Zobrazeno 1 - 10
of 130
pro vyhledávání: '"E. Salpietro"'
Autor:
E Salpietro
Publikováno v:
Superconductor Science and Technology. 19:S84-S89
The overall programme objective of ITER is to demonstrate the scientific and technological feasibility of fusion power production for peaceful purposes. ITER would accomplish this objective by demonstrating controlled burn of deuterium tritium plasma
Autor:
A Vostner, E Salpietro
Publikováno v:
Superconductor Science and Technology. 19:S90-S95
The latest achievements in the development of high performance Nb3Sn strands are reported. In the field of high energy physics (HEP) critical current densities up to 3000 A mm−2 (at 12 T, 4.2 K and 10 µV m−1) can be achieved. Current actions are
Autor:
A. Vostner, E. Salpietro
Publikováno v:
Fusion Engineering and Design. :169-172
Strands relevant for fusion with high critical current densities and moderate hysteresis losses were developed and already produced on industrial scale. Based on these achievements EFDA-CSU Garching has launched a Nb 3 Sn strand development and procu
Autor:
E. Salpietro
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 12:623-628
The paper debates the Toroidal Field Model Coil (TFMC) main design and fabrication choices, as well as, coil fabrication issues with respect to technological and project management aspects. The latest test result and the experience gained during the
Autor:
E. Salpietro
Publikováno v:
Fusion Technology. 34:797-801
(1998). ITER Toroidal Field Model Coil (TFMC) Design and Construction. Fusion Technology: Vol. 34, Proceedings of the Thirteenth Topical Meeting on the Technology of Fusion Energy. Nashville, Tenessee. June 7–11, 1998, pp. 797-801.
Autor:
E. Salpietro
Publikováno v:
Fusion Engineering and Design. 41:401-406
Objective of the Safety and Environmental Assessment of Fusion Power (SEAFP) [1] is to `assess the safety and environmental features of fusion on the basis of the conceptual studies of tokamak power reactors which incorporate safety and environmental
Autor:
E Salpietro, P Komarek
Publikováno v:
Fusion Engineering and Design. 41:213-221
The TF model coil (TFMC) is one of the seven large RD the tests of the W 7-X stellarator prototype coil in an arrangement similar to the ITER TF model coil testing.
Autor:
P. Libeyre, B. Bertrand, E. Salpietro, P. Decool, W. Maurer, G. Zahn, M. Spadoni, P. Komarek, B. Turck, A. Ulbricht
Publikováno v:
IEEE Transactions on Magnetics. 32:2260-2263
The aims of the toroidal field (TF) model coil are to test the manufacturing feasibility of the ITER TF magnet concepts, to assess the reliability of the fully integrated system by dedicated testing and to qualify the quality assurance and the testin
Autor:
presented by E. Salpietro
Publikováno v:
Fusion Technology. 21:1373-1379
Autor:
P. Bauer, P. Bruzzone, F. Cau, K. Weiss, A. Portone, E. Salpietro, M. Vogel, A. Vostner, U. (Balu) Balachandran, Kathleen Amm, David Evans, Eric Gregory, Peter Lee, Mike Osofsky, Sastry Pamidi, Chan Park, Judy Wu, Mike Sumption
Publikováno v:
AIP Conference Proceedings.
Several prototype Cable‐In‐Conduit‐Conductors (CICC) for the superconducting EDIPO (Efda DIPOle) revealed a degradation of their critical current (Ic) increasing with each loading cycle. The strong Lorentz‐forces during operation in combinati