that are typically performed at a number of levels, from a state level down to a specific facility level. One small, but particularly important, sub-assessment is that of nuclear material attractiveness, that is, assessing the quality of nuclear materials throughout the fuel cycle for use in making a nuclear explosive device. The attractiveness of materials for three different SSR fuel options is examined in this work. (author)

  15. Supply of appropriate nuclear technology for the developing world: small power reactors for electricity generation

    International Nuclear Information System (INIS)

    Heising-Goodman, C.D.

    1981-01-01

    This paper reviews the supply of small nuclear power plants (200 to 500 MWe electrical generating capacity) available on today's market, including the pre-fabricated designs of the United Kingdom's Rolls Royce Ltd and the French Alsthom-Atlantique Company. Also, the Russian VVER-440 conventionally built light-water reactor design is reviewed, including information on the Soviet Union's plans for expansion of its reactor-building capacity. A section of the paper also explores the characteristics of LDC electricity grids, reviewing methods available for incorporating larger plants into smaller grids as the Israelis are planning. Future trends in reactor supply and effects on proliferation rates are also discussed, reviewing the potential of the Indian 220 MWe pressurised heavy-water reactor, South Korean and Jananese potential for reactor exports in the Far East, and the Argentine-Brazilian nuclear programme in Latin America. This study suggests that small reactor designs for electrical power production and other applications, such as seawater desalination, can be made economical relative to diesel technology if traditional scaling laws can be altered by adopting and standardising a pre-fabricated nuclear power plant design. Also, economy can be gained if sufficient attention is concentrated on the design, construction and operating experience of suitably sized conventionally built reactor systems. (author)

  16. Small Modular Reactors: Nuclear Energy Market Potential for Near-term Deployment

    International Nuclear Information System (INIS)

    Lokhov, Alexey; Sozoniuk, Vladislav; Rothwell, Geoffrey; ); Cometto, Marco; Paillere, Henri; ); Crozat, Matt; Genoa, Paul; Joon Kim, Tae; McGough, Mike; Ingersoll, Dan; Rickman, Robin; Stout, Dan; Halnon, Greg; Chenais, Jacques; Briffod, Francois-Xavier; Perrier, Sylvain; Shahrokhi, Farshid; Kaufer, Barry; Wasylyk, Andrew; Shropshire, David; ); Danrong, Song; Swinburn, Richard

    2016-01-01

    Recent interest in small modular reactors (SMRs) is being driven by a desire to reduce the total capital costs associated with nuclear power plants and to provide power to small grid systems. According to estimates available today, if all the competitive advantages of SMRs were realised, including serial production, optimised supply chains and smaller financing costs, SMRs could be expected to have lower absolute and specific (per-kWe) construction costs than large reactors. Although the economic parameters of SMRs are not yet fully determined, a potential market exists for this technology, particularly in energy mixes with large shares of renewables. This report assesses the size of the market for SMRs that are currently being developed and that have the potential to broaden the ways of deploying nuclear power in different parts of the world. The study focuses on light water SMRs that are expected to be constructed in the coming decades and that strongly rely on serial, factory-based production of reactor modules. In a high-case scenario, up to 21 GWe of SMRs could be added globally by 2035, representing approximately 3% of total installed nuclear capacity. (authors)

  17. IAEA Expands International Cooperation on Small, Medium Sized or Modular Nuclear Reactors

    International Nuclear Information System (INIS)

    2018-01-01

    The International Atomic Energy Agency (IAEA) is launching an effort to expand international cooperation and coordination in the design, development and deployment of small, medium sized or modular reactors (SMRs), among the most promising emerging technologies in nuclear power. Significant advances have been made on SMRs, some of which will use pre-fabricated systems and components to shorten construction schedules and offer greater flexibility and affordability than traditional nuclear power plants. With some 50 SMR concepts at various stages of development around the world, the IAEA is forming a Technical Working Group (TWG) to guide its activities on SMRs and provide a forum for Member States to share information and knowledge, IAEA Deputy Director General Mikhail Chudakov said. “Innovation is crucial for nuclear power to play a key role in decarbonising the energy sector,” Chudakov, who heads the IAEA Department of Nuclear Energy, said at a conference on SMRs in Prague on 15 February. “Many Member States that are operating, expanding, introducing or considering nuclear power are quite keen on the development and deployment of SMRs.” Global interest in SMRs is growing. SMRs have the potential to meet the needs of a wide range of users and to be low carbon replacements for ageing fossil fuel fired power plants. They also display enhanced safety features and are suitable for non-electric applications, such as cooling, heating and water desalination. In addition, SMRs offer options for remote regions with less developed infrastructure and for energy systems that combine nuclear and alternative sources, including renewables.

  18. Quantum algebra Uqp(u2) and application to the rotational collective dynamics of the nuclei

    International Nuclear Information System (INIS)

    Barbier, R.

    1995-01-01

    This thesis concerns some aspects of new symmetries in Nuclear Physics. It comprises three parts. The first one is devoted to the study of the quantum algebra U qp (u 2 ). More precisely, we develop its Hopf algebraic structure and we study its co-product structure. The bases of the representation theory of U qp (u 2 ) are introduced. On one hand, we construct the finite-dimensional irreducible representations of U qp (u 2 ). On the other hand, we calculate the Clebsch-Gordan coefficients with the projection operator method. To complete our study, we construct some deformed boson mappings of the quantum algebras U qp (u 2 ), U q 2 (su 2 ) and U qp (u 1,1 ). The second part deals with the construction of a new phenomenological model of the non rigid rotator. This model is based on the quantum algebra U qp (u 2 ). The rotational energy and the E2 reduced transition probabilities are obtained. They depend on the two deformation parameters q and p of the quantum algebra. We show how the use of the two-parameter deformation of the algebra U qp (u 2 ) leads to a generalization of the U q (su 2 )-rotator model. We also introduce a new model of the anharmonic oscillator on the basis of the quantum algebra U qp (u 2 ). We show that the system of the U q (su 2 )-rotator and of the anharmonic oscillator can be coupled with the use of the deformation parameters of U qp (u 2 ). A ro-vibration energy formula and expansion 'a la' Dunham are obtained. The aim of the lest part is to apply our non rigid rotator model to the rotational collective dynamics of the superdeformed nuclei of the A∼130 - 150 and A∼190 mass regions and deformed nuclei of the actinide and rare earth series. We adjust the free parameters of our model and compare our results with those arising from four other models of the non rigid rotator. A comparative analysis is given in terms of transition energies. We calculate the dynamical moments of inertia with the fitted parameters. A comparison between the

  19. Small modular reactors (SMRs) - the way forward for the nuclear industry in Canada?

    International Nuclear Information System (INIS)

    Sam-Aggrey, H.

    2014-01-01

    Small Modular Reactors (SMRs) are being touted as safer, more cost effective and more flexible than traditional nuclear power plants (NPPs). Consequently, it has been argued that SMR technology is pivotal to the revitalization of the nuclear industry at the national and global levels. Drawing mainly on previously published literature, this paper explores the suitability of SMRs for various niche market applications in Canada. The paper examines the potential role of SMRs in providing an opportunity for remote mines and communities in northern Canada to reduce their vulnerability and dependence on costly, high-carbon diesel fuel. Other niche market applications of SMRs explored include: SMRs deployment in Saskatchewan for grid augmentation and as replacement options for Saskatchewan's ageing coal plants; the use of SMRs for bitumen extraction in the Oil Sands, and the potential use of SMRs in Canadian-owned foreign based mines. The socio-economic benefits of SMR deployments are also discussed. Building an SMR industry in Canada could complement the country's extensive expertise in uranium mining, reactor technology, plant operation, nuclear research, and environmental and safety standards, thereby enhancing Canada's ability to offer services throughout the entire nuclear life cycle. The paper also outlines some of the technical, economic and social barriers that could impede the successful introduction of SMRs in Canada. (author)

  20. A microstructural comparison of two nuclear-grade martensitic steels using small-angle neutron scattering

    Science.gov (United States)

    Coppola, R.; Fiori, F.; Little, E. A.; Magnani, M.

    1997-06-01

    Results are presented of a small-angle neutron scattering (SANS) study on two 10-13% Cr martensitic stainless steels of interest for nuclear applications, viz. DIN 1.4914 (MANET specification, for fusion reactors) and AISI 410. The investigation has focussed principally on microstructural effects associated with the differences in chromium content between the two alloys. The size distribution functions determined from nuclear and magnetic SANS components for the two steels given identical heat treatments are in accord with an interpretation based on the presence of ˜ 1 nm size CCr aggregates in the microstructure. Much larger (˜ 10 nm) scattering inhomogeneities with different magnetic contrast are also present and tentatively identified as carbides.

  1. Proceedings of the International conference: Nuclear option in countries with small and medium electricity grids

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    In order to achieve best safety and operational standards countries with limited human and material resources must put greater emphasis on their rational and efficient use. Consequently the worldwide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are of substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and co-operation amongst that group of countries is of great interest. As in the future use of nuclear energy there will be many more countries with small or medium nuclear systems, exchanging specific experience and co-operation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships.

  2. Proceedings of the International conference: Nuclear option in countries with small and medium electricity grids

    International Nuclear Information System (INIS)

    2000-01-01

    In order to achieve best safety and operational standards countries with limited human and material resources must put greater emphasis on their rational and efficient use. Consequently the worldwide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are of substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and co-operation amongst that group of countries is of great interest. As in the future use of nuclear energy there will be many more countries with small or medium nuclear systems, exchanging specific experience and co-operation between the like countries will be an additional value to the now prevailing equipment supplier - national utility relationships

  3. US market potential for small and medium-sized nuclear reactors

    International Nuclear Information System (INIS)

    Hardie, R.W.; Jackson, S.V.

    1988-01-01

    This paper presents the results of on-site interviews with representatives of 23 investor-owned utilities and 3 publicly-owned utilities. The purpose of the interviews was to obtain information on utilities' attitudes towards small and medium-sized power plants and towards building new nuclear plants in general. Most of the utilities interviewed preferred power plants smaller than the ones currently being offered, as long as the smaller plants did not incur a major economic penalty. However, according to the utilities interviewed, without changes in the current environment it is unlikely that there will be a significant market for new nuclear plants of any size. A trend in the utility industry towards generating companies appears to be a positive step. (orig.)

  4. US market potential for small and medium-sized nuclear reactors

    International Nuclear Information System (INIS)

    Hardie, R.W.; Jackson, S.V.

    1987-01-01

    This paper presents the results of on-site interviews with representatives of 23 investor-owned utilities and 3 publicly-owned utilities. The purpose of the interviews was to obtain information on utilities' attitudes toward small and medium-sized power plants and towards building new nuclear plants in general. Most of the utilities interviewed preferred power plants smaller than the ones currently being offered, as long as the smaller plants did not incur a major economic penalty. However, according to the utilities interviewed, without changes in the current environment it is unlikely that there will be a significant market for new nuclear plants of any size. A trend in the utility industry towards generating companies appears to be a positive step. (author)

  5. Very small HTGR nuclear power plant concepts for special terrestrial applications

    International Nuclear Information System (INIS)

    McDonald, C.F.; Goodjohn, A.J.

    1983-01-01

    The role of the very small nuclear power plant, of a few megawatts capacity, is perceived to be for special applications where an energy source as required but the following prevail: 1) no indigenous fossil fuel source, in long transport distances that add substantially to the cost of oil, coal in gas, and 3) secure long-term power production for defense applications with freedom from fuel supply lines. A small High Temperature Gas-Cooled reactor (HTGR) plant could provide the total energy needs for 1) a military installation, 2) an island base of strategic significance, 3) an industrial community or 4) an urban area. The small HTGR is regarded as a fixed-base installation (as opposed to a mobile system). All of the major components would be factory fabricated and transported to the site where emphasis would be placed on minimizing the construction time. The very small HTGR plant, currently in an early stage of design definition, has the potential for meeting the unique needs of the small energy user in both the military and private sectors. The plant may find acceptance for specialized applications in the industrialized nations and to meet the energy needs of developing nations. Emphasis in the design has been placed on safety, simplicity and compactness

  6. Verification of codes used for the nuclear safety assessment of the small space heterogeneous reactors with zirconium hydride moderator

    International Nuclear Information System (INIS)

    Glushkov, E.S.; Gomin, E.A.; Kompaniets, G.V.

    1994-01-01

    Computer codes used for assessment of nuclear safety for space NPP are compared taking as an example small-sized heterogeneous reactor with zirconium hydride moderator of the Topaz-2 facility. The code verifications are made for five different variants

  7. Economic evaluation of small modular nuclear reactors and the complications of regulatory fee structures

    International Nuclear Information System (INIS)

    Vegel, Benjamin; Quinn, Jason C.

    2017-01-01

    Carbon emission concerns and volatility in fossil fuel resources have renewed world-wide interest in nuclear energy as a solution to growing energy demands. Several large nuclear reactors are currently under construction in the United States, representing the first new construction in over 30 years. Small Modular Reactors (SMRs) have been in design for many years and offer potential technical and economic advantages compared with traditionally larger reactors. Current SMR capital and operational expenses have a wide range of uncertainty. This work evaluates the potential for SMRs in the US, develops a robust techno-economic assessment of SMRs, and leverages the model to evaluate US regulatory fees structures. Modeling includes capital expenses of a factory facility and capital and operational expenses with multiple scenarios explored through a component-level capital cost model. Policy regarding the licensing and regulation of SMRs is under development with proposed annual US regulatory fees evaluated through the developed techno-economic model. Results show regulatory fees are a potential barrier to the economic viability of SMRs with an alternate fee structure proposed and evaluated. The proposed fee structure is based on the re-distribution of fees for all nuclear reactors under a single structure based on reactor thermal power rating. - Highlights: • Potential demand for new small modular nuclear power in the US is established. • Capital costs are broken down on component level and include factory production. • US regulatory fees structures are evaluated, results show potential barrier. • An additional fee structure is proposed and compared with current US fee structures.

  8. Evaluating the Cost, Safety, and Proliferation Risks of Small Floating Nuclear Reactors.

    Science.gov (United States)

    Ford, Michael J; Abdulla, Ahmed; Morgan, M Granger

    2017-11-01

    It is hard to see how our energy system can be decarbonized if the world abandons nuclear power, but equally hard to introduce the technology in nonnuclear energy states. This is especially true in countries with limited technical, institutional, and regulatory capabilities, where safety and proliferation concerns are acute. Given the need to achieve serious emissions mitigation by mid-century, and the multidecadal effort required to develop robust nuclear governance institutions, we must look to other models that might facilitate nuclear plant deployment while mitigating the technology's risks. One such deployment paradigm is the build-own-operate-return model. Because returning small land-based reactors containing spent fuel is infeasible, we evaluate the cost, safety, and proliferation risks of a system in which small modular reactors are manufactured in a factory, and then deployed to a customer nation on a floating platform. This floating small modular reactor would be owned and operated by a single entity and returned unopened to the developed state for refueling. We developed a decision model that allows for a comparison of floating and land-based alternatives considering key International Atomic Energy Agency plant-siting criteria. Abandoning onsite refueling is beneficial, and floating reactors built in a central facility can potentially reduce the risk of cost overruns and the consequences of accidents. However, if the floating platform must be built to military-grade specifications, then the cost would be much higher than a land-based system. The analysis tool presented is flexible, and can assist planners in determining the scope of risks and uncertainty associated with different deployment options. © 2017 Society for Risk Analysis.

  9. Licensing process characteristics of Small Modular Reactors and spent nuclear fuel repository

    Energy Technology Data Exchange (ETDEWEB)

    Söderholm, Kristiina, E-mail: kristiina.soderholm@fortum.com [Fortum Power (Finland); Tuunanen, Jari, E-mail: jari.tuunanen@fortum.com [Fortum Power (Finland); Amaba, Ben, E-mail: baamaba@us.ibm.com [IBM Complex Systems (United States); Bergqvist, Sofia, E-mail: sofia.bergqvist@se.ibm.com [IBM Rational Software (Sweden); Lusardi, Paul, E-mail: plusardi@nuscalepower.com [NuScale Power (United States)

    2014-09-15

    Highlights: • We examine the licensing process challenges of modular nuclear facilities. • We compare the features of Small Modular Reactors and spent nuclear fuel repository. • We present the need of nuclear licensing simplification. • Part of the licensing is proposed to be internationally applicable. • Systems engineering and requirements engineering benefits are presented. - Abstract: This paper aims to increase the understanding of the licensing processes characteristics of Small Modular Reactors (SMR) compared with licensing of spent nuclear fuel repository. The basis of the SMR licensing process development lies in licensing processes used in Finland, France, the UK, Canada and the USA. These countries have been selected for this study because of their various licensing processes and recent actions in the new NPP construction. Certain aspects of the aviation industry licensing process have also been studied and selected practices have been investigated as possibly suitable for use in nuclear licensing. Suitable features for SMR licensing are emphasized and suggested. The licensing features of the spent nuclear fuel deep repository along with similar features of SMR licensing are discussed. Since there are similar types of challenges of lengthy licensing time frames, as well as modular features to be taken into account in licensing, these two different nuclear industry fields can be compared. The main SMR features to take into account in licensing are: • Standardization of the design. • Modularity. • Mass production. • Serial construction. Modularity can be divided into two different categories: the first category is simply a single power plant unit constructed of independently engineered modules (e.g. construction process for Westinghouse AP-1000 NPP) and the second one a power plant composed of many reactor modules, which are manufactured in factories and installed as needed (e.g. NuScale Power SMR design). The deep underground repository

  10. Alterations in messenger RNA and small nuclear RNA metabolism resulting from fluorouracil incorporation

    International Nuclear Information System (INIS)

    Armstrong, R.D.; Cadman, E.C.

    1985-01-01

    Studies were completed to examine the effect of 5-fluorouracil (FUra) incorporation on messenger RNA (mRNA) and small molecular weight nuclear RNA (SnRNA) metabolism. Studies of mRNA were completed using cDNA-mRNA hybridization methods to specifically examine dihydrofolate reductase (DHFR) mRNA. C 3 -L5178Y murine leukemia cells which are gene-amplified for DHFR, were exposed to FUra for 6, 12 or 24 hr, and the nuclear and cytoplasmic levels of DHFR-mRNA determined by hybridization with 32 P-DHFR-cDNA. FUra produced a dose-dependent increase in nuclear DHFR-mRNA levels, while total cytoplasmic DHFR-mRNA levels appeared to be unchanged. To examine only mRNA synthesized during FUra exposure, cells were also treated concurrently with [ 3 H] cytidine, and the [ 3 H]mRNA-cDNA hybrids measured following S 1 -nuclease treatment. FUra produced a concentration-dependent increase in nascent nuclear DHFR-mRNA levels, and a decrease in nascent cytoplasmic DHFR-mRNAs levels. These results suggest that FUra produces either an inhibition of mRNA processing, or an inhibition of nuclear-cytoplasmic transport. Preliminary experiments to examine ATP-dependent mRNA transport were completed with isolated nuclei from cells treated with FUra for 1 or 24 hr and then pulse-labeled for 1 hr with [ 3 H] cytidine. The results demonstrate a FUra-concentration and time-dependent inhibition of ATP-mediated mRNA efflux

  11. Feasibility study on nuclear core design for soluble boron free small modular reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rabir, Mohamad Hairie, E-mail: m-hairie@nuclearmalaysia.gov.my; Hah, Chang Joo; Ju, Cho Sung [Department of NPP Engineering, KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-04-29

    A feasibility study on nuclear core design of soluble boron free (SBF) core for small size (150MWth) small modular reactor (SMR) was investigated. The purpose of this study was to design a once through cycle SMR core, where it can be used to supply electricity to a remote isolated area. PWR fuel assembly design with 17×17 arrangement, with 264 fuel rods per assembly was adopted as the basis design. The computer code CASMO-3/MASTER was used for the search of SBF core and fuel assembly analysis for SMR design. A low critical boron concentration (CBC) below 200 ppm core with 4.7 years once through cycle length was achieved using 57 fuel assemblies having 170 cm of active height. Core reactivity controlled using mainly 512 number of 4 wt% and 960 12 wt% Gd rods.

  12. Size of nuclear sources from measurements of proton-proton correlations at small relative momentum

    International Nuclear Information System (INIS)

    Rebreyend, D.; Kox, S.; Merchez, F.; Noren, B.; Perrin, C.; Khelfaoui, B.; Gondrand, J.C.; Bondorf, J.P.

    1990-01-01

    This contribution will present recent measurements performed on light heavy ion reactions at intermediate energies. Nuclear source sizes were determined by measuring the correlation at small relative momentum, between two protons detected in the EMRIC set-up. This technique allows the determination of the extent of the emitting source by constructing a correlation function for the coincident protons and analyzing it in the framework of a final state interaction model. We found the apparent source size to be large compared to the dimension of the studied system and low sensitivity of the extracted radii as a function of the target mass and detection angle. We will show that simulations may be needed to fully estimate the correlation induced by detectors with small angular acceptance

  13. Advances in small zero-leak valves point to better nuclear power-plant reliability

    Energy Technology Data Exchange (ETDEWEB)

    Eacott, K B; Kin, J C; Hotta, Y [Dresser Japan, Ltd.

    1978-04-01

    In the selection of small valves less than two inches used for nuclear power plants, sufficient consideration must be given to the reliability to radioactive material, the easy operability, and the significant function, especially zero leak. These valves are classified into bellows and diaphragm seal types which must satisfy zero leak, 4000 cycles life test and good maintainability. Welded bellows, formed bellows, and metal diaphragms are actually used for these requirements. The construction of these types are shown. The requirements and principal specifications for these small valves are explained, and some examples are given. These zero leak valves are installed in reactor coolant loop system, borated water from B. A. system, pressurizer instrument system, containment spray system, high head system and off gas system for PWRS, and main steam line system, diesel generator cooling water system, re-circulation system, clean up water system, etc. for BWRS.

  14. U-2 Bono sünnipäevapidu

    Index Scriptorium Estoniae

    2002-01-01

    10. mail toimub Guitar Safari pubis Estonian U Fan Clubi eestvedamisel ansambli U-2 laulja-kitarristi Bono sünnipäevakontert. Üritust soojendab DJ Zwillig ning peaesinejateks on ansamblid The Bluesyard ja Sequence

  15. Proposed Regulation System for the Use of Small Quantities of Nuclear Material in Korea

    International Nuclear Information System (INIS)

    So, D. S.; Kim, H. S.; Lee, B. D.

    2007-01-01

    The Atomic Energy legislation does not require a person who intends to use or possess SQM(small quantities of nuclear material, below 300 grams of an uranium equivalent) to obtain a license or permit to use or possess such material. The absence of this requirement is an obstacle to the SSAC's (state system of accounting for and control) ability to effectively account for and control all nuclear material. Due to the differences of the meanings of some terminology used in the Korean Atomic Energy Law and its related regulations to those of safeguards agreement and its Protocol, there is a possibility of a difficulty occurring in the implementation of safeguards obligations. The objectives of this work are to establish an effective and rational control system for the SQM not required to obtain a license for its use or possession in Korea, and to review the definitions of some terminology used in the Atomic Energy legislation, IAEA's legal documents and guidelines to avoid any confusion in the implementation of international obligations in the nuclear control area

  16. Technology transfer on long-term radioactive waste management - a feasible option for small nuclear programmes?

    International Nuclear Information System (INIS)

    Mele, I.; Mathieson, J.

    2007-01-01

    The EU project CATT - Co-operation and technology transfer on long-term radioactive waste management for Member States with small nuclear programmes investigated the feasibility of countries with small nuclear programmes implementing long-term radioactive waste management solutions within their national borders, through collaboration on technology transfer with those countries with advanced disposal concepts. The main project objective was to analyse the existing capabilities of technology owning Member States and the corresponding requirements of potential technology acquiring Member States and, based on the findings, to develop a number of possible collaboration models and scenarios that could be used in a technology transfer scheme. The project CATT was performed as a specific support action under the EU sixth framework programme and it brought together waste management organisations from six EU Member States: UK, Bulgaria, Germany, Lithuania, Slovenia and Sweden. In addition, the EC Joint Research Centre from the Netherlands also participated as a full partner. The paper summarises the analyses performed and the results obtained within the project. (author)

  17. Development and characterization of monolithic fuel miniplate alloy U-2.5Zr-7.5Nb, coated in zircaloy

    International Nuclear Information System (INIS)

    Machado, Geraldo Correa

    2014-01-01

    The autocthonal production of nuclear fuel in Brazil for test and research reactors is restricted to MTR (Material Test Reactor) fuel type dispersion plate, using U3Si2 alloy, coated and dispersed in aluminum, developed by IPEN-SP for use in IEA-R1 reactor. Moreover, the UO 2 fuel rod type for power reactors is manufactured by Rezende (RJ) with a German technology by INB under license. Currently, Brazil is performing two programs of developing reactors. Currently, Brazil is developing two reactors. One of them is the development, by CNEN, the Brazilian Multipurpose Reactor (RMB), for testing, research and radioisotope production. The other one is the development a power reactor for naval propulsion, conducted by the Brazilian Navy. This dissertation presents the development and characterization of monolithic fuel miniplate alloy U-2.5Zr-7.5Nb, coated in zircaloy (ZRY), on a laboratory scale. Due to its innovative features and properties, this fuel can be used as fuel in both test reactors, research and producing radioisotopes for power reactors as small and medium sizes. Thus, this high potential fuel can be used in domestic reactors currently under development. The development of monolithic fuel plate type is made using the technique called 'picture-frame' where a sandwich composed of a monolith alloy U-2.5Zr- 7.5Nb coupled to a frame and coated sheets of Zry is obtained. The alloy U-2.5Zr-7.5Nb was obtained by melting in an induction furnace and then was cast into rectangular ingots of graphite, thus achieving an ingot with approximate dimensions of 170 x 50 x 60 mm. The obtained ingot was hot rolled at 850 ºC, with a 50 % reduction in thickness, in order to refine the raw structure of fusion. Samples cut from the alloy U-2.5Zr-7.5Nb, with dimensions 20 x 20 x 6 mm were placed in frames and plates Zry and joined by TIG (Tungsten Inert Gas) under an atmosphere of argon, obtaining a set of 10 mm thick, 45 mm wide and 100 mm long. The sandwiches were hot rolled to

  18. Development of Inspection Technique for Socket Weld of Small Bore Piping in Nuclear Power Plant

    International Nuclear Information System (INIS)

    Yoon, Byungsik; Kim, Yongsik; Lee, Jeongseok

    2013-01-01

    The losses incurred by unplanned shutdowns are significant; consequently, early crack initiation and crack detection, including the detection of fillet weld manufacturing defects, is of the utmost importance. Current inspection techniques are not capable of reliably inspecting socket welds; therefore, new approaches are needed. The new technique must be sensitive to socket weld cracking, which usually initiates from the root, in order to detect the cracking during the early failure phase. In 2008, Kori unit 3 experienced leakage from the drain line socket weld of a steam generator. From this experience, KHNP enforced a management program to focus on enhancing the reliability of small bore socket weld piping inspections. Currently, conventional manual ultrasonic inspection techniques are used to detect service induced fatigue cracks. But there was uncertainty on manual ultrasonic inspection because of limited access to the welds and difficulties with contact between the ultrasonic probe and the OD surface of small bore piping. In this study, phased array ultrasonic inspection techniques are applied to increase inspection speed and reliability. Additionally a manually encoded scanner has been developed to enhance contact conditions and maintain constant signal quality. A phased array UT technique and system was developed to inspect small bore socket welds. The experimental results show all artificial flaws in the specimen were detected and measured. These experimental results show, that the newly developed inspection system, has improved the reliability and speed of small bore socket weld inspection. Based on these results, future works shall focus on additional experiments, with more realistic flaw responses. By applying this technique to the field, we expect that it can improve the integrity of small bore piping in nuclear power plants

  19. Technique for detecting a small magnitude loss of special nuclear material

    International Nuclear Information System (INIS)

    Pike, D.H.; Chernick, M.R.; Downing, D.J.

    The detection of losses of special nuclear materials has been the subject of much research in recent years. The standard industry practice using ID/LEID will detect large magnitude losses. Time series techniques such as the Kalman Filter or CUSUM methods will detect small magnitude losses if they occur regularly over a sustained period of time. To date no technique has been proposed which adequately addresses the problem of detecting a small magnitude loss occurring in a single period. This paper proposes a method for detecting a small magnitude loss. The approach makes use of the influence function of Hempel. The influence function measures the effect of a single inventory difference on a group of statistics. An inventory difference for a period in which a loss occurs can be expected to produce an abnormality in the calculated statistics. This abnormality is measurable by the influence function. It is shown that a one period loss smaller in magnitude than the LEID can be detected using this approach

  20. Nuclear management in manual small incision cataract surgery by snare technique

    Directory of Open Access Journals (Sweden)

    Bhattacharya Debasish

    2009-01-01

    Full Text Available Manual small incision cataract surgery has evolved into a popular method of cataract surgery in India. However, in supra hard cataract, bringing out the whole nucleus through the sclerocorneal flap valve incision becomes difficult. A bigger incision required in such cataracts loses its value action, as the internal incision and corneal valve slips beyond the limbus into sclera. Struggling with the supra hard cataracts through a regular small incision. Phacofracture in the anterior chamber becomes a useful option in these cases. In the snare technique, a stainless steel wire loop when lassoed around the nucleus in the anterior chamber constricts from the equator, easily dividing the hardest of the nuclei into two halves. The wire loop constricts in a controlled way when the second cannula of snare is pulled. The divided halves can easily be brought out by serrated crocodile forceps. This nuclear management can be safely performed through a smaller sclerocorneal flap valve incision where the corneal valve action is retained within the limbus without sutures, and the endothelium or the incision is not disturbed. However, the technique requires space in the anterior chamber to maneuver the wire loop and anterior chamber depth more than 2.5 mm is recommended. Much evidence to this wonderful technique is not available in literature, as its popularity grew through live surgical workshops and small interactive conferences.

  1. Study on a nuclear spaceship for interplanetary cruise. Core design of a small fast reactor

    International Nuclear Information System (INIS)

    Kitamura, Taku; Yoshida, Yutaka; Honma, Yuji; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2009-01-01

    In 21st century, the field which needs nuclear power plant systems are not just on the Earth. We considered that the nuclear power is proper for the energy source of the manned spaceship for interplanetary cruise. In this study, we considered the system configuration of the spaceship, the design of power generating system, some navigational plans to reach the Mars. The system configuration of the spaceship studied in our laboratory has one or two Fast Reactor with liquid sodium coolant as main heat source, dozens of Stirling Engines as main power generators and some Plasma Rockets called VASIMR as propulsion system. Because the Fast Reactor need not thick and heavy pressure vessel and the sodium has high performance of heat transfer, they are the best suited to the space nuclear reactor system. In addition, Stirling Engine has high theoretical thermal efficiency and need not water, steam generators, steam condenser and so on. This results in absence of sodium-water reaction and significant weight saving of power generator system. The VASIMR studied at ASPL is an advanced electric propulsion device which is able to convert large amount of electric power into great propulsion force. At reactor designing, we are using the SRAC2006 code developed at JAEA and pursuing the optimal fast reactor design for spaceship. We think that smaller reactor is better. To realize a system which has inherent safety, sodium void reactivity should be negative. We adopted the design of the small fast reactor named 4S (Super Safe, Small and Simple) as a reference design. As a result, we verified that a void reactivity had negative value in some of calculation cases and we realized safe, small and simple space fast reactor. In addition, to piece out power generator system in space, we need to consider if the budget of exhaust heat from radiator panels to space needed at this case is realistic. To obtain the optimal trajectory of rapid Mars transit, we made some analysis calculation codes

  2. A data acquisition controller for small to medium scale nuclear experiments

    International Nuclear Information System (INIS)

    Bohm, C.

    1986-01-01

    A data aquisition controller and related software for small to medium scaled nuclear experiments are described. The unit is designed to be connected (via a standard terminal connection) as a peripheral to a host computer (in our case a VAX). It is based on a standard eurobus Z-80 microprocessor to which specially designed multichannel analyzer subsystems are added for data aquisition. The multichannel analyzer, which consists of single width eurocard, uses the controller memory, via direct memory access, for data storage. To this it is possible to add standard eurobus interfaces for digital and analog supervision and for control of the experimental parameters. The unit uses the host computer to interpret a host command file defining the experimental procedure. It will log in to the host when it needs assistance, but stay logged out during periods of inactivity. (orig.)

  3. Transfer of radioactive waste management expertise from Switzerland to other countries with small nuclear power programmes

    International Nuclear Information System (INIS)

    McKinley, I.; Birkhaeuser, Ph.; Kickmaier, W.; Vomvoris, S.; Zuidema, P.

    2000-01-01

    A legal requirement which coupled demonstration of the feasibility of nuclear waste disposal to the extension of reactor operational licenses beyond 1985 acted to force rapid development of the Swiss radioactive waste management programme. Over a period of almost 30 years and at a cost of approximately 800 M CHF Nagra has become established as a centre of excellence in this field. Resources include highly experienced manpower, literature and databases supporting development of national repositories for L/ILW and HLW/TRU and state-of-the-art R and D infrastructure (including 2 underground laboratories, hot-laboratory facilities at PSI (Paul Scherrer Institute), modelling groups at universities etc.). This paper reviews Nagra's experience and considers various ways in which expertise can be transferred to other small countries to minimise duplication of effort and optimise development of their own national programmes. (author)

  4. Design and static simulation of secondary loop of small PWR nuclear power plants

    International Nuclear Information System (INIS)

    Martin Lopez, L.A.N.

    1989-01-01

    A computer program that has been developed with the purpose of making easier the decisions concerning the design of the secondary loop of small PWR nuclear power plants through numerical experiments of low running costs and short time is presented. Initially, the first part of the computer program is described. It aims to preliminarily design several major components of the secondary circuit from user-defined design conditions. Next, the second part of the computer program is presented. It simulates the steady state operation at part-load conditions of the preliminary design of the plant by generating and solving systems of simultaneous nonlinear algebraic equations, their number varying from 17 to 107. The computer program has been tested for several application cases. The program results are discussed in the last part of the work, along with several aspects to be added to the program in future works. (author)

  5. A summary of methods of predicting reliability life of nuclear equipment with small samples

    International Nuclear Information System (INIS)

    Liao Weixian

    2000-03-01

    Some of nuclear equipment are manufactured in small batch, e.g., 1-3 sets. Their service life may be very difficult to determine experimentally in view of economy and technology. The method combining theoretical analysis with material tests to predict the life of equipment is put forward, based on that equipment consists of parts or elements which are made of different materials. The whole life of an equipment part consists of the crack forming life (i.e., the fatigue life or the damage accumulation life) and the crack extension life. Methods of predicting machine life has systematically summarized with the emphasis on those which use theoretical analysis to substitute large scale prototype experiments. Meanwhile, methods and steps of predicting reliability life have been described by taking into consideration of randomness of various variables and parameters in engineering. Finally, the latest advance and trends of machine life prediction are discussed

  6. Nuclear security regulatory framework analysis for small modular reactors in Canada and abroad

    Energy Technology Data Exchange (ETDEWEB)

    Farah, A., E-mail: amjad.farah@uoit.ca [University of Ontario Institute of Technology, Oshawa, ON (Canada)

    2015-07-01

    Small Modular Reactors (SMRs) are gaining global attention as a potential solution for future power plants due to claims of flexibility and cost effectiveness, while maintaining or increasing safety and security. With the change of design and the potential deployment in remote areas, however, challenges arise from a regulatory standpoint, to meet the safety and security regulations while maintaining economic feasibility. This work comprises of a review of the nuclear security regulatory frameworks in place for SMRs in Canada, USA and the IAEA; how they compare to each other, and to those of large reactors. The goal is to gauge what needs to be adjusted in order to address the changes in design between the two reactor sizes. Some key challenges concern the type of reactor, transportation of reactor components and fuel to remote areas, reduced security staff, and increased complexity of emergency planning and evacuation procedures. (author)

  7. Nuclear security regulatory framework analysis for small modular reactors in Canada and abroad

    International Nuclear Information System (INIS)

    Farah, A.

    2015-01-01

    Small Modular Reactors (SMRs) are gaining global attention as a potential solution for future power plants due to claims of flexibility and cost effectiveness, while maintaining or increasing safety and security. With the change of design and the potential deployment in remote areas, however, challenges arise from a regulatory standpoint, to meet the safety and security regulations while maintaining economic feasibility. This work comprises of a review of the nuclear security regulatory frameworks in place for SMRs in Canada, USA and the IAEA; how they compare to each other, and to those of large reactors. The goal is to gauge what needs to be adjusted in order to address the changes in design between the two reactor sizes. Some key challenges concern the type of reactor, transportation of reactor components and fuel to remote areas, reduced security staff, and increased complexity of emergency planning and evacuation procedures. (author)

  8. Small nuclear power reactor emergency electric power supply system reliability comparative analysis

    International Nuclear Information System (INIS)

    Bonfietti, Gerson

    2003-01-01

    This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

  9. High-field magnetization studies of U2T2Sn (T=Co, Ir, Pt) compounds

    International Nuclear Information System (INIS)

    Prokes, K.; Nakotte, H.; de Boer, F.R.

    1995-01-01

    High-field magnetization measurements at 4.2 K on U 2 T 2 Sn (T = Co, Ir and Pt) compounds have been performed on free and fixed powders up to 57 T. An antiferromagnetic ground state of U 2 Pt 2 Sn is corroborated by a metamagnetic transition at 22 T with very small hysteresis going up and down with field. U 2 Co 2 Sn and U 2 Ir 2 Sn show no metamagnetic transition up to 57 T which is in agreement with the non-magnetic ground state of these compounds. In all cases, the maximum applied field is not sufficient to achieve saturation. The short-pulse measurements presented here are compared with previous results obtained in quasi-static fields up to 35 T

  10. The effect of small molecules on nuclear-encoded translation diseases.

    Science.gov (United States)

    Soiferman, Devorah; Ayalon, Oshrat; Weissman, Sarah; Saada, Ann

    2014-05-01

    The five complexes of the mitochondrial respiratory chain (MRC) supply most organs and tissues with ATP produced by oxidative phosphorylation (OXPHOS). Inherited mitochondrial diseases affecting OXPHOS dysfunction are heterogeneous; symptoms may present at any age and may affect a wide range of tissues, with many diseases giving rise to devastating multisystemic disorders resulting in neonatal death. Combined respiratory chain deficiency with normal complex II accounts for a third of all respiratory deficiencies; mutations in nuclear-encoded components of the mitochondrial translation machinery account for many cases. Although mutations have been identified in over 20 such genes and our understanding of the mitochondrial translation apparatus is increasing, to date no definitive cure for these disorders exists. We evaluated the effect of seven small molecules with reported therapeutic potential in fibroblasts of four patients with combined respiratory complex disorders, each harboring a known mutation in a different nuclear-encoded component of the mitochondrial translation machinery: EFTs, GFM1, MRPS22 and TRMU. Six mitochondrial parameters were screened as follows; growth in glucose-free medium, reactive oxygen species (ROS) production, ATP content, mitochondrial content, mitochondrial membrane potential and complex IV activity. It was clearly evident that each patient displayed an individual response and there was no universally beneficial compound. AICAR increased complex IV activity in GFM1 cells and increased ATP content in MRPS22 fibroblasts but was detrimental to TRMU, who benefitted from bezafibrate. Two antioxidants, ascorbate and N-acetylcysteine (NAC), significantly improved cell growth, ATP content and mitochondrial membrane potential and decreased levels of intracellular reactive oxygen species (ROS) in EFTs fibroblasts. This study presents an expanded repertoire of assays that can be performed using the microtiter screening system with a small number

  11. Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system - 15110

    International Nuclear Information System (INIS)

    Boldon, L.; Liu, L.; Sabharwall, P.; Rabiti, C.; Bragg-Sitton, S.M.

    2015-01-01

    To assess the inherent value of energy in a thermal system, it is necessary to understand both the quantity and quality of energy available or the exergy. We study the case where nuclear energy through a small modular reactor (SMR) is supplementing the available wind energy through storage to meet the needs of the electrical grid. Nuclear power is also being used for the production of hydrogen via high temperature steam electrolysis. For a SMR exergy analysis, both the physical and economic environments must be considered. The physical environment incorporates the energy, raw materials, and reference environment, where the reference environment refers to natural resources available without limit and without cost. This paper aims to explore the use of exergy analysis methods to estimate and optimize SMR resources and costs for individual subsystems, based on thermodynamic principles-resource utilization and efficiency. The paper will present background information on exergy theory; identify the core subsystems in an SMR plant coupled with storage systems in support of renewable energy and hydrogen production; perform a thermodynamic exergy analysis; determine the cost allocation among these subsystems; and calculate unit 'exergetic' costs, unit 'exergo-economic' costs, and first and second law efficiencies. Exergetic and 'exergo-economic' costs ultimately determine how individual subsystems contribute to overall profitability and how efficiencies and consumption may be optimized to improve profitability, making SMRs more competitive with other generation technologies

  12. Analysis of the nuclear localization signal of TRF1 in non-small cell lung cancer

    Directory of Open Access Journals (Sweden)

    HU JIAN

    2009-01-01

    Full Text Available Several studies revealed a similar down-regulation of telomeric repeat binding factor 1 (TRF1 in tumors. We have previously reported the TRFl expression levels were down-regulation in non-small cell lung cancer (NSCLC. The regulation of TRFl localization is proposed to be important for the function and expression. The nuclear localization signal (NLS and nuclear export signal (NES are often important clues to localization of protein. The objective of the present study was to investigate the NLS and NES of TRFl in NSCLC patients. Thirty (30 patients with NSCLCs had undergone radical operations in The First Affiliated Hospital, College of Medicine, Zhejiang University. DNA sequences of NLSs and NESs were amplified by PCR. The PCR products were analyzed by DNA sequencing. There were four NLSs of the TRFl protein, including two monopartite and two bipartite NLSs. The NLSs sequences were included in 337KKERRVGTPQSTKKKKESRR356. The exon 8 and exon 9 of TRFl DNA were covered the NLS sequences. The sequences of predicted NESs were 11WMLDFLCLSL86 and 174NLLKLQALAV183, respectively. The exon 1, exon 3 and exon 4 of TRFl were covered the NES sequences. In NSCLCs, there was no a mutation, deletion, or substitution in NLS and NES of TRFl. We conclude that the NLS and NES sequences in NSCLCs patients did not have mutations. Down-expression of TRFl does not indicate gene mutation of NLS and NES in NSCLCs.

  13. Design of a small nuclear reactor for extending the operational envelope of the Victoria Class Submarine

    International Nuclear Information System (INIS)

    Cole, C.J.P.

    2003-01-01

    The purpose of this research is to conceptually design a small, inherently safe, quasi-homogeneous nuclear reactor that will provide enough power to maintain the hotel load of the Victoria Class Submarine and extend her operational envelope. This research is in its early stages. The purpose of this paper is to outline the background of the research, present results found to date, and indicate the direction of the research over the next two years. The Canadian Forces has recently acquired four U.K. built Upholder Class submarines to replace the ageing Oberon Class submarines purchased in the early 1960's. The Upholders, like the Oberons, are diesel-electric powered. The Upholders were renamed the Victoria Class upon commissioning in Canada. Submarines are strategic military weapons that have several roles including: intelligence gathering, inflicting surprise attacks, controlling shipping lanes and covert operations. For each of these roles the submarine must remain undetected. To remain undetected, it is imperative that the submarine remains submerged. To remain submerged and continue to function, a submarine requires an air-independent power generation system, such as a nuclear reactor. (author)

  14. Small-scale instrumentation for nuclear magnetic resonance of porous media

    International Nuclear Information System (INIS)

    Bluemich, Bernhard; Casanova, Federico; Dabrowski, Martin; Danieli, Ernesto; Haber, Agnes; Van Landeghem, Maxime; Haber-Pohlmeier, Sabina; Olaru, Alexandra; Perlo, Juan; Sucre, Oscar; Evertz, Loribeth

    2011-01-01

    The investigation of fluids confined to porous media is the oldest topic of investigation with small-scale nuclear magnetic resonance (NMR) instruments, as such instruments are mobile and can be moved to the site of the object, such as the borehole of an oil well. While the analysis was originally restricted by the inferior homogeneity of the employed magnets to relaxation measurements, today, portable magnets are available for all types of NMR measurements concerning relaxometry, imaging and spectroscopy in two types of geometries. These geometries refer to closed magnets that surround the sample and open magnets, which are brought close to the object for measurement. The current state of the art of portable, small-scale NMR instruments is reviewed and recent applications of such instruments are featured. These include the porosity analysis and description of diesel particulate filters, the determination of the moisture content in walls from gray concrete, new approaches to analyze the pore space and moisture migration in soil, and the constitutional analysis of the mortar base of ancient wall paintings.

  15. A study of a small nuclear power plant system for district heating

    International Nuclear Information System (INIS)

    Imamura, Mitsuru; Sato, Kotaro; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2008-01-01

    We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on 'MUTSU' reactor technology. 'MUTSU' had already proved its safety. And 'MUTSU' reactor was boron free reactor. It allows plant system to become more compact and simple. And load following capability by core reactivity become bigger. It means to reduce control rod movement. It leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result the core life became about 10 years. In the district heating system, there are not only district heating but also snow melting with warm water. It uses steam condenser's heat, which are only discharged now. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel. (author)

  16. Physical protection of small amounts of nuclear material or contaminated parts

    International Nuclear Information System (INIS)

    Zipper, R.

    2002-01-01

    In July 2001 an incident was recognized where a worker occupied with decontamination of structures in a shut down reprocessing plant for spent fuel illegally removed a small amount of radioactive material from the facility site. The investigations exhibited that he brought this material to the apartment of his partner in life and she incorporated significantly α-activity in the form of plutonium. Immediately after the incident was discovered the supervisory authorities and the operating company of the facility took action to minimize the harms to third parties arising from the radioactive material released and to prevent a similar event to occur. As the overall inventory of radioactive material in the shut down facility at the time the theft occurred was below the limit where measures of physical protection are required by the German regulatory work discussions were raised on consequences to be drawn from this incident to close this obvious gap. The German Federal Ministry for Environment, Nature Protection and Reactor Safety (BMU) as the superior competent authority therefore ordered GRS to draft a set of fundamental requirements for future rules to make a repetition of the initiating incident unlikely. Further discussions of the authorities involved on supplementary rules and guidelines aiming to better protect small amounts of radioactive material from being illegally removed out of nuclear facilities and laboratories are based on these fundamentals defined by GRS but not yet finished. (orig.)

  17. Book of Abstracts of 9th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    2012-01-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production in small and medium countries. Importance of international cooperation for the assessment of the nuclear option has been recognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, the Conference is organized in co-operation with IAEA. Croatian State Office for Radiological and Nuclear Safety and University of Zagreb, Faculty of Electrical Engineering and Computing have also participated in Conference organization. Session topics reflect some current emphasis, such as country energy needs, operation and safety of the operating nuclear power plants. The conference also focuses on the exchange of experience and co-operation in the fields of fuel cycle, radioactive waste management, regulatory practices and liability and insurance for nuclear damage. All contributed papers are grouped in 10 sessions: Energy planning and nuclear option; Power reactors and technologies; Nuclear energy and environment; Operation and maintenance experience; Safety culture; Nuclear safety analyses; Reactor physics and nuclear fuel cycle; Radioactive waste management and decommissioning; Public relations; Regulatory practice and general papers.

