Search Results - "Laesser, R"

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  1. 1

    Combined use of two supervised learning algorithms to model sea turtle behaviours from tri-axial acceleration data by Jeantet, L, Dell'Amico, F, Forin-Wiart, M-A, Coutant, M, Bonola, M, Etienne, D, Gresser, J, Regis, S, Lecerf, N, Lefebvre, F, de Thoisy, B, Le Maho, Y, Brucker, M, Châtelain, N, Laesser, R, Crenner, F, Handrich, Y, Wilson, R, Chevallier, D

    Published in Journal of experimental biology (23-05-2018)
    “…Accelerometers are becoming ever more important sensors in animal-attached technology, providing data that allow determination of body posture and movement and…”
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    Journal Article
  2. 2

    Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO by Poitevin, Y., Boccaccini, L.V., Zmitko, M., Ricapito, I., Salavy, J.-F., Diegele, E., Gabriel, F., Magnani, E., Neuberger, H., Lässer, R., Guerrini, L.

    Published in Fusion engineering and design (01-12-2010)
    “…Europe has developed two reference tritium breeder blankets concepts that will be tested in ITER under the form of Test Blanket Modules: (i) the Helium-Cooled…”
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    Journal Article Conference Proceeding
  3. 3

    The EU programme for modelling radiation effects in fusion reactor materials: An overview of recent advances and future goals by Dudarev, S.L., Boutard, J.-L., Lässer, R., Caturla, M.J., Derlet, P.M., Fivel, M., Fu, C.-C., Lavrentiev, M.Y., Malerba, L., Mrovec, M., Nguyen-Manh, D., Nordlund, K., Perlado, M., Schäublin, R., Van Swygenhoven, H., Terentyev, D., Wallenius, J., Weygand, D., Willaime, F.

    Published in Journal of nuclear materials (30-04-2009)
    “…The EU fusion materials modelling programme was initiated in 2002 with the objective of developing a comprehensive set of computer modelling techniques and…”
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    Journal Article Conference Proceeding
  4. 4

    ITER fuel cycle R&D: Consequences for the design by Glugla, M., Murdoch, D.K., Antipenkov, A., Beloglazov, S., Cristescu, I., Cristescu, I.-R., Day, C., Laesser, R., Mack, A.

    Published in Fusion engineering and design (01-02-2006)
    “…The ITER fuel cycle is designed to handle considerable flow rates of tritium with high flexibility and reliability; experimental work is ongoing to validate…”
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    Journal Article Conference Proceeding
  5. 5

    Fusion materials development program in the broader approach activities by Nishitani, T., Tanigawa, H., Jitsukawa, S., Nozawa, T., Hayashi, K., Yamanishi, T., Tsuchiya, K., Möslang, A., Baluc, N., Pizzuto, A., Hodgson, E.R., Laesser, R., Gasparotto, M., Kohyama, A., Kasada, R., Shikama, T., Takatsu, H., Araki, M.

    Published in Journal of nuclear materials (30-04-2009)
    “…Breeding blankets are the most important components in DEMO. The DEMO blanket has to withstand high neutron flux typically 15–30 dpa/year under continuous…”
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    Journal Article Conference Proceeding
  6. 6

    Design progress for the ITER torus and neutral beam cryopumps by Day, Chr, Haas, H., Hanke, St, Hauer, V., Luo, X., Scannapiego, M., Simon, R., Strobel, H., Fellin, F., Lässer, R., Masiello, A., Papastergiou, St, Dremel, M., Mayaux, Chr, Pearce, R.

    Published in Fusion engineering and design (01-10-2011)
    “…The ITER torus and neutral beam cryopumps are complex vacuum pumps which will be designed to the build-to-print level stage for the call for tender for…”
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    Journal Article Conference Proceeding
  7. 7

    The European integrated materials and technology programme in fusion by Andreani, R, Diegele, E, Laesser, R, van der Schaaf, B

    Published in Journal of nuclear materials (01-08-2004)
    “…The paper reviews the present EU long-term programme, which is focused on the R&D of the materials and key technologies needed for the DEMO reactor. The…”
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    Journal Article
  8. 8

    Ferritic–Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validation by Salavy, J.-F., Aiello, G., Aubert, P., Boccaccini, L.V., Daichendt, M., De Dinechin, G., Diegele, E., Giancarli, L.M., Lässer, R., Neuberger, H., Poitevin, Y., Stephan, Y., Rampal, G., Rigal, E.

    Published in Journal of nuclear materials (30-04-2009)
    “…The Helium-Cooled Lithium-Lead and the Helium-Cooled Pebble Bed are the two breeding blankets concepts for the DEMO reactor which have been selected by EU to…”
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    Journal Article Conference Proceeding
  9. 9

    The European breeding blankets development and the test strategy in ITER by Poitevin, Y., Boccaccini, L.V., Cardella, A., Giancarli, L., Meyder, R., Diegele, E., Laesser, R., Benamati, G.

