Zobrazeno 1 - 10
of 6 407
pro vyhledávání: '"A. Kallenbach"'
Autor:
M. Bernert, S. Wiesen, O. Février, A. Kallenbach, J.T.W. Koenders, B. Sieglin, U. Stroth, T.O.S.J. Bosman, D. Brida, M. Cavedon, P. David, M.G. Dunne, S. Henderson, B. Kool, T. Lunt, R.M. McDermott, O. Pan, A. Perek, H. Reimerdes, U. Sheikh, C. Theiler, M. van Berkel, T. Wijkamp, M. Wischmeier
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101376- (2023)
Future fusion reactors require a safe, steady-state divertor operation. With deep divertor detachment, which is typically induced by impurity seeding, the radiation concentrates in a small region at the X-point or on closed flux surfaces above the X-
Externí odkaz:
https://doaj.org/article/a19cf8e87ba64819b1c5210e6d695632
Autor:
E. Viezzer, M.E. Austin, M. Bernert, K.H. Burrell, P. Cano-Megias, X. Chen, D.J. Cruz-Zabala, S. Coda, M. Faitsch, O. Février, L. Gil, C. Giroud, T. Happel, G.F. Harrer, A.E. Hubbard, J.W. Hughes, A. Kallenbach, B. Labit, A. Merle, H. Meyer, C. Paz-Soldan, P. Oyola, O. Sauter, M. Siccinio, D. Silvagni, E.R. Solano
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101308- (2023)
One of our grand challenges towards fusion energy is the achievement of a high-performance plasma core coupled to a boundary solution. The high confinement mode (H-mode) provides such a high-performance fusion core due to the build-up of an edge tran
Externí odkaz:
https://doaj.org/article/8a0099a6cbcb42be8cc7520cf695211e
Autor:
S.S. Henderson, M. Bernert, C. Giroud, D. Brida, M. Cavedon, P. David, R. Dux, J.R. Harrison, A. Huber, A. Kallenbach, J. Karhunen, B. Lomanowski, G. Matthews, A. Meigs, R.A. Pitts, F. Reimold, M.L. Reinke, S. Silburn, N. Vianello, S. Wiesen, M. Wischmeier
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss , Pp 101000- (2021)
While current tokamak experiments are beginning to use real-time feedback control systems to manage the plasma exhaust, future tokamaks still require validation of theoretical models used to predict the threshold impurity concentration required to su
Externí odkaz:
https://doaj.org/article/16a3d286973141d28c8b2096805ee2b3
Autor:
A. Bortolon, V. Rohde, R. Maingi, E. Wolfrum, R. Dux, A. Herrmann, R. Lunsford, R.M. McDermott, A. Nagy, A. Kallenbach, D.K. Mansfield, R. Nazikian, R. Neu
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 384-389 (2019)
In ASDEX Upgrade with full-tungsten wall, boronization is an important tool to control tungsten sources and allow reliable operation at low collisionality. The duration of the beneficial effects is limited by the erosion of the boron layer, in partic
Externí odkaz:
https://doaj.org/article/384ae7c0715d486895843517844ffbbd
Autor:
S.S. Henderson, M. Bernert, S. Brezinsek, M. Carr, M. Cavedon, R. Dux, D.S. Gahle, J. Harrison, A. Kallenbach, B. Lipschultz, B. Lomanowski, A. Meigs, M. O’Mullane, F. Reimold, M.L. Reinke, S. Wiesen
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 147-152 (2019)
The impurity concentration in the tokamak divertor plasma is a necessary input for predictive scaling of divertor detachment, however direct measurements from existing tokamaks in different divertor plasma conditions are limited. To address this, we
Externí odkaz:
https://doaj.org/article/9599a60f24884a1ca6eb7543ec2f1515
Autor:
V. Bobkov, D. Aguiam, R. Bilato, S. Brezinsek, L. Colas, A. Czarnecka, P. Dumortier, R. Dux, H. Faugel, H. Fünfgelder, Ph. Jacquet, A. Kallenbach, A. Krivska, C.C. Klepper, E. Lerche, Y. Lin, D. Milanesio, R. Maggiora, I. Monakhov, R. Neu, J.-M. Noterdaeme, R. Ochoukov, Th. Pütterich, M. Reinke, W. Tierens, A. Tuccilo, O. Tudisco, D. Van Eester, J. Wright, S. Wukitch, W. Zhang
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 131-140 (2019)
Recent achievements in studies of the effects of ICRF (Ion Cyclotron Range of Frequencies) power on the SOL (Scrape-Off Layer) and PWI (Plasma Wall Interactions) in ASDEX Upgrade (AUG), Alcator C-Mod, and JET-ILW are reviewed. Capabilities to diagnos
Externí odkaz:
https://doaj.org/article/1ada1c533aae4148acb40564d1f36fda
Autor:
A. Kallenbach, M. Bernert, R. Dux, T. Eich, S.S. Henderson, T. Pütterich, F. Reimold, V. Rohde, H.J. Sun
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss , Pp 166-174 (2019)
Analytical expressions for the divertor radiation around the onset of detachment based on the divertor neutral pressure and the upstream separatrix density are tested against measurements on strongly nitrogen seeded high confinement mode (H-mode) dis
Externí odkaz:
https://doaj.org/article/3ba722d9e9a544eea921cf3af74523e7
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 28-35 (2017)
The main elements defining the tungsten content of an ITER plasma, i.e. the gross erosion, the prompt redeposition and the transport in the H-mode edge transport barrier are reviewed and it is investigated, whether the low tungsten concentration limi
Externí odkaz:
https://doaj.org/article/f7bb748b1ae741ccabc3141d3fb06473
Autor:
V. Bobkov, D. Aguiam, M. Baruzzo, D. Borodin, I. Borodkina, S. Brezinsek, I. Coffey, L. Colas, A. Czarnecka, E. Delabie, P. Dumortier, F. Durodie, R. Dux, H. Faugel, H. Fünfgelder, C. Giroud, M. Goniche, J. Hobirk, A. Herrmann, J. Jacquot, Ph. Jacquet, A. Kallenbach, A. Krivska, C.C. Klepper, E. Lerche, S. Menmuir, D. Milanesio, R. Maggiora, I. Monakhov, F. Nave, R. Neu, J.-M. Noterdaeme, R. Ochoukov, Th. Pütterich, M. Reinke, A. Tuccilo, O. Tudisco, D. Van Eester, Y. Wang, Q. Yang, W. Zhang
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 1194-1198 (2017)
Use of new 3-strap ICRF antennas with all-tungsten (W) limiters in ASDEX Upgrade results in a reduction of the W sources at the antenna limiters and of the W content in the confined plasma by at least a factor of 2 compared to the W-limiter 2-strap a
Externí odkaz:
https://doaj.org/article/519f272013fc4ce5b5a3c0bc6252d940
Autor:
A. Herrmann, I. Zammuto, M. Balden, H. Greuner, N. Jaksic, A. Kallenbach, M. Li, R. Neu, V. Rohde
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 205-209 (2017)
In 2013 a redesigned solid tungsten divertor, Div-III, was installed in ASDEX Upgrade. In two experimental campaigns more than 2700 plasma discharges with up to 10s duration, 110MJ plasma heating, and reaching a Psep/R of 10MW/m were conducted. Div-I
Externí odkaz:
https://doaj.org/article/ff84658a7ac441e68746aab77782360a