  18. Small molecule and peptide-mediated inhibition of Epstein-Barr virus nuclear antigen 1 dimerization

    International Nuclear Information System (INIS)

    Kim, Sun Young; Song, Kyung-A; Kieff, Elliott; Kang, Myung-Soo

    2012-01-01

    Highlights: ► Evidence that targeting EBNA1 dimer, an EBV onco-antigen, can be achievable. ► A small molecule and a peptide as EBNA1 dimerization inhibitors identified. ► Both inhibitors associated with EBNA1 and blocked EBNA1 DNA binding activity. ► Also, prevented its dimerization, and repressed viral gene transcription. -- Abstract: Latent Epstein-Barr virus (EBV) infection is associated with human B cell lymphomas and certain carcinomas. EBV episome persistence, replication, and gene expression are dependent on EBV-encoded nuclear antigen 1 (EBNA1)’s DNA binding domain (DBD)/dimerization domain (DD)-mediated sequence-specific DNA binding activity. Homodimerization of EBNA1 is essential for EBNA1 DNA binding and transactivation. In this study, we characterized a novel small molecule EBNA1 inhibitor EiK1, screened from the previous high throughput screening (HTS). The EiK1 compound specifically inhibited the EBNA1-dependent, OriP-enhanced transcription, but not EBNA1-independent transcription. A Surface Plasmon Resonance Biacore assay revealed that EiK1 associates with EBNA1 amino acid 459–607 DBD/DD. Consistent with the SPR data, in vitro gel shift assays showed that EiK1 suppressed the activity of EBNA1 binding to the cognate familial repeats (FR) sequence, but not control RBP-Jκ binding to the Jκ site. Subsequently, a cross-linker-mediated in vitro multimerization assay and EBNA1 homodimerization-dependent yeast two-hybrid assay showed that EiK1 significantly inhibited EBNA1 dimerization. In an attempt to identify more highly specific peptide inhibitors, small peptides encompassing the EBNA1 DBD/DD were screened for inhibition of EBNA1 DBD-mediated DNA binding function. The small peptide P85, covering EBNA1 a.a. 560–574, significantly blocked EBNA1 DNA binding activity in vitro, prevented dimerization in vitro and in vivo, associated with EBNA1 in vitro, and repressed EBNA1-dependent transcription in vivo. Collectively, this study describes two

  19. Small molecule and peptide-mediated inhibition of Epstein-Barr virus nuclear antigen 1 dimerization

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sun Young; Song, Kyung-A [Samsung Advanced Institute for Health Sciences and Technology (SAIHST), Sungkyunkwan University School of Medicine, Seoul (Korea, Republic of); Samsung Biomedical Research Institute (SBRI), Samsung Medical Center, Sungkyunkwan University School of Medicine, Seoul (Korea, Republic of); Kieff, Elliott [Department of Medicine, Brigham and Women' s Hospital and Harvard Medical School, Boston, MA 02115 (United States); Kang, Myung-Soo, E-mail: mkang@skku.edu [Samsung Advanced Institute for Health Sciences and Technology (SAIHST), Sungkyunkwan University School of Medicine, Seoul (Korea, Republic of); Samsung Biomedical Research Institute (SBRI), Samsung Medical Center, Sungkyunkwan University School of Medicine, Seoul (Korea, Republic of); Department of Medicine, Brigham and Women' s Hospital and Harvard Medical School, Boston, MA 02115 (United States)

    2012-07-27

    Highlights: Black-Right-Pointing-Pointer Evidence that targeting EBNA1 dimer, an EBV onco-antigen, can be achievable. Black-Right-Pointing-Pointer A small molecule and a peptide as EBNA1 dimerization inhibitors identified. Black-Right-Pointing-Pointer Both inhibitors associated with EBNA1 and blocked EBNA1 DNA binding activity. Black-Right-Pointing-Pointer Also, prevented its dimerization, and repressed viral gene transcription. -- Abstract: Latent Epstein-Barr virus (EBV) infection is associated with human B cell lymphomas and certain carcinomas. EBV episome persistence, replication, and gene expression are dependent on EBV-encoded nuclear antigen 1 (EBNA1)'s DNA binding domain (DBD)/dimerization domain (DD)-mediated sequence-specific DNA binding activity. Homodimerization of EBNA1 is essential for EBNA1 DNA binding and transactivation. In this study, we characterized a novel small molecule EBNA1 inhibitor EiK1, screened from the previous high throughput screening (HTS). The EiK1 compound specifically inhibited the EBNA1-dependent, OriP-enhanced transcription, but not EBNA1-independent transcription. A Surface Plasmon Resonance Biacore assay revealed that EiK1 associates with EBNA1 amino acid 459-607 DBD/DD. Consistent with the SPR data, in vitro gel shift assays showed that EiK1 suppressed the activity of EBNA1 binding to the cognate familial repeats (FR) sequence, but not control RBP-J{kappa} binding to the J{kappa} site. Subsequently, a cross-linker-mediated in vitro multimerization assay and EBNA1 homodimerization-dependent yeast two-hybrid assay showed that EiK1 significantly inhibited EBNA1 dimerization. In an attempt to identify more highly specific peptide inhibitors, small peptides encompassing the EBNA1 DBD/DD were screened for inhibition of EBNA1 DBD-mediated DNA binding function. The small peptide P85, covering EBNA1 a.a. 560-574, significantly blocked EBNA1 DNA binding activity in vitro, prevented dimerization in vitro and in vivo, associated

  20. CANDLE reactor: an option for simple, safe, high nuclear proliferation resistant , small waste and efficient fuel use reactor

    International Nuclear Information System (INIS)

    Sekimoto, H.

    2010-01-01

    The innovative nuclear energy systems have been investigated intensively for long period in COE-INES program and CRINES activities in Tokyo Institute of Technology. Five requirements; sustainability, safety, waste, nuclear-proliferation, and economy; are considered as inevitable requirements for nuclear energy. Characteristics of small LBE cooled CANDLE fast reactor developed in this Institute are discussed for these requirements. It satisfies clearly four requirements; safety, nonproliferation and safeguard, less wastes and sustainability. For the remaining requirement, economy, a high potential to satisfy this requirement is also shown

  1. National assessment study in Armenia using innovative nuclear reactors and fuel cycles methodology for an innovative nuclear systems in a country with small grid

    International Nuclear Information System (INIS)

    Sargsyan, V.H.; Galstyan, A.A.; Gevorgyan, A.A.

    2010-01-01

    The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was launched in November 2000 under the aegis of the IAEA. Phases 1A and IB (first Part) of the Project were dedicated to elaboration, testing and validation of the INPRO Methodology. At the Technical Meeting in Vienna (13-15 October 2004) Armenia has proposed an assessment using the INPRO Methodology for an Innovative Nuclear Energy System in a country with a small electrical grid. Such kind of study helps Armenia in analysis of Innovative Nuclear Energy System (INS), including fuel cycle options, as well as shows applicability of INPRO methodology for small countries, like Armenia. This study was based on the results given in [3] and [4], and also on the main objectives, declared by the Government of Armenia in the paper 'Energy Sector Development Strategies in the Context of Economic Development in Armenia'

  2. Implantation aspects of small and medium nuclear power plant in Latin America

    International Nuclear Information System (INIS)

    Brito, S.; Cosentino, J.; Eibenschutz, J.; Gasparian, A.E.; Lepecki, W.P.S.; Spitalnik, J.

    1984-01-01

    The nuclear energy policy adopted by the Latin America is commented. The nuclear power plants in planning are presented. An analysis about the nuclear legislation, licensing and nuclear regulation, quality assurance and formation of human resources for Latin America is done. (E.G.) [pt

  3. Nuclear Knowledge and Competence: Fundamental Prerequisites for the Safe Utilization of Radiation Sources in a Small Non-Nuclear Country — Experience of Montenegro

    International Nuclear Information System (INIS)

    Jovanovic, S.; Dlabac, A.

    2016-01-01

    Provision of adequate knowledge, competence and expertise represents a major concern when addressing nuclear and radiation safety issues in small countries — if inadequate, safety will eventually be jeopardized. Montenegro is such a small, developing and “nonnuclear” country—the use of radiation sources being modest and limited to a few ordinary applications (primarily in health care). Even though, there is (or will be in the foreseeable future) a significant need in nuclear knowledge, competence and expertise — directly or indirectly related to nuclear/radiation safety and security issues. It goes about the following, the list being not exhaustive: (i) medical applications (diagnostics, radiotherapy, palliation, sterilization of equipment, consumables, blood products, etc.), (ii) radiation protection, including various dosimetry services and QC/QA of radiation sources; (iii) environmental protection (radioecology, analytical and monitoring services, etc.), (iv) low and medium activity radioactive waste management (including a newly licenced storage), (v) industrial, geological, hydrological, agricultural, biochemical and archaeological applications (non-destructive testing, various gauges, radioisotope labeling, harmful insects sterilization, etc.), (vi) scientific and educational uses, (vii) cultural heritage preservation and investigation, (viii) legislative and regulatory aspects, including complying to international safety/security norms and joining international conventions in the field, (ix) preparedness and response to radiological and nuclear emergency situations, (x) combating illicit trafficking of nuclear and other radioactive materials, (xi) nuclear forensics, (xii) security systems based on X-ray and other nuclear methods, (xiii) introduction of some future topics (e.g., nuclear power for electricity generation and sea water desalination), (xiv) public information and communication with media, etc.

  4. Neutronic design of a plutonium-thorium burner small nuclear reactor

    International Nuclear Information System (INIS)

    Hartanto, Donny

    2010-02-01

    A small nuclear reactor using thorium and plutonium fuel has been designed from the neutronic point of view. The thermal power of the reactor is 150 MWth and it is proposed to be used to supply electricity in an island in Indonesia. Thorium and plutonium fuel was chosen because in recent years the thorium fuel cycle is one of the promising ways to deal with the increasing number of plutonium stockpiles, either from the utilization of uranium fuel cycle or from nuclear weapon dismantling. A mixed fuel of thorium and plutonium will not generate the second generation of plutonium which will be a better way to incinerate the excess plutonium compared with the MOX fuel. Three kinds of plutonium grades which are the reactor grade (RG), weapon grade (WG), and spent fuel grade (SFG) plutonium, were evaluated as the thorium fuel mixture in the 17x17 Westinghouse PWR Fuel assembly. The evaluated parameters were the multiplication factor, plutonium depletion, fissile buildup, neutron spectrum, and temperature reactivity feedback. An optimization was also done to increase the plutonium depletion by changing the Moderator to Fuel Ratio (MFR). The computer codes TRITON (coupled NEWT and ORIGEN-S) in SCALE version 6 were used as the calculation tool for this assembly level. From the evaluation and optimization of the fuel assembly, the whole core was designed. The core was consisted of 2 types of thorium fuel with different plutonium grade and it followed the checkerboard loading pattern. A new concept of enriched burnable poison was also introduced to the core. The core life is 6.4 EFPY or 75 GWd/MTHM. It can burn up to 58% of its total mass of initial plutonium. VENTURE was used as the calculation tool for the core level

  5. Closure plan for Corrective Action Unit 109: U-2bu subsidence crater, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    1999-03-01

    The U-2bu subsidence crater, Corrective Action Unit 109, will be closed in accordance with the Resource Conservation and Recovery Act, the Nevada Division of Environmental Protection operational permit, and the Federal Facility Agreement and Consent Order. The U-2bu subsidence crater is located in Area 2 of the Nevada Test Site. It was created in 1971 by an underground nuclear test with the name Miniata. The crater has a diameter of 288 meters (944 feet) and an approximate depth of 35 meters (115 feet). Based on the results of the analyses reported in the site characterization report, the only constituents of concern in the U-2bu subsidence crater include leachable lead and total petroleum hydrocarbons. Closure activities will include the excavation and disposal of impacted soil from the top of the crater. Upon completion of excavation, verification samples will be collected to show that the leachable lead has been removed to concentrations below the regulatory action level. After sample results show that the lead has been removed, the excavated area will be backfilled and a soil flood diversion berm will be constructed as a best management practice. An independent registered professional engineer will certify the site was closed following the approved Closure Plan. Post-closure care is not warranted for this site because closure activities will involve removal of the Resource Conservation and Recovery Act constituents of concern

  6. RCRA Part A permit characterization plan for the U-2bu subsidence crater. Revision 1

    International Nuclear Information System (INIS)

    1998-04-01

    This plan presents the characterization strategy for Corrective Action Unit (CAU) 109, U-2bu Subsidence Crater (referred to as U-2bu) in Area 2 at the Nevada Test Site (NTS). The objective of the planned activities is to obtain sufficient characterization data for the crater soils and observed wastes under the conditions of the current Resource Conservation and Recovery Act (RCRA) Part A permit. The scope of the characterization plan includes collecting surface and subsurface soil samples with hand augers and for the purpose of site characterization. The sampling strategy is to characterize the study area soils and look for RCRA constituents. Observable waste soils and surrounding crater soils will be analyzed and evaluated according to RCRA closure criteria. Because of the status of the crater a RCRA Part A permit site, acquired radionuclide analyses will only be evaluated in regards to the health and safety of site workers and the disposition of wastes generated during site characterization. The U-2bu Subsidence Crater was created in 1971 by a Lawrence Livermore National Laboratory underground nuclear test, event name Miniata, and was used as a land-disposal unit for radioactive and hazardous waste from 1973 to 1988

  7. Closure plan for Corrective Action Unit 109: U-2bu subsidence crater, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-03-01

    The U-2bu subsidence crater, Corrective Action Unit 109, will be closed in accordance with the Resource Conservation and Recovery Act, the Nevada Division of Environmental Protection operational permit, and the Federal Facility Agreement and Consent Order. The U-2bu subsidence crater is located in Area 2 of the Nevada Test Site. It was created in 1971 by an underground nuclear test with the name Miniata. The crater has a diameter of 288 meters (944 feet) and an approximate depth of 35 meters (115 feet). Based on the results of the analyses reported in the site characterization report, the only constituents of concern in the U-2bu subsidence crater include leachable lead and total petroleum hydrocarbons. Closure activities will include the excavation and disposal of impacted soil from the top of the crater. Upon completion of excavation, verification samples will be collected to show that the leachable lead has been removed to concentrations below the regulatory action level. After sample results show that the lead has been removed, the excavated area will be backfilled and a soil flood diversion berm will be constructed as a best management practice. An independent registered professional engineer will certify the site was closed following the approved Closure Plan. Post-closure care is not warranted for this site because closure activities will involve removal of the Resource Conservation and Recovery Act constituents of concern.

  8. Proceedings and Book of Abstracts of 8th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    2010-01-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production in small and medium countries. Importance of international cooperation for the assessment of the nuclear option has been recognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, the Conference is organized in co-operation with IAEA. Session topics reflect some current emphasis, such as country energy needs, accommodation on Kyoto restriction on CO 2 emission, new reactor technologies, operation and safety of the operating nuclear power plants. The conference also focuses on the exchange of experience and co-operation in the fields of fuel cycle, radioactive waste management, regulatory practices and liability and insurance for nuclear damage. All contributed papers are grouped in 10 sessions: Energy planning and nuclear option; Power reactors and technologies; Nuclear energy and environment; Operation and maintenance experience; Safety culture; Nuclear safety analyses; Reactor physics and nuclear fuel cycle; Radioactive waste management and decommissioning; Public relations; Regulatory practice and general papers.

  9. Book of Abstracts of 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

    Energy Technology Data Exchange (ETDEWEB)

    Cavlina, N; Pevec, D; Bajs, T

    2008-07-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production in small and medium countries. Importance of international cooperation for the assessment of the nuclear option has been recognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, the Conference is organized in co-operation with IAEA. Session topics reflect some current emphasis, such as country energy needs, accommodation on Kyoto restriction on CO{sub 2} emission, new reactor technologies, operation and safety of the operating nuclear power plants. The conference also focuses on the exchange of experience and co-operation in the fields of fuel cycle, radioactive waste management, regulatory practices and liability and insurance for nuclear damage. All contributed papers are grouped in 10 sessions: Energy planning and nuclear option; Power reactors and technologies; Operation and maintenance experience; Safety culture; Nuclear safety analyses; Reactor physics and nuclear fuel cycle; Radioactive waste management and decommissioning; Public relation; Regulatory practice; Liability and insurance for nuclear damage.

  10. Book of Abstracts of 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    Cavlina, N.; Pevec, D.; Bajs, T.

    2008-01-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production in small and medium countries. Importance of international cooperation for the assessment of the nuclear option has been recognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, the Conference is organized in co-operation with IAEA. Session topics reflect some current emphasis, such as country energy needs, accommodation on Kyoto restriction on CO 2 emission, new reactor technologies, operation and safety of the operating nuclear power plants. The conference also focuses on the exchange of experience and co-operation in the fields of fuel cycle, radioactive waste management, regulatory practices and liability and insurance for nuclear damage. All contributed papers are grouped in 10 sessions: Energy planning and nuclear option; Power reactors and technologies; Operation and maintenance experience; Safety culture; Nuclear safety analyses; Reactor physics and nuclear fuel cycle; Radioactive waste management and decommissioning; Public relation; Regulatory practice; Liability and insurance for nuclear damage

  11. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    Directory of Open Access Journals (Sweden)

    Seung Hyun Nam

    2015-10-01

    Full Text Available Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER, for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MWth and an electricity generation mode of 100 kWth, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

  12. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

    2015-10-15

    Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW{sub th} and an electricity generation mode of 100 kW{sub th}, equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and

  13. Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor

    International Nuclear Information System (INIS)

    Nam, Seung Hyun; Venneri, Paolo; Kim, Yong Hee; Lee, Jeong Ik; Chang, Soon Heung; Jeong, Yong Hoon

    2015-01-01

    Although the harsh space environment imposes many severe challenges to space pioneers, space exploration is a realistic and profitable goal for long-term humanity survival. One of the viable and promising options to overcome the harsh environment of space is nuclear propulsion. Particularly, the Nuclear Thermal Rocket (NTR) is a leading candidate for near-term human missions to Mars and beyond due to its relatively high thrust and efficiency. Traditional NTR designs use typically high power reactors with fast or epithermal neutron spectrums to simplify core design and to maximize thrust. In parallel there are a series of new NTR designs with lower thrust and higher efficiency, designed to enhance mission versatility and safety through the use of redundant engines (when used in a clustered engine arrangement) for future commercialization. This paper proposes a new NTR design of the second design philosophy, Korea Advanced NUclear Thermal Engine Rocket (KANUTER), for future space applications. The KANUTER consists of an Extremely High Temperature Gas cooled Reactor (EHTGR) utilizing hydrogen propellant, a propulsion system, and an optional electricity generation system to provide propulsion as well as electricity generation. The innovatively small engine has the characteristics of high efficiency, being compact and lightweight, and bimodal capability. The notable characteristics result from the moderated EHTGR design, uniquely utilizing the integrated fuel element with an ultra heat-resistant carbide fuel, an efficient metal hydride moderator, protectively cooling channels and an individual pressure tube in an all-in-one package. The EHTGR can be bimodally operated in a propulsion mode of 100 MW th and an electricity generation mode of 100 kW th , equipped with a dynamic energy conversion system. To investigate the design features of the new reactor and to estimate referential engine performance, a preliminary design study in terms of neutronics and thermohydraulics

  14. Big ambitions, small returns: Nuclear energy development in China and India

    Energy Technology Data Exchange (ETDEWEB)

    Xu, Yi-hong

    2010-09-15

    This paper examines nuclear energy development in China and India and the obstacles they face. It discusses the challenges for nuclear expansion: technology, economic, nuclear fuel, and public acceptance. It concludes that (1) on all three counts - energy demands, energy security and environmental pollution - the potential impact of nuclear energy will be minimal in both countries; and (2) despite the political, financial and technical obstacles for nuclear expansion and the minimal contribution of energy security, both countries will devote financial, human and political resources to their nuclear expansion. Its speed will depend on domestic and international political development.

  15. A study of a small nuclear power plant system for district heating

    International Nuclear Information System (INIS)

    Imamura, Mitsuru; Sato, Kotaro; Narabayashi, Tadashi; Shimazu, Yoichiro; Tsuji, Masashi

    2009-01-01

    We have studied nuclear power plant for district heating. Already some towns and villages in Hokkaido have requested small reactor for district heating. Using existing technology allows us to shorten development period and to keep a lid on development cost. We decided to develop new reactor based on 'MUTSU' reactor technology because 'MUTSU' had already proved its safety. And this reactor was boron free reactor. It allows plant system to reduce the chemical control system. And moderator temperature coefficient is deeply negative. It means to improve its operability and leads to dependability enhancement. We calculated burn-up calculation of erbium addition fuel. In the result, the core life became about 10 years. And we adapt the cassette type refueling during outagein in order to maintain nonproliferation. In the district heating system, a double heat exchanger system enables to response to load change in season. To obtain the acceptance of public, this system has a leak prevention system of radioactive materials to public. And road heating system of low grade heat utilization from turbine condenser leads to improve the heat utilization efficiency. We carried out performance evaluation test of district heating pipeline. Then the heat loss of pipeline is estimated at about 0.440degC/km. This result meets general condition, which is about 1degC/km. This small plant has passive safety system. It is natural cooling of containment vessel. In case of loss of coolant accident, decay heat can remove by natural convection air cooling after 6 hours. Decay heat within 6 hours can remove by evaporative heat transfer of pool on containment vessel. (author)

  16. Ecological studies of small mammals in a nuclear site on Nevada Test Site

    International Nuclear Information System (INIS)

    Bradley, W.G.; Moor, K.S.

    1978-01-01

    Ecological studies of small vertebrates in nuclear event sites in NTS began in spring 1977 with the establishment of a permanent live-trapping grid in Little Feller II. These study areas are located in Area 18, a relatively homogeneous area vegetatively and topographically. Most of the flora and fauna are typical of the Great Basin desert found in southern Nevada. Dominant vegetation includes Artemesia spp. and to a lesser extent Atriplex. Salsola is an abundant weed in areas that have been mechanically disturbed such as the vicinity of GZ. A 400-station live-trapping grid was established in Little Feller II, April 1977. Sixteen lines of live traps (25 traps per line, each trap 50 feet apart) comprise the 8.4 hectare grid encompassing GZ. Nine trapping periods have been completed to date totaling over 10,000 trap nights. Over 400 small vertebrates have been marked for permanent identification in the grid. Over 60 known residents (animals marked 3 months previously and recaptured in the same vicinity) have been collected and prepared for shipping; however, radioanalytical results were not available to include in this report. Both census and field note observations were used to develop an inventory of the vertebrates found in the study areas. Sufficient data have been generated from Little Feller II to estimate density of rodents. These data and comparative data from Area 5 (Mohave Desert), Area 11 (Transition), and Area 13 (Great Basin) are presented. It was readily apparent that rodents in general were more numerous in Little Feller II. In addition, Dipodomys ordii, a Great Basin species, was an important new addition to the rodent fauna

  17. Book of abstracts of 10th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    2014-01-01

    The International Conference "Nuclear Option in Countries with Small and Medium Electricity Grids" is the tenth in a series of meetings on the same topics organized biennially by the Croatian Nuclear Society. This topical conference was initiated in 1996 and the first conference took place in Opatija, the following seven in Dubrovnik and the last one in Zadar. This year, it again takes place in Zadar. The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production in small and medium sized countries. Importance of international cooperation for the assessment of the nuclear option has been recognised by the International Atomic Energy Agency (IAEA). As a result of this recognition, the Conference is organized in co-operation with IAEA. Croatian State Office for Radiological and Nuclear Safety and University of Zagreb, Faculty of Electrical Engineering and Computing have also participated in Conference organization. Session topics reflect some current emphasis, such as country energy needs, new reactor technologies, operation and safety of the operating nuclear power plants. The conference also focuses on the exchange of experience and co-operation in the fields of fuel cycle, radioactive waste management, regulatory practice and liability.

  18. Results of small break LOCA analysis for Kuosheng nuclear power plant using the RELAP5YA computer code

    International Nuclear Information System (INIS)

    Wang, L.C.; Jeng, S.C.; Chung, N.M.

    2004-01-01

    One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, documented and submitted for USNRC approval and the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval. A study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Kuosheng nuclear power plant. This paper presents the results of the analysis that are useful in satisfying the same requirements of the Republic Of China Atomic Energy Commission (ROCAEC). (author)

  19. Innovations in PHWR design, integration of nuclear power stations into power systems and role of small size nuclear power plants in a developing country

    International Nuclear Information System (INIS)

    Mehta, S.K.; Kakodkar, A.; Balakrishnan, M.R.; Ray, R.N.; Murthy, L.G.K.; Chamany, B.F.; Kati, S.L.

    1977-01-01

    PHWR concept of thermal reactors has been considered with a view to exploiting the limited resources of natural uranium and keeping in mind the projected nuclear power programme covering fast breeder reactors. Experience in engineering of current PHWR units in India, gradual build up of necessary infrastructure and operational experience with one unit, have helped in building up design and technological capability in the country. The R and D facilities have been so planned that additional data required for the design of bigger reactor units (i.e.500/600 MWe) could be generated with minimal augmentation. Satisfactory operation of a nuclear power station demands certain prerequisites from the connected power system. The grid should have load patterns suitable for base load operation of these stations, should be stiff so far as voltage and frequency fluctuations are concerned and should have high reliability. A typical power grid in this country is characterised by heavy loads during peak hours and very light loads during night. Regional grids are of small size and the few interconnections existing between the regional grids consist of weak tie lines. Amongst all types of the power stations, it is the nuclear system which undergoes maximum strain and economic penalty while operating when connected to such a power system. Consistent with the above, phase installation of small-size power reactor units of about 200 MWe capacity may facilitate setting up of larger unit sizes at a later date. The effect of any possible reduction in the capital cost of a larger unit power station will enable the power station to partially meet the demand of the more productive types of loads. This paper deals with some of the major design changes that are being incorporated in the PHWR type power reactors currently being set up and the research and development back-up required for the purpose. Since the unit sizes of the power reactors presently contemplated are small compared to nuclear

  20. Proceedings of the 5th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    Pevec, D.; Debrecin, N.

    2004-01-01

    The Fifth International Conference 'Nuclear Option in Countries with Small and Medium Electricity Grids' is the fifth in a series of meetings on the same topics organized biannually by the Croatian Nuclear Society. This topical conference was initiated in 1996 to be devoted to the needs and interests of countries with small or medium nuclear systems and electricity grids. The first conference took place in Opatija, and the three following in Dubrovnik. Encouraged by the successes of previous conferences in Dubrovnik we decided to organise it once more in Dubrovnik. The conference is organized with intention to focus on specific aspects of introduction and usage of nuclear energy by countries with small and medium electricity grids. Session topics reflect some current emphasis, such as development of small and medium reactors, accommodation of Kyoto restriction on CO 2 emission, nuclear terrorism risk coverage, or cooperation in nuclear fuel cycle. In order to achieve best safety and operational standards these countries with limited human and material resources must put added emphasis on their rational and efficient use. Consequently, the worldwide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are of substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and co-operation amongst that group of countries is of great interest. Exchanging specific experience and co-operation between the like countries will be additional value relative to the still prevailing equipment supplier-national utility relationships

  1. Proceedings of the 5th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    Energy Technology Data Exchange (ETDEWEB)

    Pevec, D; Debrecin, N [eds.

    2004-07-01

    The Fifth International Conference 'Nuclear Option in Countries with Small and Medium Electricity Grids' is the fifth in a series of meetings on the same topics organized biannually by the Croatian Nuclear Society. This topical conference was initiated in 1996 to be devoted to the needs and interests of countries with small or medium nuclear systems and electricity grids. The first conference took place in Opatija, and the three following in Dubrovnik. Encouraged by the successes of previous conferences in Dubrovnik we decided to organise it once more in Dubrovnik. The conference is organized with intention to focus on specific aspects of introduction and usage of nuclear energy by countries with small and medium electricity grids. Session topics reflect some current emphasis, such as development of small and medium reactors, accommodation of Kyoto restriction on CO{sub 2} emission, nuclear terrorism risk coverage, or cooperation in nuclear fuel cycle. In order to achieve best safety and operational standards these countries with limited human and material resources must put added emphasis on their rational and efficient use. Consequently, the worldwide developments on innovative reactors' systems and improved concepts for fuel utilisation and waste disposal are of substantial interest. Appropriate selections of reactor technology, fuel cycle and decommission strategies are of paramount importance. There are very successful examples of achieving safety and good operational records, so the exchange of experience and co-operation amongst that group of countries is of great interest. Exchanging specific experience and co-operation between the like countries will be additional value relative to the still prevailing equipment supplier-national utility relationships.

  2. Energy calibration issues in nuclear resonant vibrational spectroscopy: observing small spectral shifts and making fast calibrations.

    Science.gov (United States)

    Wang, Hongxin; Yoda, Yoshitaka; Dong, Weibing; Huang, Songping D

    2013-09-01

    The conventional energy calibration for nuclear resonant vibrational spectroscopy (NRVS) is usually long. Meanwhile, taking NRVS samples out of the cryostat increases the chance of sample damage, which makes it impossible to carry out an energy calibration during one NRVS measurement. In this study, by manipulating the 14.4 keV beam through the main measurement chamber without moving out the NRVS sample, two alternative calibration procedures have been proposed and established: (i) an in situ calibration procedure, which measures the main NRVS sample at stage A and the calibration sample at stage B simultaneously, and calibrates the energies for observing extremely small spectral shifts; for example, the 0.3 meV energy shift between the 100%-(57)Fe-enriched [Fe4S4Cl4](=) and 10%-(57)Fe and 90%-(54)Fe labeled [Fe4S4Cl4](=) has been well resolved; (ii) a quick-switching energy calibration procedure, which reduces each calibration time from 3-4 h to about 30 min. Although the quick-switching calibration is not in situ, it is suitable for normal NRVS measurements.

  3. Application of laser cladding method to small-diameter stainless steel pipes in actual nuclear plant

    International Nuclear Information System (INIS)

    Atago, Y.; Yamadera, M.; Tsuji, H.; Shiraiwa, T.; Kanno, M.

    1995-01-01

    Recently, to prevent stress corrosion cracking (SCC) the material of stainless steel (Type 304), a laser cladding method which produces a highly corrosion-resisting coating (cladding) to be formed on the surface of the material was developed. This is applicable to a long distance and narrow space, because of the good accessibility of the YAG (Yttrium-Aluminum Garnet) laser beam that can be transmitted through an optical fiber. In this method, a paste mixed metallic powder and heating resistive organic solvent is firstly placed on the inner surface of a small pipe and then a YAG laser beam transmitted through an optical fiber is irradiated to the paste, which will be melted and formed a clad subsequently, which is excellent in corrosion resistance. Finally, it can be achieved further resistance against the SCC due to the clad layer formed thus on the surface of the material. Recently, this Laser Cladding method was practically and successfully applied to the actual BWR Nuclear Power Plant in Japan. This report introduces the laser cladding technique, the equipments developed for practical application in the field

  4. Evaluation of vibration and vibration fatigue life for small bore pipe in nuclear power plants

    International Nuclear Information System (INIS)

    Wang Zhaoxi; Xue Fei; Gong Mingxiang; Ti Wenxin; Lin Lei; Liu Peng

    2011-01-01

    The assessment method of the steady state vibration and vibration fatigue life of the small bore pipe in the supporting system of the nuclear power plants is proposed according to the ASME-OM3 and EDF evaluation methods. The GGR supporting pipe system vibration is evaluated with this method. The evaluation process includes the filtration of inborn sensitivity, visual inspection, vibration tests, allowable vibration effective velocity calculation and vibration stress calculation. With the allowable vibration effective velocity calculated and the vibration velocity calculated according to the acceleration data tested, the filtrations are performed. The vibration stress at the welding coat is calculated with the spectrum method and compared with the allowable value. The response of the stress is calculated with the transient dynamic method, with which the fatigue life is evaluated with the Miners linear accumulation model. The vibration stress calculated with the spectrum method exceeds the allowable value, while the fatigue life calculated from the transient dynamic method is larger than the designed life with a big safety margin. (authors)

  5. Thermodynamic exergy analysis for small modular reactor in nuclear hybrid energy system

    Directory of Open Access Journals (Sweden)

    Boldon Lauren

    2016-01-01

    Full Text Available Small modular reactors (SMRs provide a unique opportunity for future nuclear development with reduced financial risks, allowing the United States to meet growing energy demands through safe, reliable, clean air electricity generation while reducing greenhouse gas emissions and the reliance on unstable fossil fuel prices. A nuclear power plant is comprised of several complex subsystems which utilize materials from other subsystems and their surroundings. The economic utility of resources, or thermoeconomics, is extremely difficult to analyze, particularly when trying to optimize resources and costs among individual subsystems and determine prices for products. Economics and thermodynamics cannot provide this information individually. Thermoeconomics, however, provides a method of coupling the quality of energy available based on exergy and the value of this available energy – “exergetic costs”. For an SMR exergy analysis, both the physical and economic environments must be considered. The physical environment incorporates the energy, raw materials, and reference environment, where the reference environment refers to natural resources available without limit and without cost, such as air input to a boiler. The economic environment includes market influences and prices in addition to installation, operation, and maintenance costs required for production to occur. The exergetic cost or the required exergy for production may be determined by analyzing the physical environment alone. However, to optimize the system economics, this environment must be coupled with the economic environment. A balance exists between enhancing systems to improve efficiency and optimizing costs. Prior research into SMR thermodynamics has not detailed methods on improving exergetic costs for an SMR coupled with storage technologies and renewable energy such as wind or solar in a hybrid energy system. This process requires balancing technological efficiencies and

  6. Assessment of two small-sized innovative nuclear reactors for electricity generation in Brazil using INPRO methodology

    International Nuclear Information System (INIS)

    Goncalves Filho, Orlando Joao Agostinho; Sefidvash, Farhang

    2009-01-01

    This paper presents the main results of the assessment study of two small-sized innovative reactors for electricity generation in Brazil using the methodology developed under the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), co-ordinated by the International Atomic Energy Agency (IAEA). INPRO was initiated in 2001 and has the main objective of helping to ensure that nuclear energy is available to contribute in a sustainable manner to the energy needs of the 21st century. Brazil joined the INPRO project since its beginning and in 2005 submitted a proposal for the assessment using INPRO methodology of two small-sized reactors (IRIS - International Reactor Innovative and Secure, and FBNR - Fixed Bed Nuclear Reactor) as potential components of an innovative nuclear energy system (INS) completed by a conventional open nuclear fuel cycle based on enriched uranium. The scope of this assessment study was restricted to the reactor component of the INS and to the methodology areas of economics and safety for IRIS, and proliferation resistance and safety for FBNR. The results indicate that both IRIS and FBNR innovative designs comply mostly with the basic principles of the areas assessed and have potential to comply with the remaining ones. (author)

  7. Inhibition of Androgen Receptor Nuclear Localization and Castration-Resistant Prostate Tumor Growth by Pyrroloimidazole-based Small Molecules.

    Science.gov (United States)

    Masoodi, Khalid Z; Xu, Yadong; Dar, Javid A; Eisermann, Kurtis; Pascal, Laura E; Parrinello, Erica; Ai, Junkui; Johnston, Paul A; Nelson, Joel B; Wipf, Peter; Wang, Zhou

    2017-10-01

    The androgen receptor (AR) is a ligand-dependent transcription factor that controls the expression of androgen-responsive genes. A key step in androgen action, which is amplified in castration-resistant prostate cancer (CRPC), is AR nuclear translocation. Small molecules capable of inhibiting AR nuclear localization could be developed as novel therapeutics for CRPC. We developed a high-throughput screen and identified two structurally-related pyrroloimidazoles that could block AR nuclear localization in CRPC cells. We show that these two small molecules, 3-(4-ethoxyphenyl)-6,7-dihydro-5 H -pyrrolo[1,2- a ]imidazole (EPPI) and 3-(4-chlorophenyl)-6,7-dihydro-5 H -pyrrolo[1,2- a ]imidazole (CPPI) can inhibit the nuclear localization and transcriptional activity of AR and reduce the proliferation of AR-positive but not AR-negative prostate cancer cell lines. EPPI and CPPI did not inhibit nuclear localization of the glucocorticoid receptor or the estrogen receptor, suggesting they selectively target AR. In LNCaP tumor xenografts, CPPI inhibited the proliferation of relapsed LNCaP tumors. These findings suggest that EPPI and CPPI could serve as lead structures for the development of therapeutic agents for CRPC. Mol Cancer Ther; 16(10); 2120-9. ©2017 AACR . ©2017 American Association for Cancer Research.

  8. Methods of contrast variation by nuclear polarisation in small-angle neutron scattering: Observation of domains of nuclear polarisation by neutron scattering

    International Nuclear Information System (INIS)

    Leymarie, E.

    2002-11-01

    In this thesis we study the theoretical and experimental aspects of Contrast Variation by Nuclear Polarization (CVNP) applied to small-angle neutron scattering. The basics of neutron scattering theory is developed by highlighting the origin of the CVNP method: the strong spin dependence of thermal neutron scattering, especially on protons. We also present the principles of NMR with a special attention on the method of dynamic nuclear polarization by the solid effect which makes it possible to control the proton polarization and therefore the contrast for neutron scattering. We present a theoretical study of the CVNP method called static which supposes that the nuclear polarization is homogeneous in the sample and constant during the experiment. We show that it allows one to obtain partial structure functions of systems with multiple components, by carrying out several acquisitions with different polarizations on a single sample. For this purpose, we tested a simple device to stabilize the nuclear polarization. We describe finally a new application of the CVNP method called dynamic. In a solution of deuterated glycerol-water containing a small concentration of paramagnetic centres, we showed the existence of domains of polarized protons at the onset of dynamic polarization. This reinforces considerably the coherent scattering of paramagnetic centres. We describe the theoretical reasons explaining the appearance of these domains of polarization, as well as the various techniques used to observe them by neutron scattering. (author)

  9. Radiological, technical and financial planning for decommissioning of small nuclear facilities in Sweden - 16177

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Sjoeblom, Rolf

    2009-01-01

    On November 1 2008, a new ordinance came into force in Sweden. It extends the implementation of nuclear liability to all nuclear facilities and companies, regardless of size. The Government has authorized the Swedish Radiation Safety Authority (SSM) to issue further regulation as warranted and appropriate, and commissioned the same Authority to oversee the implementation. Consequently, SSM is presently conducting research in order to establish a basis for the implementation of the ordinance to smaller facilities and enterprises. The goal is to enable finance to be assured in an efficient manner so that any burden on the companies is as small as possible. Thus, 'functional requirements' are identified, and used as a basis for various investigations. The aspects include technical and cost calculation prerequisites, as well as various domains of law: the environmental code, radiation and nuclear safety, financial reporting, and criminal law. It is found that the basis for the differentiation among the facility operators and owners should be the cost and the associated uncertainty. Thus, a cost calculation will have to be carried out by all. It should be based on available standards and guidance documents. It is found that this is a requirement that already exists elsewhere in the legislation, and thus no additional burden is imposed on the companies. It is found that segregated funds is the preferred option for long-term liabilities. Securities are suitable for short-term liabilities provided that the economy of the company in question is sound. Securities might also be used for long-term liabilities to cover uncertainty. It is proposed that a de minimis limit of at least kSEK 25 (about keuros 2,4 and k$ 3,4) is used. An important reason for this is that lower limits might be incompatible with the rules for financial reporting. It is also proposed that securities might be used also for long-term commitments if the total environmental liability does not exceed 1

  10. Book of Abstracts of 6th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    International Nuclear Information System (INIS)

    Cavlina, N.; Pevec, D.; Bajs, T.

    2006-01-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production. Session topics reflect some current emphasis, such as country energy needs, new reactor technologies, operation and safety of the operating nuclear power plants, environmental advantages, and organizational, educational and social requirements for countries with small and medium electricity grid. In order to achieve the best safety and operational standards, these countries must put added emphasis on rational and efficient use of human and material resources. Therefore, the conference also focuses on the exchange of experience and co-operation in the fields of safety culture, liability, regulatory practice and radioactive waste management

  11. Book of Abstracts of 6th International Conference: Nuclear Option in Countries with Small and Medium Electricity Grids

    Energy Technology Data Exchange (ETDEWEB)

    Cavlina, N; Pevec, D; Bajs, T [eds.

    2006-07-01

    The conference is organized with intention to focus on specific aspects of usage of nuclear energy for electricity production. Session topics reflect some current emphasis, such as country energy needs, new reactor technologies, operation and safety of the operating nuclear power plants, environmental advantages, and organizational, educational and social requirements for countries with small and medium electricity grid. In order to achieve the best safety and operational standards, these countries must put added emphasis on rational and efficient use of human and material resources. Therefore, the conference also focuses on the exchange of experience and co-operation in the fields of safety culture, liability, regulatory practice and radioactive waste management.

  12. U1 small nuclear RNA variants differentially form ribonucleoprotein particles in vitro.

    Science.gov (United States)

    Somarelli, Jason A; Mesa, Annia; Rodriguez, Carol E; Sharma, Shalini; Herrera, Rene J

    2014-04-25

    The U1 small nuclear (sn)RNA participates in splicing of pre-mRNAs by recognizing and binding to 5' splice sites at exon/intron boundaries. U1 snRNAs associate with 5' splice sites in the form of ribonucleoprotein particles (snRNPs) that are comprised of the U1 snRNA and 10 core components, including U1A, U1-70K, U1C and the 'Smith antigen', or Sm, heptamer. The U1 snRNA is highly conserved across a wide range of taxa; however, a number of reports have identified the presence of expressed U1-like snRNAs in multiple species, including humans. While numerous U1-like molecules have been shown to be expressed, it is unclear whether these variant snRNAs have the capacity to form snRNPs and participate in splicing. The purpose of the present study was to further characterize biochemically the ability of previously identified human U1-like variants to form snRNPs and bind to U1 snRNP proteins. A bioinformatics analysis provided support for the existence of multiple expressed variants. In vitro gel shift assays, competition assays, and immunoprecipitations (IPs) revealed that the variants formed high molecular weight assemblies to varying degrees and associated with core U1 snRNP proteins to a lesser extent than the canonical U1 snRNA. Together, these data suggest that the human U1 snRNA variants analyzed here are unable to efficiently bind U1 snRNP proteins. The current work provides additional biochemical insights into the ability of the variants to assemble into snRNPs. Copyright © 2014 Elsevier B.V. All rights reserved.

  13. Oxidation behaviour of U2Ti alloy in dry air

    International Nuclear Information System (INIS)

    Roy, S.P.; Gupta, N.K.; Jat, Ram Avtar; Parida, S.C.; Mukerjee, S.K.

    2016-01-01

    U 2 Ti alloy is being considered as promising storage material for storage of hydrogen isotopes. However, the absorption capacity of this reactive alloy can be affected due to presence of oxygen in the process gas. Hence, it is necessary to know the kinetic of this alloy in presence of oxygen. In this study, U 2 Ti alloy was prepared by arc melting method followed by vacuum annealing. The alloy was characterized by XRD, SEM and EDX methods. The isothermal oxidation behaviour of U 2 Ti alloy was investigated in the temperature range of 548-623 K in dry air for 24 hours by using thermo gravimetric technique. The oxidation curves are shown. The oxidation curves were analysed using the rate equation: (Δm/a) n = kt, where, (Δm/a) is the mass gain per unit area, n is the power exponent, k is the rate constant and t is time in (seconds). Analysis of the results shows that the oxidation reaction follows linear rate law (n ~ 1). Using the linear rate law, the rate constant (k) of oxidation reaction was evaluated at each temperature in the range 548-623 K. The variation of (ln k) with reciprocal temperature is shown. The activation energy of this oxidation reaction in the temperature range 548-623 K was calculated using the Arrhenius equation and found to be 76 kJ/mol. The XRD analysis of the oxidation products was found to be U 3 O 8 and TiO 2 . (author)

  14. Ising versus S U (2) 2 string-net ladder

    Science.gov (United States)

    Vidal, Julien

    2018-03-01

    We consider the string-net model obtained from S U (2) 2 fusion rules. These fusion rules are shared by two different sets of anyon theories. In this paper, we study the competition between the two corresponding non-Abelian quantum phases in the ladder geometry. A detailed symmetry analysis shows that the nontrivial low-energy sector corresponds to the transverse-field cluster model that displays a critical point described by the s o (2) 1 conformal field theory. Other sectors are obtained by freezing spins in this model.

  15. Multi-stage-flash desalination plants of relative small performance with integrated pressurized water reactors as a nuclear heat source

    International Nuclear Information System (INIS)

    Petersen, G.; Peltzer, M.

    1977-01-01

    In the Krupp-GKSS joint study MINIPLEX the requirements for seawater-desalination plants with a performance in the range of 10 000 to 80 000 m 3 distillate per day heated by a nuclear reactor are investigated. The reactor concept is similar to the Integrated Pressurized Water Reactor (IPWR) of the nuclear ship OTTO HAHN. The design study shows that IPWR systems have specific advantages up to 200 MWth compared to other reactor types at least being adapted for single- and dual-purpose desalination plants. The calculated costs of the desalinated water show that due to fuel cost advantages of reactors small and medium nuclear desalination plants are economically competetive with oil-fired plants since the steep rise of oil price in autumn 1973. (author)

  16. The Arabidopsis splicing factors, AtU2AF65, AtU2AF35, and AtSF1 shuttle between nuclei and cytoplasms

    KAUST Repository

    Park, Hyo-Young

    2017-04-21

    The Arabidopsis splicing factors, AtU2AF65, AtU2AF35, and AtSF1 shuttle between nuclei and cytoplasms. These proteins also move rapidly and continuously in the nuclei, and their movements are affected by ATP depletion. The U2AF65 proteins are splicing factors that interact with SF1 and U2AF35 proteins to promote U2snRNP for the recognition of the pre-mRNA 3\\' splice site during early spliceosome assembly. We have determined the subcellular localization and movement of these proteins\\' Arabidopsis homologs. It was found that Arabidopsis U2AF65 homologs, AtU2AF65a, and AtU2AF65b proteins interact with AtU2AF35a and AtU2AF35b, which are Arabidopsis U2AF35 homologs. We have examined the mobility of these proteins including AtSF1 using fluorescence recovery after photobleaching and fluorescence loss in photobleaching analyses. These proteins displayed dynamic movements in nuclei and their movements were affected by ATP depletion. We have also demonstrated that these proteins shuttle between nuclei and cytoplasms, suggesting that they may also function in cytoplasm. These results indicate that such splicing factors show very similar characteristics to their human counterparts, suggesting evolutionary conservation.

