Overview of the JET results with the ITER-like wall

JET-EFDA Contributors

doi:10.1088/0029-5515/53/10/104002

Overview of the JET results with the ITER-like wall

JET-EFDA Contributors

Laboratory for Plasma Physics

Associazione EURATOM-ENEA sulla Fusione
Culham Centre for Fusion Energy
EFDA-JET
Imperial College London
Ioffe Physical-Technical Institute of the Russian Academy of Sciences
Institute of Plasma Physics, Academy of Sciences of the Czech Republic
Commissariat à l'Énergie Atomique (CEA)
Queens University
Helsinki University of Technology
Aalto University
University of Tartu
Kurchatov Institute
Troitsk Insitute of Innovating and Thermonuclear Research (TRINITI)
Consorzio Rfx
Laboratorio Nacional de Fusión
Instituto Superior Técnico
Chalmers University of Technology
Uppsala University
Association EURATOM-MEdC
National Institute for Laser, Plasma and Radiation Physics
Max-Planck-Institut für Plasmaphysik
Università degli Studi di Catania
University of Ghent
Dublin City University
Fusion for Energy
University of Latvia
Nuclear Fuel Plant
Lehigh University
Forschungszentrum Jülich GmbH
Oak Ridge National Laboratory
Karlsruhe Institute of Technology
KTH Royal Institute of Technology
University of Texas at Austin
Institute of Plasma Physics and Laser Microfusion
University of Helsinki
Ecole Polytechnique Federale de Lausanne
Université de Nice Sophia Antipolis
Lviv Polytechnic National University
University of Milano-Bicocca
Belgian Nuclear Research Centre
The National Institute for Optoelectronics
Princeton Plasma Physics Laboratory
General Atomics
University of Cagliari
University of California
Colorado School of Mines
Japan Atomic Energy Agency
National Nuclear Center of the Republic of Kazakhstan
Wigner Research Centre for Physics
Institute for Plasma Research
Universidad Politécnica de Madrid
FOM Institute DIFFER
Russian Academy of Science
University of California, San Diego
Bulgarian Academy of Sciences
Budapest University of Technology and Economics
European Commission
NCSR 'Demokritos'
Institute of Plasma Physics Chinese Academy of Sciences
Universitat Innsbruck
University of Maryland, College Park
Seoul National University
ITER
Daegu University
Lithuanian Energy Institute
Lund University
Vienna University of Technology
International Atomic Energy Agency, Vienna
National Technical University of Athens
University of Stuttgart
Massachusetts Institute of Technology
Jozef Stefan Institute
Moscow State University
Technical University of Denmark
Universidad Carlos III de Madrid
University Mlynska
EFDA CSU-Garching
The 'Horia Hulubei' National Institute for Physics and Nuclear Engineering
University of Strathclyde
Politecnico di Torino
University of Warwick
Tampere University
University of York

Research output: Contribution to journal › Article › peer-review

109 Citations (Scopus)

Abstract

Following the completion in May 2011 of the shutdown for the installation of the beryllium wall and the tungsten divertor, the first set of JET Campaigns have addressed the investigation of the retention properties and the development of operational scenarios with the new plasma facing materials. The large reduction of the carbon content (more than a factor ten) led to a much lower Z_eff (1.2-1.4) during L- and H-mode plasmas, and radiation during the burn-through phase of the plasma initiation with the consequence that breakdown failures are almost absent. Gas balance experiments have shown that fuel retention rates with the new wall are in line with the ITER needs. The re-establishment of high-confinement scenarios compatible with the new wall has required an optimization of the control of metallic impurity sources and heat loads. Stable type I ELMy H-mode regimes with H_98,y2 close to 1 and β_N∼1.6 have been achieved in high triangularity plasmas. The ELM frequency is the main factor for the control of the metallic impurities accumulation. Pedestal temperatures tend to be lower with the new wall, leading to somewhat reduced confinement, but nitrogen seeding restores high pedestal temperatures and high confinement. Compared with the carbon wall, major disruptions with the new wall show a lower radiated power and a slower current quench. The higher heat loads on plasma-facing components due to lower radiation, made the routine use of massive gas injection for disruption mitigation essential.

Original language	English
Article number	104002
Journal	Nuclear Fusion
Volume	53
Issue number	10
DOIs	https://doi.org/10.1088/0029-5515/53/10/104002
Publication status	Published - 10 Sept 2013

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10.1088/0029-5515/53/10/104002

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@article{bc4d4d24ce794e92b78b50703578aaae,

title = "Overview of the JET results with the ITER-like wall",

abstract = "Following the completion in May 2011 of the shutdown for the installation of the beryllium wall and the tungsten divertor, the first set of JET Campaigns have addressed the investigation of the retention properties and the development of operational scenarios with the new plasma facing materials. The large reduction of the carbon content (more than a factor ten) led to a much lower Zeff (1.2-1.4) during L- and H-mode plasmas, and radiation during the burn-through phase of the plasma initiation with the consequence that breakdown failures are almost absent. Gas balance experiments have shown that fuel retention rates with the new wall are in line with the ITER needs. The re-establishment of high-confinement scenarios compatible with the new wall has required an optimization of the control of metallic impurity sources and heat loads. Stable type I ELMy H-mode regimes with H98,y2 close to 1 and βN∼1.6 have been achieved in high triangularity plasmas. The ELM frequency is the main factor for the control of the metallic impurities accumulation. Pedestal temperatures tend to be lower with the new wall, leading to somewhat reduced confinement, but nitrogen seeding restores high pedestal temperatures and high confinement. Compared with the carbon wall, major disruptions with the new wall show a lower radiated power and a slower current quench. The higher heat loads on plasma-facing components due to lower radiation, made the routine use of massive gas injection for disruption mitigation essential.",

