Results 11 to 20 of about 1,720 (162)

The radiated power limit in impurity seeded JET-ILW plasmas

Nuclear Materials and Energy, 2022
The total radiated fraction is examined in high density H-mode plasmas (Greenwald fraction of about 85 %) in JET by the variation of the auxiliary heating power of Pheat = 14 MW-29 MW.
Alexander Huber, Christian Linsmeier
exaly   +11 more sources

Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0

Nuclear Materials and Energy, 2019
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium (Be) erosion and deposition is simulated and compared to experimental results from ...
Juri Romazanov, Sebastijan Brezinsek, Dmitriy Borodin   +2 more
exaly   +15 more sources

Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall [PDF]

Nuclear Fusion, 2023
Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and ...
Y. Torikai, G. Kikuchi, A. Owada, S. Masuzaki, T. Otsuka, N. Ashikawa, M. Yajima, M. Tokitani, Y. Oya, S.E. Lee, Y. Hatano, N. Asakura, T. Hayashi, M. Oyaidzu, J. Likonen, A. Widdowson, M. Rubel, JET Contributors   +17 more
doaj   +2 more sources

Tritium retention characteristics in dust particles in JET with ITER-like wall [PDF]

Nuclear Materials and Energy, 2018
A tritium imaging plate technique (TIPT) in combination with an electron-probe microscopic analysis (EPMA) were applied to examine tritium (T) retention characteristics in individual dust particles collected in the Joint European Torus with the ITER-like
T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Hatano, Y. Asakura, Tatsuya Suzuki, Takumi Suzuki, K. Isobe, T. Hayashi, M. Tokitani, Y. Oya, D. Hamaguchi, H. Kurotaki, R. Sakamoto, Hiroyasu Tanigawa, M. Nakamichi, A. Widdowson, M. Rubel   +17 more
doaj   +3 more sources

Investigation of deuterium trapping and release in the JET divertor during the third ILW campaign using TDS

Nuclear Materials and Energy, 2019
Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed in 2015–2016 has been analysed using Thermal Desorption Spectrometry (TDS).
Kalle Heinola, Aleksandra Baron-Wiechec, Norberto Catarino   +2 more
exaly   +3 more sources

First mirror test in JET for ITER: Complete overview after three ILW campaigns

Nuclear Materials and Energy, 2019
The First Mirror Test for ITER has been carried out in JET with mirrors exposed during: (i) the third ILW campaign (ILW-3, 2015–2016, 23.33 h plasma) and (ii) all three campaigns, i.e. ILW-1 to ILW-3: 2011–2016, 63,52 h in total.
Sunwoo Moon, Elzbieta Fortuna-Zalesna, Anna Widdowson   +2 more
exaly   +3 more sources

Impact of ICRF on the scrape-off layer and on plasma wall interactions: From present experiments to fusion reactor [PDF]

Nuclear Materials and Energy, 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.
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   +30 more
doaj   +3 more sources

ICRH physics and technology achievements in JET-ILW [PDF]

EPJ Web of Conferences, 2017
ICRH was extensively used in the 2015-16 JET-ILW (ITER like wall) experimental campaign; bulk heating together with high-Z impurity chase-out from plasma centre importantly contributed to the good DD fusion performance obtained recently in JET.
Jacquet P., Van Eester D., Lerche E., Bobkov V., Blackman T., Colas L., Challis C., Czarnecka A., Dumortier P., Frigione D., Durodié F., Garzotti L., Goniche M., Graves J., Kazakov Y., Kirov K., Klepper C. C., Krawczyk N., Krivska A., Mantsinen M., Monakhov I., Nunes I., Ongena J., Reinke M., Rimini F., Zhang W.   +25 more
doaj   +5 more sources

Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

Nuclear Materials and Energy, 2017
Post-mortem analyses of individual components provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. Ion Beam techniques are
Norberto Catarino, Np Barradas, Victoria Corregidor   +2 more
exaly   +3 more sources

Modelling of tungsten erosion and deposition in the divertor of JET-ILW in comparison to experimental findings

Nuclear Materials and Energy, 2019
The erosion, transport and deposition of tungsten in the outer divertor of JET-ILW has been studied for an H-Mode discharge with low frequency ELMs.
Sebastijan Brezinsek, Alexander Huber, Gennady Sergienko   +2 more
exaly   +3 more sources