  17. The Arabidopsis splicing factors, AtU2AF65, AtU2AF35, and AtSF1 shuttle between nuclei and cytoplasms

    KAUST Repository

    Park, Hyo-Young; Lee, Keh Chien; Jang, Yun Hee; Kim, SoonKap; Thu, May Phyo; Lee, Jeong Hwan; Kim, Jeong-Kook

    2017-01-01

    The Arabidopsis splicing factors, AtU2AF65, AtU2AF35, and AtSF1 shuttle between nuclei and cytoplasms. These proteins also move rapidly and continuously in the nuclei, and their movements are affected by ATP depletion. The U2AF65 proteins are splicing factors that interact with SF1 and U2AF35 proteins to promote U2snRNP for the recognition of the pre-mRNA 3' splice site during early spliceosome assembly. We have determined the subcellular localization and movement of these proteins' Arabidopsis homologs. It was found that Arabidopsis U2AF65 homologs, AtU2AF65a, and AtU2AF65b proteins interact with AtU2AF35a and AtU2AF35b, which are Arabidopsis U2AF35 homologs. We have examined the mobility of these proteins including AtSF1 using fluorescence recovery after photobleaching and fluorescence loss in photobleaching analyses. These proteins displayed dynamic movements in nuclei and their movements were affected by ATP depletion. We have also demonstrated that these proteins shuttle between nuclei and cytoplasms, suggesting that they may also function in cytoplasm. These results indicate that such splicing factors show very similar characteristics to their human counterparts, suggesting evolutionary conservation.

  18. Estimation of thawing cryolithic area with numerical modeling in 3D geometry while exploiting underground small nuclear power plant

    Directory of Open Access Journals (Sweden)

    Melnikov N. N.

    2016-03-01

    Full Text Available The paper presents results on 3D numerical calculation of a thermal task related to assessing a thawing area when placing modules with reactor and steam-turbine facility of a small nuclear power plant in thickness of permafrost rocks. The paper discusses influence of the coefficient of thermal conductivity for large-scaled underground excavations lining and cryolithic area porosity on thawing depth and front movement velocity under different spatial directions

  19. Analytic solutions of QCD evolution equations for parton cascades inside nuclear matter at small x

    International Nuclear Information System (INIS)

    Geiger, K.

    1994-01-01

    An analytical method is presented to solve generalized QCD evolution equations for the time development of parton cascades in a nuclear environment. In addition to the usual parton branching processes in vacuum, these evolution equations provide a consistent description of interactions with the nuclear medium by accounting for stimulated branching processes, fusion, and scattering processes that are specific to QCD in a medium. Closed solutions for the spectra of produced partons with respect to the variables time, longitudinal momentum, and virtuality are obtained under some idealizing assumptions about the composition of the nuclear medium. Several characteristic features of the resulting parton distributions are discussed. One of the main conclusions is that the evolution of a parton shower in a medium is dilated as compared to free space and is accompanied by an enhancement of particle production. These effects become stronger with increasing nuclear density

  20. Closure Plan for Corrective Action Unit 109: U-2bu Subsidence Crater Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Shannon Parsons

    1999-03-01

    The U-2bu subsidence crater, Corrective Action Unit 109, will be closed in accordance with the Resource Conservation and Recovery Act, the Nevada Division of Environmental Protection operational permit, and the Federal Facilities Agreement and Consent Order. The U-2bu subsidence crater is located in Area 2 of the Nevada Test Site. It was created in 1971 by an underground nuclear test with the name Miniata. The crater has a diameter of 288 meters (944 feet) and an approximate depth of 35 meters (115 feet). The subsidence crater was used as a land disposal unit for radioactive and hazardous waste from 1973 to 1988. Site disposal history is supported by memorandums, letters, and personnel who worked at the Nevada Test Site at the time of active disposal. Closure activities will include the excavation and disposal of impacted soil form the tip of the crater. Upon completion of excavation, verification samples will be collected to show that lead has been removed to concentrations be low regulatory action level. The area will then be backfilled and a soil flood diversion berm will be constructed, and certified by an independent professional engineer as to having followed the approved Closure Plan.

  1. Workplace activities to promote small attempts for safety. Toward development of safety culture in a nuclear power plant

    International Nuclear Information System (INIS)

    Fukui, Hirokazu; Sugiman, Toshio

    2007-01-01

    Activities that could possibly grow into learning activities for developing safety culture were explored by intensive fieldwork in a nuclear power plant depending on Engestroem's activity theory. As a first step to achieve this goal, workers' small attempts that might contribute to nurturing a safety culture were investigated. Eight kinds of activity were observed and interpreted as having the possibility to facilitate small recognition and small practice, i.e., activities including (1) workgroup as community, (2) other workgroups and other departments as community, (3) meeting drawing remarks as mediating artifacts, (4) study session and Off-the-Job-Training as mediating artifact, (5) award as mediating artifact, (6) extended leave as mediating artifact, (7) check sheet as mediating artifact, and (8) skill-transfer system as mediating artifact. (author)

  2. The Fourier U(2 Group and Separation of Discrete Variables

    Directory of Open Access Journals (Sweden)

    Kurt Bernardo Wolf

    2011-06-01

    Full Text Available The linear canonical transformations of geometric optics on two-dimensional screens form the group Sp(4,R, whose maximal compact subgroup is the Fourier group U(2_F; this includes isotropic and anisotropic Fourier transforms, screen rotations and gyrations in the phase space of ray positions and optical momenta. Deforming classical optics into a Hamiltonian system whose positions and momenta range over a finite set of values, leads us to the finite oscillator model, which is ruled by the Lie algebra so(4. Two distinct subalgebra chains are used to model arrays of N^2 points placed along Cartesian or polar (radius and angle coordinates, thus realizing one case of separation in two discrete coordinates. The N^2-vectors in this space are digital (pixellated images on either of these two grids, related by a unitary transformation. Here we examine the unitary action of the analogue Fourier group on such images, whose rotations are particularly visible.

  3. Hydrogen absorption-desorption properties of U2Ti

    International Nuclear Information System (INIS)

    Yamamoto, Takuya; Tanaka, Satoru; Yamawaki, Michio

    1990-01-01

    Hydrogen absorption-desorption properties of U 2 Ti intermetallic compound was examined over the temperature range of 298 to 973 K and at hydrogen pressures below 10 5 Pa. It absorbs hydrogen up to 7.6 atoms per F.U. (formula unit) by two step reactions and hence each desorption isotherm is separated into two plateau regions. In the first plateau, a newly-found ternary hydride is formed, where the hydrogen concentration, c H , reaches 2.4 H atoms/F.U. In the second plateau, UH 3 is formed and c H reaches 7.6 H atoms/F.U. The specimen is disintegrated into fine powder in the second plateau, while in the first plateau the ternary hydride which was identified to be UTi 2 H x (x=4.8 to 6.2) showed high durability against powdering. It is predicted that UTi 2 can be suitable material for tritium storage. (orig.)

  4. Buyer's participation and well developed domestic infrastructure. Keys to successful introduction of nuclear power in a small country

    International Nuclear Information System (INIS)

    Numminen, K.; Laine, P.

    1983-01-01

    Nuclear power is advantageous for a small country such as Finland which does not possess indigenous fossil fuel. For instance, the cost of imports required by nuclear fuel is essentially smaller than the cost of production of electric energy based on coal or fuel oil. In Finland the advantageousness of nuclear power was already proved in the 1950s but before starting the first power plant project it took 15 years to develop step by step the required infrastructure: building the research institutes and training their staff, creating connections to the international organizations and elsewhere abroad, training Finnish design staff, developing the domestic industry to the high quality required by nuclear power, and establishing the necessary authorities and public administration. Thanks to thorough preparation the implementation of the plant projects progressed at a good pace in the 1970s. The lesson learned from operation of the plants is that in a small country - located far from its main supplier - the staff at the plant and the supporting staff in the power company have to be able to analyse the problems occurring, usually in the conventional equipment, and carry out quick repairs without aid from the main supplier. This requires a high level of educational attainment from the staff and the best way to achieve this is for the staff to participate in the design and construction as much as possible already in the implementation phase. In order to maintain high availability, the capability of the domestic industry must also be good - especially in the fields of mechanical industry and electronics. In Finland over 30% of electric energy was produced in 1981 by four nuclear units. Two of these were built as manifold east-west adjustment work with the Soviet supplier and the other two are of Swedish origin

  5. Coolant radiolysis studies in the high temperature, fuelled U-2 loop in the NRU reactor

    International Nuclear Information System (INIS)

    Elliot, A.J.; Stuart, C.R.

    2008-06-01

    An understanding of the radiolysis-induced chemistry in the coolant water of nuclear reactors is an important key to the understanding of materials integrity issues in reactor coolant systems. Significant materials and chemistry issues have emerged in Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and CANDU reactors that have required a detailed understanding of the radiation chemistry of the coolant. For each reactor type, specific computer radiolysis models have been developed to gain insight into radiolysis processes and to make chemistry control adjustments to address the particular issue. In this respect, modelling the radiolysis chemistry has been successful enough to allow progress to be made. This report contains a description of the water radiolysis tests performed in the U-2 loop, NRU reactor in 1995, which measured the CHC under different physical conditions of the loop such as temperature, reactor power and steam quality. (author)

  6. Facile CO cleavage by a multimetallic CsU2 nitride complex

    International Nuclear Information System (INIS)

    Falcone, Marta; Scopelliti, Rosario; Mazzanti, Marinella; Kefalidis, Christos E.; Maron, Laurent

    2016-01-01

    Uranium nitrides are important materials with potential for application as fuels for nuclear power generation, and as highly active catalysts. Molecular nitride compounds could provide important insight into the nature of the uranium-nitride bond, but currently little is known about their reactivity. In this study, we found that a complex containing a nitride bridging two uranium centers and a cesium cation readily cleaved the C≡O bond (one of the strongest bonds in nature) under ambient conditions. The product formed has a [CsU 2 (μ-CN)(μ-O)] core, thus indicating that the three cations cooperate to cleave CO. Moreover, the addition of MeOTf to the nitride complex led to an exceptional valence disproportionation of the CsU IV -N-U IV core to yield CsU III (OTf) and [MeN=U V ] fragments. The important role of multimetallic cooperativity in both reactions is illustrated by the computed reaction mechanisms.

  7. Small specimen measurements of dynamic fracture toughness of heavy section steels for nuclear pressure vessel

    International Nuclear Information System (INIS)

    Tanaka, Y.; Iwadate, T.; Suzuki, K.

    1987-01-01

    This study presents the dynamic fracture toughness properties (KId) of 12 heats of RPV steels measured using small specimens and analysed based on the current research. The correlation between the KId test and other engineering small specimen tests such as Charpy test and drop weight test are also discussed and a method to predict the KId value is presented. (orig./HP)

  8. Management of the pediatric nuclear medicine patient (or children are not small adults)

    International Nuclear Information System (INIS)

    Kieffer, C.T.; Suto, P.A.

    1983-01-01

    The first of a four-part continuing education series on pediatric nuclear medicine is presented. Included are: (1) clinical indications for performing nuclear medicine studies in children; (2) comparison of nuclear medicine procedures for adult and pedicatric patients; (3) appropriate radiopharmaceuticals for performing pediatric studies; (4) radiation protection techniques (5) the principles of pediatric radiopharmaceutical dose calculation and common calculation methods; (6) possible injection sites and administration methods (7) radiopharmaceutical clearance times and imaging times in adults and children; (8) the collimators of choice for most procedures performed in children; (9) certain behaviors exhibited by children according to their stage of emotional development and children's response to the hospital setting; and (10) patient immobilization techniques and advantages of physical restraint over sedation

  9. Market potential of small and medium-size nuclear reactors as combined heat and power plants in Europe

    International Nuclear Information System (INIS)

    Candeli, R.; Leuchs, D.; Garribba, S.F.; Hansen, U.; Lefevre, J.C.; Schoen, R.; Vivante, C.

    1988-01-01

    The preliminary results are presented concerning a study launched by the Commission of the European Communities to assess the potential market of small and medium-size nuclear reactors through EC member countries. The study was aimed at identifying those factors that may have a role in shaping the eventual deployment and diffusion of this class of nuclear reactors. In a first phase, attention focused on modular high-temperature gas-cooled reactors that would be installed to produce low-temperature heat and power. Federal Republic of Germany, Italy and France are the countries for which the investigation has been completed. The time span of interest is up to the year 2020. Referring to this horizon, an appraisal has been made of the number of nuclear units which could come on line to cope with energy demand and their timing. Through the study a distinction is made between technical potential, economic potential, and effective market potential. It is understood indeed that both economic competitiveness towards other energy sources and also institutional or organizational factors may restrict the market which could become accessible and would be covered by the new nuclear plants. (orig.)

  10. Role of small lead-cooled fast reactors for international deployment in worldwide sustainable nuclear energy supply

    International Nuclear Information System (INIS)

    Sienicki, J.J.; Wade, D.C.; Moisseytsev, A.

    2008-01-01

    Most recently, the global nuclear energy partnership (GNEP) has identified, as one of its key objectives, the development and demonstration of concepts for small and medium-sized reactors (SMRs) that can be globally deployed while assuring a high level of proliferation resistance. Lead-cooled systems offer several key advantages in meeting these goals. The small lead-cooled fast reactor concept known as the small secure transportable autonomous reactor (SSTAR) has been under ongoing development as part of the US advanced nuclear energy systems programs. Meeting future worldwide projected energy demands during this century (e.g., 1000 to 2000 GWe by 2050) in a sustainable manner while maintaining CO2 emissions at or below today's level will require massive deployments of nuclear reactors in non-fuel cycle states as well as fuel cycle states. The projected energy demands of non-fuel cycle states will not be met solely through the deployment of Light Water Reactors (LWRs) in those states without using up the world's resources of fissile material (e.g., known plus speculative virgin uranium resources = 15 million tonnes). The present U.S. policy is focused upon domestic deployment of large-scale LWRs and sodium-cooled fast spectrum Advanced Burner Reactors (ABRs) working in a symbiotic relationship that burns existing fissile material while destroying the actinides which are generated. Other major nuclear nations are carrying out the development and deployment of SFR breeders as witness the planning for SFR breeder deployments in France, Japan, China, India, and Russia. Small (less that 300 MWe) and medium (300 to 700 MWe) size reactors are better suited to the growing economies and infrastructures of many non-fuel cycle states and developing nations. For those deployments, fast reactor converters which are fissile self-sufficient by creating as much fissile material as they consume are preferred to breeders that create more fissile material than they consume. Thus

  11. Rotatable Small Permanent Magnet Array for Ultra-Low Field Nuclear Magnetic Resonance Instrumentation: A Concept Study.

    Science.gov (United States)

    Vogel, Michael W; Giorni, Andrea; Vegh, Viktor; Pellicer-Guridi, Ruben; Reutens, David C

    2016-01-01

    We studied the feasibility of generating the variable magnetic fields required for ultra-low field nuclear magnetic resonance relaxometry with dynamically adjustable permanent magnets. Our motivation was to substitute traditional electromagnets by distributed permanent magnets, increasing system portability. The finite element method (COMSOL®) was employed for the numerical study of a small permanent magnet array to calculate achievable magnetic field strength, homogeneity, switching time and magnetic forces. A manually operated prototype was simulated and constructed to validate the numerical approach and to verify the generated magnetic field. A concentric small permanent magnet array can be used to generate strong sample pre-polarisation and variable measurement fields for ultra-low field relaxometry via simple prescribed magnet rotations. Using the array, it is possible to achieve a pre-polarisation field strength above 100 mT and variable measurement fields ranging from 20-50 μT with 200 ppm absolute field homogeneity within a field-of-view of 5 x 5 x 5 cubic centimetres. A dynamic small permanent magnet array can generate multiple highly homogeneous magnetic fields required in ultra-low field nuclear magnetic resonance (NMR) and magnetic resonance imaging (MRI) instruments. This design can significantly reduce the volume and energy requirements of traditional systems based on electromagnets, improving portability considerably.

  12. New Approach to Enhance an Effect of Condition Monitoring of Mid/Small Size Rotating Equipment in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Shin You Soo; Chang, Hee Seung [KHNP, Daejeon (Korea, Republic of)

    2016-05-15

    Condition monitoring for small and medium-size rotating equipment is mainly done by a patrol inspection and a vibration measurement. These methods are useful to recognize a significant change in a sound, temperature and vibration amplitude on the bearing housing. However, such a significant change shows an abnormal condition just before failure so that there is not much time to take a right action to recover. In other words, there is a severe damage when someone detects the phenomenon. These methods are good way to detect a flaw but too late to fix. It can't detect early recognition of defect To enhance the effect of condition monitoring and recognize a defect earlier, an integrated measurement including high band frequency analysis is required. It will be implemented at one of nuclear power plants in Korea as a pilot to verify an effect and applicability at nuclear power plants.

  13. On the theoretical description of nuclear quadrupole coupling in Π states of small molecules

    Czech Academy of Sciences Publication Activity Database

    Fišer, J.; Polák, Rudolf

    2013-01-01

    Roč. 425, NOV 2013 (2013), s. 126-133 ISSN 0301-0104 Institutional support: RVO:61388955 Keywords : Π States * Nuclear quadrupole coupling constant * Electric dipole moment Subject RIV: CF - Physical ; Theoretical Chemistry Impact factor: 2.028, year: 2013

  14. The use of small modular nuclear reactors for Canadian Oil Sands applications: a proposal and way forward

    Energy Technology Data Exchange (ETDEWEB)

    Attwood, D., E-mail: ergo.applications@gmail.com [Human Factors Applications, Toronto, Ontario (Canada); Moledina, M., E-mail: mohamedmoledina@rogers.com [Consultant, Toronto, Ontario (Canada)

    2013-07-01

    It has been estimated that Canada's Oil Sands contain between 160 and 200 billion barrels of oil reserves - the second largest accumulation of oil in the world after Saudi Arabia. It is also estimated that by 2015, output from the oil sands should increase from about 1 million barrels per day (mbbl/day) to approximately 4 mbbl/day. However, Canada and the world have to pay a price for oil extraction from the sands.It is estimated that about 40 cubic metres of natural gas as fuel must be burned for each barrel of synthetic crude produced. Therefore, if oil sands production did reach 4 mbbl/day, natural gas use for oil production could seriously limit exports of natural gas to the US. It has also been estimated that every barrel of synthetic oil pollutes about 950 liters of fresh water and emits about 100 Kg of Carbon Dioxide (CO{sub 2}) along with other pollutants. Clearly an alternate source of energy is required for oil sands production that will allow our natural gas to be put to better use while simultaneously sustaining our environment. The energy must be continuously obtainable and not be subject to the intermittent availability of wind or sunlight. Nuclear energy is the obvious choice. Nuclear energy for power generation has been prevalently used around the world since the 1950's. Today, there are more than 440 Nuclear Power Plants(NPPs) operating safely worldwide. Each has different characteristics that would make them comparatively acceptable for operation in Northern Canada. This paper will briefly review the various types of nuclear plants that are currently in operation or are being licensed worldwide,as well as those that are proposed for operation in the near future including small nuclear power reactors (< 300 me). Moreover, it will propose a list of the NPP characteristics that are best suited to oil sands operation. This will lead to a proposal to encourage the development of small modular reactors (SMRs) for installation in oil sands

  15. Multivariant strategy study for the use of plutonium in a nuclear programme: the case of the large and small country

    International Nuclear Information System (INIS)

    Dievoet, J. van; Kunsch, P.; Verraver, J.

    1982-01-01

    The results of a multicriteria study into the desirability of introducing a plutonium using FBR programme into two fictitious countries, one large and one small, are presented. The strategy discussed concerns only base load electrical energy production with both fossil and nuclear fuels. A number of independent social, economic and political objectives need to be considered in the choice of power plant programme. These include the price of fuel, the safety of fuel supply, the balance of services, the new investments needed and the impact of new technology. (U.K.)

  16. Multinode analysis of small breaks for B and W's 205-fuel-assembly nuclear plants with internals vent valves

    International Nuclear Information System (INIS)

    Jones, R.C.; Dunn, B.M.; Parks, C.E.

    1976-03-01

    Multinode analyses were conducted for several small breaks in the reactor coolant system of B and W's 205-fuel-assembly nuclear plants with internals vent valves. The multinode blowdown code CRAFT was used to evaluate the hydrodynamics and transient water inventories of the reactor coolant system. The FOAM code was used to compute a swell level history for the core, and the THETA1-B code was used to perform transient fuel pin thermal calculations. Curves showing the parameters of interest are presented. The results are well within the Final Acceptance Criteria

  17. Multinode analysis of small breaks for B and W's 145-fuel-assembly nuclear plants with internals vent valves

    International Nuclear Information System (INIS)

    Parks, C.E.; Allen, R.J.; Cartin, L.R.

    1976-03-01

    Multinode analyses were conducted for several small breaks in the reactor coolant system of B and W's 145 fuel-assembly nuclear plants with internals vent valves. The multinode blowdown code CRAFT was used to evaluate the hydrodynamics and transient water inventories of the reactor coolant system. The FOAM code was used to compute a swell level history for the core, and the THETA1-B code was used to perform transient fuel pin thermal calculations. Curves showing the parameters of interest are presented. These results are well within the Final Acceptance Criteria

  18. Project of SVBR-75/100 reactor plant with improved safety for nuclear sources of small and medium power

    International Nuclear Information System (INIS)

    Dragunov, Yu. G.; Stepanov, V. S.; Klimov, N. N.; Dedul, A. V.; Bolvanchikov, S. N.; Zrodnikov, A. V.; Tolhinsky, G. I.; Komlev, O. G.

    2004-01-01

    As a result of the joint work performed recently by FSUE OKB Gidropress, SNC RF-IPPE and other organizations the technical feasibility is shown for creation and usage in nuclear power engineering of the unified reactor plant (RP) SVBR-75/100 with fast neutron reactor core and lead-bismuth coolant (LBC) in the primary circuit. Technical design of SVBR-75/100 reactor plant is based on the following: 50-year operation experience in development and operation of RP with LBC for nuclear submarines; experience in development and operation of fast reactor with sodium coolant; experience in optimization of LBC technology at nuclear submarines and ground-based test benches; conceptual design of SVBR-75 reactor plant (for renovation of Units 2, 3 and 4 of Novovoronezh NPP). Technical solutions laid down in the basis of SVBR-75/100 reactor plant design are oriented towards the industrial basis, structural materials existing in Russia, as well as the unique LBC technology with experimental and practical support. The concept of SVBR-75/100 reactor plant safety assurance is based on the following provisions: maximum usage of inherent safety supported by physical features of fast neutron reactor, chemically inert LBC in the primary circuit, integral layout and special design solutions; maximum possible combination of normal operation and safety functions in RP systems. Small power of SVBR-75/100 RP makes it possible to manufacture the complete set of RP main equipment at the factory and delivery it to NPP site as-finished practically using any transport including railway. Possible fields of application of SVBR-75/100 reactor plants: modular NPPs of different power; renovation of NPPs with light water reactors exhausted their service life; independent nuclear power sources for different applications (ground-based nuclear water-desalinating plants, etc. )(author)

  19. Data processing system for small and medium sized clinical chemistry and nuclear medical units

    Energy Technology Data Exchange (ETDEWEB)

    Mariss, P; Haubold, E; Porth, A J

    1987-06-01

    A computer system, in clinical use for over 5 years, with a group practice specializing in laboratory-nuclear medicine is described for its hardware and software configuration. In addition to the conventional tasks of a computer system (patient data acquisition, issuance of worklists, result input, plausibility control, quality assurance, findings documentation), an integrated word processing system was developed for nuclear medicine in-vitro and in-vivo diagnosis. In addition, the computer system masters major administrative tasks, such as private and panel accounts, account reminders payments to suppliers, etc. the hardware and data bank are designed in a manner which permits direct data access over a period of 18 to 21 months.

  20. A full-configuration-interaction nuclear orbital approach and application for small doped He clusters

    Energy Technology Data Exchange (ETDEWEB)

    Lara-Castells, M. P. de, E-mail: delara@iff.csic.es; Aguirre, N. F., E-mail: delara@iff.csic.es; Delgado-Barrio, G., E-mail: delara@iff.csic.es; Villarreal, P., E-mail: delara@iff.csic.es [Instituto de Física Fundamental (CSIC), Serrano 123, 28006 Madrid (Spain); Mitrushchenkov, A. O. [Université Paris-Est, Laboratoire Modélisation et Simulation Multi Echelle, MSME UMR 8208 CNRS, 5 bd Descartes, 77454 Marne-la-Vallée (France)

    2015-01-22

    An efficient full-configuration-interaction 'nuclear orbital' treatment was developed as a benchmark quantum-chemistry-like method to calculate, ground and excited, fermionic 'solvent' wave-functions and applied to {sup 3}He{sub N} clusters with atomic or molecular impurities [J. Chem. Phys. (Communication) 125, 221101 (2006)]. The main difficulty in handling doped {sup 3}He{sub N} clusters lies in the Fermi-Dirac nuclear statistics, the wide amplitudes of the He-dopant and He-He motions, and the hard-core He-He interaction at short distances. This paper overviews the theoretical approach and its recent applications to energetic, structural and spectroscopic aspects of different dopant-{sup 3}He{sub N} clusters. Preliminary results by using the latest version of the FCI-NO computational implementation, to bosonic Cl{sub 2}(X)-({sup 4}He){sub N} clusters, are also shown.

  1. Reactor type choice and characteristics for a small nuclear heat and electricity co-generation plant

    International Nuclear Information System (INIS)

    Liu Kukui; Li Manchang; Tang Chuanbao

    1997-01-01

    In China heat supply consumes more than 70 percent of the primary energy resource, which makes for heavy traffic and transportation and produces a lot of polluting materials such as NO x , SO x and CO 2 because of use of the fossil fuel. The utilization of nuclear power into the heat and electricity co-generation plant contributes to the global environmental protection. The basic concept of the nuclear system is an integral type reactor with three circuits. The primary circuit equipment is enclosed in and linked up directly with reactor vessel. The third circuit produces steam for heat and electricity supply. This paper presents basic requirements, reactor type choice, design characteristics, economy for a nuclear co-generation plant and its future application. The choice of the main parameters and the main technological process is the key problem of the nuclear plant design. To make this paper clearer, take for example a double-reactor plant of 450 x 2MW thermal power. There are two sorts of main technological processes. One is a water-water-steam process. Another is water-steam-steam process. Compared the two sorts, the design which adopted the water-water-steam technological process has much more advantage. The system is simplified, the operation reliability is increased, the primary pressure reduces a lot, the temperature difference between the secondary and the third circuits becomes larger, so the size and capacity of the main components will be smaller, the scale and the cost of the building will be cut down. In this design, the secondary circuit pressure is the highest among that of the three circuits. So the primary circuit radioactivity can not leak into the third circuit in case of accidents. (author)

  2. Development of small size wall decontamination robot systems in nuclear power plants

    International Nuclear Information System (INIS)

    Fujita, Tsuneaki; Takahashi, Tsuyosi

    2004-01-01

    This paper describes the development of wall decontamination robot systems for nuclear power plants. In nuclear power plants, it is required to reduce maintenance costs, including annual inspection, repairs and so on. Most of such maintenance activities are actually performed after decontamination processes are completed. In particular, the decontamination process of reactor wells is very important for reducing the radiation exposure of human workers. In the past, decontamination of reactor wells used to be done by extra large machine and tools, which caused long working hours and tiresome works. It was one of the reasons maintenance costs couldn't have been easily reduced. There are narrow spaces in the reactor wells that have to be decontaminated by human workers. In order to minimize the radiation exposure to humans, wall decontamination robot systems have been developed. The decontamination robots have rolled brushes and suction mechanisms and are capable of removing contaminants attached to the wall surface of the reactor wells. By making the robots smaller, it is possible to work in narrower spaces. In this paper, the effectiveness of decontamination by the developed robots is shown through experiments in the actual nuclear power plants. (author)

  3. Arguments for the installation of small LWR nuclear power plants in developing countries

    International Nuclear Information System (INIS)

    Lezenik, B.

    1977-01-01

    The differences disclosed in the IAEA-Report ''Market Survey...'' before and after the drastic increase of the oil price in 1973 indicate most unequivocally the growing economic profits of the application of nuclear power plants with smaller output. The report furthermore demonstrates in clear terms the benefits of a long-term fuel arrangement as is applied for nuclear power plants. Following these basic considerations, according to which the construction of nuclear power plants appears to be reasonable, economically speaking, the next important criterion having priority, as far as the technical aspect is concerned, is the question concerning the largest possible unit to be integrated into the grid. So as to ensure a steady mains power supply, the structure of operating power plant types, their number and unit sizes as well as their controllability and load-following behavior have to be coordinated with one another individually. As an example for the nuclear power plant Borssele (450 MW - PWR) which has been in operation since 1973, basic control concepts are outlined which together with the load-following behavior of this reactor meet the grid requirements. This is to demonstrate the flexible application of this reactor type. Manufacturing and operating experience as well as the accumulated know-how concerning design and construction of large plants in the 1200/1300 MW class offer a broad basis for the standardization of the smaller LWR-plants. The experience gained with proven components and approved systems for the fully standardized 1200/1300 MW reactors equally guarantees operating reliability and availability, since differences in output are realized by means of additive modifications of the primary system components. A comparison with, and an interpretation of, the essential design data outline the progress achieved in the standardization process. So as to ensure as efficient as possible implementation of the construction procedure, and the application of

  4. KDM6B Elicits Cell Apoptosis by Promoting Nuclear Translocation of FOXO1 in Non-Small Cell Lung Cancer

    Directory of Open Access Journals (Sweden)

    Jun Ma

    2015-08-01

    Full Text Available Background/Aims: Non-small cell lung carcinoma (NSCLC is the most common type of lung cancer and the cause of most cancer-related deaths. The molecular mechanisms that are involved in NSCLC development are currently not well understood. Accumulating evidence shows that histone demethylases play important roles in the regulation of pathological developmental processes in many diseases, including various types of cancers. Methods: Mitochondrial membrane potential assays, migration and invasion assays, caspase-3 and caspase-9 activity assays and western blot analysis were used in this research. Results: We found that overexpression of KDM6B, a demethylase that acts on histone H3 at lysine 27 (H3K27, inhibited cell growth by initiating mitochondria-dependent apoptosis and by attenuating the invasion-metastasis cascade in NSCLC cells. Moreover, our results showed that KDM6B directly interacted with FOXO1 and that overexpression of KDM6B promoted nuclear accumulation of FOXO1. The effects of KDM6B on cell apoptosis and metastasis were weakened by knockdown of FOXO1 expression. On the contrary, knocking down expression of KDM6B inhibited cell apoptosis and promoted cell growth by mitigating the nuclear translocation of FOXO1 in NSCLC cells. Conclusions: These findings suggest that KDM6B may act in a pro-apoptotic role in NSCLC by causing the nuclear translocation of FOXO1.

  5. Calculations of atomic magnetic nuclear shielding constants based on the two-component normalized elimination of the small component method

    Science.gov (United States)

    Yoshizawa, Terutaka; Zou, Wenli; Cremer, Dieter

    2017-04-01

    A new method for calculating nuclear magnetic resonance shielding constants of relativistic atoms based on the two-component (2c), spin-orbit coupling including Dirac-exact NESC (Normalized Elimination of the Small Component) approach is developed where each term of the diamagnetic and paramagnetic contribution to the isotropic shielding constant σi s o is expressed in terms of analytical energy derivatives with regard to the magnetic field B and the nuclear magnetic moment 𝝁 . The picture change caused by renormalization of the wave function is correctly described. 2c-NESC/HF (Hartree-Fock) results for the σiso values of 13 atoms with a closed shell ground state reveal a deviation from 4c-DHF (Dirac-HF) values by 0.01%-0.76%. Since the 2-electron part is effectively calculated using a modified screened nuclear shielding approach, the calculation is efficient and based on a series of matrix manipulations scaling with (2M)3 (M: number of basis functions).

  6. Market potential of small and medium-size nuclear reactors as combined heat and power plants in Europe

    International Nuclear Information System (INIS)

    Schoen, R.; Hansen, U.; Candeli, R.; Leuchs, D.; Garribba, S.F.; Lefevre, J.C.; Vivante, C.

    1987-01-01

    A Study has been launched and supported by the Commission of the European Communities to assess the potential market of small and medium size nuclear reactors through EC Countries and to identify those factors which may play a dominant role in this respect. In its first phase, the Study addresses to modular high-temperature gas-cooled reactors that would be installed to produce low-temperature heat and power. Federal Republic of Germany, Italy and France are the countries for which the investigation has been either completed or is under way. The time span of interest is up to the year 2020. Referring to this horizon an appraisal has been made of the number of nuclear units which could come on line to cope with energy demand and their timing. Through the Study a distinction is made between technical potential, economic potential, and effective market potential. It is understood indeed that both economic competitiveness towards other energy sources and institutional or organizational factors may restrict the market which could be covered by this class of nuclear reactors. (author)

  7. Cluster emission at pre-equilibrium stage in Heavy Nuclear Reactions. A Model considering the Thermodynamics of Small Systems

    International Nuclear Information System (INIS)

    Bermudez Martinez, A.; Damiani, D.; Guzman Martinez, F.; Rodriguez Hoyos, O.; Rodriguez Manso, A.

    2015-01-01

    Cluster emission at pre-equilibrium stage, in heavy ion fusion reactions of 12 C and 16 O nuclei with 116 Sn, 208 Pb, 238 U are studied. the energy of the projectile nuclei was chosen at 0.25GeV, 0.5GeV and 1GeV. A cluster formation model is developed in order to calculate the cluster size. Thermodynamics of small systems was used in order to examine the cluster behavior inside the nuclear media. This model is based on considering two phases inside the compound nucleus, on one hand the nuclear media phase, and on the other hand the cluster itself. The cluster acts like an instability inside the compound nucleus, provoking an exchange of nucleons with the nuclear media through its surface. The processes were simulated using Monte Carlo methods. We obtained that the cluster emission probability shows great dependence on the cluster size. This project is aimed to implement cluster emission processes, during the pre-equilibrium stage, in the frame of CRISP code (Collaboration Rio-Sao Paulo). (Author)

  8. Small specimen test technology of fracture toughness in structural material F82H steel for fusion nuclear reactors

    International Nuclear Information System (INIS)

    Wakai, Eiichi; Ohtsuka, Hideo; Jitsukawa, Shiro; Matsukawa, Shingo; Ando, Masami

    2006-03-01

    Small specimen test technology (SSTT) has been developed to investigate mechanical properties of nuclear materials. SSTT has been driven by limited availability of effective irradiation volumes in test reactors and accelerator-based neutron and charged particle sources, and it is very useful for the reduction of waste materials produced in nuclear engineering. In this study new bend test machines have been developed to obtain fracture behaviors of F82H steel for very small bend specimens of pre-cracked t/2-1/3CVN (Charpy V-notch) with 20 mm-length and DFMB (deformation and fracture mini bend specimen) with 9 mm-length and disk compact tension of 0.18DCT type, and fracture behaviors were examined to evaluate DBTT (ductile-brittle transition temperature) at temperature from -180 to 25degC. The effect of specimen size on DBTT of F82H steel was also examined by using Charpy type specimens such as 1/2t-CVN, 1/3CVN and t/2-1/3CVN. In this paper, it also provides the information of the specimens irradiated at 250degC and 350degC to about 2 dpa in the capsule of 04M-67A and 04M-68A of JMTR experiments. (author)

  9. Modeling operator actions during a small break loss-of-coolant accident in a Babcock and Wilcox nuclear power plant

    International Nuclear Information System (INIS)

    Ghan, L.S.; Ortiz, M.G.

    1991-01-01

    A small break loss-of-accident (SBLOCA) in a typical Babcock and Wilcox (B ampersand W) nuclear power plant was modeled using RELAP5/MOD3. This work was performed as part of the United States Regulatory Commission's (USNRC) Code, Scaling, Applicability and Uncertainty (CSAU) study. The break was initiated by severing one high pressure injection (HPI) line at the cold leg. Thus, the small break was further aggravated by reduced HPI flow. Comparisons between scoping runs with minimal operator action, and full operator action, clearly showed that the operator plays a key role in recovering the plant. Operator actions were modeled based on the emergency operating procedures (EOPs) and the Technical Bases Document for the EOPs. The sequence of operator actions modeled here is only one of several possibilities. Different sequences of operator actions are possible for a given accident because of the subjective decisions the operator must make when determining the status of the plant, hence, which branch of the EOP to follow. To assess the credibility of the modeled operator actions, these actions and results of the simulated accident scenario were presented to operator examiners who are familiar with B ampersand W nuclear power plants. They agreed that, in general, the modeled operator actions conform to the requirements set forth in the EOPs and are therefore plausible. This paper presents the method for modeling the operator actions and discusses the simulated accident scenario from the viewpoint of operator actions

  10. Development and validation of calculation schemes dedicated to the interpretation of small reactivity effects for nuclear data improvement

    International Nuclear Information System (INIS)

    Gruel, A.

    2011-01-01

    Reactivity measurements by the oscillation technique, as those performed in the Minerve reactor, enable to access various neutronic parameters on materials, fuels or specific isotopes. Usually, expected reactivity effects are small, about ten pcm at maximum. Then, the modeling of these experiments should be very precise, to obtain reliable feedback on the pointed parameters. Especially, calculation biases should be precisely identified, quantified and reduced to get precise information on nuclear data. The goal of this thesis is to develop a reference calculation scheme, with well quantified uncertainties, for in-pile oscillation experiments. In this work are presented several small reactivity calculation methods, based on deterministic and/or stochastic calculation codes. Those method are compared thanks to a numerical benchmark, against a reference calculation. Three applications of these methods are presented here: a purely deterministic calculation with exact perturbation theory formalism is used for the experimental validation of fission product cross sections, in the frame of reactivity loss studies for irradiated fuel; an hybrid method, based on a stochastic calculation and the exact perturbation theory is used for the readjustment of nuclear data, here 241 Am; and a third method, based on a perturbative Monte Carlo calculation, is used in a conception study. (author) [fr

  11. Design characteristics for pressurized water small modular nuclear power reactors with focus on safety

    Energy Technology Data Exchange (ETDEWEB)

    Kani, Iraj Mahmoudzadeh [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; Zandieh, Mehdi [Tehran Univ. (Iran, Islamic Republic of). Civil Faculty; International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty; Abadi, Saeed Kheirollahi Hossein [International Univ. of Imam Khomeini (Iran, Islamic Republic of). Architecture Faculty

    2016-05-15

    Small Modular Reactors (SMRs) are a technology, attracting attention. Light water SMR possess an upgraded design case and emphasize the significance of integral models. Beside of these advantages, SMRs has faced numerous challenges, e.g. licensing, cost/investment, safety and security observation, social and environmental issues in building new plants.

  12. The role of small and medium size reactors in the future US nuclear market

    International Nuclear Information System (INIS)

    Twilley, R.C.

    2002-01-01

    This paper addresses the various aspects of siting and sizing new generating facilities in the USA. Environmental and licensing issues are discussed. The economic considerations and assumptions for new plants are presented. Also, the electric transmission and distribution system characteristics and constraints are described with the potential role for several small and medium size designs summarized. (authors)

  13. Advanced Small-Safe Long-Life Lead Cooled Reactor Cores for Future Nuclear Energy

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jin Hyeong; Hong, Ser Gi [Kyung Hee University, Seoul (Korea, Republic of)

    2014-10-15

    One of the reasons for use of the lead or lead-bismuth alloy coolants is the high boiling temperature that avoids the possibility of coolant voiding. Also, these coolants are compatible with air, steam, and water. Therefore, intermediate coolant loop is not required as in the sodium cooled reactors 3. Lead is considered to be more attractive coolant than lead-bismuth alloy because of its higher availability, lower price, and much lower amount of polonium activity by factor of 104 relatively to lead. On the other hand, lead has higher melting temperature of 601K than that of lead-bismuth (398K), which narrows the operating temperature range and also leads to the possibility of freezing and blockage in fresh cores. Neutronically, the lead and lead-bismuth have very similar characteristics to each other. The lead-alloy coolants have lower moderating power and higher scattering without increasing moderation for neutrons below 0.5MeV, which reduces the leakage of the neutrons through the core and provides an excellent reflecting capability for neutrons. Due to the above features of lead or lead-alloy coolants, there have been lots of studies on the small lead cooled core designs. In this paper, small-safe long-life lead cooled reactor cores having high discharge burnup are designed and neutronically analyzed.. The cores considered in this work rates 110MWt (36.7MWe). In this work, the long-life with high discharge burnup was achieved by using thorium or depleted uranium blanket loaded in the central region of the core. Also, we considered a reference core having no blanket for the comparison. This paper provides the detailed neutronic analyses for these small long-life cores and the detailed analyses of the reactivity coefficients and the composition changes in blankets. The results of the core design and analyses show that our small long-life cores can be operated without refueling over their long-lives longer than 45EFPYs (Effective Full Power Year). In this work

  14. Size dependent diffusive parameters and tensorial diffusion equations in neutronic models for optically small nuclear systems

    International Nuclear Information System (INIS)

    Premuda, F.

    1983-01-01

    Two lines in improved neutron diffusion theory extending the efficiency of finite-difference diffusion codes to the field of optically small systems, are here reviewed. The firs involves the nodal solution for tensorial diffusion equation in slab geometry and tensorial formulation in parallelepiped and cylindrical gemometry; the dependence of critical eigenvalue from small slab thicknesses is also analitically investigated and finally a regularized tensorial diffusion equation is derived for slab. The other line refer to diffusion models formally unchanged with respect to the classical one, but where new size-dependent RTGB definitions for diffusion parameters are adopted, requiring that they allow to reproduce, in diffusion approach, the terms of neutron transport global balance; the trascendental equation for the buckling, arising in slab, sphere and parallelepiped geometry from the above requirement, are reported and the sizedependence of the new diffusion coefficient and extrapolated end point is investigated

  15. Small high temperature gas-cooled reactors with innovative nuclear burning

    International Nuclear Information System (INIS)

    Liem, Peng Hong; Ismail; Sekimoto, Hiroshi

    2008-01-01

    Since the innovative concept of CANDLE (Constant Axial shape of Neutron Flux, nuclide densities and power shape During Life of Energy producing reactor) burning strategy was proposed, intensive research works have been continuously conducted to evaluate the feasibility and the performance of the burning strategy on both fast and thermal reactors. We learned that one potential application of the burning strategy for thermal reactors is for the High Temperature Gas-Cooled Reactors (HTGR) with prismatic/block-type fuel elements. Several characteristics of CANDLE burning strategy such as constant reactor characteristics during burn-up, no need for burn-up reactivity control mechanism, proportionality of core height with core lifetime, sub-criticality of fresh fuel elements, etc. enable us to design small sized HTGR with a high degree of safety easiness of operation and maintenance, and long core lifetime which are required for introducing the reactors into remote areas or developing countries with limited infrastructures and resources. In the present work, we report our evaluation results on small sized block-type HTGR designs with CANDLE burning strategy and compared with other existing small HTGR designs including the ones with pebble fuel elements, under both uranium and thorium fuel cycles. (author)

  16. Simulation of the behaviour of small and medium nuclear reactors on PCs

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1999-01-01

    The International Atomic Energy Agency (IAEA) has established a programme in nuclear reactor simulation computer programs to assist its Member States in education and training. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the supply or development of simulation programs and training material, sponsors training courses and workshops, and distributes documentation and computer programs. One of the simulation programs distributed by the IAEA is the the Advanced Reactor Simulator which simulates the behaviour of BWR, PWR and HWR reactor types. For this package, the modeling approach and assumptions are broadly described, together with a general description of the operation of the computer program. (author)

  17. Screening of nuclear structure function F2A(x,Q2) at small x values

    International Nuclear Information System (INIS)

    Davidovs'kij, V.V.

    1999-01-01

    The U-matrix method have been applied to build an amplitude for virtual photon absorption by nuclei which satisfies unitarity.This amplitude have been utilised to obtain the expression for the structure function F 2A ,which is convenient to perform analytical calculations with.Profile functions of nuclei with Gauss,Woods-Saxon and constant density distribution have been considered.It is shown that effects of quark-antiquark pair rescattering in nucleus cause the screening of F 2A and the change of power-like behaviour of F 2A to logarithmic one at small x. Numerical estimations are given

  18. Development of technologies for nuclear reactors of small and medium sized

    International Nuclear Information System (INIS)

    2011-08-01

    This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

  19. High energy approximations for nuclear knockout form factors at small momentum transfer

    International Nuclear Information System (INIS)

    Amado, R.D.; Cannata, F.; Dedonder, J.P.

    1985-01-01

    We obtain an explicit approximate expression for the nucleon knockout form factor at small momentum transfer induced by a scalar probe in a single particle model in terms of the momentum space bound state wave function. Our form preserves the orthogonality constraint without using explicitly the final state scattering wave function. We examine the leading large momentum behavior of the momentum space wave function and of correction terms to our expression for the form factor in the case where the bound state is an s state

  20. Design Study of Modular Nuclear Power Plant with Small Long Life Gas Cooled Fast Reactors Utilizing MOX Fuel

    Science.gov (United States)

    Ilham, Muhammad; Su'ud, Zaki

    2017-01-01

    Growing energy needed due to increasing of the world’s population encourages development of technology and science of nuclear power plant in its safety and security. In this research, it will be explained about design study of modular fast reactor with helium gas cooling (GCFR) small long life reactor, which can be operated over 20 years. It had been conducted about neutronic design GCFR with Mixed Oxide (UO2-PuO2) fuel in range of 100-200 MWth NPPs of power and 50-60% of fuel fraction variation with cylindrical pin cell and cylindrical balance of reactor core geometry. Calculation method used SRAC-CITATION code. The obtained results are the effective multiplication factor and density value of core reactor power (with geometry optimalization) to obtain optimum design core reactor power, whereas the obtained of optimum core reactor power is 200 MWth with 55% of fuel fraction and 9-13% of percentages.

  1. The near boiling reactor: design of a small nuclear reactor for extending the operational envelope of the Victoria Class Submarine

    International Nuclear Information System (INIS)

    Cole, C.; Bonin, H.

    2005-01-01

    A small, inherently safe nuclear reactor that will provide enough power to maintain the hotel load of the Victoria Class Submarine and extend her operational envelope, has been conceptually designed. The final reactor concept, named the Near Boiling (NB) Reactor, employs TRISO fuel particles in Zirconium cladded fuel rods. The reactor is light water moderated and cooled. The core life is specifically designed to coincide with the refit cycle of the Victoria Class Submarine. The reactor employs a simple and reliable control and shut down system that requires little intervention on the part of the submarine's crew. Also, a kinetic model is developed that demonstrates the inherent safety features of the reactor during several accident scenarios. (author)

  2. The near boiling reactor: design of a small nuclear reactor for extending the operational envelope of the Victoria Class Submarine

    Energy Technology Data Exchange (ETDEWEB)

    Cole, C.; Bonin, H. [Royal Military College of Canada, Dept. of Chemistry and Chemical Engineering, Kingston, Ontario (Canada)]. E-mail: chris.cole@rmc.ca; bonin-h@rmc.ca

    2005-07-01

    A small, inherently safe nuclear reactor that will provide enough power to maintain the hotel load of the Victoria Class Submarine and extend her operational envelope, has been conceptually designed. The final reactor concept, named the Near Boiling (NB) Reactor, employs TRISO fuel particles in Zirconium cladded fuel rods. The reactor is light water moderated and cooled. The core life is specifically designed to coincide with the refit cycle of the Victoria Class Submarine. The reactor employs a simple and reliable control and shut down system that requires little intervention on the part of the submarine's crew. Also, a kinetic model is developed that demonstrates the inherent safety features of the reactor during several accident scenarios. (author)

  3. Small bore pipe acceptance criteria for watts bar nuclear plant Tennessee Valley Authority

    International Nuclear Information System (INIS)

    Sun, W.S.; Lee, R.L.; Kalyanan, N.

