Zobrazeno 1 - 10
of 35
pro vyhledávání: '"R. Mattas"'
Autor:
M.A Abdou, The APEX TEAM, A Ying, N Morley, K Gulec, S Smolentsev, M Kotschenreuther, S Malang, S Zinkle, T Rognlien, P Fogarty, B Nelson, R Nygren, K McCarthy, M.Z Youssef, N Ghoniem, D Sze, C Wong, M Sawan, H Khater, R Woolley, R Mattas, R Moir, S Sharafat, J Brooks, A Hassanein, D Petti, M Tillack, M Ulrickson, T Uchimoto
Publikováno v:
Fusion Engineering and Design. 54:181-247
This study, called APEX, is exploring novel concepts for fusion chamber technology that can substantially improve the attractiveness of fusion energy systems. The emphasis of the study is on fundamental understanding and advancing the underlying engi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::351859dc4f1cc295b6072191243a35ed
https://doi.org/10.1016/s0920-3796(00)00433-6
https://doi.org/10.1016/s0920-3796(00)00433-6
Publikováno v:
Fusion Technology. 26:300-315
Changes in ITER requirements and conditions in the Engineering Design Activity (EDA), and the desire to obtain greater operating flexibility, led to a reconsideration of the ITER Conceptual Design Activity (CDA) blanket designs. The current strategy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89126800c2f255e1c60c8d209584c5d8
https://doi.org/10.13182/fst94-a40178
https://doi.org/10.13182/fst94-a40178
Autor:
R MATTAS
Publikováno v:
Journal of Nuclear Materials. :139-145
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8e56797aed995f83e72e4d5b6d683e8e
https://doi.org/10.1016/0022-3115(92)90741-3
https://doi.org/10.1016/0022-3115(92)90741-3
Autor:
Y. Strebkov, E. Zolti, R. Mattas, P. Lorenzetto, K. Ioki, R. Raffray, T. Kuroda, K. Mohri, Michael C. Billone, Y. Gohar, A. Cardella, W. Dänner, S. Majumdar, Hideyuki Takatsu, D. Lousteau
Publikováno v:
Proceedings of 16th International Symposium on Fusion Engineering.
A breeding blanket design has been developed for ITER to provide the necessary tritium fuel to achieve the technical objectives of the Enhanced Performance Phase. It uses a ceramic breeder and water coolant for compatibility with the ITER machine des
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::40ecfcfac794bc3ba777bb85eea1fb18
https://doi.org/10.1109/fusion.1995.534253
https://doi.org/10.1109/fusion.1995.534253
Autor:
R. Mattas, B. Lipschultz, M.A. Ulrickson, J.N. Brooks, S. Allen, R. McGrath, J. Davis, D. Hill
The Plasma Facing Components (PFC) Facilities Review Panel was chartered by the US Department of Energy, Office of Fusion Energy, ITER (International Thermonuclear Experimental Reactor) and Technology Division, to outline the program plan and identif
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::67f3e5076a09cdd46a17aebe1c0ee6a2
https://doi.org/10.2172/10194895
https://doi.org/10.2172/10194895
Autor:
R. Mattas, D. E. Post
Publikováno v:
Fusion Technology. 8:779-790
Poloidal divertors and pumped limiters are the leading candidates for impurity and particle control systems for ignited tokamaks. Such systems must be able to provide heat removal and He pumping while satisfying the requirements for minimum plasma co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::77462ccb21ecba37f699adb2d6e89d67
https://doi.org/10.13182/fst85-a40130
https://doi.org/10.13182/fst85-a40130
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Akademický článek
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