    Published in Fusion engineering and design (01-11-2005)
    “…In Europe, two breeding blankets are currently developed for DEMO reactor specifications, corresponding to two different research lines, one using a liquid…”
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    Journal Article Conference Proceeding
  10. 10

    The ancillary systems of the European test blanket modules: Configuration and integration in TIER by Ricapito, I., Bede, O., Boccaccini, L.V., Ciampichetti, A., Ghidersa, B., Guerrini, L., Lässer, R., Neuberger, H., Poitevin, Y., Salavy, J.F.

    Published in Fusion engineering and design (01-12-2010)
    “…The conceptual design of the ancillary systems of the European Test Blanket Modules (TBMs), namely the PbLi circuit, the Helium Cooling Systems (HCSs), the…”
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    Journal Article Conference Proceeding
  11. 11

    Structural materials development and databases by van der Schaaf, B., Diegele, E., Laesser, R., Moeslang, A.

    Published in Fusion engineering and design (01-02-2006)
    “…Fusion plants will have a large scale and therefore need a high availability and reliability to generate electricity economically. The materials total life…”
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    Journal Article Conference Proceeding
  12. 12

    EU fuel cycle development priorities for ITER by Murdoch, D., Cristescu, I., Day, C., Glugla, M., Laesser, R., Mack, A.

    Published in Fusion engineering and design (01-10-2007)
    “…The paper describes the key elements of the EU fuel cycle development for ITER. The programme is now closely focused on the systems allocated to the EU for…”
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    Journal Article Conference Proceeding
  13. 13

    Protection of the primary circuits and effect on the design of the inner deuterium/tritium fuel cycle of ITER by Glugla, M., Caldwell-Nichols, C., Cristescu, I.R., Doerr, L., Hellriegel, G., Laesser, R., Murdoch, D., Schaefer, P.

    Published in Fusion engineering and design (01-11-2005)
    “…The confinement of tritium within its respective processing systems is clearly one of the most important safety objectives for fusion reactors. Consequently,…”
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    Journal Article Conference Proceeding
  14. 14

    Experience gained during the modification of the Caprice system to Caper by Glugla, M, Lässer, R, Le, T.L, Penzhorn, R.-D, Simon, K.H

    Published in Fusion engineering and design (01-11-2000)
    “…The experimental facility Caprice was designed to comply with the requirements for clean-up of tokamak exhaust gases. In the last 3 years simulated fusion…”
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    Journal Article Conference Proceeding
  15. 15

    Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials by Giancarli, L., Chuyanov, V., Abdou, M., Akiba, M., Hong, B.G., Lässer, R., Pan, C., Strebkov, Y.

    Published in Journal of nuclear materials (01-08-2007)
    “…Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from…”
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    Journal Article
  16. 16

    Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&D activities by Zmitko, M., Poitevin, Y., Boccaccini, L., Salavy, J.-F., Knitter, R., Möslang, A., Magielsen, A.J., Hegeman, J.B.J., Lässer, R.

    Published in Journal of nuclear materials (01-10-2011)
    “…Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium–Lead and the Helium-Cooled…”
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    Journal Article Conference Proceeding
  17. 17

    Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&; amp; D activities by Zmitko, M, Poitevin, Y, Boccaccini, L, Salavy, J-F, Knitter, R, Moslang, A, Magielsen, A J, Hegeman, JBJ, Laesser, R

    Published in Journal of nuclear materials (01-10-2011)
    “…Europe has developed two reference tritium breeder blankets concepts for a DEMO fusion reactor: the Helium-Cooled Lithium-Lead and the Helium-Cooled…”
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    Journal Article
  18. 18

    Gas species, their evolution and segregation through the ITER vacuum systems by Pearce, R.J.H., Antipenkov, A., Bersier, J.L., Boussier, B., Bryan, S., Dremel, M., Hughes, S., Sekachev, I., Worth, L., Baylor, L., Gardner, W., Meitner, S., Wikus, P., Laesser, R., Papastergiou, S.

    Published in Vacuum (31-05-2012)
    “…This paper takes the ITER fueling requirements and current knowledge of gas balance and exhaust from operating tokamaks to predict all likely gas inputs into…”
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    Journal Article
  19. 19

    Modelling irradiation effects in fusion materials by Victoria, M., Dudarev, S., Boutard, J.L., Diegele, E., Lässer, R., Almazouzi, A., Caturla, M.J., Fu, C.C., Källne, J., Malerba, L., Nordlund, K., Perlado, M., Rieth, M., Samaras, M., Schaeublin, R., Singh, B.N., Willaime, F.

    Published in Fusion engineering and design (01-10-2007)
    “…We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future…”
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    Journal Article Conference Proceeding
  20. 20

    Design of the ITER torus prototype cryopump by Hauer, V., Boissin, J.-C., Day, Chr, Haas, H., Mack, A., Murdoch, D., Lässer, R., Wykes, M.

    Published in Fusion engineering and design (01-10-2007)
    “…Forschungszentrum Karlsruhe (FZK) is developing the ITER prototype torus exhaust pumping system, comprising eight identical cryosorption pumps to provide a…”
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    Journal Article Conference Proceeding