    1991-01-01

    Small bore pipe (≤2 inches NPS) is traditionally analyzed by simplified techniques using Cook Book approach, which yield conservative results. However, reconciliation of these systems for as-built condition where the original criteria is observed to have been exceeded (or due to additions etc.) generally becomes a time consuming and expensive operation since a rigorous computer aided analysis or a detailed hand calculation becomes necessary. The acceptance criteria in this paper can be effectively used in such cases. The approach involves utilizing basic engineering principles and plant specific parameters (such as earthquake spectra) to estimate the system response such as pipe stress due to various loading conditions, piping frequency, support and anchor loads, valve acceleration etc

  4. Case study on the feasibility of small and medium nuclear power plants in Egypt

    International Nuclear Information System (INIS)

    1994-04-01

    The IAEA agreed to co-operate with the Arab Republic of Egypt in performing a case study on the feasibility of small and medium power reactors (SMPRs) as a technical assistance project. The major objective of this study is to examine the feasibility of SMPRs to supply a portion of the future electrical energy requirements in the long term power programme of Egypt. The IAEA is grateful to all who provided information and assisted in the drafting and review of the report, in particular to the Advisory Group which performed the study in a co-operative effort. It is hoped that the report will meet the interests of policy makers, managers, engineers and economists in Member States, particularly in developing countries, and that it will provide a useful basis for specific studies to prepare decisions on SMPR projects. Refs, figs and tabs

  5. Development of a model and test equipment for cold flow tests at 500 atm of small nuclear light bulb configurations

    Science.gov (United States)

    Jaminet, J. F.

    1972-01-01

    A model and test equipment were developed and cold-flow-tested at greater than 500 atm in preparation for future high-pressure rf plasma experiments and in-reactor tests with small nuclear light bulb configurations. With minor exceptions, the model chamber is similar in design and dimensions to a proposed in-reactor geometry for tests with fissioning uranium plasmas in the nuclear furnace. The model and the equipment were designed for use with the UARL 1.2-MW rf induction heater in tests with rf plasmas at pressures up to 500 atm. A series of cold-flow tests of the model was then conducted at pressures up to about 510 atm. At 504 atm, the flow rates of argon and cooling water were 3.35 liter/sec (STP) and 26 gal/min, respectively. It was demonstrated that the model is capable of being operated for extended periods at the 500-atm pressure level and is, therefore, ready for use in initial high-pressure rf plasma experiments.

  6. U-2g0 cyclotron operational experience and improvement

    International Nuclear Information System (INIS)

    Gigal, B.N.; Gul'bekyan, G.G.; Kozlov, S.I.; Oganesyan, R.Ts.

    1983-01-01

    Brief description of main syste's of the U-200 isochronous 2-m cyclotron put into opera ion in 1968 is given and its operational characteristics a e presented. The cyclotron is used for conducting inve tigations in the field of nuclear physics. Ions from d uterium to argon have been accelerated in the cyclotro'. Annual time of target irradiation constitutes 2000-4000. The specific features of the cyclotron are: high l vel of a magnetic field (of about 20 kOe), possibili y of acceleration of ions with different mass-to-charge ratio a low correcting winding power, simple and high-e fective beam extraction by the method of charge exchange on a thin target allowing to vary smoothly energy of extracted ons. An experience in the U-200 cyclotron development and o eration is used as the basis for designing and choosing basic parameters of the U-200P, U-250, U-400 heavy ion cyclotrons

  7. Self-Reliance and Sustainability of Nuclear Analytical Laboratories in Small States of Central Europe: The Slovenian Case

    International Nuclear Information System (INIS)

    Korun, M.

    2013-01-01

    customers is performed under contracts lasting at least one year. The main customer is the nuclear power plant, which accounts for about 80% of the income. The Laboratory is not the only provider of services in gamma-ray spectrometry either within the Institute, or in Slovenia. Therefore it is exposed to the pressures of the competitive market, but also to pressures originating from informal ties between the users and other providers of the monitoring service. It should be observed that in a small country the influence of such ties is more important relative to the influence of the market than in larger countries, where the size of the market provides more opportunity for substitution or acquisition of new customers. The large share of one customer in its income makes the Laboratory extremely vulnerable. It should be observed as well that Slovenia has become a member of the European Union and therefore its market is open to competitors from abroad. (author)

  8. Analysis of world experience in constructing underground small nuclear power plants and assessment of its potential use in the Russian Arctic regions

    Directory of Open Access Journals (Sweden)

    Smirnov Yu. G.

    2016-03-01

    Full Text Available The paper considers the common ideology and main idea of locating underground nuclear plants. Specific examples in domestic and foreign experience have been analyzed. It has been established that underground small nuclear power plants can be used as an alternative source of electric and thermal energy for solving defense-strategic and social-economic tasks particularly when developing mineral raw material resources in the Russian Arctic regions

  9. Microincision versus small-incision coaxial cataract surgery using different power modes for hard nuclear cataract.

    Science.gov (United States)

    Kim, Eun Chul; Byun, Yong Soo; Kim, Man Soo

    2011-10-01

    To compare the efficacy of microincision and small-incision coaxial phacoemulsification in treating hard cataracts using different ultrasound power modes. Department of Ophthalmology, Seoul St. Mary's Hospital, College of Medicine, Catholic University of Korea, Seoul, Korea. Randomized clinical trial. Eyes with hard cataract were randomized to have an initial incision of 1.80 mm, 2.20 mm, or 2.75 mm. The eyes in each group were equally randomized to treatment with burst, pulse, or continuous mode. Ultrasound time (UST), mean cumulative dissipated energy (CDE), corrected distance visual acuity (CDVA), surgically induced corneal astigmatism, incisional and central corneal thickness (CCT), and endothelial cell counts were evaluated. The study enrolled 180 eyes, 60 in each group. Two months postoperatively, there were no statistically significant differences in UST, CDE, CDVA, CCT, or percentage endothelial cell loss between the 3 incision groups. The 2.75 mm incision induced more astigmatism at 2 months and less incisional corneal edema at 1 week than the 1.80 mm or 2.20 mm incision (Phard cataract. The intraoperative energy use and ocular damage was less with the pulse and burst modes than with the continuous mode. No author has a financial or proprietary interest in any material or method mentioned. Copyright © 2011 ASCRS and ESCRS. Published by Elsevier Inc. All rights reserved.

  10. Transient core characteristics of small molten salt reactor coupling problem between heat transfer/flow and nuclear fission reaction

    International Nuclear Information System (INIS)

    Yamamoto, Takahisa; Mitachi, Koshi

    2004-01-01

    This paper performed the transient core analysis of a small Molten Salt Reactor (MSR). The emphasis is that the numerical model employed in this paper takes into account the interaction among fuel salt flow, nuclear reaction and heat transfer. The model consists of two group diffusion equations for fast and thermal neutron fluexs, balance equations for six-group delayed neutron precursors and energy conservation equations for fuel salt and graphite moderator. The results of transient analysis are that (1) fission reaction (heat generation) rate significantly increases soon after step reactivity insertion, e.g., the peak of fission reaction rate achieves about 2.7 times larger than the rated power 350 MW when the reactivity of 0.15% Δk/k 0 is inserted to the rated state, and (2) the self-control performance of the small MSR effectively works under the step reactivity insertion of 0.56% Δk/k 0 , putting the fission reaction rate back on the rated state. (author)

  11. Obtaining of U-2.5Zr7.5Nb and U-3Zr-9Nb alloys by sintering process

    International Nuclear Information System (INIS)

    Mazzeu, Thiago de Oliveira; Paula, Joao Bosco de; Ferraz, Wilmar Barbosa; Santos, Ana Maria Matildes dos; Brina, Jose Giovanni Mascarenhas

    2011-01-01

    The development of metallic fuels with low enrichment to be used in research and test reactors, as well in the future pressurized water reactors, focuses on the search for uranium alloys of high density. Alloying elements such as Zr, Nb and Mo are added to uranium to improve fuel performance in reactors. In this context, the Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) in Belo Horizonte is developing the U-2.5Zr-7.5Nb and U- 3Zr-9Nb (weight %) alloys by the innovative process of sintering that utilizes raw materials in the form of powders. The powders were pressed at 400MPa and then sintered under a vacuum of about 5 x 10-6 Torr at temperatures ranging from 1050 deg to 1300 deg C. The densities of the alloys were measured geometrically and by hydrostatic method using water. The microstructures of the pellets were observed by scanning electron microscopy (SEM) and the elements of alloying were identified by energy dispersive X-ray spectroscopy (SEM/EDS) analysis. The obtained results showed a small increasing density with rising sintering temperature. The highest density achieved was approximately 80% of theoretical density. It was also qualitatively observed that the superficial oxidation of the pellets increased with increasing sintering temperature thus avoiding the fusion of the alloys at higher temperatures. (author)

  12. A multi-stage-flash desalination plant of relative small performance with an integrated pressurized water reactor as a nuclear heat source

    International Nuclear Information System (INIS)

    Peltzer, M.; Petersen, G.

    1976-01-01

    In the Krupp-GKSS joint study MINIPLEX the requirements for seawater-desalination-plants with a performance in the range of 10,000 to 80,000 m 3 /d heated by a nuclear reactor are investigated. The reactor concept is similar to the integrated pressurized water reactor (IPWR) of the nuclear ship OTTO HAHN. The calculated costs of the desalinated water show, that due to the fuel cost advantages of reactors small and medium nuclear desalination plants are economically competetive with oil-fired plants since the steep rise of oil price in autumn 1973. (orig.) [de

  13. Decision on the Exclusion of Small Quantities of Nuclear Substances outside a Nuclear Installation from the Application of the Convention on Third Party Liability in the Field of Nuclear Energy (This Decision was adopted at the 133. Session of the Steering Committee for Nuclear Energy held on 3-4 November 2016.)

    International Nuclear Information System (INIS)

    2017-01-01

    The steering committee, having regard to the Convention on Third Party Liability in the Field of Nuclear Energy of 29 July 1960, as amended by the Additional Protocol of 28 January 1964, by the Protocol of 16 November 1982 and by the Protocol of 12 February 2004, and, in particular, Article 1(b) thereof; considering that, by virtue of that Article, the Steering Committee may, if in its view the small extent of the risks involved so warrants, exclude any nuclear installation, nuclear fuel or nuclear substances from the application of the Paris Convention; considering that nuclear substances in transport or use outside a nuclear installation, within defined limits and under specifically prescribed conditions during transport, should, in view of the small extent of the risks involved, be excluded from the application of the Paris Convention; having regard to its Decision of 18 October 2007 on the Exclusion of Small Quantities of Nuclear Substances outside a Nuclear Installation from the Application of the Convention on Third Party Liability in the Field of Nuclear Energy of 29 July 1960 as amended; considering that the 2005 Edition of the Regulations for the Safe Transport of Radioactive Material of the International Atomic Energy Agency referred to in the Annex to the above-mentioned Decision, has been replaced by revised editions, the most recent of which is the 2012 Edition, which is used as the basis for corresponding national and international regulations in this field; considering the need for a decision the annex of which is in line with the 2012 Edition of those Regulations; decides: 1. Nuclear substances which are consigned by an operator to a recipient for use shall be excluded from the application of the Paris Convention for the period during which they are outside a nuclear installation provided that the consignment, when leaving a nuclear installation, complies with the provisions set forth in the Annex to this Decision and with other relevant

  14. Facile CO Cleavage by a Multimetallic CsU2 Nitride Complex.

    Science.gov (United States)

    Falcone, Marta; Kefalidis, Christos E; Scopelliti, Rosario; Maron, Laurent; Mazzanti, Marinella

    2016-09-26

    Uranium nitrides are important materials with potential for application as fuels for nuclear power generation, and as highly active catalysts. Molecular nitride compounds could provide important insight into the nature of the uranium-nitride bond, but currently little is known about their reactivity. In this study, we found that a complex containing a nitride bridging two uranium centers and a cesium cation readily cleaved the C≡O bond (one of the strongest bonds in nature) under ambient conditions. The product formed has a [CsU2 (μ-CN)(μ-O)] core, thus indicating that the three cations cooperate to cleave CO. Moreover, the addition of MeOTf to the nitride complex led to an exceptional valence disproportionation of the CsU(IV) -N-U(IV) core to yield CsU(III) (OTf) and [MeN=U(V) ] fragments. The important role of multimetallic cooperativity in both reactions is illustrated by the computed reaction mechanisms. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  15. Decommissioning of four small nuclear waste storage buildings and an evaporation plant

    International Nuclear Information System (INIS)

    Hedvall, R.H.; Ellmark, C.; Stocker, P.

    2008-01-01

    A small-scale decommissioning concept was applied with staff from an earlier project wish strong knowledge of radiation protection, minimized radiation doses and environmental pollution. The project was therefore initiated with less than 10 people involved using standard hand held equipment. The aim of the decommissioning project was to set free as much material as possible, i.e. remove waste from the regulatory control regime and also free the remaining structures and buildings for conventional demolition and subsequent reuse of the property. Complete decommissioning will be concluded at the end of 2008 when all waste is taken case of. This is the fourth in a series of important decommissioning projects in Studsvik since the 1980s. Some of the conclusions are: 1) Obtain a group with well-known personnel that have been working together before for the entire project For a project larger than this, project management assistant would have made follow-up more efficient. Experts in instrumentation and statistics are also important. Also important is knowledge about practical decisions that would make the project more efficient in terms of time. Interviews and historical facts are important when choosing which nuclides are of most interest for measurements (but be critic). 2) Be sure all authoritative requirements are followed, like setting up a work environment plan at the entrance to the site and placing a fence around the work site. 3) Check all individual radiation exposures before project start and do whole body measurements both before and after the project. Urine samples should be taken if alpha contamination is a risk. 4) Calculate for unwanted and 'not what you expected' situations in the time schedule. 5) Be aware of contaminations and radiation sources outside the actual area. They might have to be moved. 6) Calculate and order bins and containers for waste storage well in advance. Stay informed of the updated amount of waste and keep it in locked storage. 7

  16. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  17. R2U2: Monitoring and Diagnosis of Security Threats for Unmanned Aerial Systems

    Science.gov (United States)

    Schumann, Johann; Moosbruger, Patrick; Rozier, Kristin Y.

    2015-01-01

    We present R2U2, a novel framework for runtime monitoring of security properties and diagnosing of security threats on-board Unmanned Aerial Systems (UAS). R2U2, implemented in FPGA hardware, is a real-time, REALIZABLE, RESPONSIVE, UNOBTRUSIVE Unit for security threat detection. R2U2 is designed to continuously monitor inputs from the GPS and the ground control station, sensor readings, actuator outputs, and flight software status. By simultaneously monitoring and performing statistical reasoning, attack patterns and post-attack discrepancies in the UAS behavior can be detected. R2U2 uses runtime observer pairs for linear and metric temporal logics for property monitoring and Bayesian networks for diagnosis of security threats. We discuss the design and implementation that now enables R2U2 to handle security threats and present simulation results of several attack scenarios on the NASA DragonEye UAS.

  18. RLIM interacts with Smurf2 and promotes TGF-β induced U2OS cell migration

    International Nuclear Information System (INIS)

    Huang, Yongsheng; Yang, Yang; Gao, Rui; Yang, Xianmei; Yan, Xiaohua; Wang, Chenji; Jiang, Sirui; Yu, Long

    2011-01-01

    Highlights: → RLIM directly binds to Smurf2. → RLIM enhances TGF-β responsiveness in U2OS cells. → RLIM promotes TGF-β driven migration of osteosarcoma U2OS cells. -- Abstract: TGF-β (transforming growth factor-β), a pleiotropic cytokine that regulates diverse cellular processes, has been suggested to play critical roles in cell proliferation, migration, and carcinogenesis. Here we found a novel E3 ubiquitin ligase RLIM which can directly bind to Smurf2, enhancing TGF-β responsiveness in osteosarcoma U2OS cells. We constructed a U2OS cell line stably over-expressing RLIM and demonstrated that RLIM promoted TGF-β-driven migration of U2OS cells as tested by wound healing assay. Our results indicated that RLIM is an important positive regulator in TGF-β signaling pathway and cell migration.

  19. Modeling Chilled-Water Storage System Components for Coupling to a Small Modular Reactor in a Nuclear Hybrid Energy System

    Science.gov (United States)

    Misenheimer, Corey Thomas

    The intermittency of wind and solar power puts strain on electric grids, often forcing carbonbased and nuclear sources of energy to operate in a load-follow mode. Operating nuclear reactors in a load-follow fashion is undesirable due to the associated thermal and mechanical stresses placed on the fuel and other reactor components. Various Thermal Energy Storage (TES) elements and ancillary energy applications can be coupled to nuclear (or renewable) power sources to help absorb grid instabilities caused by daily electric demand changes and renewable intermittency, thereby forming the basis of a candidate Nuclear Hybrid Energy System (NHES). During the warmer months of the year in many parts of the country, facility air-conditioning loads are significant contributors to the increase in the daily peak electric demand. Previous research demonstrated that a stratified chilled-water storage tank can displace peak cooling loads to off-peak hours. Based on these findings, the objective of this work is to evaluate the prospect of using a stratified chilled-water storage tank as a potential TES reservoir for a nuclear reactor in a NHES. This is accomplished by developing time-dependent models of chilled-water system components, including absorption chillers, cooling towers, a storage tank, and facility cooling loads appropriate for a large office space or college campus, as a callable FORTRAN subroutine. The resulting TES model is coupled to a high-fidelity mPower-sized Small Modular Reactor (SMR) Simulator, with the goal of utilizing excess reactor capacity to operate several sizable chillers in order to keep reactor power constant. Chilled-water production via single effect, lithium bromide (LiBr) absorption chillers is primarily examined in this study, although the use of electric chillers is briefly explored. Absorption chillers use hot water or low-pressure steam to drive an absorption-refrigeration cycle. The mathematical framework for a high-fidelity dynamic

  20. Magnetic, transport and electronic structure properties of U2RuGa8

    International Nuclear Information System (INIS)

    Troc, R.; Bukowski, Z.; SuIkowski, C.; Morkowski, J.A.; Szajek, A.; CheIkowska, G.

    2005-01-01

    A single crystal of uranium ternary intermetallic of U 2 RuGa 8 was grown by the Ga self-flux method. This compound crystallizes in the tetragonal unit cell of space group P4/mmm. Despite the fairly large U-U shortest distance of 4.22A, this compound shows no signs of any magnetic ordering down to 1.9K. Instead, the susceptibility measured along the a and c axes, goes through a broad maximum at T max =220K showing a distinct anisotropy. For j||a there is a weak temperature dependence of the electrical resistivity with a large value of ρ 0 =117μΩcm, while for j||c the ρ(T) curve goes through a maximum at about 130K. The magnetoresistivity measured along two crystallographic directions is small and positive. The thermopower S for the two directions studied is positive and larger along the a-axis. It goes through a broad maximum at 175K reaching a value of 45μV/K. The electronic structure has been calculated by the tight-binding linear muffin-tin orbital method (TB-LMTO) and the results were used in calculation of the valence band near the Fermi level compared next to that found in photoemission experiment. The core 4f spectra are also presented. All the above properties are discussed in view of mixed valence behaviour of uranium atom in this compound

  1. Cloning of the cDNA for U1 small nuclear ribonucleoprotein particle 70K protein from Arabidopsis thaliana

    Science.gov (United States)

    Reddy, A. S.; Czernik, A. J.; An, G.; Poovaiah, B. W.

    1992-01-01

    We cloned and sequenced a plant cDNA that encodes U1 small nuclear ribonucleoprotein (snRNP) 70K protein. The plant U1 snRNP 70K protein cDNA is not full length and lacks the coding region for 68 amino acids in the amino-terminal region as compared to human U1 snRNP 70K protein. Comparison of the deduced amino acid sequence of the plant U1 snRNP 70K protein with the amino acid sequence of animal and yeast U1 snRNP 70K protein showed a high degree of homology. The plant U1 snRNP 70K protein is more closely related to the human counter part than to the yeast 70K protein. The carboxy-terminal half is less well conserved but, like the vertebrate 70K proteins, is rich in charged amino acids. Northern analysis with the RNA isolated from different parts of the plant indicates that the snRNP 70K gene is expressed in all of the parts tested. Southern blotting of genomic DNA using the cDNA indicates that the U1 snRNP 70K protein is coded by a single gene.

  2. Proposed full automatic control system for the Medical Small Cyclotron C-30 at the Institute of Nuclear Studies, Poland

    International Nuclear Information System (INIS)

    Jankowski, A.

    1987-01-01

    The computer control system for the C-30 Medical Small Cyclotron, which is currently under construction at the Institute of Nuclear Studies will be presented. The features of this simple and secure system are briefly discussed. Some efforts have been done to make a conversational system easily understandable for operators. The keystone of the control system is an fibre optical link (wireless) between the cyclotron and the computer. The control system is based on the use of an extended configuration of the IBM PC/AT computer. A new system software is used to execute multitask hierarchical programs to control the cyclotron. The comercial adapters for control and data aquisition, connected with the fibre optic communication channels are used to transmit data and control codes. Two colour graphic CRT displays the ongoing status and function of each controlled units so that the operator can monitor the whole system conditions at a glance. The paper gives a general description of the programs which are executed on the computer. It also shows how the cyclotron is controlled by dedicated computer practically without special electronic equipment except of the hardware safety cutout switch. The cyclotron is protected against operating incidents and mistakes by a complex system of interlocks. (author)

  3. A molecular phylogeny of the marine red algae (Rhodophyta) based on the nuclear small-subunit rRNA gene.

    Science.gov (United States)

    Ragan, M A; Bird, C J; Rice, E L; Gutell, R R; Murphy, C A; Singh, R K

    1994-01-01

    A phylogeny of marine Rhodophyta has been inferred by a number of methods from nucleotide sequences of nuclear genes encoding small subunit rRNA from 39 species in 15 orders. Sequence divergences are relatively large, especially among bangiophytes and even among congeners in this group. Subclass Bangiophycidae appears polyphyletic, encompassing at least three lineages, with Porphyridiales distributed between two of these. Subclass Florideophycidae is monophyletic, with Hildenbrandiales, Corallinales, Ahnfeltiales, and a close association of Nemaliales, Acrochaetiales, and Palmariales forming the four deepest branches. Cermiales may represent a convergence of vegetative and reproductive morphologies, as family Ceramiaceae is at best weakly related to the rest of the order, and one of its members appears to be allied to Gelidiales. Except for Gigartinales, for which more data are required, the other florideophyte orders appear distinct and taxonomically justified. A good correlation was observed with taxonomy based on pit-plug ultrastructure. Tests under maximum-likelihood and parsimony of alternative phylogenies based on structure and chemistry refuted suggestions that Acrochaetiales is the most primitive florideophyte order and that Gelidiales and Hildenbrandiales are sister groups. PMID:8041780

  4. U2AF1 mutations alter splice site recognition in hematological malignancies.

    Science.gov (United States)

    Ilagan, Janine O; Ramakrishnan, Aravind; Hayes, Brian; Murphy, Michele E; Zebari, Ahmad S; Bradley, Philip; Bradley, Robert K

    2015-01-01

    Whole-exome sequencing studies have identified common mutations affecting genes encoding components of the RNA splicing machinery in hematological malignancies. Here, we sought to determine how mutations affecting the 3' splice site recognition factor U2AF1 alter its normal role in RNA splicing. We find that U2AF1 mutations influence the similarity of splicing programs in leukemias, but do not give rise to widespread splicing failure. U2AF1 mutations cause differential splicing of hundreds of genes, affecting biological pathways such as DNA methylation (DNMT3B), X chromosome inactivation (H2AFY), the DNA damage response (ATR, FANCA), and apoptosis (CASP8). We show that U2AF1 mutations alter the preferred 3' splice site motif in patients, in cell culture, and in vitro. Mutations affecting the first and second zinc fingers give rise to different alterations in splice site preference and largely distinct downstream splicing programs. These allele-specific effects are consistent with a computationally predicted model of U2AF1 in complex with RNA. Our findings suggest that U2AF1 mutations contribute to pathogenesis by causing quantitative changes in splicing that affect diverse cellular pathways, and give insight into the normal function of U2AF1's zinc finger domains. © 2015 Ilagan et al.; Published by Cold Spring Harbor Laboratory Press.

  5. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  6. General Nuclear Medicine

    Science.gov (United States)

    ... Resources Professions Site Index A-Z General Nuclear Medicine Nuclear medicine imaging uses small amounts of radioactive ... of General Nuclear Medicine? What is General Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  7. Children's (Pediatric) Nuclear Medicine

    Science.gov (United States)

    ... Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts ... Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical imaging ...

  8. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Resources Professions Site Index A-Z Children's (Pediatric) Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small ... of Children's Nuclear Medicine? What is Children's (Pediatric) Nuclear Medicine? Nuclear medicine is a branch of medical ...

  9. Nuclear survivin and its relationship to DNA damage repair genes in non-small cell lung cancer investigated using tissue array.

    Directory of Open Access Journals (Sweden)

    Songliu Hu

    Full Text Available To investigate the predictive role and association of nuclear survivin and the DNA double-strand breaks repair genes in non-small cell lung cancer (NSCLC: DNA-dependent protein kinase catalytic subunit (DNA-PKcs, Ku heterodimeric regulatory complex 70-KD subunit (Ku70 and ataxia-telangiectasia mutated (ATM.The protein expression of nuclear survivin, DNA-PKcs, Ku70 and ATM were investigated using immunohistochemistry in tumors from 256 patients with surgically resected NSCLC. Furthermore, we analyzed the correlation between the expression of nuclear survivin, DNA-PKcs, Ku70 and ATM. Univariate and multivariate analyses were performed to determine the prognostic factors that inuenced the overall survival and disease-free survival of NSCLC.The expression of nuclear survivin, DNA-PKcs, Ku70 and ATM was significantly higher in tumor tissues than in normal tissues. By dichotomizing the specimens as expressing low or high levels of nuclear survivin, nuclear survivin correlated significantly with the pathologic stage (P = 0.009 and lymph node status (P = 0.004. The nuclear survivin levels were an independent prognostic factor for both the overall survival and the disease-free survival in univariate and multivariate analyses. Patients with low Ku70 and DNA-PKcs expression had a greater benefit from radiotherapy than patients with high expression of Ku70 (P = 0.012 and DNA-PKcs (P = 0.02. Nuclear survivin expression positively correlated with DNA-PKcs (P<0.001 and Ku70 expression (P<0.001.Nuclear survivin may be a prognostic factor for overall survival in patients with resected stage I-IIIA NSCLC. DNA-PKcs and Ku70 could predict the effect of radiotherapy in patients with NSCLC. Nuclear survivin may also stimulates DNA double-strand breaks repair by its interaction with DNA-PKcs and Ku70.

  10. Utilization of small-angle neutron scattering to decide the maximum loading of nuclear waste in cement matrix

    International Nuclear Information System (INIS)

    Das, Avik; Mazumder, S.; Sen, D.; Yalmali, V.; Shah, J.G.

    2014-01-01

    Nuclear power plants generate many kinds of hazardous nuclear waste which are needed to be disposed in an eco-friendly manner. Many different waste incarceration techniques have been adapted for managing the nuclear waste of different category of radioactivity. Immobilisation of low and intermediate level radioactive wastes in cement matrix is one of the widely used and cost-effective techniques in waste management. However, loading of nuclear waste in cement matrix can alter the mesoscopic structure of the hydrated cement and hence, it is very important to set the maximum limit of waste loading in cement for providing proper physical isolation to the nuclear waste

  11. Small zeolite column tests for removal of cesium from high radioactive contaminated water in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hijikata, Takatoshi; Uozumi, Koichi; Tukada, Takeshi; Koyama, Tadafumi; Ishikawa, Keiji; Ono, Shoichi; Suzuki, Shunichi; Denton, Mark; Raymont, John

    2011-01-01

    After the earthquake on March 11th 2011, a large amount (more than 0.12 million m 3 ) of highly radioactive contaminated water had pooled in Fukushima Daiichi nuclear power station. As an urgent issue, highly radioactive nuclides should be removed from this contaminated water to reduce radioactivity in the turbine buildings and nuclear reactor buildings. Removal of Cs from this contaminated water is a key issue, because 134 Cs and 137 Cs are highly radioactive γ-emitting nuclides. The zeolite column system was used for Cs and Sr removal from the radioactive water of Three-Mile Island Unit 2, and modified columns were then developed as a Cs removal method for high-level radioactive water in US national laboratories (WRSC, ORNL, PNNL, Hanford, etc.). In order to treat Fukushima's highly contaminated water with a similar system, it was necessary to understand the properties of zeolite to remove Cs from sea salt as well as the applicability of the column system to a high throughput of around 1200 m 3 /d. The kinetic characteristics of the column were another property to be understood before actual operation. Hence, a functional small-scale zeolite column system was installed in CRIEPI for conducting the experiments to understand decontamination behaviors. Each column has a 2- or 3-cm inner diameter and a 12-cm height, and 12 g of zeolite-type media was packed into the column. The column experiments were carried out with Kurion-zeolite, Herschelite, at different feed rates of simulated water with different concentrations of Cs and sea salt. As for the water with 4 ppm Cs and 0 ppm sea salt, only a 10% Cs concentration was observed in the effluent after 20,000 bed volumes were fed at a rate of 33 cm/min, which corresponds to the actual system. On the other hand, a 40% Cs concentration was observed in the effluent after only 50 bed volumes were passed for water with 2 ppm Cs and 3.4 wt.% sea salt at a feed rate of 34 cm/min. As the absorption of Cs is hampered by the

  12. Unlimited Horizons: Design and Development of the U-2. [NASA Aeronautics Book Series

    Science.gov (United States)

    Merlin, Peter W.

    2015-01-01

    This book describes the creation, history, design, and research value of the U-2 program. It also describes the involvement of NACA, as a cover story, and the later use by NASA of these aircraft as environmental research platforms.

  13. Unobtrusive Software and System Health Management with R2U2 on a Parallel MIMD Coprocessor

    Science.gov (United States)

    Schumann, Johann; Moosbrugger, Patrick

    2017-01-01

    Dynamic monitoring of software and system health of a complex cyber-physical system requires observers that continuously monitor variables of the embedded software in order to detect anomalies and reason about root causes. There exists a variety of techniques for code instrumentation, but instrumentation might change runtime behavior and could require costly software re-certification. In this paper, we present R2U2E, a novel realization of our real-time, Realizable, Responsive, and Unobtrusive Unit (R2U2). The R2U2E observers are executed in parallel on a dedicated 16-core EPIPHANY co-processor, thereby avoiding additional computational overhead to the system under observation. A DMA-based shared memory access architecture allows R2U2E to operate without any code instrumentation or program interference.

  14. Childhood leukemia near nuclear plants in the United Kingdom: The evolution of a systematic approach to studying rare disease in small geographic areas

    International Nuclear Information System (INIS)

    Beral, V.

    1990-01-01

    A cluster of childhood leukemia in a village near a nuclear plant in northern England prompted further studies of cancer in the vicinity of other nuclear plants in the United Kingdom. These studies demonstrated that the risk of childhood leukemia was increased near certain other nuclear plants. Although the reasons for the increase are still unclear, the scientific debate stimulated by these findings has clarified some of the special methodological problems encountered when studying rare diseases in small areas. Firstly, unless a specific hypothesis is defined in advance, the relevance of a single geographic cluster of disease can rarely be interpreted. Even when a prior hypothesis exists, the small number of cases which generally occur in a small area make the findings highly sensitive to reporting, diagnostic, or classification errors. The statistical power of such investigations is also usually low and only marked increases in risk can be detected. Furthermore, conventional statistical tests may be inappropriate if the underlying spatial distribution of the disease is not random; and little is known about the background distribution of disease in small areas. Investigations of specific hypotheses about defined sources of environmental contamination, especially if they can be replicated, are more likely to result in conclusive findings that are in-depth studies of individual clusters

  15. Bordeaux Gradignan Nuclear Research Centre - CENBG - 2005-2008 Activity report. From infinitely small to infinitely large, nuclear science in the service of mankind

    International Nuclear Information System (INIS)

    2009-01-01

    The Bordeaux Gradignan Nuclear Research Centre (CENBG) is a joint research unit of the CNRS/IN2P3 and the University Bordeaux 1 'Science and Technology'. The laboratory is composed of permanent researchers, permanent engineers and technicians and PhD students, post-docs and visitors. The scientific program covers a broad range of topics in nuclear physics, particle physics, astro-particle physics as well as applications of subatomic physics to different multidisciplinary fields. The main research subjects are: exotic nuclei far from the valley of beta stability and rare radioactive decays; neutrino physics (type and mass of the neutrino) and double beta decay; high energy gamma ray astronomy; innovative approaches to nuclear power generation and transmutation of nuclear waste; laser induced nuclear excitations; the effects of various environmental exposures studied via macro, micro or nano-ion beams using the new platform AIFIRA; and finally theoretical studies of nuclear and hadronic matter. All these activities take place within strong national and international collaborations involving the academic world and enabling the selection and training of high-quality students and post-doctoral researchers. To promote dissemination in the regional and national network, within the technologies developed at the laboratory in the domain of characterization with beams of ions or neutrons, there exists a transfer unit ARCANE which works through contracts. This document is the 2005-2008 Activity report of CNBG, content: 1 - Foreword; 2 - Research activities (Astro-particle, downstream of the fuel cycle and nuclear energy; laser nuclear excitations; physics-biology interface; neutrino and low radioactivities; exotic nuclei; theoretical physics); 3 - Services; 4 - Platform and cell facilities; 5 - other actions; 6 - scientific production; 7 - personnel

  16. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  17. How to balance the future in a small country with huge traditions of nuclear applications: the Swedish example

    International Nuclear Information System (INIS)

    Pazsit, Imre

    2005-01-01

    After a short historical perspective of how the Swedish energy situation has reached the present status, the paper says that the interplay of many beneficial circumstances put Sweden into the nuclear track toward the peaceful utilization of nuclear energy and technology at a very early stage of development in Europe. It adds then that the future of nuclear power in Sweden, just as in the previous decades, is not predictable in detail. It is however likely that nuclear power remains a significant contributor of electricity production in the coming decades, either at the same or an increased level, in the frame of a long-term agreement and consensus between industry and government. (S. Ohno)

  18. Proposal for the small high temperature gas cooled reactor (application of nuclear energy in the changing and emerging energy markets)

    International Nuclear Information System (INIS)

    Remond R Pahladsingh

    2005-01-01

    With the peaking of the oil-production (2006) on the global energy-markets, already predicted by M.K. Hubbert in 1970 and the limited possibilities to use coal as an alternative, the world has come in a critical situation. Exponential growth in global population and the demand of energy (IEA) have created a unique, but known, problem in the present time. The difference with the past is the period in which the changes will take place is not centuries or decades but most likely a few years. There is no alternative for oil to anticipate on the coming energy-crisis. The coal-industry has been demolished in Europe and America, under the pressure of the environmental lobby, and the nuclear industry is in very bad shape. Large scale nuclear plants can only be built in strong power grids; the present power grids are exposed to de-investment and less maintenance in liberalized and de-regulated economies. Furthermore the Digital Society is placing additional requirements on reliability and quality of our electric power systems. Life extension programs in the nuclear industry have shown that the present industry is robust, safety standards are high but at the same time no breakthrough technology has come to the market. The manpower in the nuclear industry is ageing. There are no real indications of growth in the large scale nuclear industry. The present industry is heavily relaying on the present grid concepts that have shown many difficulties in recent past and the increased failures in power-grids will create constraints to excel the option of nuclear energy in the electric power industry This paper is a request to the nuclear industry to come with a revival program, easy to implement nuclear technology and to help the world to solve the huge energy-problems that present and future generations are facing in the world. The proposal in the paper is a request to bring nuclear energy back in our society (Yes in my backyard-YIMBY) so that the many fruitful uses of nuclear energy

  19. Non-circadian expression masking clock-driven weak transcription rhythms in U2OS cells.

    Directory of Open Access Journals (Sweden)

    Julia Hoffmann

    Full Text Available U2OS cells harbor a circadian clock but express only a few rhythmic genes in constant conditions. We identified 3040 binding sites of the circadian regulators BMAL1, CLOCK and CRY1 in the U2OS genome. Most binding sites even in promoters do not correlate with detectable rhythmic transcript levels. Luciferase fusions reveal that the circadian clock supports robust but low amplitude transcription rhythms of representative promoters. However, rhythmic transcription of these potentially clock-controlled genes is masked by non-circadian transcription that overwrites the weaker contribution of the clock in constant conditions. Our data suggest that U2OS cells harbor an intrinsically rather weak circadian oscillator. The oscillator has the potential to regulate a large number of genes. The contribution of circadian versus non-circadian transcription is dependent on the metabolic state of the cell and may determine the apparent complexity of the circadian transcriptome.

  20. Split-Family SUSY, U(2)^5 Flavour Symmetry and Neutrino Physics

    CERN Document Server

    Jones-Pérez, Joel

    2014-01-01

    In split-family SUSY, one can use a U(2)^3 symmetry to protect flavour observables in the quark sector from SUSY contributions. However, attempts to extend this procedure to the lepton sector by using an analogous U(2)^5 symmetry fail to reproduce the neutrino data without introducing some form of fine-tuning. In this work, we solve this problem by shifting the U(2)^2 symmetry acting on leptons towards the second and third generations. This allows neutrino data to be reproduced without much difficulties, as well as protecting the leptonic flavour observables from SUSY. Key signatures are a $\\mu\\to e\\gamma$ branching ratio possibly observable in the near future, as well as having selectrons as the lightest sleptons.

  1. Determination of interstitial oxygen atom position in U2N3+xOy by near edge structure study

    Science.gov (United States)

    Jiang, A. K.; Zhao, Y. W.; Long, Z.; Hu, Y.; Wang, X. F.; Yang, R. L.; Bao, H. L.; Zeng, R. G.; Liu, K. Z.

    2018-06-01

    The determination of interstitial oxygen atom site in U2N3+xOy film could facilitate the understanding of the oxidation mechanism of α-U2N3 and the effect of U2N3+xOy on anti-oxidation. By comparing the similarities and variances between N K edge and O K edge electron energy loss spectra (EELS) for oxidized α-U2N3 and UO2, the present work looks at the local structure of nitrogen and oxygen atoms in U2N3+xOy film, identifying the most possible position of interstitial O atom.

  2. Decree No. 79-623 of 13 July 1979 publishing the Decision on the exclusion of certain categories of nuclear substances from the scope of the Convention of 29 July 1960 on Third Party Liability in the Field of Nuclear Energy and the Decision (with an annex) on the exclusion of small quantities of nuclear substances from the scope of the Convention of 29 July 1960 on Third Party Liability in the Field of Nuclear Energy, adopted on 27 October 1977

    International Nuclear Information System (INIS)

    1979-01-01

    This decree lays down that certain specified quantities and categories of nuclear substances are excluded from the nuclear operator's liability. This implements in France two Decisions taken by the NEA Steering Committee under the Paris Convention which enables the Committee to exclude from the operator's liability, nuclear installations, fuel or substances if the small extent of the risks involved so warrants. Both Decisions are reproduced in the Decree. (NEA) [fr

  3. Application of laboratory data from small-scale simulators to human performance issues in the nuclear industry

    International Nuclear Information System (INIS)

    Spettell, C.M.

    1986-01-01

    Laboratory analogs of nuclear power plant tasks were simulated on personal computers in two experimental studies. Human performance data were collected during each experimental study. The goal of the first experiment was to validate a quantitative model of dependence among human errors during testing, calibration, and maintenance activities. This model, the Multiple Sequential Failure (MSF) model (NUREG/CR-2211) has been used to quantify dependent human error failure probabilities for human reliability analyses in Probabilistic Risk Assessments (PRAs). The goal of the second experiment was to examine the relationship among psychological and behavioral characteristics of individuals and their performance at controlling a simulated nuclear power plant. These studies demonstrated the usefulness of the experimental psychology approach for validating models of human performance at nuclear power plant tasks

  4. Small-medium sized nuclear coal and gas power plant: A probabilistic analysis of their financial performances and influence of CO2 cost

    International Nuclear Information System (INIS)

    Locatelli, Giorgio; Mancini, Mauro

    2010-01-01

    Nations or regions with limited electrical grid and restricted financial resources are a suitable market for small medium power plants with a size of 300-400 MWe. The literature presents several comparisons about the economics of large power plants (of about 1000 MWe); however there are not probabilistic analysis regarding the economics of small medium power plants. This paper fills this gap comparing, with a Monte Carlo evaluation, the economical and financial performances of a nuclear reactor, a coal fired power plant and a combined cycle gas turbine (CCGT) of 335 MWe. The paper aims also to investigate the effect of the carbon tax and electrical energy price on the economics of these plants. The analysis show as, without any carbon tax, the coal plant has the lowest levelised unit electricity cost (LUEC) and the highest net present value (NPV). Introducing the carbon tax the rank changes: depending on its amount the first and the nuclear after becomes the plant with lower LUEC and highest NPV. Therefore, the uncertainty in the carbon tax cost increases the risk of investing in a coal plant above the level of the new small medium reactor.

  5. Modeling the effect in of criticality from changes in key parameters for small High Temperature Nuclear Reactor (U-BatteryTM) using MCNP4C

    International Nuclear Information System (INIS)

    Pauzi, A M

    2013-01-01

    The neutron transport code, Monte Carlo N-Particle (MCNP) which was wellkown as the gold standard in predicting nuclear reaction was used to model the small nuclear reactor core called U -battery TM, which was develop by the University of Manchester and Delft Institute of Technology. The paper introduces on the concept of modeling the small reactor core, a high temperature reactor (HTR) type with small coated TRISO fuel particle in graphite matrix using the MCNPv4C software. The criticality of the core were calculated using the software and analysed by changing key parameters such coolant type, fuel type and enrichment levels, cladding materials, and control rod type. The criticality results from the simulation were validated using the SCALE 5.1 software by [1] M Ding and J L Kloosterman, 2010. The data produced from these analyses would be used as part of the process of proposing initial core layout and a provisional list of materials for newly design reactor core. In the future, the criticality study would be continued with different core configurations and geometries.

  6. Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Cardenas V, J.; Mugica R, C. A.; Godinez S, V.

    2013-10-01

    In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft 2 (4.6 cm 2 ), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

  7. Point group invariants in the Uqp(u(2)) quantum algebra picture

    International Nuclear Information System (INIS)

    Kibler, M.

    1993-07-01

    Some consequences of a qp-quantization of a point group invariant developed in the enveloping algebra of SU(2) are examined. A set of open problems concerning such invariants in the U qp (u(2)) quantum algebra picture is briefly discussed. (author) 18 refs

  8. The Role of U2AF1 Mutations in the Pathogenesis of Myelodysplastic Syndromes

    Science.gov (United States)

    2016-12-01

    splicing contribute to disease patho mutation in the spliceosome gene U2AF1 and observed hemat also occur in patients with MDS or acute myeloid...Method for Combining Non-Independent, One-Sided Tests of Significance. Biometrics 31, 987–992. Buschbeck, M., Uribesalgo, I., Wibowo, I., Rué, P

  9. Investigations of mechanical properties and Debye temperature of U2Ti

    International Nuclear Information System (INIS)

    Chattaraj, D.; Dash, Smruti; Kulkarni, S.G.

    2012-01-01

    U 2 Ti is a potential solid state material for safe storage, supply and recovery of hydrogen isotopes. It is not pyrophoric and its hydride is resistance to powdering upon hydrogenation. These two properties made this alloy advantageous over the conventionally used uranium as tritium getter material. Hence, thorough study of material properties like thermodynamic and elastic properties of U 2 Ti is important. Recently, present authors have reported thermodynamic functions for U 2 Ti. However, elastic moduli of this alloy have not been reported. The second derivatives of the internal energy with respect to strain, gives adiabatic elastic constants. Thus adiabatic elastic constants are related to interatomic potentials of material. They are also related to the thermal properties of a solid through the Debye theory. For metal hydride material, the elastic constants are useful for an evaluation of the elastic contribution to the hydrogen-hydrogen interaction energy and the elastic energy associated with the precipitation of hydride phases. The present paper reports the ultrasonic measurement of the elastic moduli and Debye temperature of U 2 Ti at room temperature using 38 DL plus ultrasonic velocitymeter

  10. Characterization of off-gases from a small-scale, joule-heated ceramic melter for nuclear waste vitrification

    International Nuclear Information System (INIS)

    Woolsey, G.B.; Wilhite, E.L.

    1980-01-01

    This paper confirmed with actual nuclear waste the thermodynamic predictions of the fate of some of the semivolatiles in off-gas. Ruthenium behaves erratically and it is postulated that it migrates as a finely divided solid, rather than as a volatile oxide. Provisions for handling these waste off-gasses will be incorporated in the design of facilities for vitrifying SRP waste

  11. Structural instability and ground state of the U_2Mo compound

    International Nuclear Information System (INIS)

    Losada, E.L.; Garcés, J.E.

    2015-01-01

    This work reports on the structural instability at T = 0 °K of the U_2Mo compound in the C11_b structure under the distortion related to the C_6_6 elastic constant. The electronic properties of U_2Mo such as density of states (DOS), bands and Fermi surface (FS) are studied to understand the source of the instability. The C11_b structure can be interpreted as formed by parallel linear chains along the z-directions each one composed of successive U–Mo–U blocks. Hybridization due to electronic interactions inside the U–Mo–U blocks is slightly modified under the D_6 distortion. The change in distance between chains modifies the U–U interaction and produces a split of f-states. The distorted structure is stabilized by a decrease in energy of the hybridized states, mainly between d-Mo and f-U states, together with the f-band split. Consequently, an induced Peierls distortion is produced in U_2Mo due to the D_6 distortion. It is important to note that the results of this work indicate that the structure of the ground state of the U_2Mo compound is not the assumed C11_b structure. It is suggested for the ground state a structure with hexagonal symmetry (P6 #168), ∼0.1 mRy below the energy of the recently proposed Pmmn structure. - Highlights: • Structural instability of the C11b compound due to the D6 deformation. • Induced Peierls distortion due to the D6 deformation. • Distorted structure is stabilized by hybridization and split of f-Uranium state. • P6 (#168) suggested ground state for the U_2Mo compound.

  12. Multinode analysis of small breaks for B and W's 177-fuel-assembly nuclear plants with raised loop arrangement and internals vent valves

    International Nuclear Information System (INIS)

    Cartin, L.R.; Hill, J.M.; Parks, C.E.

