Results 1 to 10 of about 451,392 (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.
G F Matthews, A G Meigs, S Silburn
exaly   +10 more sources

Sawtooth pacing with on-axis ICRH modulation in JET-ILW [PDF]

Nuclear Fusion, 2017
A novel technique for sawteeth control in tokamak plasmas using ion-cyclotron resonance heating (ICRH) has been developed in the JET-ILW tokamak [2].
Andrea Murari, Dirk Van Eester, Pierre Dumortier   +2 more
exaly   +6 more sources

Comparing pedestal structure in JET-ILW H-mode plasmas with a model for stiff ETG turbulent heat transport. [PDF]

Philos Trans A Math Phys Eng Sci, 2023
A predictive model for the electron temperature profile of the H-mode pedestal is described, and its results are compared with the pedestal structure of JET-ILW plasmas.
Field AR, Chapman-Oplopoiou B, Connor JW, Frassinetti L, Hatch DR, Roach CM, Saarelma S, JET contributors.   +7 more
europepmc   +2 more sources

Qualitative effects of resistivity in JET-ILW Europed pedestal predictions

Nuclear Fusion
The effect of resistive MHD in the pedestal predictions for JET-ILW has been investigated, using the Europed workflow (Saarelma et al 2018 Plasma Phys. Control. Fusion 60 014042) with the resistive MHD stability code CASTOR (Kerner et al 1998 J.
A. Lafay-Labrosse, H. Nyström, L. Frassinetti, S. Saarelma, JET Contributors, The EUROfusion Tokamak Exploitation Team   +5 more
doaj   +3 more sources

Pedestal structure, stability and scalings in JET-ILW: the EUROfusion JET-ILW pedestal database [PDF]

Nuclear Fusion, 2020
The EUROfusion JET-ILW pedestal database is described, with emphasis on three main issues. First, the technical aspects are introduced, including a description of the data selection, the datasets, the diagnostics used, the experimental and theoretical ...
L. Frassinetti, S. Saarelma, G. Verdoolaege, M. Groth, J. Hillesheim, P. Bílková, P. Boehm, M. Dunne, R. Fridström, E. Giovannozzi, F. Imbeaux, B. Labit, E. D. L. Luna, C. Maggi, M. Owsiak, R. Scannell   +15 more
semanticscholar   +8 more sources

Composition of electron temperature gradient driven plasma turbulence in JET-ILW tokamak plasmas

Physical Review Research
This letter reports on new fundamental insights into small scale plasma turbulence that is responsible for confinement degradation on the JET tokamak. We compare the structure of electron temperature gradient (ETG) driven turbulence in the edge region of
B. Chapman-Oplopoiou, J. Walker, D. R. Hatch, T. Görler, JET contributors   +4 more
doaj   +2 more sources

Operational challenges for long pulses on JET-ILW

Plasma Physics and Controlled Fusion
The typical pulse on the JET tokamak is ∼10 s during the main phase of the discharge, however long discharge operation (>30 s) is possible with sufficient preparation and care.
D. King, E. Lerche, X. Litaudon, S. Brezinsek, E. Joffrin, F. Auriemma, M. Beldishevski, N. Balshaw, M. Baruzzo, A. Boboc, P. Card, I. Carvalho, P. Carvalho, I. Coffey, P. Mccullen, S. Dalley, E. Delabie, P. Dumortier, R. Felton, S. Gerasimov, Z. Ghani, A. Goodyear, N. Hawkes, R. Henriques, S. Hotchin, P. Jacquet, I. Jepu, D. Keeling, D. Kinna, D. Kos, E. Litherland-Smith, R. Lobel, P. Lomas, C. Lowry, J. Mailloux, M. Maslov, D. Matveev, A. Meigs, S. Menmuir, J. Mitchell, I. Monakhov, C. Noble, M. Poradzinski, F. Rimini, S. Silburn, E. Solano, H. Sun, C. Srinivasan, B. Thomas, D. Valcarcel, R. Villari, J. Waterhouse, A. West, I. Young   +53 more
semanticscholar   +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

Tritium removal from JET-ILW after T and D–T experimental campaigns

Nuclear Fusion, 2023
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium removal from wall
D. Matveev, D. Douai, T. Wauters, A. Widdowson, I. Jepu, M. Maslov, S. Brezinsek, T. Dittmar, I. Monakhov, P. Jacquet, P. Dumortier, H. Sheikh, R. Felton, C. Lowry, D. Ciric, J. Banks, R. Buckingham, H. Weisen, L. Laguardia, G. Gervasini, E. de la Cal, E. Delabie, Z. Ghani, J. Gaspar, J. Romazanov, M. Groth, H. Kumpulainen, J. Karhunen, S. Knipe, S. Aleiferis, T. Loarer, A. Meigs, C. Noble, G. Papadopoulos, E. Pawelec, S. Romanelli, S. Silburn, E. Joffrin, E. Tsitrone, F. Rimini, C.F. Maggi, JET Contributors   +41 more
doaj   +2 more sources

Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy

Nuclear Fusion, 2023
This work was carried out to identify sources of errors, uncertainties and discrepancies in studies of fuel retention in wall components from the JET tokamak using methods based on thermal desorption.
Y. Zayachuk, I. Jepu, M. Zlobinski, C. Porosnicu, N. Catarino, E. Pajuste, P. Petersson, L. Dittrich, J.P. Coad, E. Grigore, C. Postolache, E. Alves, G. Kizane, M. Rubel, A. Widdowson   +14 more
doaj   +2 more sources