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pro vyhledávání: '"J.G. van der Laan"'
Akademický článek
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Autor:
L. Worth, Stefan Wikman, J.G. van der Laan, V.R. Barabash, Yann Carin, S. M. Gonzalez de Vicente, T. Hirai, Walter H. Fietz, Mark R. Gilbert, Shinya Konishi
Publikováno v:
Fusion Engineering and Design. 125:245-249
The ITER project aims to demonstrate scientific and technological feasibility of controlled energy production through thermonuclear fusion and the IAEA plays a pro-active role in catalyzing innovation and enhancing the worldwide commitment to fusion.
Autor:
Dieter Leichtle, M. Harb, Jin Hun Park, J.P. Martins, J.G. van der Laan, J. Bergman, Byoung-Yoon Kim
Publikováno v:
Fusion Engineering and Design. 168:112402
In ITER [1] , it is foreseen to have two Test Blanket Systems (TBS) installed in two dedicated Equatorial Ports (EP) for the purpose of testing and validating different concepts of tritium breeding blankets [2] . Each TBS consists of a Test Blanket M
Autor:
W. Shu, A. Dammann, J.G. van der Laan, R. Pascal, J.J. Cordier, David Campbell, J.M. Fourneron, S. Chiocchio, Mario Merola, Joëlle Elbez-Uzan, M. Iseli, A. Siarras, Iva Schneiderova, B. Levesy, Scott Willms, Byoung-Yoon Kim, D. Lazarov, M. Gasparotto, W. Ring, J.-C. Nevière, V.R. Barabash, Michael Loughlin, J.P. Friconneau, C.-Y. Jung, Joseph Snipes, G. Dell’Orco, L. Giancarli
Publikováno v:
Fusion Engineering and Design
The paper describes the organization of the Test Blanket Module (TBM) program, its overall objective and schedule and the status of the technical activities within the ITER Organization-Central Team (IO-CT). The latter include the design integration
Autor:
M. Iseli, D. Torcy, Yoshinori Kawamura, J.G. van der Laan, H. Zhang, V. Chaudhari, D.W. Lee, C.S. Pitcher, D. Ugolini, D. Canas, P. Petit
Publikováno v:
Fusion Engineering and Design. :222-226
Test Blanket Systems (TBS) will be operated in ITER in order to prepare the next steps towards fusion power generation. After the initial operation in H/He plasmas, the introduction of D and T in ITER will mark the transition to nuclear operation. Th
Autor:
R. Pascal, J.G. van der Laan, Bradut-Eugen Ghidersa, B. Cuquel, T. Jourdan, M. Iseli, J.-C. Nevière, L. Giancarli, W. Ring, David Demange
Publikováno v:
Fusion Engineering and Design. :1889-1892
This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for
Autor:
D. Blagoeva, J. Opschoor, C. Sârbu, Gerald Pintsuk, M. Jong, J.G. van der Laan, P. ten Pierick, H. Nolles, T. Bakker
Publikováno v:
Journal of Nuclear Materials. 442:S198-S203
This paper is an overview of the very first results obtained on pure tungsten (W) and oxide dispersed strengthened (ODS) W alloys produced by the Metal Injection Molding (MIM) technique for fusion applications. An extensive mechanical and physical ch
Akademický článek
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This article reviews the research on ceramic tritium breeding materials and the development of these materials, which aims at providing the tritium required for the deuterium–tritium fuel cycle in magnetic fusion reactors. In particular, the perfor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14e66e147a283456c78cff324cc205e6
https://doi.org/10.1016/b978-0-12-803581-8.00733-5
https://doi.org/10.1016/b978-0-12-803581-8.00733-5
Publikováno v:
Journal of Nuclear Materials. 417:104-107
The irradiation-induced stress relaxation behavior of Eurofer97 at 300 °C up to 3.4 dpa and under pre-stress loads typical for the ITER applications is investigated. The bolt specimens are pre-loaded from 30% to 90% of the yield strength. To verify