    1976-03-01

    Multinode analyses were conducted for several small breaks in the reactor coolant system of B and W's 177-fuel-assembly nuclear plants with a raised loop arrangement and internals vent valves. The multinode blowdown code CRAFT was used to evaluate the hydrodynamics and transient water inventories of the reactor coolant system. The FOAM code was used to compute a swell level history for the core, and THETAL-B was used to perform transient fuel pin thermal calculations. Curves showing parameters of interest are presented. The results of these analyses are acceptable within the guidelines set forth in the Final Acceptance Criteria

  13. The possibility of the mixed valence state in the uranium intermetallic compounds: UCoGa5, U2Ru2Sn and U2RuGa8

    International Nuclear Information System (INIS)

    Troc, Robert

    2007-01-01

    The mixed valence (MV) phenomenon has been observed so far in a large number of various compounds but containing only lanthanides. These properties are usually associated with the mixing of the localised f-state and the band states. The usual valence state for magnetic uranium intermetallics is the trivalent state 5f 3 or hybridised 5f 2 6d 1 , both are nearly degenerate in energy and can compete for a stability of the compound. In some cases a gain in an energy minimum may be achieved by very fast fluctuating between these two states with a time of 10 -14 s, which does not allow to yield the ordered state even if the exchange interactions (favourite the U-U distances) would be able for that. The latter cases seem to concern the described here intermetallics: one ternary compound based on Co, UCoGa 5 , and the two uranium ternary compounds based on Ru, namely U 2 Ru 2 Sn and U 2 RuGa 8 which all crystallize in a tetragonal unit cell. All these compounds show a maximum in their temperature dependences of the magnetic susceptibility measured along and perpendicular to the c-axis. Such a behaviour, which is reminiscent of a number of Ce (Sm, Eu) and Yb compounds for which χ(T) has in the past been considered by Sales and Wohlleben (SW) by applying their ICF model or by Lawrance et al. following their scaling procedure. It turned out that these phenomenological models can also be applied to the considered here two Ru-based uranium ternaries from which some reliable energy parameters could be found. In order to further support the mixing valence scenario for the first such cases in uranium compounds presented here, the transport and thermodynamic properties are also discussed. However, some of the most important results confirming the MV state, e.g., in U 2 RuGa 8 , has recently been achieved from the inelastic neutron scattering performed in the Rutherford Appleton Laboratory on the ISIS facility. From these measurements a characteristic gap of 60 meV has been

  14. Development of a numerical code for the analysis of the linear stability of the U1 and U2 reactors of the CNLV

    International Nuclear Information System (INIS)

    Espinosa P, G.; Estrada P, C.E.; Nunez C, A.; Amador G, R.

    2001-01-01

    The computer code ANESLI-1 developed by the CNSNS and UAM-I, has the main goal of making stability analysis of nuclear reactors of the BWR type, more specifically, the reactors of the U1 and U2 of the CNLV. However it can be used for another kind of applications. Its capacity of real time simulator, allows the prediction of operational transients, and conditions of dynamic steady states. ANESLI-1 was developed under a modular scheme, which allows to extend or/and to improve its scope. The lineal stability analysis predicts the instabilities produced by the wave density phenomenon. (Author)

  15. Gene expression analyses of the small intestine of pigs in the ex-evacuation zone of the Fukushima Daiichi Nuclear Power Plant.

    Science.gov (United States)

    Morimoto, Motoko; Kato, Ayaka; Kobayashi, Jin; Okuda, Kei; Kuwahara, Yoshikazu; Kino, Yasushi; Abe, Yasuyuki; Sekine, Tsutomu; Fukuda, Tomokazu; Isogai, Emiko; Fukumoto, Manabu

    2017-11-15

    After the accident at the Fukushima Daiichi Nuclear Power Plant, radioactive contaminants were released over a widespread area. Monitoring the biological effects of radiation exposure in animals in the ex-evacuation zone should be continued to understand the health effects of radiation exposure in humans. The present study aimed to clarify the effects of radiation by investigating whether there is any alteration in the morphology and gene expressions of immune molecules in the intestine of pigs and inobuta (wild boar and domestic pig hybrid) in the ex-evacuation zone in 2012. Gene expression analysis was performed in small intestine samples from pigs, which were collected from January to February 2012, in the ex-evacuation zone. Pigs lived freely in this zone, and their small intestine was considered to be affected by the dietary intake of radioactive contaminants. Several genes were selected by microarray analysis for further investigation using real-time polymerase chain reaction. IFN-γ, which is an important inflammatory cytokine, and TLR3, which is a pattern recognize receptor for innate immune system genes, were highly elevated in these pigs. The expressions of the genes of these proteins were associated with the radiation level in the muscles. We also examined the alteration of gene expressions in wild boars 5 years after the disaster. The expression of IFN-γ and TLR3 remained high, and that of Cyclin G1, which is important in the cell cycle, was elevated. We demonstrated that some changes in gene expression occurred in the small intestine of animals in the ex-evacuation zone after radiation. It is difficult to conclude that these alterations are caused by only artificial radionuclides from the Fukushima Daiichi Nuclear Power Plant. However, the animals in the ex-evacuation zone might have experienced some changes owing to radioactive materials, including contaminated soil, small animals, and insects. We need to continue monitoring the effects of long

  16. Development of technologies for nuclear reactors of small and medium sized; Desarrollo de Tecnologias para Reactores Nucleares de pequeno y medio tamano

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-08-15

    This meeting include: countries presentations, themes and objectives of the training course, reactor types, design, EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, ATMEA 1, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR, React ores enfriados con metales liquidos, Hs, Prism,Terra Power, Hyper ion, appliance's no electric as de energia, Generation IV Reactors,VHTR, Gas Fast Reactor, Sodium Fast Reactor, Molten salt Reactor, Lfr, Water Cooled Reactor, Technology Assessment Process, Fukushima accident.

  17. Mpn1, Mutated in Poikiloderma with Neutropenia Protein 1, Is a Conserved 3′-to-5′ RNA Exonuclease Processing U6 Small Nuclear RNA

    Directory of Open Access Journals (Sweden)

    Vadim Shchepachev

    2012-10-01

    Full Text Available Clericuzio-type poikiloderma with neutropenia (PN is a rare genodermatosis associated with mutations in the C16orf57 gene, which codes for the uncharacterized protein hMpn1. We show here that, in both fission yeasts and humans, Mpn1 processes the spliceosomal U6 small nuclear RNA (snRNA posttranscriptionally. In Mpn1-deficient cells, U6 molecules carry 3′ end polyuridine tails that are longer than those in normal cells and lack a terminal 2′,3′ cyclic phosphate group. In mpn1Δ yeast cells, U6 snRNA and U4/U6 di-small nuclear RNA protein complex levels are diminished, leading to precursor messenger RNA splicing defects, which are reverted by expression of either yeast or human Mpn1 and by overexpression of U6. Recombinant hMpn1 is a 3′-to-5′ RNA exonuclease that removes uridines from U6 3′ ends, generating terminal 2′,3′ cyclic phosphates in vitro. Finally, U6 degradation rates increase in mpn1Δ yeasts and in lymphoblasts established from individuals affected by PN. Our data indicate that Mpn1 promotes U6 stability through 3′ end posttranscriptional processing and implicate altered U6 metabolism as a potential mechanism for PN pathogenesis.

  18. High-pressure study of the non-Fermi liquid material U2Pt2In

    International Nuclear Information System (INIS)

    Estrela, P.; Visser, A. de; Boer, F.R. de; Pereira, L.C.J.

    2001-01-01

    The effect of hydrostatic pressure (p≤1.8 GPa) on the non-Fermi liquid state of U 2 Pt 2 In is investigated by electrical resistivity measurements in the temperature interval 0.3-300 K. The experiments were carried out on single-crystals with the current along (I parallel c) and perpendicular (I parallel a) to the tetragonal axis. The pressure effect is strongly current-direction dependent. For I parallel a we observe a rapid recovery of the Fermi-liquid T 2 -term with pressure. A comparison of the data with the magnetotransport theory of Rosch provides evidence for the location of U 2 Pt 2 In at an antiferromagnetic quantum critical point. For I parallel c the resistivity increases under pressure, indicating the enhancement of an additional scattering mechanism. (orig.)

  19. Magnetic structure of the heavy-fermion compound U2Zn17

    DEFF Research Database (Denmark)

    Cox, D. E; Shirane, G.; Shapiro, S. M.

    1986-01-01

    The phase transition of U2Zn17 at 9.7K has been investigated by neutron powder diffraction. The transition corresponds to the onset of antiferromagnetic order where the U moments are oriented antiparallel to their neighbors within the basal planes and the near neighbor along the c^ axis of this r...... of this rhombohedral compound. At 5K, the ordered moments lie within the basal planes and are of magnitude (0.8±0.1) μB, which is substantially below the paramagnetic moment of 2.25 μB/U atom given by high-temperature susceptibility data......The phase transition of U2Zn17 at 9.7K has been investigated by neutron powder diffraction. The transition corresponds to the onset of antiferromagnetic order where the U moments are oriented antiparallel to their neighbors within the basal planes and the near neighbor along the c^ axis...

  20. Small chances - great consequences or the consequences of a large-scale accident in a nuclear power plant

    International Nuclear Information System (INIS)

    Dijk, G. van; Smit, W.A.

    1977-01-01

    This report is a sequel to the previous Boerderijcahier (no. 7502) which discussed long-term effects of soil contamination in case of a nuclear power plant accident. In this report the short-term health effects are discussed. Models describing the local consequences of a severe accident are developed, taking into account the possible weather conditions (meteorological model), the evacuation possibilities and the inhabitability of certain areas. In each case long-term and short-term effects are discussed. The safety studies by various departments of the Netherlands' government and the Rasmussen report are commented on

  1. A small floating seawater desalination plant by using a nuclear heating reactor coupled with the MED process

    Energy Technology Data Exchange (ETDEWEB)

    Xue Dazhi; Zhang Dafang; Dong Duo [Institute of Nuclear Energy Technology, Tsinghua University, Beijing (China)

    2000-03-01

    Based on the experience of development of nuclear district heating reactor (NHR) a seawater desalination plant using NHR coupled with the multi-effect distillation (MED) process is being designed. With the same technology a floating desalination plant was proposed to supply potable water to remote areas or islands. With a 10 MWth NHR the floating plant could produce 4000 m{sup 3}/d of potable water and 750 kW of electricity. The design of NHR-10 and the safety features are described. The coupling scheme and parameters are given. Some special considerations for using in ship condition are also presented in this paper. (author)

  2. Synthesis, crystal structure and magnetic properties of U2RuGa8

    International Nuclear Information System (INIS)

    Grin', Yu.N.; Rogl', P.; Aksel'rud, L.G.; Pecharskij, V.K.; Yarmolyuk, Ya.P.

    1988-01-01

    Synthesis of a new uranium intermetallic compound of U 2 RuGa 8 composition was conducted. The compound crystallizes in Ho 2 CoGa 8 structural type, met earlier only in compounds of rare earths. Magnetic susceptibility of the compound is rather high and is practically independent of temperature in 80-300 K range. This feature is typical for paramagnetism of electron gas and testifies to the absence of localized magnetic moments on ruthenium and uranium atoms

  3. Lower Neurocognitive Function in U-2 Pilots: Relationship to White Matter Hyperintensities

    Science.gov (United States)

    2014-07-09

    computer-based instrument, more com- prehensive neuropsychological testing is required to draw conclu- sions about the general cognitive profile of...consistency with other neuropsychological instrument batteries.24 MRI assessment. Structural MRI data for U2Ps were collected at the Research Imaging...report no disclo- sures. L. Rowland serves as an editorial board member of Schizophrenia Bulletin and is funded by NIH grants R01MH094520 and

  4. Small things matter: Implications of APP intracellular domain AICD nuclear signaling in the progression and pathogenesis of Alzheimer's disease.

    Science.gov (United States)

    Bukhari, Hassan; Glotzbach, Annika; Kolbe, Katharina; Leonhardt, Gregor; Loosse, Christina; Müller, Thorsten

    2017-09-01

    Alzheimer's disease (AD) is the most common neurodegenerative disease with tens of millions of people affected worldwide. The pathogenesis is still poorly understood and various therapeutical approaches targeting the amyloid β (Aβ) peptide, a product of the amyloidogenic cleavage of the amyloid precursor protein (APP), failed. Moreover, a couple of studies critically questioned the relevance of Aβ in the pathogenesis of AD. Thus, new ideas need to be studied and one highly interesting hypothesis is the APP mediated signal transduction to the nucleus. As a consequence nuclear -potentially toxic- structures emerge, which were recently found to a high extent in human AD tissue and thus, may contribute to neurodegeneration. Relevant for the signaling machinery are modifications at the very C-terminal end of the precursor protein, the APP intracellular domain (AICD). In this review we update the knowledge on mechanisms on AICD referring to our 2008 article: The amyloid precursor protein intracellular domain (AICD) as modulator of gene expression, apoptosis, and cytoskeletal dynamics-Relevance for Alzheimer's disease (T. Muller, et al., 2008). We summarize how AICD is generated and degraded, we describe its intramolecular motifs, translational modifications, and how those as well as APP dimerization influence AICD generation and function. Moreover, we resume the AICD interactome and elucidate AICDs involvement in nuclear signaling, transcriptional regulation, cell death, DNA repair and cell cycle re-entry and we give insights in its physiological function. Results are summarized in the comprehensive poster "The world of AICD". Copyright © 2017 Elsevier Ltd. All rights reserved.

  5. Characterization of infiltration into fractured, welded tuff using small borehole data collection technique: State of Nevada, agency for nuclear projects/nuclear waste project office

    International Nuclear Information System (INIS)

    Linderfelt, W.

    1986-10-01

    Knowledge of all aspects of the hydrologic cycle is required for consideration of Yucca mountain as a high level radioactive waste site. Surface processes are especially important in controlling the quantity and quality of water infiltrating into the unsaturated zone, available for recharging the aquifer. The investigation reported herein uses small bore drill holes to access the near surface fractured rock environment. The study was conducted in northern Nevada at the north end of the Pah Rah range, east of Pyramid Lake as an analog to Yucca Mountain. The results of this study will be used to better understand the chemistry and flow of the near surface flow regime of Yucca Mountain and to evaluate proposed techniques for use in future investigations. 7 refs., 6 figs., 3 tabs

  6. Dihydroptychantol A, a macrocyclic bisbibenzyl derivative, induces autophagy and following apoptosis associated with p53 pathway in human osteosarcoma U2OS cells

    International Nuclear Information System (INIS)

    Li Xia; Wu, William K.K.; Sun Bin; Cui Min; Liu Shanshan; Gao Jian; Lou Hongxiang

    2011-01-01

    Dihydroptychantol A (DHA), a novel macrocyclic bisbibenzyl compound extracted from liverwort Asterella angusta, has antifungal and multi-drug resistance reversal properties. Here, the chemically synthesized DHA was employed to test its anti-cancer activities in human osteosarcoma U2OS cells. Our results demonstrated that DHA induced autophagy followed by apoptotic cell death accompanied with G 2 /M-phase cell cycle arrest in U2OS cells. DHA-induced autophagy was morphologically characterized by the formation of double membrane-bound autophagic vacuoles recognizable at the ultrastructural level. DHA also increased the levels of LC3-II, a marker of autophagy. Surprisingly, DHA-mediated apoptotic cell death was potentiated by the autophagy inhibitor 3-methyladenine, suggesting that autophagy may play a protective role that impedes the eventual cell death. Furthermore, p53 was shown to be involved in DHA-meditated autophagy and apoptosis. In this connection, DHA increased nuclear expression of p53, induced p53 phosphorylation, and upregulated p53 target gene p21 Waf1/Cip1 . In contrast, cytoplasmic p53 was reduced by DHA, which contributed to the stimulation of autophagy. In relation to the cell cycle, DHA decreased the expression of cyclin B 1 , a cyclin required for progression through the G 2 /M phase. Taken together, DHA induces G 2 /M-phase cell cycle arrest and apoptosis in U2OS cells. DHA-induced apoptosis was preceded by the induction of protective autophagy. DHA-mediated autophagy and apoptosis are associated with the cytoplasmic and nuclear functions of p53.

  7. Calculation of the real part of the nuclear amplitude at high s and small t from the Coulomb amplitude

    Energy Technology Data Exchange (ETDEWEB)

    Gauron, P.; Nicolescu, B. [Universite Pierre et Marie Curie, Theory Group, Lab. de Physique Nucleaire et des Hautes Energies (LPNHE), CNRS 75 - Paris (France)

    2005-07-01

    A new method for the determination of the real part of the elastic scattering amplitude is examined for high energy proton-proton at small momentum transfer. This method allows us to decrease the number of model assumptions, to obtain the real part in a narrow region of momentum transfer and to test different models. The possible non-exponential behavior of the real part was found on the base of the analysis of the ISR experimental data. (authors)

  8. Contribution to the U$_2$C$_3$ formation by the synthetic reaction and by the decomposition of UC$_2$; Beitrag zur U$_2$C$_3$-bildung nach der synthetischen reaktion und durch zerfall von UC$_2$

    Energy Technology Data Exchange (ETDEWEB)

    Buschinelli, A. J.A.

    1974-06-01

    This work is a contribution to the study of the mechanism and of the kinetics of the U$_2$C$_3$ formation by the synthetic reaction. The influences of a mechanical and a thermical pre-treatment of the samples on the reaction kinetics were investigated and discussed taking into account other information from the literature. The relative increasing of the U$_2$C$_3$ nucleation rate due to the pulverization corresponds approximately to the surface enlargement of the pulverized material. The activation energy for the synthetic reaction in powder was found to be 94 +- 7 kcal/mol. The negative influence of nitrogen, oxygen and tungsten on the U$_2$C$_3$ formation was reported. In the decomposition of UC$_2$ to U$_2$C$_3$ and graphite, the influences of the morphology of the graphite precipitate and the fast neutron irradiation on the beginning of the U$_2$C$_3$ formation were also investigated.

  9. Small Molecule Antagonists of the Nuclear Androgen Receptor for the Treatment of Castration-Resistant Prostate Cancer.

    Science.gov (United States)

    Johnson, James K; Skoda, Erin M; Zhou, Jianhua; Parrinello, Erica; Wang, Dan; O'Malley, Katherine; Eyer, Benjamin R; Kazancioglu, Mustafa; Eisermann, Kurtis; Johnston, Paul A; Nelson, Joel B; Wang, Zhou; Wipf, Peter

    2016-08-11

    After a high-throughput screening campaign identified thioether 1 as an antagonist of the nuclear androgen receptor, a zone model was developed for structure-activity relationship (SAR) purposes and analogues were synthesized and evaluated in a cell-based luciferase assay. A novel thioether isostere, cyclopropane (1S,2R)-27, showed the desired increased potency and structural properties (stereospecific SAR response, absence of a readily oxidized sulfur atom, low molecular weight, reduced number of flexible bonds and polar surface area, and drug-likeness score) in the prostate-specific antigen luciferase assay in C4-2-PSA-rl cells to qualify as a new lead structure for prostate cancer drug development.

  10. Nuclear reactor plant with a small gas-cooled HT reactor accommodated in a steel pressure vessel

    International Nuclear Information System (INIS)

    Schoening, J.; Elter, C.

    1986-01-01

    The plant has a small HT reactor and an He/He heat exchanger situated above this, with preferably two parallel circulating blowers connected after it. It also has at least one post-shutdown heat removal system, which is situated after the He/He heat exchanger in the direction of flow and which always has the total quantity of primary helium flowing through it. In one version of the design, the heat exchanger consists of two concentric bundles of helices connected after one another, which have primary helium flowing in one direction and secondary helium in the opposite direction. (orig./HP) [de

  11. Risks of nuclear waste disposal in space. III - Long-term orbital evolution of small particle distribution

    Science.gov (United States)

    Friedlander, A. L.; Wells, W. C.

    1980-01-01

    A study of long term risks is presented that treats an additional pathway that could result in earth reentry, namely, small radioactive particles released in solar orbit due to payload fragmentation by accidental explosion or meteoroid impact. A characterization of such an event and of the initial mass size distribution of particles is given for two extremes of waste form strength. Attention is given to numerical results showing the mass-time distribution of material and the fraction of initial mass intercepted by earth. It is concluded that it appears that program planners need not be to concerned about the risks of this particular failure mechanism and return pathway.

  12. South Africa's nuclear model: A small and innovative reactor is seen as the model for new electricity plants. The project is nearing the starting blocks

    International Nuclear Information System (INIS)

    Ferreira, Tom

    2004-01-01

    Although nuclear power generation has by far the best safety and environmental record of any technology in general use, it has for many years been unable to make any meaningful inroads into the wall of negative perceptions that have arisen against it. But sentiments are changing rapidly on a global scale. The flare-up of oil prices is a sobering reminder of the volatility in the energy market, the exhaustibility of fossil fuels and the urgent need for stable, reliable, non-polluting sources of electrical power that are indispensable to a modern industrial economy. Today, new types of nuclear plants are prized, and South Africa is moving ahead. The State energy provider, Eskom, is internationally regarded as the leader in the field of the Pebble Bed Modular Reactor (PBMR) technology, a 'new generation' nuclear power plant. A decision on the PBMR project's future is on the near horizon. Should approvals be received in the coming months to proceed to the project's next phase, construction of the PBMR demonstration plant will start in 2006, in which case the reactor will start in 2010 and handed over to the client, Eskom, in 2011. Eskom has conditionally undertaken to purchase the first commercial units. Pebble bed reactors are small, about one-sixth the size of most current nuclear plants. Multiple PBMRs can share a common control center and occupy an area of no more than three football fields. More specifically, the PBMR is a helium-cooled, graphite moderated high temperature reactor (HTR). The concept is based on experience in the UK, United States and particularly Germany where prototype reactors were operated successfully between the late 1960s and 1980s. Although it is not the only high-temperature, gas-cooled nuclear reactor being developed in the world, the South African project is internationally regarded as a front-runner. The South African PBMR includes unique and patented technological innovations which make it particularly competitive. The Chief Executive

  13. Bone marrow evaluation in small cell carcinoma of the lung. [Radiographic and nuclear medical examinations also performed

    Energy Technology Data Exchange (ETDEWEB)

    Giaccone, G.; Ciuffreda, L.; Donadio, M.; Ferrati, P.; Risio, M.; Leria, G.; Bonardi, G.; Calciati, A.

    1987-01-01

    Bone marrow examination is commonly included in the staging of small cell lung carcinoma (SCLC). We reviewed marrow samples of 103 patients. Marrow examination was mainly performed by unilateral or bilateral biopsy of iliac crests, using a Jamshidi needle. Only 6 of 97 evaluable cases (6.2%) were positive for marrow metastases at staging, and in 3 cases (3%) bone marrow was the only metastatic site. No focal metastases were found in additional sections made from the blocks of negative samples. In our experience bone marrow biopsy was of little value in staging SCLC. Bilateral biopsy plus aspirate, with the addition of more sophisticated staining techniques might, however, provide a higher yield of positive marrow involvement.

  14. Diffraction study on the nonstoichiometric α-U2N3+x phase

    International Nuclear Information System (INIS)

    Serizawa, H.; Fukuda, K.; Ishii, Y.; Funahashi, S.; Katsura, M.

    1993-01-01

    X-ray and neutron diffraction studies were performed on nonstoichiometric α-U 2 N 3+ x having a composition range 1.68 2 N 3+x in this composition range was distorted Mn 2 O 3 -type. Structure parameters of U and N atoms were determined. The results showed that positions of U atoms varied continuously with nitrogen content. No evidence of the modification from bcc to fcc could be obtained. Interatomic distances of U-U and U-N were determined. The position parameter of N atoms showed that N atoms were slightly deviated from the tetrahedral site. (author)

  15. Intense Resistance Exercise Promotes the Acute and Transient Nuclear Translocation of Small Ubiquitin-Related Modifier (SUMO-1 in Human Myofibres

    Directory of Open Access Journals (Sweden)

    Sebastian Gehlert

    2016-04-01

    Full Text Available Protein sumoylation is a posttranslational modification triggered by cellular stress. Because general information concerning the role of small ubiquitin-related modifier (SUMO proteins in adult skeletal muscle is sparse, we investigated whether SUMO-1 proteins will be subjected to time-dependent changes in their subcellular localization in sarcoplasmic and nuclear compartments of human type I and II skeletal muscle fibers in response to acute stimulation by resistance exercise (RE. Skeletal muscle biopsies were taken at baseline (PRE, 15, 30, 60, 240 min and 24 h post RE from 6 male subjects subjected to a single bout of one-legged knee extensions. SUMO-1 localization was determined via immunohistochemistry and confocal laser microscopy. At baseline SUMO-1 was localized in perinuclear regions of myonuclei. Within 15 and up to 60 min post exercise, nuclear SUMO-1 localization was significantly increased (p < 0.01, declining towards baseline levels within 240 min post exercise. Sarcoplasmic SUMO-1 localization was increased at 15 min post exercise in type I and up to 30 min post RE in type II myofibres. The changing localization of SUMO-1 proteins acutely after intense muscle contractions points to a role for SUMO proteins in the acute regulation of the skeletal muscle proteome after exercise.

  16. Evaluation of the applicability of existing nuclear power plant regulatory requirements in the U.S. to advanced small modular reactors.

    Energy Technology Data Exchange (ETDEWEB)

    LaChance, Jeffrey L.; Wheeler, Timothy A.; Farnum, Cathy Ottinger; Middleton, Bobby D.; Jordan, Sabina Erteza; Duran, Felicia Angelica; Baum, Gregory A.

    2013-05-01

    The current wave of small modular reactor (SMR) designs all have the goal of reducing the cost of management and operations. By optimizing the system, the goal is to make these power plants safer, cheaper to operate and maintain, and more secure. In particular, the reduction in plant staffing can result in significant cost savings. The introduction of advanced reactor designs and increased use of advanced automation technologies in existing nuclear power plants will likely change the roles, responsibilities, composition, and size of the crews required to control plant operations. Similarly, certain security staffing requirements for traditional operational nuclear power plants may not be appropriate or necessary for SMRs due to the simpler, safer and more automated design characteristics of SMRs. As a first step in a process to identify where regulatory requirements may be met with reduced staffing and therefore lower cost, this report identifies the regulatory requirements and associated guidance utilized in the licensing of existing reactors. The potential applicability of these regulations to advanced SMR designs is identified taking into account the unique features of these types of reactors.

  17. Prospects for the utilization of small nuclear plants for civil ships, floating heat and power stations and power seawater desalination complexes

    International Nuclear Information System (INIS)

    Polunichev, V.I.

    2000-01-01

    Small power nuclear reactor plants developed by OKB Mechanical Engineering are widely used as propulsion plants in various civil ships. Russia is the sole country in the world that possesses a powerful icebreaker and transport fleet which offers effective solution for vital socio-economic tasks of Russia's northern regions by maintaining a year-round navigation along the Arctic sea route. In the future, intensification of freighting volumes is expected in Arctic seas and at estuaries of northern rivers. Therefore, further replenishment of nuclear-powered fleet is needed by new generation ice-breakers equipped with advanced reactor plants. Adopted progressive design and technology solutions, reliable equipment and safety systems being continuously perfected on the basis of multi year operation experience feedback, addressing updated safety codes and achievement of science and technology, allow the advanced propulsion reactor plants of this type to be recommended as energy sources for floating heat and power co-generation stations and power-seawater desalination complexes. (author)

  18. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts of radioactive materials called radiotracers, a special ... is a branch of medical imaging that uses small amounts of radioactive material to diagnose and determine ...

  19. Development of a numerical code for the analysis of the linear stability of the U1 and U2 reactors of the CNLV; Desarrollo de un codigo numerico para el analisis de estabilidad lineal de los reactores de las U1 y U2 de la CNLV

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa P, G.; Estrada P, C.E. [Universidad Autonoma Metropolitana-Iztapalapa, 09000 Mexico D.F. (Mexico); Nunez C, A.; Amador G, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, Mexico D.F. (Mexico)

    2001-07-01

    The computer code ANESLI-1 developed by the CNSNS and UAM-I, has the main goal of making stability analysis of nuclear reactors of the BWR type, more specifically, the reactors of the U1 and U2 of the CNLV. However it can be used for another kind of applications. Its capacity of real time simulator, allows the prediction of operational transients, and conditions of dynamic steady states. ANESLI-1 was developed under a modular scheme, which allows to extend or/and to improve its scope. The lineal stability analysis predicts the instabilities produced by the wave density phenomenon. (Author)

  20. Hydrochemical patterns of a small lake and a stream in an uplifting area proposed as a repository site for spent nuclear fuel, Forsmark, Sweden

    Science.gov (United States)

    Rönnback, Pernilla; Åström, Mats

    2007-10-01

    SummaryThe overall aim of this study was to increase the understanding of the chemical dynamics of small catchments. The focus was on a small oligotropic lake and its major inflow stream in an uplifting area in eastern Sweden (Forsmark) proposed as a repository site for spent nuclear fuel. The hydrochemical sampling campaign lasted for nearly 4 years with sample collection monthly to semi-monthly, and continuous flow measurements carried out over the last 20 months. All this was done as part of the Swedish Nuclear Fuel and Waste Management Company's (SKBs) Site Investigation Programme. The major findings were: (1) as a result of the calcareous overburden caused by redistributed Paleozoic deposits, pH and the Ca and HCO3- concentrations were relatively high in both the stream and lake throughout the period, (2) limnic primary production resulted in decreased concentrations of Ca, HCO3-, NH4+, NO3- and Si, and increased pH and concentrations of chlorophyll a, O 2, DON, POC, PON and POP in the lake in summer, while in other seasons (in winter in particular) when the production was minimal or non-existent the concentrations in the lake and the inflow stream were similar, (3) intrusion of brackish-water resulted in moderately to strongly increased concentrations of Cl -, Na, Mg, Br -, SO42-, K and Sr in the lake: the ratio versus Cl - were for Na and Br - always similar to those in sea water, for Mg and SO42- similar to those in sea water at elevated Cl - concentrations (>3 mM), while K and Sr always occurred in relative excess as compared to sea water, (4) high U concentrations in both the stream and the lake was derived most likely from reduced U-minerals in the overburden and was predicted to be carried to >90% in the form of calcium uranyl carbonate, in a model in which colloidal Fe and Al oxyhydroxides were not considered, (5) the rare earth elements (REEs) had similar concentrations and fractionation patterns in the stream and lake, unlike those found in the

  1. Small nuclear power reactor emergency electric power supply system reliability comparative analysis; Analise da confiabilidade do sistema de suprimento de energia eletrica de emergencia de um reator nuclear de pequeno porte

    Energy Technology Data Exchange (ETDEWEB)

    Bonfietti, Gerson

    2003-07-01

    This work presents an analysis of the reliability of the emergency power supply system, of a small size nuclear power reactor. Three different configurations are investigated and their reliability analyzed. The fault tree method is used as the main tool of analysis. The work includes a bibliographic review of emergency diesel generator reliability and a discussion of the design requirements applicable to emergency electrical systems. The influence of common cause failure influences is considered using the beta factor model. The operator action is considered using human failure probabilities. A parametric analysis shows the strong dependence between the reactor safety and the loss of offsite electric power supply. It is also shown that common cause failures can be a major contributor to the system reliability. (author)

  2. Evaluation of ductile-brittle transition behavior with neutron irradiation in nuclear reactor pressure vessel steels using small punch test

    International Nuclear Information System (INIS)

    Kim, M. C.; Lee, B. S.; Oh, Y. J.

    2003-01-01

    A Small Punch (SP) test was performed to evaluate the ductile-brittle transition temperature before and after neutron irradiation in Reactor Pressure Vessel (RPV) steels produced by different manufacturing (refining) processes. The results were compared to the standard transition temperature shifts from the Charpy test and Master Curve fracture toughness test in accordance with the ASTM standard E1921. The samples were taken from 1/4t location of the vessel thickness and machined into a 10x10x0.5mm dimension. Irradiation of the samples was carried out in the research reactor at KAERI (HANARO) at about 290 .deg. C of the different fluence levels respectively. SP tests were performed in the temperature range of RT to -196 .deg. C using a 2.4mm diameter ball. For the materials before and after irradiation, SP transition temperatures (T sp ), which are determined at the middle of the upper and lower SP energies, showed a linear correlation with the Charpy index temperature, T 41J . T sp from the irradiated samples was increased as the fluence level increased and was well within the deviation range of the unirradiated data. The TSP had a correlation with the reference temperature (T 0 ) from the master curve method using a pre-cracked Charpy V-notched (PCVN) specimen

  3. Ground state structure of U2Mo: static and lattice dynamics study

    International Nuclear Information System (INIS)

    Mukherjee, D.; Sahoo, B.D.; Joshi, K.D.; Kaushik, T.C.

    2016-01-01

    According to experimental reports, the ground state stable structure of U 2 Mo is tetragonal. However, various theoretical studies performed in past do not get tetragonal phase as the stable structure at ambient conditions. Therefore, the ground state structure of U 2 Mo is still unresolved. In an attempt to understand the ground state properties of this system, we have carried out first principle electronic band structure calculations. The structural stability analysis carried out using evolutionary structure search algorithm in conjunction with ab-inito method shows that a hexagonal structure (space group P6/mmm) is the lowest enthalpy structure at ambient condition and remains stable upto 200 GPa. The elastic and lattice dynamical stability further supports the stability of this phase at ambient condition. Further, using the 0 K calculations in conjunction with finite temperature corrections, we have derived the isotherm and shock adiabat (Hugoniot) of this material. Various equilibrium properties such as ambient pressure volume, bulk modulus, pressure derivative of bulk modulus etc. are derived from equation of state. (author)

  4. Cyberinfrastructure for the collaborative development of U2U decision support tools

    Directory of Open Access Journals (Sweden)

    Larry L. Biehl

    2017-01-01

    Full Text Available This paper describes the use of cyberinfrastructure to create interactive applications as part of the Useful to Usable (U2U project. These applications transform historical climate data, knowledge, and models into decision support tools for end users such as crop farmers, university Extension educators, and other agricultural advisors. In creating a cyberinfrastructure to support the U2U project, four major challenges have been addressed: designing and developing highly usable web applications with frequent feedback, establishing a software engineering environment to support iterative development, integrating and synthesizing historical and current datasets from a variety of sources (local vs. remote, different access methods, and formats, and supporting project collaboration needs of data and document sharing, project management, and public outreach. The overall goals of the cyberinfrastructure and its architecture design are described. Methods for data retrieval and synthesis, as well as the various software components utilized are discussed. The development and integration of tools into the collaborative HUBzero framework are highlighted, including the use of HUBzero’s core features to share ideas, algorithms, and results. A highly iterative development process that includes feedback from experts and end-users to feed requirement definition, design and application updates are also examined.

  5. Subjective experiences of watching stereoscopic Avatar and U2 3D in a cinema

    Science.gov (United States)

    Pölönen, Monika; Salmimaa, Marja; Takatalo, Jari; Häkkinen, Jukka

    2012-01-01

    A stereoscopic 3-D version of the film Avatar was shown to 85 people who subsequently answered questions related to sickness, visual strain, stereoscopic image quality, and sense of presence. Viewing Avatar for 165 min induced some symptoms of visual strain and sickness, but the symptom levels remained low. A comparison between Avatar and previously published results for the film U2 3D showed that sickness and visual strain levels were similar despite the films' runtimes. The genre of the film had a significant effect on the viewers' opinions and sense of presence. Avatar, which has been described as a combination of action, adventure, and sci-fi genres, was experienced as more immersive and engaging than the music documentary U2 3D. However, participants in both studies were immersed, focused, and absorbed in watching the stereoscopic 3-D (S3-D) film and were pleased with the film environments. The results also showed that previous stereoscopic 3-D experience significantly reduced the amount of reported eye strain and complaints about the weight of the viewing glasses.

  6. An extended conventional fuel cycle for the B and W mPower{sup TM} small modular nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Scarangella, M. J. [Babcock and Wilcox Company, 109 Ramsey Place, Lynchburg, VA 24502 (United States)

    2012-07-01

    The B and W mPower{sup TM} reactor is a small pressurized water reactor (PWR) with an integral once-through steam generator and a thermal output of about 500 MW; it is intended to replace aging fossil power plants of similar output. The core is composed of 69 reduced-height PWR assemblies with the familiar 17 x 17 fuel rod array. The Babcock and Wilcox Company (B and W) is offering a core loading and cycle management plan for a four-year cycle based on its presumed attractiveness to potential customers. This option is a once-through fuel cycle in which the entire core is discharged and replaced after four years. In addition, a conventional fuel utilization strategy, employing a periodic partial reload and shuffle, was developed as an alternative to the four-year once-through fuel cycle. This study, which was performed using the Studsvik core design code suite, is a typical multi-cycle projection analysis of the type performed by most fuel management organizations such as fuel vendors and utilities. In the industry, the results of such projections are used by the financial arms of these organizations to assist in making long-term decisions. In the case of the B and W mPower reactor, this analysis demonstrates flexibility for customers who consider the once-through fuel cycle unacceptable from a fuel utilization standpoint. As expected, when compared to the once-through concept, reloads of the B and W mPower reactor will achieve higher batch average discharge exposure, will have adequate shut-down margin, and will have a relatively flat hot excess reactivity trend at the expense of slightly increased peaking. (authors)

  7. Electronic structure of crystalline uranium nitrides UN, U2N3 and UN2: LCAO calculations with the basis set optimization

    International Nuclear Information System (INIS)

    Evarestov, R A; Panin, A I; Bandura, A V; Losev, M V

    2008-01-01

    The results of LCAO DFT calculations of lattice parameters, cohesive energy and bulk modulus of the crystalline uranium nitrides UN, U 2 N 3 and UN 2 are presented and discussed. The LCAO computer codes Gaussian03 and Crystal06 are applied. The calculations are made with the uranium atom relativistic effective small core potential by Stuttgart-Cologne group (60 electrons in the core). The calculations include the U atom basis set optimization. Powell, Hooke-Jeeves, conjugated gradient and Box methods are implemented in the author's optimization package, being external to the codes for molecular and periodic calculations. The basis set optimization in LCAO calculations improves the agreement of the lattice parameter and bulk modulus of UN crystal with the experimental data, the change of the cohesive energy due to the optimization is small. The mixed metallic-covalent chemical bonding is found both in LCAO calculations of UN and U 2 N 3 crystals; UN 2 crystal has the semiconducting nature

  8. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  9. Safety issues and their ranking for 'small series' WWER-1000 nuclear power plants. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    2000-09-01

    This report presents the safety issues in 'small series' WWER-1000 nuclear power plants (NPPs). Safety issues are deviations from current recognized safety practices in design and operation judged to be safety significant by their impact on the plants' defence in depth. This report is intended to serve as reference for the development of plant specific safety improvement programmes and for the evaluation of measures proposed and/or implemented. The identification of safety issues is based on safety studies conducted by the operators of 'small series' WWER-1000 units and by organizations dealing with these reactors, on findings of IAEA safety missions to 'small series' WWER-1000 plants in South Ukraine, at Novovoronezh and Kalinin, and on information obtained from specialists from various countries during an IAEA consultants meeting, 8-12 September 1997 in Vienna, within the framework of the Extra budgetary Programme on the Safety of WWER and RBMK NPPs. Safety issues are first presented according to their impact on the main safety functions and are then described individually. The safety issues are characterized by issue title and specified by issue clarification. Safety issues connected with plant design are followed by the ranking of the issue and ranking justification. Altogether 85 safety issues have been identified, 12 of which are in Category III (defence in depth is insufficient, immediate corrective action is necessary), 38 in Category 11 (defence in depth is degraded, action is needed to resolve the issue) and 22 in Category I (departure from international practices, to be addressed as part of actions to resolve higher priority issues). In the case of operational safety issues (13 safety issues) no ranking is provided as the available material was considered insufficient. For each safety issue, comments and recommendations are made by the IAEA; the status of corresponding measures to improve safety implemented or planned at each site are presented in the

  10. Simple calculation of hybridization effects in UTX and U2T2X compounds

    International Nuclear Information System (INIS)

    Prokes, K.; Brueck, E.; Nakotte, H.; De Chatel, P.F.; De Boer, F.R.

    1995-01-01

    The band widths of several UTX and U 2 T 2 X compounds (T: transition metal, X: p-metal) are evaluated by means of a tight-binding method. The magnetism in both groups of compounds is governed by the hybridization between U f-states and transition-metal d-states. Comparing the sum of all hybridization effects, we find approximately the same hybridization effects in both groups of compounds. We also observe a decrease of the band width with increasing atomic number Z within a transition-metal series. By comparing the band width with the theoretical critical energies for the f 3 and f 2 configurations, it is in some cases possible to predict whether the ground state is magnetically ordered or not. ((orig.))

  11. Crystal structure of U2+xCo2Ga1-x

    International Nuclear Information System (INIS)

    Zelinskii, A.V.; Fedorchuk, A.A.

    1995-01-01

    In studies of phase equilibria in the U-Co-Ga system at 600 degrees C, the authors found a ternary compound close in composition to U 2 Co 2 Ga. A sample of composition U 42 Co 40 Ga 18 was prepared by arc-melting a mixture of high-purity U (99.4%), Co (99.99%), and Ga (99.99%) in a purified argon atmosphere. The sample was homogenized at 600 degrees C for 720 h in an evacuated quartz tube and then quenched in cold water. In structure determination, the authors used a DRON-4-07 powder X-ray diffractometer (CuK α radiation, 0.02 degrees 2θ scan step) and the CSD software package. The X-ray diffraction pattern showed tetragonal symmetry, with lattice parameters obtained from least-squares refinements a = 0.707729(5) and c = 0.34707(4) nm

  12. Reactor waste heat utilization and district heating reactors. Nuclear district heating in Sweden - Regional reject heat utilization schemes and small heat-only reactors

    International Nuclear Information System (INIS)

    Hannerz, K.; Larsson, Y.; Margen, P.

    1977-01-01

    A brief review is given of the current status of district heating in Sweden. In future, district heating schemes will become increasingly interesting as a means of utilizing heat from nuclear reactors. Present recommendations in Sweden are that large reactors should not be located closer than about 20 km from large population centres. Reject heat from such reactors is cheap at source. To minimize the cost of long distance hot water transmission large heat rates must be transmitted. Only areas with large populations can meet this requirement. The three areas of main interest are Malmoe/Lund/Helsingborg housing close to 0.5 million; Greater Stockholm housing 1 to 1.5 million and Greater Gothenburg housing about 0.5 million people. There is an active proposal that the Malmoe/Lund/Helsingborg region would be served by a third nuclear unit at Barsebaeck, located about 20 km from Malmoe/Lund and supplying 950 MW of base load heat. Preliminary proposals for Stockholm involve a 2000 MW heat supply; proposals for Gothenburg are more tentative. The paper describes progress on these proposals and their technology. It also outlines technology under development to increase the economic range of large scale heat transport and to make distribution economic even for low heat-density family housing estates. Regions apart from the few major urban areas mentioned above require the adoption of a different approach. To this end the development of a small, simple low-temperature reactor for heat-only production suitable for urban location has been started in Sweden in close contact with Finland. Some results of the work in progress are presented, with emphasis on the safety requirements. An outline is given in the paper as to how problems of regional heat planning and institutional and legislative issues are being approached

  13. Towards critical physics in 2+1d with U(2N)-invariant fermions

    Energy Technology Data Exchange (ETDEWEB)

    Hands, Simon [Department of Physics, College of Science, Swansea University,Singleton Park, Swansea SA2 8PP (United Kingdom)

    2016-11-04

    Interacting theories of N relativistic fermion flavors in reducible spinor representations in 2+1 spacetime dimensions are formulated on a lattice using domain wall fermions (DWF), for which a U(2N) global symmetry is recovered in the limit that the wall separation L{sub s} is made large. The Gross-Neveu (GN) model is studied in the large-N limit and an exponential acceleration of convergence to the large-L{sub s} limit is demonstrated if the usual parity-invariant mass mψ̄ψ is replaced by the U(2N)-equivalent im{sub 3}ψ̄γ{sub 3}ψ. The GN model and two lattice variants of the Thirring model are simulated for N=2 using a hybrid Monte Carlo algorithm, and studies made of the symmetry-breaking bilinear condensate and its associated susceptibility, the axial Ward identity, and the mass spectrum of both fermion and meson excitations. Comparisons are made with existing results obtained using staggered fermions. For the GN model a symmetry-breaking phase transition is observed, the Ward identity is recovered, and the spectrum found to be consistent with large-N expectations. There appears to be no obstruction to the study of critical UV fixed-point physics using DWF. For the Thirring model the Ward identity is not recovered, the spectroscopy measurements are inconclusive, and no symmetry breaking is observed all the way up to the effective strong coupling limit. This is consistent with a critical Thirring flavor number N{sub c}<2, contradicting earlier staggered fermion results.

  14. The near boiling reactor: Conceptual design of a small inherently safe nuclear reactor to extend the operational capability of the Victoria Class submarine

    Science.gov (United States)

    Cole, Christopher J. P.

    Nuclear power has several unique advantages over other air independent energy sources for nuclear combat submarines. An inherently safe, small nuclear reactor, capable of supply the hotel load of the Victoria Class submarines, has been conceptually developed. The reactor is designed to complement the existing diesel electric power generation plant presently onboard the submarine. The reactor, rated at greater than 1 MW thermal, will supply electricity to the submarine's batteries through an organic Rankine cycle energy conversion plant at 200 kW. This load will increase the operational envelope of the submarine by providing up to 28 continuous days submerged, allowing for an enhanced indiscretion ratio (ratio of time spent on the surface versus time submerged) and a limited under ice capability. The power plant can be fitted into the existing submarine by inserting a 6 m hull plug. With its simplistic design and inherent safety features, the reactor plant will require a minimal addition to the crew. The reactor employs TRISO fuel particles for increased safety. The light water coolant remains at atmospheric pressure, exiting the core at 96°C. Burn-up control and limiting excess reactivity is achieved through movable reflector plates. Shut down and regulatory control is achieved through the thirteen hafnium control rods. Inherent safety is achieved through the negative prompt and delayed temperature coefficients, as well as the negative void coefficient. During a transient, the boiling of the moderator results in a sudden drop in reactivity, essentially shutting down the reactor. It is this characteristic after which the reactor has been named. The design of the reactor was achieved through modelling using computer codes such as MCNP5, WIMS-AECL, FEMLAB, and MicroShield5, in addition to specially written software for kinetics, heat transfer and fission product poisoning calculations. The work has covered a broad area of research and has highlighted additional areas

  15. The near boiling reactor : conceptual design of a small inherently safe nuclear reactor to extend the operational capability of the Victoria Class submarine

    International Nuclear Information System (INIS)

    Cole, C.J.P.

