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Autor:
R. Lässer, Chr. Day, St. Hanke, H. Strobel, M. Dremel, Volker Hauer, X. Luo, F. Fellin, Chr. Mayaux, R. Simon, M. Scannapiego, A. Masiello, R. Pearce, St. Papastergiou, H. Haas
Publikováno v:
Fusion Engineering and Design. 86:2188-2191
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 manufacturing. Although being completely different in size, the pumps share the same concept of cr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b8e427d495bc840b8840a5147f4af865
https://doi.org/10.1016/j.fusengdes.2010.11.023
https://doi.org/10.1016/j.fusengdes.2010.11.023
Publikováno v:
Fusion Science and Technology. 60:1159-1162
Extraction of tritium from liquid lead lithium eutectic alloy is a key topic for the feasibility of any PbLi based tritium breeding blanket (BB). Particularly in DEMO, high tritium extraction efficiency will be required in order to keep low the triti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f6d4f05bc6c3b684bab94d4906f1606
https://doi.org/10.13182/fst11-a12621
https://doi.org/10.13182/fst11-a12621
Autor:
E. Magnani, M. Zmitko, F. Gabriel, Yves Poitevin, Heiko Neuberger, L. Guerrini, Italo Ricapito, J.-F. Salavy, R. Lässer, Lorenzo Virgilio Boccaccini, E. Diegele
Publikováno v:
Fusion Engineering and Design. 85:2340-2347
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 Lithium–Lead which uses the liquid Pb–15.7Li as both breeder and neutron multiplier, (i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d1f05f45457bc064bd6ea97c2299eafd
https://doi.org/10.1016/j.fusengdes.2010.09.027
https://doi.org/10.1016/j.fusengdes.2010.09.027
Autor:
E. Diegele, Y. Stephan, Yves Poitevin, E. Rigal, L. Giancarli, Giacomo Aiello, Lorenzo Virgilio Boccaccini, Philippe Aubert, J.-F. Salavy, M. Daichendt, R. Lässer, G. Rampal, Heiko Neuberger, G. De Dinechin
Publikováno v:
Journal of Nuclear Materials. :922-926
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 be tested in ITER in the framework of the Test Blanket Module projects. They both use a 9%Cr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::256e4d2558b20b6e30e64603cb306fb6
https://doi.org/10.1016/j.jnucmat.2008.12.239
https://doi.org/10.1016/j.jnucmat.2008.12.239
Autor:
L.A. Sedano, F. Gabriel, M. Gasparotto, D.K. Murdoch, J.-F. Salavy, Ion Cristescu, M. Zmitko, Lorenzo Virgilio Boccaccini, Anton Möslang, Italo Ricapito, A.J. Magielsen, R. Pearce, R. Lässer, S. Knipe, G. Piazza, N. Bekris Bekris, A. Antipenkov, G. Dell’Orco, C. J. Caldwell-Nichols, Y. Poitevin, A. Perevezentsev, Ch. Grisolia, Ch. Day, O. Gastaldi, Manfred Glugla
Publikováno v:
Fusion Science and Technology. 54:39-44
Tritium as one of the two fuel components for fusion power plays a special role in any fusion device. Due to its volatile character, radioactivity and easy incorporation as HTO it needs to be contr...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a92f078ac5d411b41a38d9575555fba4
https://doi.org/10.13182/fst08-a1761
https://doi.org/10.13182/fst08-a1761
Publikováno v:
Fusion Engineering and Design. 82:2113-2119
Forschungszentrum Karlsruhe (FZK) is developing the ITER prototype torus exhaust pumping system, comprising eight identical cryosorption pumps to provide a high pumping speed and capacity, and fast regeneration. The prototype pump features an integra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0327aaddd52fe8599a9bc60b90687605
https://doi.org/10.1016/j.fusengdes.2007.07.039
https://doi.org/10.1016/j.fusengdes.2007.07.039
Autor:
M. Victoria, J.-L. Boutard, R. Lässer, A. Almazouzi, Michael Rieth, Kai Nordlund, Jan Källne, E. Diegele, Bachu Narain Singh, M. Samaras, Francois Willaime, Lorenzo Malerba, Sergei L. Dudarev, Maria J. Caturla, Manuel Perlado, R. Schaeublin, Chu-Chun Fu
Publikováno v:
Fusion Engineering and Design. 82:2413-2421
We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future development. Large-scale density functional theory (DFT) calculations reveal the structure of the po
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::552dc8181bba5fb2de046ff27df6d3a6
https://doi.org/10.1016/j.fusengdes.2007.05.079
https://doi.org/10.1016/j.fusengdes.2007.05.079
Autor:
E. Diegele, J.-L. Boutard, B. van der Schaaf, Reinhard Pippan, Nadine Baluc, Sergei L. Dudarev, M. Gasparotto, R. Lässer, Anton Möslang, B. Riccardi
Publikováno v:
Fusion Engineering and Design. 82:511-520
DEMO in-vessel materials will be exposed to high neutron flux and high fluence, creating displacement cascades and transmutation products. This results in changes of the microstructure leading to degradation of mechanical and physical properties. The
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dbdb56cdc3d99bebf253c7c452795c3f
https://doi.org/10.1016/j.fusengdes.2007.06.031
https://doi.org/10.1016/j.fusengdes.2007.06.031
Autor:
J. Sundström, Yves Poitevin, Lorenzo Virgilio Boccaccini, R. Lässer, G. Dell'Orco, J.-F. Salavy, E. Diegele, M. Zmitko
Publikováno v:
Fusion Engineering and Design. 82:2164-2170
The testing of breeding blanket concepts in ITER is recognized as an essential milestone in the development of a future reactor ensuring tritium self-sufficiency, extraction of high grade heat and electricity production. Europe is currently developin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ec3c0076f63282d155a49f85dbb6aa07
https://doi.org/10.1016/j.fusengdes.2007.07.023
https://doi.org/10.1016/j.fusengdes.2007.07.023