    2005-01-01

    Nuclear power has several unique advantages over other air independent energy sources for nuclear combat submarines. An inherently safe, small nuclear reactor, capable of supply the hotel load of the 'Victoria' Class submarines, has been conceptually developed. The reactor is designed to complement the existing diesel electric power generation plant presently onboard the submarine. The reactor, rated at greater than 1 MW thermal, will supply electricity to the submarine's batteries through an organic Rankine cycle energy conversion plant at 200 kW. This load will increase the operational envelope of the submarine by providing up to 28 continuous days submerged, allowing for an enhanced indiscretion ratio (ratio of time spent on the surface versus time submerged) and a limited under ice capability. The power plant can be fitted into the existing submarine by inserting a 6 m hull plug. With its simplistic design and inherent safety features, the reactor plant will require a minimal addition to the crew. The reactor employs TRISO fuel particles for increased safety. The light water coolant remains at atmospheric pressure, exiting the core at 96 o C. Burn-up control and limiting excess reactivity is achieved through movable reflector plates. Shut down and regulatory control is achieved through the thirteen hafnium control rods. Inherent safety is achieved through the negative prompt and delayed temperature coefficients, as well as the negative void coefficient. During a transient, the boiling of the moderator results in a sudden drop in reactivity, essentially shutting down the reactor. It is this characteristic after which the reactor has been named. The design of the reactor was achieved through modelling using computer codes such as MCNP5, WIMS-AECL, FEMLAB, and MicroShield5, in addition to specially written software for kinetics, heat transfer and fission product poisoning calculations. The work has covered a broad area of research and has highlighted additional

  16. Modulation of expression of the nuclear receptor NR0B2 (small heterodimer partner 1 and its impact on proliferation of renal carcinoma cells

    Directory of Open Access Journals (Sweden)

    Prestin K

    2016-08-01

    Full Text Available Katharina Prestin,1,* Maria Olbert,2,* Janine Hussner,1 Tamara L Isenegger,1 Daniel G Gliesche,1 Kerstin Böttcher,2 Uwe Zimmermann,3 Henriette E Meyer zu Schwabedissen1 1Department of Pharmaceutical Sciences, Biopharmacy, University of Basel, Basel, Switzerland; 2Center of Drug Absorption and Transport, Institute of Pharmacology, 3Department of Urology, University Medicine Greifswald, Greifswald, Germany *These authors contributed equally to this work Abstract: Mammalian nuclear receptors (NRs are transcription factors regulating the expression of target genes that play an important role in drug metabolism, transport, and cellular signaling pathways. The orphan and structurally unique receptor small heterodimer partner 1 (syn NR0B2 is not only known for its modulation of drug response, but has also been reported to be involved in hepatocellular carcinogenesis. Indeed, previous studies show that NR0B2 is downregulated in human hepatocellular carcinoma, suggesting that NR0B2 acts as a tumor suppressor via inhibition of cellular growth and activation of apoptosis in this tumor entity. The aim of our study was to elucidate whether NR0B2 may also play a role in other tumor entities. Comparing NR0B2 expression in renal cell carcinoma and adjacent nonmalignant transformed tissue revealed significant downregulation in vivo. Additionally, the impact of heterologous expression of NR0B2 on cell cycle progression and proliferation in cells of renal origin was characterized. Monitoring fluorescence intensity of resazurin turnover in RCC-EW cells revealed no significant differences in metabolic activity in the presence of NR0B2. However, there was a significant decrease of cellular proliferation in cells overexpressing this NR, and NR0B2 was more efficient than currently used antiproliferative agents. Furthermore, flow cytometry analysis showed that heterologous overexpression of NR0B2 significantly reduced the amount of cells passing the G1 phase, while on

  17. Structural Basis for Polypyrimidine Tract Recognition by the Essential Pre-mRNA Splicing Factor U2AF65

    International Nuclear Information System (INIS)

    Sickmier, E.; Frato, K.; Shen, H.; Paranawithana, S.; Green, M.; Kielkopf, C.

    2006-01-01

    The essential pre-mRNA splicing factor, U2AF 65 , guides the early stages of splice site choice by recognizing a polypyrimidine (Py)-tract consensus sequence near the 3'-splice site. Since Py-tracts are relatively poorly conserved in higher eukaryotes, U2AF 65 is faced with the problem of specifying uridine-rich sequences, yet tolerating a variety of nucleotide substitutions found in natural Py-tracts. To better understand these apparently contradictory RNA binding characteristics, the X-ray structure of the U2AF 65 RNA binding domain bound to a Py-tract composed of seven uridines has been determined at 2.5Angstroms resolution. Specific hydrogen bonds between U2AF 65 and the uracil bases provide an explanation for polyuridine recognition. Flexible sidechains and bound water molecules form the majority of the base contacts, and potentially could rearrange when the U2AF 65 structure adapts to different Py-tract sequences. The energetic importance of conserved residues for Py-tract binding is established by analysis of site-directed mutant U2AF 65 proteins using surface plasmon resonance

  18. Optimization of reloading Laguna Verde Central U1/U2, Federal Electricity Commission; Optimizacion de recargas Central Laguna Verde U1/U2, Comision Federal de Electricidad

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa G, J.M. [Central Nucleoelectrica Laguna Verde, Carretera Cardel-Nautla Km. 45.5, Municipio de Alto Lucero, Veracruz (Mexico)

    2006-07-01

    The Laguna Verde Central from the beginning of the commercial operation settled down as maximum priority 'the total safety in its operation' taking in consideration the so much experience of the good operation and of multiple recharges made in a sure and reliable way, and without separate us of the safety mystic of the CLV, but looking for to be better every day a new challenge it settled down 'to compare us with the best plants in the world' and certainly to work to classify us like one of them. For this we established a 4.0 year old plan (2003/2006) for the effectiveness all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level (nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station, attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect, summing up means to be good in all the aspects). All the above mentioned would allow us to qualify us as level 1 of WANO (world proprietors association of nuclear centrals) at the end of the year 2006 and to pass to be part of this select group. After analyzing the acting record of the power station, evaluating our technical and economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and availability besides the dose and production cost is the duration of the recharge periods, for this reason the present work is elaborated. (Author)

  19. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    International Nuclear Information System (INIS)

    Miller, Thomas M.; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-01-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical

  20. RNA-binding domain of the A protein component of the U1 small nuclear ribonucleoprotein analyzed by NMR spectroscopy is structurally similar to ribosomal proteins

    International Nuclear Information System (INIS)

    Hoffman, D.W.; Query, C.C.; Golden, B.L.; White, S.W.; Keene, J.D.

    1991-01-01

    An RNA recognition motif (RRM) of ∼80 amino acids constitutes the core of RNA-binding domains found in a large family of proteins involved in RNA processing. The U1 RNA-binding domain of the A protein component of the human U1 small nuclear ribonucleoprotein (RNP), which encompasses the RRM sequence, was analyzed by using NMR spectroscopy. The domain of the A protein is a highly stable monomer in solution consisting of four antiparallel β-strands and two α-helices. The highly conserved RNP1 and RNP2 consensus sequences, containing residues previously suggested to be involved in nucleic acid binding, are juxtaposed in adjacent β-strands. Conserved aromatic side chains that are critical for RNA binding are clustered on the surface to the molecule adjacent to a variable loop that influences recognition of specific RNA sequences. The secondary structure and topology of the RRM are similar to those of ribosomal proteins L12 and L30, suggesting a distant evolutionary relationship between these two types of RNA-associated proteins

  1. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Thomas M., E-mail: millertm@ornl.gov; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-12-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical.

  2. Simulation with the MELCOR code of two severe accident sequences, Station Blackout and Small Break LOCA, for the Atucha I nuclear power plant

    International Nuclear Information System (INIS)

    Valle Cepero, Reinaldo

    2004-01-01

    The results of the PSA-I applied to the Atucha I nuclear power plant (CNA I) determine the accidental sequences with the most influence related to the probability of the core reactor damage. Among those sequences are include, the Station Blackout and lost of primary coolant, combine with the failure of the emergency injection systems by pipe breaks of diameters between DN100 - DN25 or equivalent areas, Small LOCA. This paper has the objective to model and analyze the behavior of the primary circuit and the pressure vessel during the evolution of those two accidental sequences. It presented a detailed analysis of the main phenomena that occur from the initial moment of the accident to the failure moment of the pressure vessel and the melt material fall to the reactor cavity. Two sequences were taken into account, considering the main phenomena (core uncover, heating, fuel element oxidation, hydrogen generation, degradation and relocation of the melt material, failure of the support structures, etc.) and the time of occurrence, of those events will be different, if it is considered that both sequences will be developed in different scenarios. One case is an accident with the primary circuit to a high pressure (Station Blackout scenario) and the other with a early primary circuit depressurization due to the lost of primary coolant. For this work the MELCOR 1.8.5 code was used and it allows within a unified framework to modeling an extensive spectrum of phenomenology associated with the severe accidents. (author)

  3. Resveratrol enhances radiosensitivity of human non-small cell lung cancer NCI-H838 cells accompanied by inhibition of nuclear factor-kappa B activation

    International Nuclear Information System (INIS)

    Liao, Hui-Fen; Kuo Cheng-Deng; Yang, Yuh-Cheng; Lin, Chin-Ping; Tai, Hung-Chi; Chen, Yu-Jen; Chen, Yu-Yawn

    2005-01-01

    Resveratrol, a polyphenol in red wine, possesses many pharmacological activities including cardio-protection, chemoprevention, anti-tumor effects, and nuclear factor-kappa B (NF-κB) inactivation. The present study was designed to evaluate the effects and possible mechanism of resveratrol in enhancing radiosensitivity of lung cancer cells. Human non-small cell lung cancer NCI-H838 cells were irradiated with or without resveratrol pretreatment. The surviving fraction and sensitizer enhancement ratio (SER) were estimated by using a colony formation assay and linear-quadratic model. The cell-cycle distribution was evaluated by using prospidium iodide staining and flow cytometry. An enzyme-linked immunosorbent assay (ELISA)-based assay with immobilized oligonucleotide was performed to assess the DNA binding activity of NF-κB. Resveratrol had no direct growth-inhibitory effect on NCI-H838 cells treated for 24 hours with doses up to 25 μM. Pretreatment with resveratrol significantly enhanced cell killing by radiation, with an SER up to 2.2. Radiation activated NF-κB, an effect reversed by resveratrol pretreatment. Resveratrol resulted in a decrease of cells in the G 0 /G 1 phase and an increase in the S phase. Our results demonstrate that resveratrol enhances the radiosensitivity of NCI-H838 cells accompanied by NF-κB inhibition and S-phase arrest. (author)

  4. Topical Anti-Nuclear Factor-Kappa B Small Interfering RNA with Functional Peptides Containing Sericin-Based Hydrogel for Atopic Dermatitis

    Directory of Open Access Journals (Sweden)

    Takanori Kanazawa

    2015-09-01

    Full Text Available The small interfering RNA (siRNA is suggested to offer a novel means of treating atopic dermatitis (AD because it allows the specific silencing of genes related to AD pathogenesis. In our previous study, we found that siRNA targeted against RelA, an important nuclear factor-kappa B (NF-κB subdomain, with functional peptides, showed therapeutic effects in a mouse model of AD. In the present study, to develop a topical skin application against AD, we prepared a hydrogel containing anti-RelA siRNA and functional peptides and determined the intradermal permeation and the anti-AD effects in an AD mouse model. We selected the silk protein, sericin (SC, which is a versatile biocompatible biomaterial to prepare hydrogel as an aqueous gel base. We found that the siRNA was more widely delivered to the site of application in AD-induced ear skin of mice after topical application via the hydrogel containing functional peptides than via the preparation without functional peptides. In addition, the ear thickness and clinical skin severity of the AD-induced mice treated with hydrogel containing anti-RelA siRNA with functional peptides improved more than that of mice treated with the preparation formulated with negative siRNA.

  5. Lattice QCD at the physical point meets S U (2 ) chiral perturbation theory

    Science.gov (United States)

    Dürr, Stephan; Fodor, Zoltán; Hoelbling, Christian; Krieg, Stefan; Kurth, Thorsten; Lellouch, Laurent; Lippert, Thomas; Malak, Rehan; Métivet, Thibaut; Portelli, Antonin; Sastre, Alfonso; Szabó, Kálmán; Budapest-Marseille-Wuppertal Collaboration

    2014-12-01

    We perform a detailed, fully correlated study of the chiral behavior of the pion mass and decay constant, based on 2 +1 flavor lattice QCD simulations. These calculations are implemented using tree-level, O (a )-improved Wilson fermions, at four values of the lattice spacing down to 0.054 fm and all the way down to below the physical value of the pion mass. They allow a sharp comparison with the predictions of S U (2 ) chiral perturbation theory (χ PT ) and a determination of some of its low energy constants. In particular, we systematically explore the range of applicability of next-to-leading order (NLO) S U (2 ) χ PT in two different expansions: the first in quark mass (x expansion), and the second in pion mass (ξ expansion). We find that these expansions begin showing signs of failure for Mπ≳300 MeV , for the typical percent-level precision of our Nf=2 +1 lattice results. We further determine the LO low energy constants (LECs), F =88.0 ±1.3 ±0.2 and BMS ¯(2 GeV )=2.61 (6 )(1 ) GeV , and the related quark condensate, ΣMS ¯(2 GeV )=(272 ±4 ±1 MeV )3 , as well as the NLO ones, ℓ¯3=2.6 (5 )(3 ) and ℓ¯4=3.7 (4 )(2 ), with fully controlled uncertainties. We also explore the next-to-next-to-leading order (NNLO) expansions and the values of NNLO LECs. In addition, we show that the lattice results favor the presence of chiral logarithms. We further demonstrate how the absence of lattice results with pion masses below 200 MeV can lead to misleading results and conclusions. Our calculations allow a fully controlled, ab initio determination of the pion decay constant with a total 1% error, which is in excellent agreement with experiment.

  6. Creating subgroups of U(2w) for quantum-minus computers

    International Nuclear Information System (INIS)

    De Vos, Alexis; Boes, Michiel

    2011-01-01

    Classical reversible computers on w bits are isomorphic to the (finite) symmetric group S 2 w ; quantum computers on w qubits are isomorphic to the (Lie) unitary group U(2 w ). We investigate and classify groups X which represent computers intermediate between classical reversible computers and quantum computers. Such intermediate groups X may exist in three flavours: - finite groups of order larger than (2 w )!,; - infinite but discrete groups, and; - Lie groups of dimension smaller than (2 w ). The larger the group, the more powerful the computer may be, but the smaller the group, the easier it can be to build the computer hardware. In the present paper, we investigate the first two flavours only. For our purpose, we start from 1-qubit transformations, represented by 2 x 2 unitary matrices. We call this group the creator. Its members are called gates and act on one qubit. Controlled gates are quantum circuits acting on w qubits, such that the 1-qubit transformation (applied to a particular qubit) depends on the state of the w - 1 other qubits. The controlled gates generate the group X of 2 w x 2 w matrices, called the creation. We discuss all creators of order up to 8. Additionally a creator of order 16 and one of order 192 are discussed.

  7. Creating subgroups of U(2{sup w}) for quantum-minus computers

    Energy Technology Data Exchange (ETDEWEB)

    De Vos, Alexis; Boes, Michiel, E-mail: alex@elis.UGent.b [Imec v.z.w. and Vakgroep elektronika en informatiesystemen Universiteit Gent Sint Pietersnieuwstraat 41 B - 9000 Gent (Belgium)

    2011-03-01

    Classical reversible computers on w bits are isomorphic to the (finite) symmetric group S{sub 2}{sup w}; quantum computers on w qubits are isomorphic to the (Lie) unitary group U(2{sup w}). We investigate and classify groups X which represent computers intermediate between classical reversible computers and quantum computers. Such intermediate groups X may exist in three flavours: - finite groups of order larger than (2{sup w}); - infinite but discrete groups, and; - Lie groups of dimension smaller than (2{sup w}). The larger the group, the more powerful the computer may be, but the smaller the group, the easier it can be to build the computer hardware. In the present paper, we investigate the first two flavours only. For our purpose, we start from 1-qubit transformations, represented by 2 x 2 unitary matrices. We call this group the creator. Its members are called gates and act on one qubit. Controlled gates are quantum circuits acting on w qubits, such that the 1-qubit transformation (applied to a particular qubit) depends on the state of the w - 1 other qubits. The controlled gates generate the group X of 2{sup w} x 2{sup w} matrices, called the creation. We discuss all creators of order up to 8. Additionally a creator of order 16 and one of order 192 are discussed.

  8. IAEA news: • Newcomer countries face common challenges in nuclear infrastructure development. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators. • IAEA reaches milestone in disposal of radioactive sources

    International Nuclear Information System (INIS)

    Kollar, Lenka; Dyck, Elisabeth; Dixit, Aabha; Gaspar, Miklos; Gil, Laura

    2016-01-01

    • Newcomer countries face common challenges in nuclear infrastructure development: Countries embarking on a nuclear power programme need to make sure that the development of their legal, regulatory and support infrastructure keeps pace with the construction of the power plant itself. This is the only way to ensure that the programme proceeds in a safe, secure and sustainable way, concluded participants of a workshop on nuclear power infrastructure development hosted at the IAEA last February. • Safety and licensing requirements for small modular reactors: IAEA hosts first workshop for regulators: A new generation of advanced, prefab nuclear power reactors called small modular reactors (SMRs) could be licensed and hit the market as early as 2020, and the IAEA is helping regulators prepare for their debut. In a series of workshops that began earlier this year, the IAEA is working closely with regulators on approaches to safety and licensing ahead of potential SMR deployment worldwide. • IAEA reaches milestone in disposal of radioactive sources: Successful tests of a promising technology for moving and storing low level radioactive sealed sources are paving the way for a new disposal method for dealing with small volumes of radioactive waste around the world. The method, which involves placing and covering sealed sources in a narrow hole a few hundred metres deep, would allow countries to safely and securely take charge of their own disused radioactive sources. The proof of concept for the technology was tested in Croatia late last year — without the use of actual radioactive material.

  9. Contrast variation by dynamic nuclear polarization and time-of-flight small-angle neutron scattering. I. Application to industrial multi-component nanocomposites1

    Science.gov (United States)

    Noda, Yohei; Koizumi, Satoshi; Masui, Tomomi; Mashita, Ryo; Kishimoto, Hiroyuki; Yamaguchi, Daisuke; Kumada, Takayuki; Takata, Shin-ichi; Ohishi, Kazuki; Suzuki, Jun-ichi

    2016-01-01

    Dynamic nuclear polarization (DNP) at low temperature (1.2 K) and high magnetic field (3.3 T) was applied to a contrast variation study in small-angle neutron scattering (SANS) focusing on industrial rubber materials. By varying the scattering contrast by DNP, time-of-flight SANS profiles were obtained at the pulsed neutron source of the Japan Proton Accelerator Research Complex (J-PARC). The concentration of a small organic molecule, (2,2,6,6-tetramethylpiperidine-1-yl)oxy (TEMPO), was carefully controlled by a doping method using vapour sorption into the rubber specimens. With the assistance of microwave irradiation (94 GHz), almost full polarization of the paramagnetic electronic spin of TEMPO was transferred to the spin state of hydrogen (protons) in the rubber materials to obtain a high proton spin polarization (P H). The following samples were prepared: (i) a binary mixture of styrene–butadiene random copolymer (SBR) with silica particles (SBR/SP); and (ii) a ternary mixture of SBR with silica and carbon black particles (SBR/SP/CP). For the binary mixture (SBR/SP), the intensity of SANS significantly increased or decreased while keeping its q dependence for P H = −35% or P H = 40%, respectively. The q behaviour of SANS for the SBR/SP mixture can be reproduced using the form factor of a spherical particle. The intensity at low q (∼0.01 Å−1) varied as a quadratic function of P H and indicated a minimum value at P H = 30%, which can be explained by the scattering contrast between SP and SBR. The scattering intensity at high q (∼0.3 Å−1) decreased with increasing P H, which is attributed to the incoherent scattering from hydrogen. For the ternary mixture (SBR/SP/CP), the q behaviour of SANS was varied by changing P H. At P H = −35%, the scattering maxima originating from the form factor of SP prevailed, whereas at P H = 29% and P H = 38%, the scattering maxima disappeared. After decomposition of the total SANS according to inverse matrix

  10. Thermal properties of KUO3(s) and K2U2O7 - by high temperature Calvet calorimeter

    International Nuclear Information System (INIS)

    Jayanthi, K.; Iyer, V.S.; Venugopal, V.

    1998-01-01

    The thermal properties of KUO 3 (s) and K 2 U 2 O 7 (s) were determined using a high temperature Calvet calorimeter by drop method. The enthalpy increments, (H T o - H 298.15 0 ), in kJ/mol for KUO 3 (s) and K 2 U 2 O 7 (s) can be represented by, H T o - H 298.15 0 KUO 3 (s) kJ/mol ± 0.7 = -39.15 + 0.129T + 0.1005x10 -4 T 2 (369-714K) and H T o -H 298.15 0 K 2 U 2 O 7 (s) kJ/mol ± 0.7 = -52.99 + 0.1361T + 0.146x10 -3 T 2 (391 - 683K). (author)

  11. Epitope mapping of the U1 small nuclear ribonucleoprotein particle in patients with systemic lupus erythematosus and mixed connective tissue disease.

    Science.gov (United States)

    Somarelli, J A; Mesa, A; Rodriguez, R; Avellan, R; Martinez, L; Zang, Y J; Greidinger, E L; Herrera, R J

    2011-03-01

    Systemic lupus erythematosus (SLE) and mixed connective tissue disease (MCTD) are autoimmune illnesses characterized by the presence of high titers of autoantibodies directed against a wide range of 'self ' antigens. Proteins of the U1 small nuclear ribonucleoprotein particle (U1 snRNP) are among the most immunogenic molecules in patients with SLE and MCTD. The recent release of a crystallized U1 snRNP provides a unique opportunity to evaluate the effects of tertiary and quaternary structures on autoantigenicity within the U1 snRNP. In the present study, an epitope map was created using the U1 snRNP crystal structure. A total of 15 peptides were tested in a cohort of 68 patients with SLE, 29 with MCTD and 26 healthy individuals and mapped onto the U1 snRNP structure. Antigenic sites were detected in a variety of structures and appear to include RNA binding domains, but mostly exclude regions necessary for protein-protein interactions. These data suggest that while some autoantibodies may target U1 snRNP proteins as monomers or apoptosis-induced, protease-digested fragments, others may recognize epitopes on assembled protein subcomplexes of the U1 snRNP. Although nearly all of the peptides are strong predictors of autoimmune illness, none were successful at distinguishing between SLE and MCTD. The antigenicity of some peptides significantly correlated with several clinical symptoms. This investigation implicitly highlights the complexities of autoimmune epitopes, and autoimmune illnesses in general, and demonstrates the variability of antigens in patient populations, all of which contribute to difficult clinical diagnoses.

  12. Cycloalkyl-based unsymmetrical unsaturated (U2)-NHC ligands: Flexibility and dissymmetry in ruthenium-catalysed olefin metathesis

    KAUST Repository

    Rouen, Mathieu

    2014-01-01

    Air-stable Ru-indenylidene and Hoveyda-type complexes bearing new unsymmetrical unsaturated N-heterocyclic carbene (U2-NHC) ligands combining a mesityl unit and a flexible cycloalkyl moiety as N-substituents were synthesised. Structural features, chemical stabilities and catalytic profiles in olefin metathesis of this new library of cycloalkyl-based U2-NHC Ru complexes were studied and compared with their unsymmetrical saturated NHC-Ru homologues as well as a set of commercially available Ru-catalysts bearing either symmetrical SIMes or IMes NHC ligands. © 2014 the Partner Organisations.

  13. Nuclear materials

    International Nuclear Information System (INIS)

    1996-01-01

    In 1998, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) performed 38 inspections, 25 of them were performed in co-operation with IAEA inspectors. There is no fresh nuclear fuel at Bohunice A-1 NPP at present. Fresh fuel of Bohunice V-1 and V-2 NPPs is inspected in the fresh fuel storage.There are 327 fresh fuel assemblies in Mochovce NPP fresh fuel storage. In addition to that, are also 71 small users of nuclear materials in Slovakia. In most cases they use: covers made of depleted uranium for non-destructive works, detection of level in production plants, covers for therapeutical sources at medical facilities. In. 1995, NRA SR issued 4 new licences for nuclear material withdrawal. In the next part manipulation with nuclear materials, spent fuel stores and illegal trafficking in nuclear materials are reported

  14. Alpha Particles and X Rays Interact in Inducing DNA Damage in U2OS Cells.

    Science.gov (United States)

    Sollazzo, Alice; Brzozowska, Beata; Cheng, Lei; Lundholm, Lovisa; Haghdoost, Siamak; Scherthan, Harry; Wojcik, Andrzej

    2017-10-01

    Survivors of the atomic bombings of Hiroshima and Nagasaki are monitored for health effects within the Life Span Study (LSS). The LSS results represent the most important source of data about cancer effects from ionizing radiation exposure, which forms the foundation for the radiation protection system. One uncertainty connected to deriving universal risk factors from these results is related to the problem of mixed radiation qualities. The A-bomb explosions generated a mixed beam of the sparsely ionizing gamma radiation and densely ionizing neutrons. However, until now the possible interaction of the two radiation types of inducing biological effects has not been taken into consideration. The existence of such interaction would suggest that the application of risk factors derived from the LSS to predict cancer effects after pure gamma-ray irradiation (such as in the Fukushima prefecture) leads to an overestimation of risk. To analyze the possible interaction of radiation types, a mixed-beam exposure facility was constructed where cells can be exposed to sparsely ionizing X rays and densely ionizing alpha particles. U2OS cells were used, which are stably transfected with a plasmid coding for the DNA repair gene 53BP1 coupled to a gene coding for the green fluorescent protein (GFP). The induction and repair of DNA damage, which are known to be related to cancer induction, were analyzed. The results suggest that alpha particles and X rays interact, leading to cellular and possibly cancer effects, which cannot be accurately predicted based on assuming simple additivity of the individual mixed-beam components.

  15. Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2

    International Nuclear Information System (INIS)

    Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A.; Naranjo U, J. L.

    2013-10-01

    This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

  16. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... are small, diagnostic nuclear medicine procedures result in low radiation exposure, acceptable for diagnostic exams. Thus, the radiation risk is very low compared with the potential benefits. Nuclear medicine diagnostic ...

  17. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Tell your doctor about your child’s recent illnesses, medical conditions, medications and allergies. Depending on the type ... Nuclear Medicine? Nuclear medicine is a branch of medical imaging that uses small amounts of radioactive material ...

  18. RBC nuclear scan

    Science.gov (United States)

    ... page: //medlineplus.gov/ency/article/003835.htm RBC nuclear scan To use the sharing features on this page, please enable JavaScript. An RBC nuclear scan uses small amounts of radioactive material to ...

  19. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Nuclear Medicine? Nuclear medicine is a branch of medical imaging that uses small amounts of radioactive material to ... a radiologist or other physician. To locate a medical imaging or radiation oncology provider in your community, you ...

  20. Useful to Usable (U2U): Transforming climate information into usable tools to support Midwestern agricultural production

    Science.gov (United States)

    Prokopy, L. S.; Widhalm, M.

    2014-12-01

    There is a close connection between weather and climate patterns and successful agricultural production. Therefore, incorporating climate information into farm management is likely to reduce the risk of economic losses and increase profitability. While weather and climate information is becoming ever more abundant and accessible, the use of such information in the agricultural community remains limited. Useful to Usable (U2U): Transforming Climate Variability and Change Information for Cereal Crop Producers is a USDA-NIFA funded research and extension project focused on improving the use of climate information for agricultural production in the Midwestern United States by developing user-driven decision tools and training resources. The U2U team is a diverse and uniquely qualified group of climatologists, crop modelers, agronomists, and social scientists from 9 Midwestern universities and two NOAA Regional Climate Centers. Together, we strive to help producers make better long-term plans on what, when and where to plant and also how to manage crops for maximum yields and minimum environmental damage. To ensure relevance and usability of U2U products, our social science team is using a number of techniques including surveys and focus groups to integrate stakeholder interests, needs, and concerns into all aspects of U2U research. It is through this coupling of physical and social science disciplines that we strive to transform existing climate information into actionable knowledge.

  1. Conserved number of U2 snDNA sites in Piabina argentea, Piabarchus stramineus and two Bryconamericus species (Characidae, Stevardiinae

    Directory of Open Access Journals (Sweden)

    Diovani Piscor

    2018-03-01

    Full Text Available ABSTRACT The chromosomal location of 5S rRNA and U2 snRNA genes of Piabina argentea, Piabarchus stramineus and two Bryconamericus species from two different Brazilian river basins were investigated, in order to contribute to the understanding of evolutionary characteristics of these repetitive DNAs in the subfamily Stevardiinae. The diploid chromosome number was 2n = 52 for Bryconamericus cf. iheringii, Bryconamericus turiuba, Piabarchus stramineus and Piabina argentea. The 5S rDNA clusters were located on one chromosome pair in P. stramineus and B. cf. iheringii, and on two pairs in B. turiuba and P. argentea. The U2 snDNA clusters were located on the one pair in all species. Two-color FISH experiments showed that the co-localization between 5S rDNA and U2 snDNA in P. stramineus can represent a marker for this species. Thus, the present study demonstrated that the number of U2 snDNA clusters observed for the four species was conserved, but particular characteristics can be found in the genome of each species.

  2. Exact solutions of sl-boson system in U(2l + 1) reversible O(2l + 2) transitional region

    CERN Document Server

    Zhang Xin

    2002-01-01

    Exact eigen-energies and the corresponding wavefunctions of the interacting sl-boson system in U(2l + 1) reversible O(2l +2) transitional region are obtained by using an algebraic Bethe Ansatz with the infinite dimensional Lie algebraic technique. Numerical algorithm for solving the Bethe Ansatz equations by using mathematical package is also outlined

  3. Project EROS development of a new reactor concept with liquid fuel based on molten fluorides for reducing the amount and hazard of nuclear waste. Demonstration of promising P and T technology at small scale

    International Nuclear Information System (INIS)

    Hron, Miloslav J.

    2005-01-01

    concept of liquid fuel based on molten fluorides. The proposal and organization of the project was based upon the activity of the national consortium TRANSMUTATION having been established in November 1996 by four leading institutions in nuclear research: Nuclear Research Institute Rez plc, Nuclear Physics Institute of Academy of Sciences, SKODA Nuclear Machinery plc and Faculty of Nuclear Sciences and Physical Engineering of the Czech Technical University in Prague to whom Technical University in Brno (specialized for a secondary circuit problems) has associated in the year 2000. The governmental authorities of the Czech Republic as well as the future utilities of the developed technology: Radwaste Repository Authority, CEZ a.s. (Czech Power Comp.), SKODA Works Company Nuclear Machinery Branch plc and some other bodies have been providing necessary funding. The substantial part of the project has been incorporated in suitable forms of international collaboration; the European Union's, so called, Framework Programs are supposed to be the most convenient ones, in particular. The individual parts of the project have been incorporated to the corresponding tasks (Work Packages) of the MOST (Molten Salt Technology) Project of the 5th Framework Program of the EC since November 2001 for the period of two years and then they have been prolonged for two more years. There is a convenient incorporation of the whole complex being proposed into the 6th Framework Program for the next three years (2006-2008) as a basis for a European participation in the Generation IV as well as other forms of a multinational co-operation, too. There will be a current status of the project being focused on an experimental verification of the selected technology, in a full scale at room temperature and in a small scale under conditions close to operational, described in the paper. (author)

  4. Prognostic significance of nuclear factor of activated T-cells 5 expression in non-small cell lung cancer patients who underwent surgical resection.

    Science.gov (United States)

    Cho, Hyun Jin; Yun, Hwan-Jung; Yang, Hee Chul; Kim, Soo Jin; Kang, Shin Kwang; Che, Chengri; Lee, Sang Do; Kang, Min-Woong

    2018-06-01

    Nuclear factor of activated T-cells 5 (NFAT5) is known to be correlated with migration or invasion of tumor cells based on previous in vitro studies. The aim of this study was to analyze the relationship between NFAT5 expression and clinical prognosis in non-small cell lung cancer (NSCLC) patients who underwent surgical resection. A total of 92 NSCLC patients who underwent surgical resection were enrolled. The tissue microarray core was obtained from surgically resected tumor specimens. NFAT5 expression was evaluated by immunohistochemistry. Relationships of NFAT5 expression with disease recurrence, overall survival, and disease-free survival (DFS) were analyzed. The mean age of 92 patients was 63.7 y. The median follow-up duration was 63.3 mo. Fifty-one (55%) patients exhibited positive expression of NFAT5. Disease recurrence in the NFAT5-positive group was significantly (P = 0.022) higher than that in the NFAT5-negative group. NFAT5-positive expression (odds ratio: 2.632, 95% confidence interval: 1.071-6.465, P = 0.035) and pathologic N stage (N1-2 versus N0; odds ratio: 3.174, 95% confidence interval: 1.241-8.123, P = 0.016) were independent and significant risk factors for disease recurrence. DFS of the NFAT5-positive group was significantly worse than that of the NFAT5-negative group (89.7 versus 48.7 mo, P = 0.011). A multivariate analysis identified NFAT5 expression (P < 0.029) as a significant independent risk factor for DFS of patients with postoperative pathologic T and N stages (P < 0.001 and P = 0.017, respectively). NFAT5 expression is a useful prognostic biomarker for NSCLC patients who underwent surgical resection. Copyright © 2018 Elsevier Inc. All rights reserved.

  5. Optimization of reloading Laguna Verde Central U1/U2, Federal Electricity Commission

    International Nuclear Information System (INIS)

    Espinosa G, J.M.

    2006-01-01

    The Laguna Verde Central from the beginning of the commercial operation settled down as maximum priority 'the total safety in its operation' taking in consideration the so much experience of the good operation and of multiple recharges made in a sure and reliable way, and without separate us of the safety mystic of the CLV, but looking for to be better every day a new challenge it settled down 'to compare us with the best plants in the world' and certainly to work to classify us like one of them. For this we established a 4.0 year old plan (2003/2006) for the effectiveness all the processes in the power station that allowed us to measure our acting with the same parameters that settle down at international level (nuclear safety, industrial safety, radiological safety, capacity factor, readiness factor, cleaning of the power station, attachment to procedures, attention to the detail and certainly to be competitive in the economic aspect, summing up means to be good in all the aspects). All the above mentioned would allow us to qualify us as level 1 of WANO (world proprietors association of nuclear centrals) at the end of the year 2006 and to pass to be part of this select group. After analyzing the acting record of the power station, evaluating our technical and economic capacity, the location of the installation besides revising the international experiences was defined that one of the concepts that impact considerably so much to the capacity factors and availability besides the dose and production cost is the duration of the recharge periods, for this reason the present work is elaborated. (Author)

  6. A pan-cancer analysis of transcriptome changes associated with somatic mutations in U2AF1 reveals commonly altered splicing events.

    Directory of Open Access Journals (Sweden)

    Angela N Brooks

    Full Text Available Although recurrent somatic mutations in the splicing factor U2AF1 (also known as U2AF35 have been identified in multiple cancer types, the effects of these mutations on the cancer transcriptome have yet to be fully elucidated. Here, we identified splicing alterations associated with U2AF1 mutations across distinct cancers using DNA and RNA sequencing data from The Cancer Genome Atlas (TCGA. Using RNA-Seq data from 182 lung adenocarcinomas and 167 acute myeloid leukemias (AML, in which U2AF1 is somatically mutated in 3-4% of cases, we identified 131 and 369 splicing alterations, respectively, that were significantly associated with U2AF1 mutation. Of these, 30 splicing alterations were statistically significant in both lung adenocarcinoma and AML, including three genes in the Cancer Gene Census, CTNNB1, CHCHD7, and PICALM. Cell line experiments expressing U2AF1 S34F in HeLa cells and in 293T cells provide further support that these altered splicing events are caused by U2AF1 mutation. Consistent with the function of U2AF1 in 3' splice site recognition, we found that S34F/Y mutations cause preferences for CAG over UAG 3' splice site sequences. This report demonstrates consistent effects of U2AF1 mutation on splicing in distinct cancer cell types.

  7. Decompression Sickness and U-2 Operations: Summary of Research, Findings, and Recommendations Regarding Use of Exercise During Prebreathe

    Science.gov (United States)

    2010-03-01

    Research Laboratory Hypobaric DCS Research Database developed at Brooks AFB, TX, which has detailed information on over 3,000 research chamber... hyperbaric oxygen therapy resulting in complete resolution of all symptoms. After instituting EDP, the same pilot flew 36 U-2 high flights without any...consultation with base SGP and USAFSAM Hyperbarics and MAJCOM/SGPA. Earlier guidance in the 1980’s was much more restrictive and, in fact, permanently

  8. The influence of U-2 fraction of a tortoise spleen extract on the formation of ectopic locus of haemopoiesis

    International Nuclear Information System (INIS)

    Turdyev, A.A.; Prus, E.K.; Basova, A.R.

    1990-01-01

    The implantation of a bone marrow fragment of intact mouse donors below the kidney capsule of irradiated (7 Gy) recipients leads to the formation of the haemopoiesis locus that somewhat exceeds, by mass and cellularity, the new-formed locus of control animals. The U-2 fraction of a tortoise spleen extract administered to recipients irradiated with the same dose increases the mass and cellularity of the haemopoiesis locus by 2.2 and 4.9 times respectively

  9. Nuclear medicine

    International Nuclear Information System (INIS)

    Kand, Purushottam

    2012-01-01

    Nuclear medicine is a specialized area of radiology that uses very small amounts of radioactive materials to examine organ function and structure. Nuclear medicine is older than CT, ultrasound and MRI. It was first used in patients over 60-70 years ago. Today it is an established medical specialty and offers procedures that are essential in many medical specialities like nephrology, pediatrics, cardiology, psychiatry, endocrinology and oncology. Nuclear medicine refers to medicine (a pharmaceutical) that is attached to a small quantity of radioactive material (a radioisotope). This combination is called a radiopharmaceutical. There are many radiopharmaceuticals like DTPA, DMSA, HIDA, MIBI and MDP available to study different parts of the body like kidneys, heart and bones etc. Nuclear medicine uses radiation coming from inside a patient's body where as conventional radiology exposes patients to radiation from outside the body. Thus nuclear imaging study is a physiological imaging, whereas diagnostic radiology is anatomical imaging. It combines many different disciplines like chemistry, physics mathematics, computer technology, and medicine. It helps in diagnosis and to treat abnormalities very early in the progression of a disease. The information provides a quick and accurate diagnosis of wide range of conditions and diseases in a person of any age. These tests are painless and most scans expose patients to only minimal and safe amounts of radiation. The amount of radiation received from a nuclear medicine procedure is comparable to, or often many times less than, that of a diagnostic X-ray. Nuclear medicine provides an effective means of examining whether some tissues/organs are functioning properly. Therapy using nuclear medicine in an effective, safe and relatively inexpensive way of controlling and in some cases eliminating, conditions such as overactive thyroid, thyroid cancer and arthritis. Nuclear medicine imaging is unique because it provides doctors with

  10. Improving motor reliability in nuclear power plants: Volume 2, Functional indicator tests on a small electric motor subjected to accelerated aging

    International Nuclear Information System (INIS)

    Subudhi, M.; Taylor, J.H.; Lofaro, R.; Sugarman, A.C.; Sheets, M.W.; Skreiner, K.M.

    1987-11-01

    A ten horsepower electric motor was artificially aged by plug reverse cycling for test purposes. The motor was manufactured in 1967 and was in service at a commercial nuclear power plant for twelve years. Various tests were performed on the motor throughout the aging process. The motor failed after 3.79 million reversals (3 seconds per reversal) over seven months of testing. Each test parameter was trended to assess its suitability in monitoring aging and service wear degradation in motors. Results and conclusions are discussed relative to the applicability of the tests performed to nuclear power plant motor maintenance programs. 15 refs., 28 figs., 1 tab

  11. The long-term impact of a man-made disaster: An examination of a small town in the aftermath of the Three Mile Island Nuclear Reactor Accident.

    Science.gov (United States)

    Goldsteen, R; Schorr, J K

    1982-03-01

    This paper explores the long-term effects of a nuclear accident on residents' perceptions of their physical and mental health, their trust of public officials, and their attitudes toward the future risks of nuclear power generation In their community. We find that in the period after the accident at Three Mile Island that there are constant or Increasing levels of distress reported by community residents. We conclude that the effects of a technological disaster may often be more enduring than those natural disaster and that greater research efforts should be made to Investigate the long-term consequences of man-made catastrophies of all types.

  12. Study on operation conditions and an operation system of a nuclear powered submersible research vessel, 'report of working group on application of a very small nuclear reactor to an ocean research'

    International Nuclear Information System (INIS)

    Ura, Tamaki; Takamasa, Tomoji; Nishimura, Hajime

    2001-07-01

    JAERI has studied on design of a nuclear powered submersible research vessel, which will navigate under sea mainly in the Arctic Ocean, as a part of the design activity of advanced marine reactors. This report describes operation conditions and an operating system of the vessel, which were discussed by the specialists of hull design, sound positioning, ship motions and oceanography, etc. The design conditions on ship motions for submersible vessels were surveyed considering regulations in our country, and ship motions were evaluated in the cases of underwater and surface navigations taking account of observation activities in the Arctic Ocean. The effect of ship motions on the compact nuclear reactor SCR was assessed. A submarine transponder system and an on-ice communication buoy system were examined as a positioning and communication system, supposing the activity under ice. The interval between transponders or communication buoys was recommended as 130 km. Procedures to secure safety of nuclear powered submersible research vessel were discussed according to accidents on the hull or the nuclear reactor. These results were reflected to the concept of the nuclear powered submersible research vessel, and subjects to be settled in the next step were clarified. (author)

  13. Study on operation conditions and an operation system of a nuclear powered submersible research vessel, 'report of working group on application of a very small nuclear reactor to an ocean research'

    Energy Technology Data Exchange (ETDEWEB)

    Ura, Tamaki [Tokyo Univ., Tokyo (Japan); Takamasa, Tomoji [Tokyo Univ. of Mercantile Marine, Tokyo (Japan); Nishimura, Hajime [Japan Marine Science and Technology Center, Yokosuka, Kanagawa (JP)] [and others

    2001-07-01

    JAERI has studied on design of a nuclear powered submersible research vessel, which will navigate under sea mainly in the Arctic Ocean, as a part of the design activity of advanced marine reactors. This report describes operation conditions and an operating system of the vessel, which were discussed by the specialists of hull design, sound positioning, ship motions and oceanography, etc. The design conditions on ship motions for submersible vessels were surveyed considering regulations in our country, and ship motions were evaluated in the cases of underwater and surface navigations taking account of observation activities in the Arctic Ocean. The effect of ship motions on the compact nuclear reactor SCR was assessed. A submarine transponder system and an on-ice communication buoy system were examined as a positioning and communication system, supposing the activity under ice. The interval between transponders or communication buoys was recommended as 130 km. Procedures to secure safety of nuclear powered submersible research vessel were discussed according to accidents on the hull or the nuclear reactor. These results were reflected to the concept of the nuclear powered submersible research vessel, and subjects to be settled in the next step were clarified. (author)

  14. Mechanical and Instrumental Experiences from the Erection, Commissioning, and Operation of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

    International Nuclear Information System (INIS)

    Joensson, K.

    1965-05-01

    A radio chemical pilot plant for the reprocessing of irradiated nuclear fuels has been built by AB Atomenergi at Kjeller in Norway. In the report a short description of the main equipment is given as well as of the procedure during the erection of the plant. Finally the results and experiences from the cold tests, tracer tests and active runs are indicated

  15. Mechanical and Instrumental Experiences from the Erection, Commissioning, and Operation of a Small Pilot Plant for Development Work on Aqueous Reprocessing of Nuclear Fuels

    Energy Technology Data Exchange (ETDEWEB)

    Joensson, K

    1965-05-15

    A radio chemical pilot plant for the reprocessing of irradiated nuclear fuels has been built by AB Atomenergi at Kjeller in Norway. In the report a short description of the main equipment is given as well as of the procedure during the erection of the plant. Finally the results and experiences from the cold tests, tracer tests and active runs are indicated.

  16. Development of a standard data base for FBR core nuclear design (XIII). Analysis of small sample reactivity experiments at ZPPR-9

    International Nuclear Information System (INIS)

    Sato, Wakaei; Fukushima, Manabu; Ishikawa, Makoto

    2000-09-01

    A comprehensive study to evaluate and accumulate the abundant results of fast reactor physics is now in progress at O-arai Engineering Center to improve analytical methods and prediction accuracy of nuclear design for large fast breeder cores such as future commercial FBRs. The present report summarizes the analytical results of sample reactivity experiments at ZPPR-9 core, which has not been evaluated by the latest analytical method yet. The intention of the work is to extend and further generalize the standard data base for FBR core nuclear design. The analytical results of the sample reactivity experiments (samples: PU-30, U-6, DU-6, SS-1 and B-1) at ZPPR-9 core in JUPITER series, with the latest nuclear data library JENDL-3.2 and the analytical method which was established by the JUPITER analysis, can be concluded as follows: The region-averaged final C/E values generally agreed with unity within 5% differences at the inner core region. However, the C/E values of every sample showed the radial space-dependency increasing from center to core edge, especially the discrepancy of B-1 was the largest by 10%. Next, the influence of the present analytical results for the ZPPR-9 sample reactivity to the cross-section adjustment was evaluated. The reference case was a unified cross-section set ADJ98 based on the recent JUPITER analysis. As a conclusion, the present analytical results have sufficient physical consistency with other JUPITER data, and possess qualification as a part of the standard data base for FBR nuclear design. (author)

  17. Nuclear power under strain

    International Nuclear Information System (INIS)

    1978-08-01

    The German citizen faces the complex problem of nuclear power industry with slight feeling of uncertainty. The topics in question can only be briefly dealt with in this context, e.g.: 1. Only nuclear energy can compensate the energy shortage. 2. Coal and nuclear energy. 3. Keeping the risk small. 4. Safety test series. 5. Status and tendencies of nuclear energy planning in the East and West. (GL) [de

  18. Iran's nuclear programme

    International Nuclear Information System (INIS)

    Boureston, J.; Marvin, B.

    2004-01-01

    Iran's nuclear program is discussed, activity of enterprises connected with the nuclear industry of the country is evaluated. IAEA initiated inspection of some industrial sites with the aim of data acquisition about nuclear developments of Iran. Uranium ore mining and reducing to small size, uranium conversion, uranium enrichment, fabrication of nuclear fuel, production of plutonium: plant of heavy water production, spent fuel reprocessing are discussed [ru

  19. Fanconi anemia FANCD2 and FANCI proteins regulate the nuclear dynamics of splicing factors.

    Science.gov (United States)

    Moriel-Carretero, María; Ovejero, Sara; Gérus-Durand, Marie; Vryzas, Dimos; Constantinou, Angelos

    2017-12-04

    Proteins disabled in the cancer-prone disorder Fanconi anemia (FA) ensure the maintenance of chromosomal stability during DNA replication. FA proteins regulate replication dynamics, coordinate replication-coupled repair of interstrand DNA cross-links, and mitigate conflicts between replication and transcription. Here we show that FANCI and FANCD2 associate with splicing factor 3B1 (SF3B1), a key spliceosomal protein of the U2 small nuclear ribonucleoprotein (U2 snRNP). FANCI is in close proximity to SF3B1 in the nucleoplasm of interphase and mitotic cells. Furthermore, we find that DNA replication stress induces the release of SF3B1 from nuclear speckles in a manner that depends on FANCI and on the activity of the checkpoint kinase ATR. In chromatin, both FANCD2 and FANCI associate with SF3B1, prevent accumulation of postcatalytic intron lariats, and contribute to the timely eviction of splicing factors. We propose that FANCD2 and FANCI contribute to the organization of functional domains in chromatin, ensuring the coordination of DNA replication and cotranscriptional processes. © 2017 Moriel-Carretero et al.

  20. On small clusters

    International Nuclear Information System (INIS)

    Bernardes, N.

    1984-01-01

    A discussion is presented of zero-point motion effects on the binding energy of a small cluster of identical particles interacting through short range attractive-repulsive forces. The model is appropriate to a discussion of both Van der Waals as well as nuclear forces. (Author) [pt

  1. Nuclear technologies

    International Nuclear Information System (INIS)

    Toyama, Makoto; Hamasaki, Manabu; Kobayashi, Masahiko; Hoshide, Akihiko; Katayama, Kimio; Nozawa, H.; Karigome, Satoshi

    2010-01-01

    In recent days, energy security is becoming a major global concern and it has been recognized that a major reduction in greenhouse-gas emissions is required to combat climate change. Considerable expansion and new introduction of nuclear power generation are currently being planned and considered for the further in various parts of the world. Nuclear technologies of the latest 10 years in Japan were reviewed with their characteristics, advancement and future perspective. Steady efforts have been made to construct new nuclear power stations with computer-aided engineering system and modular and prefabricated structures, extend the interval of periodic inspections under the new inspection system that should improve both safety and reliability, implement advanced measures against aging and develop the next-generation light water reactors including a medium small reactor. Export of nuclear power plants has been promoted with international business alliance or cooperation. Activities to close nuclear fuel cycle to ensure sustainable nuclear energy utilization have been promoted. Decommissioning technologies for Tokai power station have been developed and accumulated know-how will be utilized in light water reactors. (T. Tanaka)

  2. Nuclear law - Nuclear safety

    International Nuclear Information System (INIS)

    Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

    2012-01-01

    This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

  3. Analysis of the right-handed Majorana neutrino mass in an S U (4 )×S U (2 )L×S U (2 )R Pati-Salam model with democratic texture

    Science.gov (United States)

    Yang, Masaki J. S.

    2017-03-01

    In this paper, we attempt to build a unified model with the democratic texture, that has some unification between up-type Yukawa interactions Yν and Yu . Since the S3 L×S3 R flavor symmetry is chiral, the unified gauge group is assumed to be Pati-Salam type S U (4 )c×S U (2 )L×S U (2 )R. The breaking scheme of the flavor symmetry is considered to be S3 L×S3 R→S2 L×S2 R→0 . In this picture, the four-zero texture is desirable for realistic masses and mixings. This texture is realized by a specific representation for the second breaking of the S3 L×S3 R flavor symmetry. Assuming only renormalizable Yukawa interactions, type-I seesaw mechanism, and neglecting C P phases for simplicity, the right-handed neutrino mass matrix MR can be reconstructed from low energy input values. Numerical analysis shows that the texture of MR basically behaves like the "waterfall texture." Since MR tends to be the "cascade texture" in the democratic texture approach, a model with type-I seesaw and up-type Yukawa unification Yν≃Yu basically requires fine-tunings between parameters. Therefore, it seems to be more realistic to consider universal waterfall textures for both Yf and MR, e.g., by the radiative mass generation or the Froggatt-Nielsen mechanism. Moreover, analysis of eigenvalues shows that the lightest mass eigenvalue MR 1 is too light to achieve successful thermal leptogenesis. Although the resonant leptogenesis might be possible, it also requires fine-tunings of parameters.

  4. Nuclear astrophysics

    International Nuclear Information System (INIS)

    Lehoucq, Roland; Klotz, Gregory

    2015-11-01

    Astronomy deals with the position and observation of the objects in our Universe, from planets to galaxies. It is the oldest of the sciences. Astrophysics is the study of the physical properties of these objects. It dates from the start of the 20. century. Nuclear astrophysics is the marriage of nuclear physics, a laboratory science concerned with the infinitely small, and astrophysics, the science of what is far away and infinitely large. Its aim is to explain the origin, evolution and abundance of the elements in the Universe. It was born in 1938 with the work of Hans Bethe, an American physicist who won the Nobel Prize for physics in 1967, on the nuclear reactions that can occur at the center of stars. It explains where the incredible energy of the stars and the Sun comes from and enables us to understand how they are born, live and die. The matter all around us and from which we are made, is made up of ninety-two chemical elements that can be found in every corner of the Universe. Nuclear astrophysics explains the origin of these chemical elements by nucleosynthesis, which is the synthesis of atomic nuclei in different astrophysical environments such as stars. Nuclear astrophysics provides answers to fundamental questions: - Our Sun and the stars in general shine because nuclear reactions are taking place within them. - The stars follow a sequence of nuclear reaction cycles. Nucleosynthesis in the stars enables us to explain the origin and abundance of elements essential to life, such as carbon, oxygen, nitrogen and iron. - Star explosions, in the form of supernovae, disperse the nuclei formed by nucleosynthesis into space and explain the formation of the heaviest chemical elements such as gold, platinum and lead. Nuclear astrophysics is still a growing area of science. (authors)

  5. Hydrogen Safety Analysis of the OPR1000 Nuclear Power Plant during a Severe Accident by a Small-Break Loss of Coolant

    International Nuclear Information System (INIS)

    Kim, Jong Tae; Park, Soo Yong; Ha, Kwang Soon; Hong, Seong Wan; Kim, Sang Baik

    2009-01-01

    A huge amount of hydrogen can be generated in a nuclear reactor and released into the reactor containment if a hypothetical severe accident happens. Even for the accident, the hydrogen concentrations must be safely controlled. In order to prove a nuclear power plant (NPP) safe from hydrogen, a simulation of hydrogen distributions in the containment are usually conducted by using a 1-dimensional thermo-hydraulic system code. If there exists a possibility of a hydrogen explosion in the containment, it is required to install a hydrogen mitigation system such as igniters or hydrogen recombiner. For a licensing of NPP construction and operation, the hydrogen combustion and hydrogen mitigation system in the containment is one of the important safety issues. In Korea, two OPR1000 NPPs by the name of Shin-Wolsung 1 and 2 are under construction. The hydrogen safety and its control for the new NPPs will be evaluated in detail until a licensing of the operation. Until now, simulations of the hydrogen behaviors in the OPR1000 have been conducted by a lumped method for each compartment in the containment using CONTAIN or MAAP. This 1-dimensional method is very efficient for a long-term simulation of an accident because of its fast running time, and it is very effective for establishing the averaged hydrogen concentrations in each compartment. But a 3-dimensional flow structure developed by a discharged mass from a reactor vessel and local concentrations of hydrogen are difficult to be resolved by the lumped method. In this study, hydrogen distributions and characteristics of hydrogen mixture cloud such as a possibility of flame acceleration in each compartment of OPR1000 containment were evaluated by using GASFLOW code

  6. The nuclear winter

    International Nuclear Information System (INIS)

    Velikhow, Y.P.

    1986-01-01

    Nuclear winter is an example of possible secondary effects, and if we speak of secondary we are thinking of small-scale second-order effects, but a nuclear winter is not a second-order effect. If you calculate the amount of heat produced by a nuclear explosion, it is a very small amount which does not have any chance of changing the Earth's climate, but a nuclear explosion drives or stars some new mechanism - the mechanism of nuclear winter - after 100 megatons of dust are transferred to the upper atmosphere. Another example of such amplification is radioactive fall-out, especially long-life radioactive fall-out after the possible elimination of the nuclear power industry, nuclear storage and distribution of storage waste around the globe. This is a very powerful amplification mechanism

  7. Small x physics

    International Nuclear Information System (INIS)

    Kwiecinski, J.

    1993-01-01

    The QCD expectations concerning the small x limit of parton distributions where x is the Bjorken scaling variable are reviewed. This includes discussion of the evolutions equations in the small x region, the Lipatov equation which sums the leading powers of ln(1/x) and the shadowing effects. Phenomenological implantations of the theoretical expectations for the deep inelastic lepton-hadron scattering in the small x region which will be accessible at the HERA ep collider are described. We give predictions for structure functions F 2 and F L and discuss specific processes sensitive to the small x physics such as heavy quark production, deep inelastic diffraction and jet production in deep inelastic lepton scattering. A brief review of nuclear shadowing in the inelastic lepton nucleus scattering at small x is also presented. (author). 86 refs, 29 figs

  8. Nuclear reactor

    International Nuclear Information System (INIS)

    Batheja, P.; Huber, R.; Rau, P.

    1985-01-01

    Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

  9. Ce2Co3Ge5: a new U2Co3Si5 - type valance fluctuating compound

    International Nuclear Information System (INIS)

    Layek, Samar; Hossain, Zakir

    2010-01-01

    Poly crystalline sample of Ce 2 Co 3 Ge 5 have been prepared by arc melting and consequently annealing at 1100 deg C. Rietveld refinement of XRD shows that it crystallize in the orthorhombic U 2 Co 3 Si 5 structure (space group Ibam) with crystal parameters a= 9.802A, b= 11.777A and c= 5.941A and unit cell volume V= 684.8 A 3 The unit cell volume of Ce 2 Co 3 Ge 5 is seen clearly to deviate from that expected on the basis of lanthanide contraction. From susceptibility measurement, effective magnetic moment of this compound μ eff = 0.95 μ B which is lower than magnetic moment free for Ce 3+ ions (2.54 μB) but higher than that of non-magnetic Ce 4+ state (0 μ B ). All these results clearly indicated Ce 2 Co 3 Ge 5 to be a mixed valance compound. (author)

  10. A molecule with small rotational constants containing an atom with a large nuclear quadrupole moment: The microwave spectrum of trans-1-iodoperfluoropropane

    Science.gov (United States)

    Dewberry, C. T.; Grubbs, G. S.; Cooke, S. A.

    2009-09-01

    Using pulsed jet chirped-pulse, and cavity-based Fourier transform microwave spectroscopies over 900 transitions have been recorded for the title molecule in the 1-4 GHz and 8-18 GHz regions. The C,C and C carbon-13 species have been observed in natural abundance allowing a substitution structure for the CCC backbone to be determined. Nearly all the transitions observed were either a-type R branches or b-type Q branches. No c-type transitions were observed consistent with only the trans conformer being present under our experimental conditions. The χaa,χbb,χcc and χab components of the iodine nuclear quadrupole coupling tensor have been determined. Of note, several forbidden, ΔJ±2 transitions, and one ΔJ±3 transition were observed with quite reasonable intensity. These observations have been rationalized through considerations of near degeneracies between energy levels connected via a large χab value (≈1 GHz).

  11. Photogeologic study of small-scale linear features near a potential nuclear-waste repository site at Yucca Mountain, southern Nye County, Nevada

    International Nuclear Information System (INIS)

    Throckmorton, C.K.

    1987-01-01

    Linear features were mapped from 1:2400-scale aerial photographs of the northern half of the potential underground nuclear-waste repository site at Yucca Mountain by means of a Kern PG 2 stereoplotter. These features were thought to be the expression of fractures at the ground surface (fracture traces), and were mapped in the caprock, upper lithophysal, undifferentiated lower lithophysal and hackly units of the Tiva Canyon Member of the Miocene Paintbrush Tuff. To determine if the linear features corresponded to fracture traces observed in the field, stations (areas) were selected on the map where the traces were both abundant and located solely within one unit. These areas were visited in the field, where fracture-trace bearings and fracture-trace lengths were recorded. Additional data on fracture-trace length and fracture abundance, obtained from ground-based studies of cleared pavements located within the study area were used to help evaluate data collected for this study. 16 refs., 4 figs., 2 tabs

  12. Morphometric Characterization of Small Cell Lymphocytic Lymphoma

    Directory of Open Access Journals (Sweden)

    Chisoi Anca

    2014-11-01

    Full Text Available The morphometry in histopathology is used to characterize cell populations belonging to different tissues and to identify differences in their parameters with prognostic implications. To achieve morphometric examination were selected 6 of 24 cases identified as small cell lymphocytic lymphoma. For each case analysis was done on five fields, for each field measuring the parameters of 20 cells. The studied parameters were for cytoplasm: cytoplasmic area, maximum and minimum cytoplasmic diameter, cytoplasmic perimeter; for nucleus were measured: nuclear area, minimum and maximum nuclear diameter, nuclear perimeter, nuclear contour index, nuclear ellipticity index, nuclear irregularity index. Also the nucleocytoplasmic ratio was calculated in all studied cases. Small cell lymphocytic lymphoma is characterized in morphometric terms having a small cytoplasmic area (average 29.206 and also a small nuclear area (mean 28.939 having a nucleo-cytoplasmic ratio appearance suggestive for adult lymphocyte. A nuclear contour index small value (3.946, ellipticity index value also small (3.521 and small nuclear irregularity index (3.965. Standard deviations, in any of the studied morphometric categories, is around or below 1 suggesting monomorphic cell appearance. These morphometric and microscopic features characterized mainly by a small population of adult lymphocytes, monomorphic, with rounded hipercromic nuclei, dense chromatin, support the framing into indolent lymphoma group in terms of clinical outcome.

  13. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs.

  14. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

  15. Nuclear Security for Floating Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Skiba, James M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Scherer, Carolynn P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  16. Illicit Nuclear Trafficking Scams

    International Nuclear Information System (INIS)

    Moore, G.M.

    2010-01-01

    Nuclear Trafficking Scams are situations where the scam artist(s) offer something (material or information) that is not what he/she/they represent it to be. Example of a scam is when attempt is made to sell fake nuclear material. The offered material may not be nuclear material or may be of a lower grade. The offered material may not actually exist . Radioactive material may be offered as nuclear material. A small sample of actual nuclear material may be offered, but the bulk material may be something else.

  17. Small Molecule Inhibiting Nuclear Factor-kB Ameliorates Oxidative Stress and Suppresses Renal Inflammation in Early Stage of Alloxan-Induced Diabetic Nephropathy in Rat.

    Science.gov (United States)

    Borgohain, Manash P; Lahkar, Mangala; Ahmed, Sahabuddin; Chowdhury, Liakat; Kumar, Saurabh; Pant, Rajat; Choubey, Abhinav

    2017-05-01

    Diabetic nephropathy is one of the major microvascular complications of diabetes mellitus which ultimately gives rise to cardiovascular diseases. Prolonged hyperglycaemia and chronic renal inflammation are the two key players in the development and progression of diabetic nephropathy. Nuclear factor kB (NF-kB)-mediated inflammatory cascade is a strong contributor to the renovascular inflammation in diabetic nephropathy. Here, we studied the effects of piceatannol, a potent NF-kB inhibitor, on various oxidative stress markers and NF-kB dependent diabetic renoinflammatory cascades in rat induced by alloxan (ALX). Experimental diabetes was induced in male Wistar rats by a single intraperitoneal dose, 150 mg/kg body-weight (b.w.) of ALX. Diabetic rats were treated with Piceatannol (PCTNL) at a dose of 30 and 50 mg/kg b.w. After 14 days of oral treatment, PCTNL significantly restored blood sugar level, glomerular filtration rate, serum markers and plasma lipids. PCTNL administration also reversed the declined activity of cellular antioxidant machineries namely superoxide dismutase and glutathione and the elevated levels of malondialdehyde and nitric oxide. Moreover, piceatannol-treated groups showed marked inhibition of renal pro-inflammatory cytokines and NF-kB p65/p50 binding to DNA. Renal histopathological investigations also supported its ameliorative effects against diabetic kidney damage. Importantly, effects were more prominent at a dose of 50 mg/kg, and in terms of body-weight gain, PCTNL failed to effect significantly. However, overall findings clearly demonstrated that PCTNL provides remarkable renoprotection in diabetes by abrogating oxidative stress and NF-kB activation - and might be helpful in early stage of diabetic nephropathy. © 2016 Nordic Association for the Publication of BCPT (former Nordic Pharmacological Society).

  18. Nuclear winter or nuclear fall?

    Science.gov (United States)

    Berger, André

    Climate is universal. If a major modern nuclear war (i.e., with a large number of small-yield weapons) were to happen, it is not even necessary to have a specific part of the world directly involved for there to be cause to worry about the consequences for its inhabitants and their future. Indeed, smoke from fires ignited by the nuclear explosions would be transported by winds all over the world, causing dark and cold. According to the first study, by Turco et al. [1983], air surface temperature over continental areas of the northern mid-latitudes (assumed to be the nuclear war theatre) would fall to winter levels even in summer (hence the term “nuclear winter”) and induce drastic climatic conditions for several months at least. The devastating effects of a nuclear war would thus last much longer than was assumed initially. Discussing to what extent these estimations of long-term impacts on climate are reliable is the purpose of this article.

  19. Small Data

    NARCIS (Netherlands)

    S. Pemberton (Steven)

    2014-01-01

    htmlabstractThe term “Open Data” often goes hand in hand with the term “Big Data”, where large data sets get released allowing for analysis, but the Cinderella of the Open Data ball is Small Data, small amounts of data, nonetheless possibly essential, that are too small to be put in some database or

  20. Performance evaluation of the conventional Brazilian industries radiation protection in the small industrial gauges and industrial radiography areas; Sistema de avaliacao de desempenho em radioprotecao das industrias convencionais brasileiras nas areas de medidores nucleares e radiografia industrial

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joyra Amaral dos

    1999-08-01

    This works evaluates by punctuation the performance in conventional Brazilian industries radiation protection area which make use of small industrial gauges and industrial radiography. It proposes, procedures for industry self-evaluation, besides a new radiation protection plans pattern for the small industrial gauges area. The data source where inspection reports of Dosimetry Radiation Protection Institute/Nuclear Energy Commission conventional Brazilian industries' radiation protection plans, beyond visitation to the inspection place. The performance evaluation has been realized both in the administrative and operational aspects of the industries. About of 60% of the industries have a satisfactory register control which does not happen to the operational control. The performance evaluation advantage is that industries may self-evaluate, foreseeing Dosimetry Radiation Protection Institute's regulation inspections, correcting its irregularities, automatically improving its services. The number of industries which have obtained satisfactory performance in both areas is below 70%, both in administrative and operational aspects. Such number can be considered a low one as it is radiation protection. The procedures propose in this work aim to improve such a situation. (author)

  1. Your Radiologist Explains Nuclear Medicine

    Medline Plus

    Full Text Available ... other diagnostic tests. Nuclear medicine imaging procedures use small amounts of radioactive materials – called radiotracers – that are ... However, because the amount of radiotracer used is small, the level of radiation exposure is relatively low ...

  2. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... small amount of energy in the form of gamma rays. Special cameras detect this energy, and with ... imaging techniques used in nuclear medicine include the gamma camera and single-photon emission-computed tomography (SPECT). ...

  3. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... top of page What are the benefits vs. risks? Benefits The information provided by nuclear medicine examinations ... diagnosis or to determine appropriate treatment, if any. Risks Because the doses of radiotracer administered are small, ...

  4. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... exams at the same time. An emerging imaging technology, but not readily available at this time is ... leaving the nuclear medicine facility. Through the natural process of radioactive decay, the small amount of radiotracer ...

  5. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... leaving the nuclear medicine facility. Through the natural process of radioactive decay, the small amount of radiotracer ... possible charges you will incur. Web page review process: This Web page is reviewed regularly by a ...

  6. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... the most useful information needed to make a diagnosis or to determine appropriate treatment, if any. Risks Because the doses of radiotracer administered are small, diagnostic nuclear medicine procedures result in low radiation exposure, ...

  7. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Because the doses of radiotracer administered are small, diagnostic nuclear medicine procedures result in low radiation exposure, acceptable for diagnostic exams. Thus, the radiation risk is very low ...

  8. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... molecular information. In many centers, nuclear medicine images can be superimposed with computed tomography (CT) or magnetic ... small hand-held device resembling a microphone that can detect and measure the amount of the radiotracer ...

  9. Business Opportunities for Small Reactors

    International Nuclear Information System (INIS)

    Minato, Akio; Nishimura, Satoshi; Brown, Neil W.

    2007-01-01

    This report assesses the market potential and identifies a number of potential paths for developing the small nuclear reactor business. There are several potential opportunities identified and evaluated. Selecting a specific approach for the business development requires additional information related to a specific market and sources of capital to support the investment. If and how a market for small nuclear plants may develop is difficult to predict because of the complexity of the economic and institutional factors that will influence such development. Key factors are; economics, safety, proliferation resistance and investment risk. The economic and political interest of any of the identified markets is also dependent on successful demonstration of the safety and reliability of small nuclear reactor. Obtaining a US-NRC Standard Design approval would be an important development step toward establishing a market for small reactors. (authors)

  10. Nuclear explosives and hydrocarbons

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P

    1971-10-01

    A nuclear explosive 12 in. in diam and producing very little tritium is feasible in France. Such a device would be well adapted for contained nuclear explosions set off for the purpose of hydrocarbon storage or stimulation. The different aspects of setting off the explosive are reviewed. In the particular case of gas storage in a nuclear cavity in granite, it is demonstrated that the dose of irradiation received is extremely small. (18 refs.)

  11. French nuclear organization

    International Nuclear Information System (INIS)

    Naudet, G.

    1993-01-01

    The French nuclear organization is characterized by two main features: the small number of firms involved and the role of the Government. In this text we give the French organization for nuclear industry and the role of Government and public authorities. 7 figs

  12. Assessment of the burning behavior of protected and unprotected cables and cable trays in nuclear installations using small- and large-scale experiments

    Energy Technology Data Exchange (ETDEWEB)

    Siemon, Matthias; Riese, Olaf; Zehfuss, Jochen [Technische Univ. Braunschweig (Germany). Inst. fuer Baustoffe, Massivbau und Brandschutz (iBMB)

    2015-12-15

    Electric installations and cables are a main fire risk source in industrial buildings and power plants. In general, cables and cable systems are associated with flash-over phenomena due to pyrolysis of fuel gases induced by the heat of an adjacent fire, fire spread along cable trays affecting additional areas besides the fire origin, being an ignition source due to malfunction. If burning, cables can emit large amounts of smoke and toxic products affecting occupants as well as the long-term functionality of structure and installations. Paying attention to these risks has led to the development of fire retardant non-corrosive (non-halogenated) cables which are qualified to reduce the individual or all of the risks mentioned. For existing installations in industrial buildings and power plants with halogenated cables, different protection measures are available and widely applied retroactively. Important protective measures are intumescent or ablative coatings, cable casings and bindings. For qualification of the effects of the protection measures, small-scale tests investigating a single cable specimen as well as large-scale cable tray test setups have been developed and carried out in the last 20 years at iBMB. In this paper, these test results are analysed regarding their effects on the heat release, ignition time and fire spread over cable trays. Furthermore, national and international research projects have investigated the burning behaviour of different cable types, tray installations, tray loading and spacing and ventilation conditions. As a conclusion, the main outcomes of past researches are summarized. Influence factors (e.g. pre-heating due to high power utilization, influence of cable aging) which have not been accounted for in detail are emphasized. The modelling of unprotected cables has been internationally studied in recent years. For future applications, the question of applicability of recently developed sub-models on the fire behaviour of protected

  13. Nuclear Medicine

    Science.gov (United States)

    ... Parents/Teachers Resource Links for Students Glossary Nuclear Medicine What is nuclear medicine? What are radioactive tracers? ... funded researchers advancing nuclear medicine? What is nuclear medicine? Nuclear medicine is a medical specialty that uses ...

  14. Equation of state of U2Mo up-to Mbar pressure range: Ab-initio study

    Science.gov (United States)

    Mukherjee, D.; Sahoo, B. D.; Joshi, K. D.; Kaushik, T. C.

    2018-04-01

    Experimentally, U2Mo is known to exist in tetragonal structure at ambient conditions. In contrast to experimental reports, the past theoretical studies carried out in this material do not find this phase to be stable structure at zero pressure. In order to examine this discrepancy between experiment and theory, we have performed ab-initio electronic band structure calculations on this material. In our theoretical study, we have attempted to search for lowest enthalpy structure at ambient as well at high pressure up to 200 GPa, employing evolutionary structure search algorithm in conjunction with ab-inito method. Our investigations suggest that a hexagonal structure with space group symmetry P6/mmm is the lowest enthalpy structure not only at ambient pressure but also up to pressure range of ˜200 GPa. To further, substantiate the results of these static lattice calculations the elastic and lattice dynamical stability has also been analysed. The theoretical isotherm derived from these calculations has been utilized to determine the Hugoniot of this material. Various physical properties such as zero pressure equilibrium volume, bulk modulus and its pressure derivative has also been derived from theoretical isotherm.

  15. The homeobox transcription factor HOXA9 is a regulator of SHOX in U2OS cells and chicken micromass cultures.

    Directory of Open Access Journals (Sweden)

    Claudia Durand

    Full Text Available The homeobox gene SHOX encodes for a transcription factor that plays an important role during limb development. Mutations or deletions of SHOX in humans cause short stature in Turner, Langer and Leri-Weill syndrome as well as idiopathic short stature. During embryonic development, SHOX is expressed in a complex spatio-temporal pattern that requires the presence of specific regulatory mechanisms. Up to now, it was known that SHOX is regulated by two upstream promoters and several enhancers on either side of the gene, but no regulators have been identified that can activate or repress the transcription of SHOX by binding to these regulatory elements. We have now identified the homeodomain protein HOXA9 as a positive regulator of SHOX expression in U2OS cells. Using luciferase assays, chromatin immunoprecipitation and electrophoretic mobility shift assays, we could narrow down the HOXA9 binding site to two AT-rich sequences of 31 bp within the SHOX promoter 2. Virus-induced Hoxa9 overexpression in a chicken micromass model validated the regulation of Shox by Hoxa9 (negative regulation. As Hoxa9 and Shox are both expressed in overlapping regions of the developing limb buds, a regulatory relationship of Hoxa9 and Shox during the process of limb development can be assumed.

  16. Nuclear safety. Seguranca nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Aveline, A [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Inst. de Fisica

    1981-01-01

    What is nuclear safety Is there any technical way to reduce risks Is it possible to put them at reasonable levels Are there competitiveness and economic reliability to employ the nuclear energy by means of safety technics Looking for answers to these questions the author describes the sources of potential risks to nuclear reactors and tries to apply the answers to the Brazilian Nuclear Programme. (author).

  17. Small Data

    OpenAIRE

    Pemberton, Steven

    2014-01-01

    htmlabstractThe term “Open Data” often goes hand in hand with the term “Big Data”, where large data sets get released allowing for analysis, but the Cinderella of the Open Data ball is Small Data, small amounts of data, nonetheless possibly essential, that are too small to be put in some database or online dataset to be put to use. RDFa is a technology that allows Cinderella to go to the ball.

  18. Invisible nuclear; converting nuclear

    International Nuclear Information System (INIS)

    Park, Jongmoon

    1993-03-01

    This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

  19. Human regulator of telomere elongation helicase 1 (RTEL1) is required for the nuclear and cytoplasmic trafficking of pre-U2 RNA

    OpenAIRE

    Schertzer , Michael; Jouravleva , Karina; Perderiset , Mylène; Dingli , Florent; Loew , Damarys; Le Guen , Tangui; Bardoni , Barbara; De Villartay , Jean-Pierre; Revy , Patrick; Londono-Vallejo , Arturo

    2015-01-01

    International audience; Hoyeraal-Hreidarsson syndrome (HHS) is a severe form of Dyskeratosis congenita characterized by developmental defects, bone marrow failure and im-munodeficiency and has been associated with telom-ere dysfunction. Recently, mutations in Regulator of Telomere ELongation helicase 1 (RTEL1), a helicase first identified in Mus musculus as being responsible for the maintenance of long telomeres, have been identified in several HHS patients. Here we show that RTEL1 is require...

  20. Seismic qualification tests of fans of the NPP of Laguna Verde U-1 and U-2; Pruebas de calificacion sismica de ventiladores de la Central Laguna Verde U1 and U2

    Energy Technology Data Exchange (ETDEWEB)

    Jarvio C, G.; Garcia H, E. E.; Arguelles F, R.; Vela H, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Naranjo U, J. L., E-mail: gilberto.jarvio@inin.gob.mx [Comision Federal de Electricidad, Gerencia de Centrales Nucleoelectricas, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Dos Bocas, Veracruz (Mexico)

    2013-10-15

    This work presents the results of the seismic qualification tests applied to the fans that will be installed in the control panels of the three divisions of the diesel generators of the nuclear power plant (NPP) of Laguna Verde, Unit-1 and Unit-2. This seismic qualification process of the fans was carried out using two specimens that were tested in the seismic table (vibrating) of the Engineering Institute of Universidad Nacional Autonoma de Mexico (UNAM), in accordance with the requirements of the standard IEEE 344-1975, to satisfy the established requirements of seismic qualification in the technical specifications and normative documents required by the nuclear standards, in order to demonstrate its application in the diesel generators Divisions I, II and III of the NPP. The seismic qualification tests were developed on specimens that were retired of the NPP of Laguna Verde recently with a service life of 7.75 years. (Author)

  1. The G4-ECONS Economic Evaluation Tool for Generation IV Reactor Systems and its Proposed Application to Deliberately Small Reactor Systems and Proposed New Nuclear Fuel Cycle Facilities. Annex IX

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-12-15

    At the outset of the international Generation IV programme, it was decided that the six candidate reactor systems will ultimately be evaluated on the basis of safety, sustainability, non-proliferation attributes, technical readiness and projected economics. It is likely that the same factors will influence the evaluation of deliberately small reactor systems1 and new fuel cycle facilities, such as reprocessing plants that are being considered under the more recent Global Nuclear Energy Partnership (GNEP). This annex describes how the development of an economic modelling system has evolved to address the issue of economic competitiveness for both the Generation IV and GNEP programmes. In 2004, the Generation IV Economic Modelling Working Group (EMWG) commissioned the development of a Microsoft Excel based model capable of calculating the levelized unit electricity cost (LUEC) in mills/kW.h (1 mill = $10{sup -3}) or $/MW.h for multiple types of reactor system being developed under the Generation IV programme. This overall modelling system is now called the Generation IV spreadsheet calculation of nuclear systems (G4-ECONS), and is being expanded to calculate costs of energy products in addition to electricity, such as hydrogen and desalinated water. A version has also been developed to evaluate the costs of products or services from fuel cycle facilities. The cost estimating methodology and algorithms are explained in detail in the Generation IV Cost Estimating Guidelines and in the G4-ECONS User's Manual. The model was constructed with relatively simple economic algorithms such that it could be used by almost any nation without regard to country specific taxation, cost accounting, depreciation or capital cost recovery methodologies. It was also designed with transparency to the user in mind (i.e. all algorithms and cell contents are visible to the user). A short description of version 1.0 G4-ECONS-R (reactor economics model) has also been published in the

  2. The G4-ECONS Economic Evaluation Tool for Generation IV Reactor Systems and its Proposed Application to Deliberately Small Reactor Systems and Proposed New Nuclear Fuel Cycle Facilities. Annex IX

    International Nuclear Information System (INIS)

    2013-01-01

    At the outset of the international Generation IV programme, it was decided that the six candidate reactor systems will ultimately be evaluated on the basis of safety, sustainability, non-proliferation attributes, technical readiness and projected economics. It is likely that the same factors will influence the evaluation of deliberately small reactor systems1 and new fuel cycle facilities, such as reprocessing plants that are being considered under the more recent Global Nuclear Energy Partnership (GNEP). This annex describes how the development of an economic modelling system has evolved to address the issue of economic competitiveness for both the Generation IV and GNEP programmes. In 2004, the Generation IV Economic Modelling Working Group (EMWG) commissioned the development of a Microsoft Excel based model capable of calculating the levelized unit electricity cost (LUEC) in mills/kW.h (1 mill = $10 -3 ) or $/MW.h for multiple types of reactor system being developed under the Generation IV programme. This overall modelling system is now called the Generation IV spreadsheet calculation of nuclear systems (G4-ECONS), and is being expanded to calculate costs of energy products in addition to electricity, such as hydrogen and desalinated water. A version has also been developed to evaluate the costs of products or services from fuel cycle facilities. The cost estimating methodology and algorithms are explained in detail in the Generation IV Cost Estimating Guidelines and in the G4-ECONS User's Manual. The model was constructed with relatively simple economic algorithms such that it could be used by almost any nation without regard to country specific taxation, cost accounting, depreciation or capital cost recovery methodologies. It was also designed with transparency to the user in mind (i.e. all algorithms and cell contents are visible to the user). A short description of version 1.0 G4-ECONS-R (reactor economics model) has also been published in the Proceedings of

  3. Compliance of national radiation protection regulatory infrastructure with international norms: a prerequisite for self-sustainability of technical support organization in a small 'non-nuclear' country: example of Montenegro

    International Nuclear Information System (INIS)

    Jovanovic, Slobodan

    2008-01-01

    Full text: Regulatory control of radiation sources in a country is based upon two essential elements of regulatory infrastructure: national RP legislation system (including nuclear law and subsequent regulations) at one side and institutions regulatory authority (RA) and technical support organizations (TSO) at the other. International norms and standards in radiation protection are (or should be, in principle) transposed through international legal instruments (conventions, treaties, directives, codes) into national regulatory systems, thus making radiation protection regulatory practices standardized and omnipresent. We know, however, that this is often not the case, to more or less extent. More one goes down the pyramid (i.e. from international norms via national regulatory infrastructure to actual RP practice), more there is chance that ultimate/bottom practical actions will not be undertaken properly, or even not at all. One of the key elements in the above mentioned (potentially problematic) RP bottom level is how technical support to regulatory authority is organized. RP legal requirements create a market of services to be effectuated by competent professional organizations, TSO 's. In a small country, there is usually not more than one (if any) of the kind not rarely just surviving at the edge of existence. A TSO scope of RP interests/activities typically include: (1) radiation monitoring and measurements in the environment (air, soil, waters, biota), as well as in public areas, working and living places, (2) personal, workplace and field dosimetry, (3) import, export and trade control of radioactivity in food, forage, construction materials, toys, cosmetics and other goods/consumables, (4) quality control (QC) of radiation sources in medicine, industry, etc., (5) low/medium activity radioactive waste management, (6) transport of radioactive materials, (7) a role in national radiological emergency preparedness and response scheme and (8) advisory services

  4. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... measure the amount of the radiotracer in a small area of your child's body. top of page How is the procedure performed? Nuclear medicine imaging is usually performed on an ... Intravenous: a small needle is used to inject the radiotracer. The ...

  5. Nuclear power prospects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-09-15

    A survey of the nuclear power needs of the less-developed countries and a study of the technology and economics of small and medium scale power reactors are envisioned by the General Conference. Agency makes its services available to Member States to assist them for their future nuclear power plans, and in particular in studying the technical and economic aspects of their power programs. The Agency also undertakes general studies on the economics of nuclear power, including the collection and analysis of cost data, in order to assist Member States in comparing and forecasting nuclear power costs in relation to their specific situations

  6. Small hydro

    International Nuclear Information System (INIS)

    Bennett, K.; Tung, T.

    1995-01-01

    A small hydro plant in Canada is defined as any project between 1 MW and 15 MW but the international standard is 10 MW. The global market for small hydro development was considered good. There are some 1000 to 2000 MW of generating capacity being added each year. In Canada, growth potential is considered small, primarily in remote areas, but significant growth is anticipated in Eastern Europe, Africa and Asia. Canada with its expertise in engineering, manufacturing and development is considered to have a good chance to take advantage of these growing markets

  7. Finding the chiral gravitational wave background of an axion-S U (2 ) inflationary model using CMB observations and laser interferometers

    Science.gov (United States)

    Thorne, Ben; Fujita, Tomohiro; Hazumi, Masashi; Katayama, Nobuhiko; Komatsu, Eiichiro; Shiraishi, Maresuke

    2018-02-01

    A detection of B-mode polarization of the cosmic microwave background (CMB) anisotropies would confirm the presence of a primordial gravitational wave background (GWB). In the inflation paradigm, this would be an unprecedented probe of the energy scale of inflation as it is directly proportional to the power spectrum of the GWB. However, similar tensor perturbations can be produced by the matter fields present during inflation, breaking the simple relationship between energy scale and the tensor-to-scalar ratio r . It is therefore important to find ways of distinguishing between the generation mechanisms of the GWB. Without doing a full model selection, we analyze the detectability of a new axion-S U (2 ) gauge field model by calculating the signal-to-noise ratio of future CMB and interferometer observations sensitive to the chirality of the tensor spectrum. We forecast the detectability of the resulting CMB temperature and B-mode (TB) or E-mode and B-mode (EB) cross-correlation by the LiteBIRD satellite, considering the effects of residual foregrounds, gravitational lensing, and assess the ability of such an experiment to jointly detect primordial TB and EB spectra and self-calibrate its polarimeter. We find that LiteBIRD will be able to detect the chiral signal for r*>0.03 , with r* denoting the tensor-to-scalar ratio at the peak scale, and that the maximum signal-to-noise ratio for r*advanced stage of a LISA-like mission, which is designed to be sensitive to the intensity and polarization of the GWB. We find that such experiments would complement CMB observations as they would be able to detect the chirality of the GWB with high significance on scales inaccessible to the CMB. We conclude that CMB two-point statistics are limited in their ability to distinguish this model from a conventional vacuum fluctuation model of GWB generation, due to the fundamental limits on their sensitivity to parity violation. In order to test the predictions of such a model as

  8. All Small Nuclear RNAs (snRNAs) of the [U4/U6.U5] Tri-snRNP Localize to Nucleoli; Identification of the Nucleolar Localization Element of U6 snRNA

    Science.gov (United States)

    Gerbi, Susan A.; Lange, Thilo Sascha

    2002-01-01

    Previously, we showed that spliceosomal U6 small nuclear RNA (snRNA) transiently passes through the nucleolus. Herein, we report that all individual snRNAs of the [U4/U6.U5] tri-snRNP localize to nucleoli, demonstrated by fluorescence microscopy of nucleolar preparations after injection of fluorescein-labeled snRNA into Xenopus oocyte nuclei. Nucleolar localization of U6 is independent from [U4/U6] snRNP formation since sites of direct interaction of U6 snRNA with U4 snRNA are not nucleolar localization elements. Among all regions in U6, the only one required for nucleolar localization is its 3′ end, which associates with the La protein and subsequently during maturation of U6 is bound by Lsm proteins. This 3′-nucleolar localization element of U6 is both essential and sufficient for nucleolar localization and also required for localization to Cajal bodies. Conversion of the 3′ hydroxyl of U6 snRNA to a 3′ phosphate prevents association with the La protein but does not affect U6 localization to nucleoli or Cajal bodies. PMID:12221120

  9. Nuclear fuel pin

    International Nuclear Information System (INIS)

    Hartley, Kenneth; Moulding, T.L.J.; Rostron, Norman.

    1979-01-01

    Fuel pin for use in fast breeder nuclear reactors containing fissile and fertile areas of which the fissile and fertile materials do not mix. The fissile material takes the shape of large and small diameter microspheres (the small diameter microspheres can pass through the interstices between the large microspheres). The barrier layers being composed of microspheres with a diameter situated between those of the large and small microspheres ensure that the materials do not mix [fr

  10. Small-scale nuclear fusion needs investors

    International Nuclear Information System (INIS)

    Kasteren, J. van.

    1985-01-01

    The only Dutch high-risk research company 'Convector' needs money. In the beginning of October, investors could put at most five million Dutch florins in a highly disputed project for the development of a thermonuclear reactor, based on the principle of globular lightnings. (G.J.P.)

  11. The problem of nuclear power

    International Nuclear Information System (INIS)

    Heimbrecht, J.; Kade, G.; Krusewitz, K.; Moldenhauer, B.; Steinhaus, K.; Weish, P.

    1977-01-01

    The battle over the problems of nuclear power has gone on in the Federal Republic for several years. The Buergerinitiativen, which used to be small and largely unpolitical, have become a major social force during this time. Subjects: 1) Dangers of nuclear power - can the risk be justified; 2)The necessity of nuclear power; 3) The enforcement of nuclear power - political and economic background; 4) Limits of power generation - limits of growth or limits of the system. (orig./HP) [de

  12. [Nuclear theory

    International Nuclear Information System (INIS)

    Haxton, W.

    1990-01-01

    This report discusses research in nuclear physics. Topics covered in this paper are: symmetry principles; nuclear astrophysics; nuclear structure; quark-gluon plasma; quantum chromodynamics; symmetry breaking; nuclear deformation; and cold fusion

  13. Small head size after atomic irradiation

    International Nuclear Information System (INIS)

    Miller, R.W.; Mulvihill, J.J.

    1975-01-01

    A study of children exposed to nuclear explosions in Hiroshima and Nagasaki showed small head size and mental retardation when exposure occurred less than 18 weeks of gestational age. Increased frequency of small head size occurred when maternal exposure was 10 to 19 rad. Tables and graphs are presented to show relationships between dose, gestational age, and frequency of small head size

  14. Public attitudes regarding nuclear wastes

    International Nuclear Information System (INIS)

    Rankin, W.L.

    1978-01-01

    This paper traces the history of public attitudes regarding nuclear waste issues. A majority of the public has recently developed the attitude that nuclear wastes are a serious problem, and a small percentage of the public opposes nuclear power mainly because of nuclear waste issues. However, a majority of the public has confidence in the ability of technologists to solve the problems associated with nuclear waste disposal. Finally, the attitudes of nuclear technologists regarding waste disposal differed greatly from the attitudes of other groups, especially environmentalists

  15. Nuclear topics

    International Nuclear Information System (INIS)

    Lukner, C.

    1982-07-01

    The pamphlet touches on all aspects of nuclear energy, from the world energy demands and consumption, the energy program of the Federal Government, nuclear power plants in the world, nuclear fusion, nuclear liability up to the nuclear fuel cycle and the shutdown of nuclear power plants. (HSCH) [de

  16. Small reminder for those who believe in the future of the French nuclear industry and for those who don't. The impossibility of a dispassionate debate on the future of the nuclear in France. Are nuclear and renewable really complementary?

    International Nuclear Information System (INIS)

    Audigier, Pierre

    2016-01-01

    In this article, the author briefly recalls and comments the present context: an uncertain evolution of the world fossil fuel market, a grotesque European electricity market, an always more complex and constraining regulation of nuclear safety, and a still unclear French policy. Then, he proposes a critical overview of some popular beliefs on the priority given to energy savings, on nuclear energy (its role in the energy mix and in front of renewable energies, its impact on the financial situation of EDF, its related costs), on the issue of intermittency of renewable energies, and on the strengths and weaknesses of nuclear energy. He finally proposes some initiatives to provide the public with unbiased information

  17. Nuclear power and nuclear weapons

    International Nuclear Information System (INIS)

    Vaughen, V.C.A.

    1983-01-01

    The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

  18. Radioactivity: ''small users, big problems''

    International Nuclear Information System (INIS)

    McDonnell, C.

    1993-01-01

    In the United Kingdom there are at least one thousand small users of radioactivity in industry, in medicine, in higher education establishments and even schools. These users of small amounts of radioactivity, covering a wide variety of forms and applications, have difficulty in disposing of their wastes. Disposal provisions for users outside the nuclear industry, the practical problems they encounter and the future developments likely are discussed. (UK)

  19. Nuclear medicine

    International Nuclear Information System (INIS)

    Casier, Ph.; Lepage, B.

    1998-01-01

    Except for dedicated devices for mobile nuclear cardiology for instance, the market is set on variable angulation dual heads cameras. These cameras are suited for all general applications and their cost effectiveness is optimized. Now, all major companies have such a camera in their of products. But, the big question in nuclear medicine is about the future of coincidence imaging for the monitoring of treatments in oncology. Many companies are focused on WIP assessments to find out the right crustal thickness to perform both high energy FDG procedures and low energy Tc procedures, with the same SPECT camera. The classic thickness is 3/8''. Assessments are made with 1/2'', 5/8'' or 3/4'' crystals. If FDG procedures proved to be of great interest in oncology, it may lead to the design of a dedicated SPECT camera with a 1'' crustal. Due to the short half of FDG, it may be the dawning of slip ring technology. (e.g. Varicam from Elscint). The three small heads camera market seems to be depressed. Will the new three large heads camera unveiled by Picker, reverse that trend? The last important topic in nuclear medicine is the emergence of new flat digital detectors to get rid of the old bulky ones. Digirad is the first company to manufacture a commercial product based on that technology. Bichron, Siemens and General Electric are working on that development, too. But that technology is very expensive and the market for digital detection in nuclear medicine is not as large as the market in digital detection in radiology. (author)

  20. Who needs a small reactor?

    International Nuclear Information System (INIS)

    Wood, Janet.

    1991-01-01

    The opportunities and problems facing small reactors were debated at the Delhi seminar. It was established that these were markets where small reactors, producing heat as well as electricity, might be of use. Small combined heat and power reactors would be more useful in district heating than would large reactors, as their optimum heat production is in line with current district heating schemes. Most process heat requirements are below 900 o C and so may be provided by small nuclear plants. Several areas in electricity supply where small and medium sized reactors could find a market were also identified. Despite good reasons for favouring nuclear plants in these markets, such as no production of carbon dioxide, no need to use expensive oil or other scarce fossil fuels and flexibility, these are, however, disincentives to potential buyers. While serial production would decrease plant costs, the lead plants would bear heavy financial risks. Currently too many options in plant design make it difficult to present the advantages of small reactor technology. Siting reactors near centres of population would be problematical. The disposal of spent fuel and radioactive wastes would create problems in developing or non-nuclear countries. Over and above all these problems, however, was that of public acceptance. Some ways of overcoming these disincentives were discussed. (author)

  1. Orphan Nuclear Receptor Small Heterodimer Partner Negatively Regulates Growth Hormone-mediated Induction of Hepatic Gluconeogenesis through Inhibition of Signal Transducer and Activator of Transcription 5 (STAT5) Transactivation*

    Science.gov (United States)

    Kim, Yong Deuk; Li, Tiangang; Ahn, Seung-Won; Kim, Don-Kyu; Lee, Ji-Min; Hwang, Seung-Lark; Kim, Yong-Hoon; Lee, Chul-Ho; Lee, In-Kyu; Chiang, John Y. L.; Choi, Hueng-Sik

    2012-01-01

    Growth hormone (GH) is a key metabolic regulator mediating glucose and lipid metabolism. Ataxia telangiectasia mutated (ATM) is a member of the phosphatidylinositol 3-kinase superfamily and regulates cell cycle progression. The orphan nuclear receptor small heterodimer partner (SHP: NR0B2) plays a pivotal role in regulating metabolic processes. Here, we studied the role of ATM on GH-dependent regulation of hepatic gluconeogenesis in the liver. GH induced phosphoenolpyruvate carboxykinase (PEPCK) and glucose 6-phosphatase gene expression in primary hepatocytes. GH treatment and adenovirus-mediated STAT5 overexpression in hepatocytes increased glucose production, which was blocked by a JAK2 inhibitor, AG490, dominant negative STAT5, and STAT5 knockdown. We identified a STAT5 binding site on the PEPCK gene promoter using reporter assays and point mutation analysis. Up-regulation of SHP by metformin-mediated activation of the ATM-AMP-activated protein kinase pathway led to inhibition of GH-mediated induction of hepatic gluconeogenesis, which was abolished by an ATM inhibitor, KU-55933. Immunoprecipitation studies showed that SHP physically interacted with STAT5 and inhibited STAT5 recruitment on the PEPCK gene promoter. GH-induced hepatic gluconeogenesis was decreased by either metformin or Ad-SHP, whereas the inhibition by metformin was abolished by SHP knockdown. Finally, the increase of hepatic gluconeogenesis following GH treatment was significantly higher in the liver of SHP null mice compared with that of wild-type mice. Overall, our results suggest that the ATM-AMP-activated protein kinase-SHP network, as a novel mechanism for regulating hepatic glucose homeostasis via a GH-dependent pathway, may be a potential therapeutic target for insulin resistance. PMID:22977252

  2. Nuclear rights - nuclear wrongs

    Energy Technology Data Exchange (ETDEWEB)

    Paul, E.F.; Miller, F.D.; Paul, J.; Ahrens, J.

    1986-01-01

    This book contains 11 selections. The titles are: Three Ways to Kill Innocent Bystanders: Some Conundrums Concerning the Morality of War; The International Defense of Liberty; Two Concepts of Deterrence; Nuclear Deterrence and Arms Control; Ethical Issues for the 1980s; The Moral Status of Nuclear Deterrent Threats; Optimal Deterrence; Morality and Paradoxical Deterrence; Immoral Risks: A Deontological Critique of Nuclear Deterrence; No War Without Dictatorship, No Peace Without Democracy: Foreign Policy as Domestic Politics; Marxism-Leninism and its Strategic Implications for the United States; Tocqueveille War.

  3. Small reactor operating mode

    International Nuclear Information System (INIS)

    Snell, V.G.

    1997-01-01

    There is a potential need for small reactors in the future for applications such as district heating, electricity production at remote sites, and desalination. Nuclear power can provide these at low cost and with insignificant pollution. The economies required by the small scale application, and/or the remote location, require a review of the size and location of the operating staff. Current concepts range all the way from reactors which are fully automatic, and need no local attention for days or weeks, to those with reduced local staff. In general the less dependent a reactor is on local human intervention, the greater its dependence on intrinsic safety features such as passive decay heat removal, low-stored energy and limited reactivity speed and depth in the control systems. A case study of the design and licensing of the SLOWPOKE Energy System heating reactor is presented. (author)

  4. Nuclear moments

    CERN Document Server

    Kopferman, H; Massey, H S W

    1958-01-01

    Nuclear Moments focuses on the processes, methodologies, reactions, and transformations of molecules and atoms, including magnetic resonance and nuclear moments. The book first offers information on nuclear moments in free atoms and molecules, including theoretical foundations of hyperfine structure, isotope shift, spectra of diatomic molecules, and vector model of molecules. The manuscript then takes a look at nuclear moments in liquids and crystals. Discussions focus on nuclear paramagnetic and magnetic resonance and nuclear quadrupole resonance. The text discusses nuclear moments and nucl

  5. The Influence of Poly Vinil Alcohol Amount and Temperatures of the SolProcess on the Formation of (NH4)2U2O7 Gel

    International Nuclear Information System (INIS)

    Indra-Suryawan; Bangun-Wasito; Damunir; Hidayati; Setyo-Sulardi; Bambang-Siswanto; Ari-Handayani

    2000-01-01

    Research on the influence of poly vinil alcohol and temperatures on theresulted sol solutions. The sols were fed into gelation process using ammoniamedium and resulted were (NH 4 ) 2 U 2 O 7 gels spherical. The PVA variablesaddition on the sol process were 10; 15; 20; 25 and 30 g/1l uranyl nitrates.The temperature variables on the sol process were 75, 80, 85, 90 and 95 o C.The sol which successfully resulted (NH 4 ) 2 U 2 O 7 gel the gelation processwas on the PVA amount of 15 g and 90 o C. The resulted gel was then washed,dried and calcinate. The characterization of shape and surface of gel havebeen carried out using SEM photography. The density of gels were measured.For the 15 g PVA addition, the density was 8.3710 g/ml. While for process at90 o C, the density was 7.8871 g/ml. (author)

  6. Transport Nuclear Liability Insurance

    International Nuclear Information System (INIS)

    Folens, M.

    2006-01-01

    Although transport of nuclear substances represents only a very small part of the global transport of dangerous goods, it takes place every day all over the world and it is part of our daily life. Transport of nuclear material takes also place at every stage of the nuclear fuel cycle; radioactive materials are carried out all over the world by all major modes of transport: sea, air, road and rail. Despite the large number of nuclear transports, they are not considered as posing a serious risk. A major nuclear incident is almost always associated with the operating of fixed installations such as nuclear power plants; just think about Three Mile Island and Chernobyl. This perception is strengthened by the absence so far of serious accidents in the nuclear transport sector and this finding is in fact proof of the very safe conditions of nuclear transport. But accidents can never be excluded entirely and in some cases damages could be as large as those caused by fixed installations. This means that protection of the interests of possible victims should also be covered in a correct way. That is why the special nuclear liability regime has also been developed to cover damage caused by a nuclear transport accident. As stated by Patrick Reyners, the prime motivation for originally adopting a special nuclear regime was the harmonisation of national legislation and that nowhere more than in the field of international transport operations is such harmonisation felt desirable . The international legal regime has been developed along two tracks, one based on the mode of transport and the other based on the notion of dangerous goods. The linkage between those two tracks is of permanent concern and the mode of transport is the key element to determine which international instrument should be applicable. The purpose of this paper is to briefly introduce the financial security provided by the insurance industry to cover the international nuclear liability regime for nuclear

  7. Monte Carlo analysis of the SU(2)xU(1) and U(2) lattice gauge theories at different space-time dimensionalities

    International Nuclear Information System (INIS)

    Baig, M.; Colet, J.

    1986-01-01

    Using Monte Carlo simulations the SU(2)xU(1) lattice gauge theory has been analyzed, which is equivalent for the Wilson action to a U(2) theory, at space-time dimensionalities from d=3 to 5. It has been shown that there exist first-order phase transitions for both d=4 and d=5. A monopole-condensation mechanism seems to be responsible for these phase transitions. At d=3 no phase transitions have been detected. (orig.)

  8. Hyperpolarized [U-(2) H, U-(13) C]Glucose reports on glycolytic and pentose phosphate pathway activity in EL4 tumors and glycolytic activity in yeast cells.

    Science.gov (United States)

    Timm, Kerstin N; Hartl, Johannes; Keller, Markus A; Hu, De-En; Kettunen, Mikko I; Rodrigues, Tiago B; Ralser, Markus; Brindle, Kevin M

    2015-12-01

    A resonance at ∼181 ppm in the (13) C spectra of tumors injected with hyperpolarized [U-(2) H, U-(13) C]glucose was assigned to 6-phosphogluconate (6PG), as in previous studies in yeast, whereas in breast cancer cells in vitro this resonance was assigned to 3-phosphoglycerate (3PG). These peak assignments were investigated here using measurements of 6PG and 3PG (13) C-labeling using liquid chromatography tandem mass spectrometry (LC-MS/MS) METHODS: Tumor-bearing mice were injected with (13) C6 glucose and the (13) C-labeled and total 6PG and 3PG concentrations measured. (13) C MR spectra of glucose-6-phosphate dehydrogenase deficient (zwf1Δ) and wild-type yeast were acquired following addition of hyperpolarized [U-(2) H, U-(13) C]glucose and again (13) C-labeled and total 6PG and 3PG were measured by LC-MS/MS RESULTS: Tumor (13) C-6PG was more abundant than (13) C-2PG/3PG and the resonance at ∼181 ppm matched more closely that of 6PG. (13) C MR spectra of wild-type and zwf1Δ yeast cells showed a resonance at ∼181 ppm after labeling with hyperpolarized [U-(2) H, U-(13) C]glucose, however, there was no 6PG in zwf1Δ cells. In the wild-type cells 3PG was approximately four-fold more abundant than 6PG CONCLUSION: The resonance at ∼181 ppm in (13) C MR spectra following injection of hyperpolarized [U-(2) H, U-(13) C]glucose originates predominantly from 6PG in EL4 tumors and 3PG in yeast cells. © 2014 Wiley Periodicals, Inc.

  9. Small modular reactors are 'crucial technology'

    Science.gov (United States)

    Johnston, Hamish

    2018-03-01

    Small modular nuclear reactors (SMRs) offer a way for the UK to reduce carbon dioxide emissions from electricity generation, while allowing the country to meet the expected increase in demand for electricity from electric vehicles and other uses.

  10. World Nuclear Association position statement: Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Saint-Pierre, Sylvain

    2006-01-01

    experience and knowledge will only reinforce this already robust safety record. The current generation of humankind must not abdicate its duty to employ available, affordable and scientifically reliable means to meet its responsibility for disposing safely of nuclear waste and used nuclear fuel. Continued development of deep geological repositories and their operation beginning in this decade is essential if this responsibility is to be met. The nuclear industry has demonstrated that it accepts the management responsibility for nuclear waste and used nuclear fuel as a fundamental duty and is prepared to fulfill its obligation with professional dedication and technological skill. The following annexes complete the document: - Annex A, A Broader Perspective on Nuclear Waste and Used Nuclear Fuel; - Annex B, Common Mis-perceptions about Nuclear Waste; - Annex C, Nuclear Waste and Used Nuclear Fuel Repositories; Annex D, Nuclear Waste: A Surprisingly Small Burden; Annex E, Background Information

  11. Nuclear waste

    International Nuclear Information System (INIS)

    1989-01-01

    This paper reviews the Department of Energy's management of underground single-shell waste storage tanks at its Hanford, Washington, site. The tanks contain highly radioactive and nonradioactive hazardous liquid and solid wastes from nuclear materials production. Hundreds of thousands of gallons of these wastes have leaked, contaminating the soil, and a small amount of leaked waste has reached the groundwater. DOE does not collect sufficient data to adequately trace the migration of the leaks through the soil, and studies predicting the eventual environmental impact of tank leaks do not provide convincing support for DOE's conclusion that the impact will be low or nonexistent. DOE can do more to minimize the environmental risks associated with leaks. To reduce the environmental impact of past leaks, DOE may be able to install better ground covering over the tanks to reduce the volume of precipitation that drains through the soil and carries contaminants toward groundwater

  12. Mobile nuclear power systems

    International Nuclear Information System (INIS)

    Andersson, B.

    1988-11-01

    This report is meant to present a general survey of the mobile nuclear power systems and not a detailed review of their technical accomplishments. It is based in published material mainly up to 1987. Mobile nuclear power systems are of two fundamentally different kinds: nuclear reactors and isotopic generators. In the reactors the energy comes from nuclear fission and in the isotopic generators from the radioactive decay of suitable isotopes. The reactors are primarily used as power sourves on board nuclear submarines and other warships but have also been used in the space and in remote places. Their thermal power has ranged from 30 kWth (in a satellite) to 175 MWth (on board an aircraft carrier). Isotopic generators are suitable only for small power demands and have been used on board satellites and spaceprobes, automatic weatherstations, lighthouses and marine installations for navigation and observation. (author)

  13. Nuclear energy: the real cost

    International Nuclear Information System (INIS)

    Spencer, K.; Marshall, R.; Sweet, C.; Prior, M.; Welsh, I.; Bunyard, P.; Goldsmith, E.; Hildyard, N.; Jeffery, J.W.

    1981-01-01

    This report on the discussions within a small group of academics falls under the headings: chairman's foreword; summary and recommendations; the government's nuclear power programme and its implications; the CEGB's planning record; the past performance of Britain's nuclear power stations - a guide for the future (query); nuclear power -early uncertainties; historic costs - 'the fraud inherent in all inflationary finance'; current cost accounting; fuel costs - coal stays steady, nuclear rises; net effective cost and the rationale for nuclear power; reinterpreting net effective costs; other considerations; conclusions and recommendations; references. (U.K.)

  14. Elecnuc. Nuclear power plants worldwide

    International Nuclear Information System (INIS)

    1998-01-01

    This small folder presents a digest of some useful information concerning the nuclear power plants worldwide and the situation of nuclear industry at the end of 1997: power production of nuclear origin, distribution of reactor types, number of installed units, evolution and prediction of reactor orders, connections to the grid and decommissioning, worldwide development of nuclear power, evolution of power production of nuclear origin, the installed power per reactor type, market shares and exports of the main nuclear engineering companies, power plants constructions and orders situation, evolution of reactors performances during the last 10 years, know-how and development of nuclear safety, the remarkable facts of 1997, the future of nuclear power and the energy policy trends. (J.S.)

  15. Evaluation of the electrochemical behavior of U2.5Zr7.5Nb and U3Zr9Nb uranium alloys in relation to the pH and the solution aeration

    International Nuclear Information System (INIS)

    Mansur, Fabio Abud; Santos, Ana Maria Matildes dos; Ferraz, Wilmar Barbosa; Figueiredo, Celia de Araujo

    2011-01-01

    The Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) is developing, in cooperation with the Centro Tecnologico da Marinha (CTMSP), the advanced nuclear plate type fuel for the second core of the land-based reactor prototype of the Laboratorio de Geracao Nucleo-Eletrica (LABGENE). Recent investigations have shown that the fuel made of uranium-based niobium and zirconium alloys reaches the best performance relative to other fuels, e.g. UO 2 . Niobium and Zirconium also increase the corrosion resistance and the mechanical strength of the uranium alloys. By means of electrochemical techniques the corrosion behavior of alloys U 2 . 5 Zr 7.5 Nb and U 3 Zr 9 Nb, developed at CDTN and heat treated in the temperature range of 200 deg C to 600 deg C, was assessed. The effect of the parameters pH and solution aeration was studied as well as the influence of zirconium and niobium alloying elements in the corrosion of uranium. The techniques used were open circuit potential, electrochemical impedance and potentiodynamic anodic polarization at room temperature. The tests were performed in a three-electrode electrochemical cell with Ag/AgCl (3M KCl) as the reference electrode and a platinum plate as the auxiliary electrode. The potentiodynamic polarization curves of uranium and its alloys in acidic solutions showed regions with anodic currents limited by a passive film. The presence of niobium and zirconium contributed for the formation of this film. The impedance data showed the presence of two semicircles in the Bode diagram, indicating the occurrence of two distinct electrochemical processes. The data were fitted to an equivalent circuit model in order to obtain parameters of the electrochemical processes and evaluate the effect of the studied variables. (author)

  16. Nuclear energy: biological effects and environmental impact

    International Nuclear Information System (INIS)

    Boonefaes, M.

    1987-01-01

    This thesis is concerned with the large development of nuclear power plants and the recent nuclear catastrophe which has made clear how the hazards resulting from radioactivity affect public health and the environment. Environmental effects of nuclear power plants operating in normal conditions are small, but to obtain nuclear power plants of reduced radioactivity, optimization of their design, construction, operation and waste processing plays a decisive role. Biological effects of ionizing radiations and environmental impacts of Nuclear Power plants are developed [fr

  17. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  18. Your Radiologist Explains Nuclear Medicine

    Medline Plus

    Full Text Available ... or before abnormalities can be detected with other diagnostic tests. Nuclear medicine imaging procedures use small amounts ... relatively low and the benefit of an accurate diagnosis far outweighs any risk. To learn more about ...

  19. Small talk

    Directory of Open Access Journals (Sweden)

    Ryszard Przybylski

    2016-12-01

    Full Text Available The poem Small talk conjures up a communicative situation in which the main character, a newcomer from Poland, answers conventional questions related to their country. Bearing in mind the fact that this poem is set during a military dictatorship, superficial interest in his homeland may trigger a feeling of impatience. This is at least the impression formed if we adopt the perspective defined within the romantic tradition, and when taking into account the conventional poetry of martial law in Poland. Nevertheless, Barańczak retains an ironic distance towards such communicative situations and, as a consequence, does not create poetry that meets most readersʼ expectations. His poetic imperative for verbal art to be the expression of mistrust remains valid.

  20. Small Composers

    DEFF Research Database (Denmark)

    Holgersen, Sven-Erik; Bruun, Peter; Tjagvad, Mette

    2018-01-01

    the study: What expectations do the class teacher and the professional musicians have to the creative practice, i.e. to the collaboration and to the musical outcome? To which extent do the collaborating partners share a common understanding of the aim, content and method of the workshop? How do the roles......The present chapter discusses roles and responsibilities of the collaborating partners in a creative music workshop called Small Composers. The aim is to be attentive to a number of potential alterations implicated by the collaborating partners’ different backgrounds. The following questions guided...... and responsibilities of the collaborating partners become visible through the practice? How do the professional identities of the teacher and the musicians become visible and what are the implications for the workshop as a musical community of practice?...

  1. Nuclear knowledge management

    International Nuclear Information System (INIS)

    Constantin, Marin; Ghitescu, Petre

    2007-01-01

    Nuclear knowledge is characterized by high-complexity and variety of the component topics and long duration required by the build-up of individual competence. At organizational level, these characteristics made the power of an organization or institution to be determined by the capital accumulated of existing knowledge. Furthermore, the capacity of an organization to re-generate and raise the knowledge capital according to the specific processes it is running according to the existing demand decides its position/ranking in the economy of nuclear field. Knowledge management emphasizes re-utilization of existing practice and experience, upgrade, enrich and re-value of accumulated knowledge. The present paper identifies and classifies the nuclear knowledge steps, namely: tacit knowledge, explicit knowledge, preserving, transfer, knowledge capture etc. On this basis there are identified the existing problems of nuclear knowledge management in Romania such as: difficulties to keep within the country the existing expertise, lack of interest in nuclear education, low level of organization of existing knowledge due to a small number of data bases, an insufficient integration of existing knowledge in IT systems, lack of ontology and taxonomy or an average structuralism. Nuclear knowledge in Romania is facing a major challenge which is generated by the future development of nuclear facilities. It is related to the rising demand of expertise and experts. This challenge is better solved by partnership between end users and institutions of Research and Development and university organization as well which could ensure the generation, transfer and preservation of nuclear knowledge. (authors)

  2. Nuclear energy applications - ethical considerations

    International Nuclear Information System (INIS)

    Hoermann, K.

    1980-01-01

    Following an Austrian referendum in 1978 which showed a small majority against operation of nuclear power stations, the economic penalties involved by this decision are qualitatively discussed, with emphasis on reduced standards of living. Religious considerations are examined and the difficulty of obtaining informed public opinion is stressed. Alternative sources of energy, including nuclear fusion, are briefly referred to. (G.M.E.)

  3. Quarklei: nuclear physics from QCD

    International Nuclear Information System (INIS)

    Goldman, T.

    1985-01-01

    The difficulties posed for nuclear physics by either recognizing or ignoring QCD, are discussed. A QCD model for nuclei is described. A crude approximation is shown to qualitatively reproduce saturation of nuclear binding energies and the EMC effect. The model is applied seriously to small nuclei, and to hypernuclei

  4. Your Radiologist Explains Nuclear Medicine

    Medline Plus

    Full Text Available ... can be detected with other diagnostic tests. Nuclear medicine imaging procedures use small amounts of radioactive materials – called radiotracers – that ... outweighs any risk. To learn more about nuclear medicine, visit Radiology Info dot org. Thank you for your ... of Use | Links | Site Map Copyright © 2018 Radiological Society of ...

  5. Nuclear science

    International Nuclear Information System (INIS)

    1989-01-01

    This fact sheet answers specific questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant number sign 1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  6. Nuclear science

    International Nuclear Information System (INIS)

    1989-04-01

    This report answers questions about the Department of Energy's possible acquisition and conversion of a partially completed commercial nuclear power plant to a nuclear materials production facility. The nuclear power plant is the Washington Nuclear Plant No.1 owned by the Washington Public Power Supply System and is located on DOE's Hanford Reservation near Richland, Washington

  7. Nuclear medicine

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1986-01-01

    Several growth areas for nuclear medicine were defined. Among them were: cardiac nuclear medicine, neuro-psychiatric nuclear medicine, and cancer diagnosis through direct tumor imaging. A powerful new tool, Positron Emission Tomography (PET) was lauded as the impetus for new developments in nuclear medicine. The political environment (funding, degree of autonomy) was discussed, as were the economic and scientific environments

  8. Nuclear option

    Energy Technology Data Exchange (ETDEWEB)

    Kemm, K R

    1978-05-01

    The global outlook is that nuclear reactors are here to stay and South Africa has already entered the nuclear power stakes. This article discusses the rocketing oil prices, and the alternatives that can be used in power generation, the good safety record of the nuclear industry and the effect that South Africa's first nuclear power station should have on the environment.

  9. Nuclear resisters

    International Nuclear Information System (INIS)

    1981-01-01

    The booklet contains six papers by different authors, under the headings: dangers along the nuclear fuel cycle; the nuclear profiteers; the nuclear state is a police state; a non-disposable future (renewable energy sources, energy conservation); nuclear weapons - out of control; man made madness. (U.K.)

  10. Magnetic hyperfine interactions of U2 center in CaF2, SrF2 and BaF2

    International Nuclear Information System (INIS)

    Graf, C.J.F.

    1976-02-01

    The magnetic hyperfine parameters of the U 2 center in CaF 2 , SeF 2 and BaF 2 , using a molecular orbitals scheme have been calculated. The need for the inclusion of mechanisms such as Pauli Repulsion and Covalence in order to describe the electronic structure of the defect has been shown. In the molecular orbitals model a weak covalence parameter has been phenomenologically introduced, mixing the is atomic wavefunction of hydrogen with a properly symmetrized linear combination of 2p F - functions centered on the ions of the first fluorine shell. The results obtained are compared with experimental measurements of EPR and ENDOR. (Author) [pt

  11. Parvoviral nuclear import: bypassing the host nuclear-transport machinery.

    Science.gov (United States)

    Cohen, Sarah; Behzad, Ali R; Carroll, Jeffrey B; Panté, Nelly

    2006-11-01

    The parvovirus Minute virus of mice (MVM) is a small DNA virus that replicates in the nucleus of its host cells. However, very little is known about the mechanisms underlying parvovirus' nuclear import. Recently, it was found that microinjection of MVM into the cytoplasm of Xenopus oocytes causes damage to the nuclear envelope (NE), suggesting that the nuclear-import mechanism of MVM involves disruption of the NE and import through the resulting breaks. Here, fluorescence microscopy and electron microscopy were used to examine the effect of MVM on host-cell nuclear structure during infection of mouse fibroblast cells. It was found that MVM caused dramatic changes in nuclear shape and morphology, alterations of nuclear lamin immunostaining and breaks in the NE of infected cells. Thus, it seems that the unusual nuclear-import mechanism observed in Xenopus oocytes is in fact used by MVM during infection of host cells.

  12. Nuclear links

    International Nuclear Information System (INIS)

    1981-01-01

    The subject is dealt with in sections: introduction; energy and the third world; world energy consumption 1978; oil -the energy dilemma; nuclear chains - introduction; uranium; Namibia; enrichment and reprocessing; countries with enrichment and reprocessing facilities; waste; conclusion; why take the nuclear option; third world countries with nuclear reactors; the arms connection; government spending and human resources 1977 (by countries); nuclear power - the final solution; the fascists; world bank; campaigns; community action in Plogoff; Australian labour movement; NUM against nuclear power; Scottish campaign; students against nuclear energy; anti-nuclear campaign; partizans; 3W1 disarmament and development; campaign ATOM; CANUC; 3W1; SANE. (U.K.)

  13. Header [nuclear battery

    International Nuclear Information System (INIS)

    Goslee, D.E.; Barr, H.N.

    1976-01-01

    The invention relates to a nuclear-powered microwatt thermoelectric generator, small in size, efficient in operation, and which will last for a considerable period of time. The generator is suitable for implanting within the human body for powering devices such as cardiac pacemakers

  14. Industry plots nuclear revival

    International Nuclear Information System (INIS)

    Nogee, A.

    1984-01-01

    A successful revival of the nuclear power industry will require standardization and a reduction in the number of companies managing construction, according to Atomic Industrial Forum spokesmen. In describing the concept of a few superutilities to build nuclear plants, they emphasize the need for a nuclear culture among construction management. Future plant designs emphasize small scale, with design, engineering, licensing, financing, operator training, and paperwork completed before the sale. Utilities continue to pursue economy-of-scale despite the evidence that small-scale reactors can be economical and are more appropriate for fluctuating demand growth. Financiers want more say in construction plans in the future, while utilities want to establish generating subsidiaries for wholesale power sales

  15. Nuclear Option in Korea

    International Nuclear Information System (INIS)

    Han, K. I.

    2002-01-01

    With sixteen(16) operating nuclear units in Korea, the share of nuclear power generation reached 41% of the total electric power generation as of December 2000. A prediction is that it would further increase to 44.5% by year 2015 according to the national long term power development plan. Four units are currently under construction with 6 more units in order. With little domestic energy resource and increasing energy demand to support national economic growth, Korea has chosen nuclear power as one of the major energy sources to ensure stable power supply and to promote energy self-sufficiency. It has been recognized that nuclear power in Korea is not a selective option but rather a necessity. The Korean nuclear power development started with construction of a 600 MWe size reactor that was designed and constructed by foreign vendors. As the national grid capacity became larger, the size of nuclear units increased to 1000 MWe class. In the mean time, the need for nuclear technology self-reliance grew not only in operation and maintenance but also in construction, manufacturing and design. For this, a nuclear technology self-reliance program has been embarked with the support of the Government and utility, and the 1000 MWe class KSNP(Korean Standard Nuclear Power Plant) has been developed. The KSNPs are currently being designed, manufactured, constructed and operated by relevant Korean entities themselves. To fit into a larger capacity national grid and also to improve nuclear economic competitiveness, the 1400 MWe class KNGR(Korean Next Generation Reactor) design has been developed uprating the 1000 MWe KSNP design. Its construction project is currently under contract negotiation, and is planned to be finished by 2010. In the mean time, to be ready for future electric power market deregulation, the 600 MWe class small KSNP design is being developed downsizing the KSNP. A modular small size reactor, SMART(System Integrated Modular Advanced Reactor) is also being

  16. Nuclear data needs in Thailand

    International Nuclear Information System (INIS)

    Chongkum, S.

    1999-01-01

    The major nuclear facilities in Thailand are composed of nuclear research reactor, neutron generators, electron linear accelerators and 1 GeV Synchrotron facility, which is under construction. The other small facilities are radioisotope sources and X ray tubes for X ray diffraction and fluorescence studies. Office of Atomic Energy for Peace (OAEP) is the function arm for nuclear institutions in Thailand. Its major roles are nuclear regulatory, coordinating for nuclear affairs and foreign relations, R and D for nuclear science and technology and giving nuclear services. Nuclear data activities concerning Thai Research Reactor (TRR-1/M1) are for examples: neutronics and thermalhydraulics for reactor operation, neutron energy spectrum and neutron flux measurement for neutron activation analysis and isotope production, neutron and gamma doses, shielding and material testing for radiation safety, and neutron beam experiments. OAEP is taking part in the areas of regional cooperation on utilization of nuclear research reactors, education and training, sharing of research reactor experimental facilities, establishment of nuclear data program and information exchange. The nuclear data reports have been shared among institutions in Thailand through OAEP, which is served as a central nuclear data depository including e.g., INIS, IAEA-NDS, Joint Research Centre Commission of the European Communities and Japanese Nuclear Data Committee (JNDC). This report shows the nuclear facilities in Thailand, the roles of the Office of Atomic Energy for Peace on nuclear data depository and nuclear power development program. The main activities at the Thai Research Reactor TRR-1/M1 concerning nuclear data needs for specific uses in both theoretical and experimental aspects are also described. (J.P.N.)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  18. The emerging nuclear suppliers

    International Nuclear Information System (INIS)

    Dunn, L.A.

    1990-01-01

    Since the early 1980s, a growing amount of attention has been paid to a small group of mostly developing countries that have come to be called the emerging nuclear suppliers. Argentina and Brazil, China and South Korea, India and Pakistan, Spain and Yugoslavia have frequently been mentioned in this category. Their actual and potential nuclear export dealings and policies have been the subject of academic writings and policy papers, of scholarly symposia and exchanges at meetings of the traditional nuclear suppliers. With foundation and other support, UCLA's Center for International and Strategic Affairs has begun a major project to develop a database on the transactions, policies, and export control institutions of the emerging suppliers. This chapter provides some guidelines for policy toward the emerging nuclear suppliers

  19. Discovery of novel small molecule activators of β-catenin signaling.

    Directory of Open Access Journals (Sweden)

    Folkert Verkaar

    Full Text Available Wnt/β-catenin signaling plays a major role in embryonic development and adult stem cell maintenance. Reduced activation of the Wnt/β-catenin pathway underlies neurodegenerative disorders and aberrations in bone formation. Screening of a small molecule compound library with a β-galactosidase fragment complementation assay measuring β-catenin nuclear entry revealed bona fide activators of β-catenin signaling. The compounds stabilized cytoplasmic β-catenin and activated β-catenin-dependent reporter gene activity. Although the mechanism through which the compounds activate β-catenin signaling has yet to be determined, several key regulators of Wnt/β-catenin signaling, including glycogen synthase kinase 3 and Frizzled receptors, were excluded as the molecular target. The compounds displayed remarkable selectivity, as they only induced β-catenin signaling in a human osteosarcoma U2OS cell line and not in a variety of other cell lines examined. Our data indicate that differences in cellular Wnt/β-catenin signaling machinery can be exploited to identify cell type-specific activators of Wnt/β-catenin signaling.

  20. Nuclear power in human medicine

    International Nuclear Information System (INIS)

    Kuczera, Bernhard

    2012-01-01

    The public widely associate nuclear power with the megawatt dimensions of nuclear power plants in which nuclear power is released and used for electricity production. While this use of nuclear power for electricity generation is rejected by part of the population adopting the polemic attitude of ''opting out of nuclear,'' the application of nuclear power in medicine is generally accepted. The appreciative, positive term used in this case is nuclear medicine. Both areas, nuclear medicine and environmentally friendly nuclear electricity production, can be traced back to one common origin, i.e. the ''Atoms for Peace'' speech by U.S. President Eisenhower to the U.N. Plenary Assembly on December 8, 1953. The methods of examination and treatment in nuclear medicine are illustrated in a few examples from the perspective of a nuclear engineer. Nuclear medicine is a medical discipline dealing with the use of radionuclides in humans for medical purposes. This is based on 2 principles, namely that the human organism is unable to distinguish among different isotopes in metabolic processes, and the radioactive substances are employed in amounts so small that metabolic processes will not be influenced. As in classical medicine, the application of these principles serves two complementary purposes: diagnosis and therapy. (orig.)

  1. The U2 snDNA Is a Useful Marker for B Chromosome Detection and Frequency Estimation in the Grasshopper Abracris flavolineata.

    Science.gov (United States)

    Milani, Diogo; Palacios-Gimenez, Octavio M; Cabral-de-Mello, Diogo C

    2017-01-01

    In this study, we describe a strategy to determine the presence of B chromosomes in the living grasshopper Abracris flavolineata by FISH using U2 snDNA as a probe in interphase hemolymph nuclei. In individuals without B chromosomes, (0B) 2 dot signals were noticed, corresponding to A complement U2 snDNA clusters. In +1B and +2B individuals, 4 or 8 additional signals were noticed, respectively. In all cases, the absence or presence of 1 or 2 B chromosomes correlated in hemolymph and in somatic or germline tissues, validating the efficiency of the marker. Our data suggest that the B chromosome of A. flavolineata is present in all somatic tissues. B-carrying individuals showed the same number of B chromosomes in germ and somatic cells, suggesting that the B is mitotically stable. The marker was used to compare B chromosome frequency in the analyzed population with a sample collected previously, in order to test for B frequency changes and differences of B chromosome prevalence among sexes, but no statistically significant differences were noticed. The identification of living animals harboring B chromosomes will be very useful in future studies of B chromosome transmission, as well as in functional studies involving RNA analysis, thus contributing to the understanding of evolutionary history and the possible role of the B chromosome in A. flavolineata. © 2017 S. Karger AG, Basel.

  2. Dosage of the Abcg1-U2af1 region modifies locomotor and cognitive deficits observed in the Tc1 mouse model of Down syndrome.

    Directory of Open Access Journals (Sweden)

    Damien Marechal

    Full Text Available Down syndrome (DS results from one extra copy of human chromosome 21 and leads to several alterations including intellectual disabilities and locomotor defects. The transchromosomic Tc1 mouse model carrying an extra freely-segregating copy of human chromosome 21 was developed to better characterize the relation between genotype and phenotype in DS. The Tc1 mouse exhibits several locomotor and cognitive deficits related to DS. In this report we analyzed the contribution of the genetic dosage of 13 conserved mouse genes located between Abcg1 and U2af1, in the telomeric part of Hsa21. We used the Ms2Yah model carrying a deletion of the corresponding interval in the mouse genome to rescue gene dosage in the Tc1/Ms2Yah compound mice to determine how the different behavioral phenotypes are affected. We detected subtle changes with the Tc1/Ms2Yah mice performing better than the Tc1 individuals in the reversal paradigm of the Morris water maze. We also found that Tc1/Ms2Yah compound mutants performed better in the rotarod than the Tc1 mice. This data support the impact of genes from the Abcg1-U2af1 region as modifiers of Tc1-dependent memory and locomotor phenotypes. Our results emphasize the complex interactions between triplicated genes inducing DS features.

  3. Fisetin, a dietary flavonoid induces apoptosis via modulating the MAPK and PI3K/Akt signalling pathways in human osteosarcoma (U-2 OS cells

    Directory of Open Access Journals (Sweden)

    Jian-Ming Li

    2015-12-01

    Full Text Available Human osteosarcoma is the most prevalent primary malignant bone tumor with high frequency of invasion and metastasis. Strong resistance coupled with toxicity of the currently available chemotherapeutic drugs poses challenge in treatment. The study aimed to investigate if fisetin, a dietary flavonoid induced apoptosis in human osteosarcoma (U-2 OS cells. Fisetin at 20-100 µM effectively reduced the viability of OS cells, and induced apoptosis by significantly inducing the expression of caspases (Caspases- 3,-8 and -9 and pro-apoptotic proteins (Bax and Bad with subsequent down-regulation of Bcl-xL and Bcl-2. While fisetin inhibited PI3K/Akt pathway and ERK1/2, it caused enhanced expressions of p-JNK, p-c-Jun and p-p38. Fisetin-induced ROS generation and decrease in mitochondrial membrane potential would have also contributed to rise in apoptotic cell counts. The observations suggest that fisetin was able to effectively induce apoptosis of U-2 OS cells through ROS generation and modulation of MAPK and PI3K/Akt signalling cascades.

  4. Nuclear manpower development

    International Nuclear Information System (INIS)

    Hwang, I. A.; Lee, K. B.; Shin, B. C.

    2011-12-01

    The nuclear manpower development project has concentrated on the systemisation and specialization of education and training programs and has actively carried out diverse activities to create new nuclear courses based on the experience of the Nuclear Training and Education Center (NTC) accumulated over the past years. As the demand of education program for training nuclear manpower is increasing due to the remarkable growth of nuclear industry, NTC developed customized education programs making the most use of nuclear experiment equipment and providing practical exercise with research reactor. For improving organizational performance and the development of skilled manpower, KAERI-ACE 2.0 system offered diverse programs addressing the type of occupation and position based on individual competency. Also education on IT was carried out to improve public relations on nuclear and field trips were arranged to encourage local residents' better understanding of the nuclear industry. As a continuous effort, In 2011, NTC specially conducted a survey of employees who are attached to small and medium sized business, and analyzed the present business situations and education requirements for the development of a Pre/under job education program. Prior to this, a briefing session took place for mutual exchange of opinions of industry and academia, based on which a test operation on 'Basic Radiation Education' was carried out. This program has a significance that it was first step toward connection between the nuclear industry and academia as well as an opportunity to educate the employee involved in nuclear engineering field. In 2012, this program is planned to be expanded. With reference to the in-house training, NTC established an 'e-HRD system' providing available resources concerned with education program for cultivating talented personnel. All the education programs are based on individual competency. The e-HRD system will be test operated in 2012 and applied to the

  5. Nuclear battery materials and application of nuclear batteries

    International Nuclear Information System (INIS)

    Hao Shaochang; Lu Zhenming; Fu Xiaoming; Liang Tongxiang

    2006-01-01

    Nuclear battery has lots of advantages such as small volume, longevity, environal stability and so on, therefore, it was widely used in aerospace, deep-sea, polar region, heart pacemaker, micro-electromotor and other fields etc. The application of nuclear battery and the development of its materials promote each other. In this paper the development and the latest research progress of nuclear battery materials has been introduced from the view of radioisotope, electric energy conversion and encapsulation. And the current and potential applications of the nuclear battery are also summarized. (authors)

  6. Current status of nuclear power development

    International Nuclear Information System (INIS)

    Dias, P.M.

    1994-01-01

    Nuclear power is not a viable energy source for Sri Lanka at present because of a number of reasons, the main reason being the non-availability of small and economically viable nuclear power plants. However several suppliers of nuclear power plants are in the process of developing small and medium power plants (SMPRs) which could be economically competitive with coal. The paper deals with past and future trends of nuclear power plants, their economics and safety. It also deals with environmental effects and public acceptance of nuclear power plants

  7. MENA. New Nuclear

    International Nuclear Information System (INIS)

    Kovachev, Milko

    2012-01-01

    MENA region summary: UAE - Ground broken on reactor site; Turkey - Contracts for NPP signed, legal and regulatory infrastructure well-developed; Jordan - Committed plans, NPP procurement process initiated, legal and regulatory infrastructure developing; Egypt - Well-developed plans and legal & regulatory infrastructure, but commitment pending; Saudi Arabia – Commitment made; Algeria, Tunisia - Developing Plans; Kuwait, Oman, Qatar , Bahrain, Morocco - Considered civil nuclear power as an option but no immediate prospects for development. MENA region continues to express strong willingness to diversify its power mix with nuclear and renewables. Gulf States, GCC countries are participating in the collaborative study of a potential nuclear energy programme in the region since 2006. Bahrain, Kuwait, Qatar and Oman are studying the option, however given their small populations and the limited size of their electricity grids, Qatar, Bahrain, and Oman have less capacity to support domestic nuclear power programs. The Fukushima accident has played a role in one country’s decision to abandon nuclear energy for power generation: Kuwaiti government— largely influenced by the events in Japan—decided to reverse its policy on nuclear energy. Valued at US$200 billion, the Middle East’s new nuclear build market holds immense opportunities for expertise, component suppliers and service providers

  8. Nuclear Power

    International Nuclear Information System (INIS)

    Douglas-Hamilton, J.; Home Robertson, J.; Beith, A.J.

    1987-01-01

    In this debate the Government's policy on nuclear power is discussed. Government policy is that nuclear power is the safest and cleanest way of generating electricity and is cheap. Other political parties who do not endorse a nuclear energy policy are considered not to be acting in the people's best interests. The debate ranged over the risks from nuclear power, the UK safety record, safety regulations, and the environmental effects of nuclear power. The Torness nuclear power plant was mentioned specifically. The energy policy of the opposition parties is strongly criticised. The debate lasted just over an hour and is reported verbatim. (UK)

  9. The Global Outlook for Small Reactors: Opportunities, Challenges and Implementation

    International Nuclear Information System (INIS)

    Hughes, A.

    2012-01-01

    The fascinating topic of small nuclear is becoming more prevalent on the nuclear agenda. The discussions are generally focused within the country of technical origin. In this presentation 'The global outlook for small reactors' Rolls-Royce along with energy business analysts Douglas-Westwood present their shared views on the global opportunities for Small Reactor deployment in the context of the wider energy market. The presentation will: provide a compressive overview of trends and dynamics relating to Small Reactors in the context of the current world energy market, identify specific Small Reactor opportunities and areas of interest, address the challenges and potential solutions for Small Reactor deployment and operation.(author).

  10. Scenarios simulation of severe accident type small loss of coolant (Loca), with the code MELCOR version 2.1 for the nuclear power plant of Laguna Verde; Simulacion de escenarios de accidente severo tipo perdida de refrigerante (Loca) pequeno, con el codigo MELCOR version 2.1 para la central nucleo-electrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Cardenas V, J.; Mugica R, C. A.; Godinez S, V., E-mail: Jaime.cardenas@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    In this work was carried out the analysis of two scenarios of the accident type with loss of coolant in a recirculation loop for a break with smaller ares to 0.1 ft{sup 2} (4.6 cm{sup 2}), which is classified according to their size like small Loca. The first simulated scenario was a small Loca without action of the emergency coolant injection systems, and the second was a small Loca with only the available system LPCS. This design base accident was taken into account for its relevance with regard to the damage to the core and the hydrogen generation. Was also observed and analyzed the response of the action of the ECCS that depend of the loss of coolant reason and this in turn depends of the size and type of the pipe break. The specified scenarios were simulated by means of the use of MELCOR model for the nuclear power plant of Laguna Verde that has the Comision Nacional de Seguridad Nuclear y Salvaguardias. (Author)

  11. JPRS Report, Nuclear Developments

    National Research Council Canada - National Science Library

    1991-01-01

    Partial Contents: Medium Range Missiles, Rocket Engine, Nuclear Submarine, Nuclear Reactor, Nuclear Inspection, Nuclear Weapons, Transfer Technology, Scud, Safety, Nuclear Power, Chernobyl Trial, ,CHemical Weapons...

  12. Nuclear forensics

    International Nuclear Information System (INIS)

    Venugopal, V.

    2010-01-01

    Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone activity

  13. Nuclear power

    International Nuclear Information System (INIS)

    1987-01-01

    ''Nuclear Power'' describes how a reactor works and examines the different designs including Magnox, AGR, RBMK and PWR. It charts the growth of nuclear generation in the world and its contributions to world energy resources. (author)

  14. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  15. Nuclear regulation

    International Nuclear Information System (INIS)

    1990-04-01

    Because of an accidental release in 1986 of low-level waste stored at the Wright-Patterson Air Force Base, Ohio, several individuals inhaled small amounts of a radioactive substance. GAO examined the Nuclear Regulatory Commission's oversight of the Department of Defense's use, handling, and disposal of radioactive material and found that no comprehensive DOD waste disposal program exists and none of the three services knows the full extent of its low-level radioactive waste disposal problems. Throughout the 1980s, the Army and the Air Force had, on occasion, been banned from disposal sites for failing to comply with federal and state requirements. By December 1992, two of the three sites now used by DOD to disposed of waste will close, and only a limited number of new sites may be available for several years. In the interim, DID will pay substantial surcharges to dispose of waste. After January 1993, DOD will have to comply with disposal requirements for as many as 16 sites or store waste on-site pending the availability of new sites. This report discusses how GAO believes DOD needs to take full advantage of the time between now and January 1993 to establish a low-level radioactive waste disposal program. DOD also needs to work with other federal agencies, compacts, and states to determine the feasibility of dedicating a portion of one or more disposal sites for the government's use

  16. First observations of tritium in ground water outside chimneys of underground nuclear explosions, Yucca Flat, Nevada Test Site

    International Nuclear Information System (INIS)

    Crow, N.B.

    1976-01-01

    Abnormal levels of radionuclides had not been detected in ground water at the Nevada Test Site beyond the immediate vicinity of underground nuclear explosions until April 1974, when above-background tritium activity levels were detected in ground-water inflow from the tuff beneath Yucca Flat to an emplacement chamber being mined in hole U2aw in the east-central part of Area 2. No other radionuclides were detected in a sample of water from the chamber. In comparison with the amount of tritium estimated to be present in the ground water in nearby nuclear chimneys, the activity level at U2aw is very low. To put the tritium activity levels at U2aw into proper perspective, the maximum tritium activity level observed was significantly less than the maximum permissible concentration (MPC) for a restricted area, though from mid-April 1974 until the emplacement chamber was expended in September 1974, the tritium activity exceeded the MPC for the general public. Above-background tritium activity was also detected in ground water from the adjacent exploratory hole, Ue2aw. The nearest underground nuclear explosion detonated beneath the water table, believed to be the source of the tritium observed, is Commodore (U2am), located 465 m southeast of the emplacement chamber in U2aw. Commodore was detonated in May 1967. In May 1975, tritium activity May significantly higher than regional background. was detected in ground water from hole Ue2ar, 980 m south of the emplacement chamber in U2aw and 361 m from a second underground nuclear explosion, Agile (U2v), also detonated below the water table, in February 1967. This paper describes these occurrences of tritium in the ground water. A mechanism to account for the movement of tritium is postulated

  17. New developments in small reactors

    International Nuclear Information System (INIS)

    McDonnell, F.N.; Reed, A.

    1990-08-01

    During the fifty years since nuclear fission was discovered, nuclear energy has emerged to play an increasingly important role in meeting global energy needs. At the recent World Energy Conference in Montreal, 1989 September, experts agreed that nuclear power will continue to be an essential part of the future energy mix. The demand for economic and reliable energy sources is driven by the growth in the world's population and the essential role energy plays in industrial development. Global energy requirements, expected to double over the next 40 years, will seriously challenge suppliers in their ability to meet the demand. Ultimately, efficient energy utilization will become singularly important. Industrialization and economic development manifest themselves in urbanization. Urban dwellers consume significantly more energy per capita compared with their rural neighbours. Consequently, concentrated and environmentally acceptable energy sources, combined with efficient distribution systems, are now recognized as essential to meet urban energy demands. In considering the alternatives that will meet these requirements, nuclear energy qualifies as both a concentrated and environmentally benign source. Nuclear electricity generation is a mature technology that paves the way for other applications. If nuclear energy is to realize its full potential as a safe and cost-effective alternative to fossil fuels, applications beyond those that are currently being serviced by large, central nuclear power stations must be identified, and appropriately designed and sized reactors developed as an investment in the future. To meet this potential, new small reactor concepts are being developed to satisfy the expected energy demands, while also displaying characteristics that address current public concerns for providing minimal environmental impact. Concepts ranging in sized from 10 MW(t) to 1000 MW(t) are being pursued in a number of countries, including Canada, USA, UK, China, and

  18. Nuclear energy

    International Nuclear Information System (INIS)

    Kuhn, W.

    1986-01-01

    This loose-leaf collection is made up of five didactically prepared units covering the following subjects: basic knowledge on nuclear energy, nuclear energy in relation to energy economy, site issues, environmental compatibility of nuclear energy, and nuclear energy in the focus of political and social action. To this was added a comprehensive collection of material: specific scientific background material, a multitude of tables, diagrams, charts etc. for copying, as well as 44 transparent charts, mostly in four colours. (orig./HP) [de

  19. Nuclear structure

    International Nuclear Information System (INIS)

    Eastham, D.A.; Joy, T.

    1986-01-01

    The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

  20. Nuclear power: the future reassessed

    Energy Technology Data Exchange (ETDEWEB)

    Roberts, L [East Anglia Univ., Norwich (UK). Environmental Risk Assessment Unit (ERAU)

    1991-02-01

    In recommending that consent be given for the construction of a further Pressurized Water Reactor at Hinkley Point in Somerset, UK, the Inspector at the Public Inquiry underlined two major benefits: (i) the contribution an additional large nuclear plant would make to the strategic objective of diversity of supply, and (ii) the environmental benefits of nuclear power compared to many alternative forms of electricity generation. The major environmental advantages of nuclear power over fossil fuel combustion arise both because of the small amounts of fuel required - 1/18,000 compared to coal - thus minimizing transport needs and land use, and because of the virtual absence of atmospheric emissions from nuclear stations. Nuclear reactors emit no acid gases and the nuclear fuel cycle gives rise to only small amounts of carbon dioxide. An expansion of the nuclear option is often opposed on three grounds; the need to dispose of radioactive waste; the danger of the proliferation of nuclear weapons and the risk of a large scale accident. However all these doubts can be answered and the arguments supporting nuclear safety are summarized. It is argued that the contribution to primary energy demand in Europe could be doubled or trebled by 2020 with considerable benefits in overall safety environmental impacts at no extra cost. (author).