author = "F. Romanelli and I. Abel and V. Afanesyev and M. Aftanas and G. Agarici and Aggarwal, \{K. M.\} and L. Aho-Mantila and E. Ahonen and M. Aints and M. Airila and R. Akers and Th Alarcon and R. Albanese and A. Alexeev and A. Alfier and P. Allan and S. Almaviva and A. Alonso and B. Alper and H. Altmann and D. Alves and G. Ambrosino and V. Amosov and F. Andersson and \{Andersson Sund{\'e}n\}, E. and V. Andreev and Y. Andrew and M. Angelone and M. Anghel and A. Anghel and C. Angioni and G. Apruzzese and N. Arcis and P. Arena and A. Argouarch and M. Ariola and K. Crombe and K. Cromb{\'e} and P. Dumortier and F. Durodi{\'e} and S. Jachmich and E. Lerche and F. Louche and A. Lyssoivan and A. Messiaen and J. Ongena and \{Van Eester\}, D. and G. Verdoolaege and M. Vervier and T. Wauters and \{JET-EFDA Contributors\}",

year = "2013",

month = sep,

day = "10",

doi = "10.1088/0029-5515/53/10/104002",

language = "English",

volume = "53",

journal = "Nuclear Fusion",

issn = "0029-5515",

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T1 - Overview of the JET results with the ITER-like wall

AU - Romanelli, F.

AU - Abel, I.

AU - Afanesyev, V.

AU - Aftanas, M.

AU - Agarici, G.

AU - Aggarwal, K. M.

AU - Aho-Mantila, L.

AU - Ahonen, E.

AU - Aints, M.

AU - Airila, M.

AU - Akers, R.

AU - Alarcon, Th

AU - Albanese, R.

AU - Alexeev, A.

AU - Alfier, A.

AU - Allan, P.

AU - Almaviva, S.

AU - Alonso, A.

AU - Alper, B.

AU - Altmann, H.

AU - Alves, D.

AU - Ambrosino, G.

AU - Amosov, V.

AU - Andersson, F.

AU - Andersson Sundén, E.

AU - Andreev, V.

AU - Andrew, Y.

AU - Angelone, M.

AU - Anghel, M.

AU - Anghel, A.

AU - Angioni, C.

AU - Apruzzese, G.

AU - Arcis, N.

AU - Arena, P.

AU - Argouarch, A.

AU - Ariola, M.

AU - Crombe, K.

AU - Crombé, K.

AU - Dumortier, P.

AU - Durodié, F.

AU - Jachmich, S.

AU - Lerche, E.

AU - Louche, F.

AU - Lyssoivan, A.

AU - Messiaen, A.

AU - Ongena, J.

AU - Van Eester, D.

AU - Verdoolaege, G.

AU - Vervier, M.

AU - Wauters, T.

AU - JET-EFDA Contributors

PY - 2013/9/10

Y1 - 2013/9/10

N2 - Following the completion in May 2011 of the shutdown for the installation of the beryllium wall and the tungsten divertor, the first set of JET Campaigns have addressed the investigation of the retention properties and the development of operational scenarios with the new plasma facing materials. The large reduction of the carbon content (more than a factor ten) led to a much lower Zeff (1.2-1.4) during L- and H-mode plasmas, and radiation during the burn-through phase of the plasma initiation with the consequence that breakdown failures are almost absent. Gas balance experiments have shown that fuel retention rates with the new wall are in line with the ITER needs. The re-establishment of high-confinement scenarios compatible with the new wall has required an optimization of the control of metallic impurity sources and heat loads. Stable type I ELMy H-mode regimes with H98,y2 close to 1 and βN∼1.6 have been achieved in high triangularity plasmas. The ELM frequency is the main factor for the control of the metallic impurities accumulation. Pedestal temperatures tend to be lower with the new wall, leading to somewhat reduced confinement, but nitrogen seeding restores high pedestal temperatures and high confinement. Compared with the carbon wall, major disruptions with the new wall show a lower radiated power and a slower current quench. The higher heat loads on plasma-facing components due to lower radiation, made the routine use of massive gas injection for disruption mitigation essential.

AB - Following the completion in May 2011 of the shutdown for the installation of the beryllium wall and the tungsten divertor, the first set of JET Campaigns have addressed the investigation of the retention properties and the development of operational scenarios with the new plasma facing materials. The large reduction of the carbon content (more than a factor ten) led to a much lower Zeff (1.2-1.4) during L- and H-mode plasmas, and radiation during the burn-through phase of the plasma initiation with the consequence that breakdown failures are almost absent. Gas balance experiments have shown that fuel retention rates with the new wall are in line with the ITER needs. The re-establishment of high-confinement scenarios compatible with the new wall has required an optimization of the control of metallic impurity sources and heat loads. Stable type I ELMy H-mode regimes with H98,y2 close to 1 and βN∼1.6 have been achieved in high triangularity plasmas. The ELM frequency is the main factor for the control of the metallic impurities accumulation. Pedestal temperatures tend to be lower with the new wall, leading to somewhat reduced confinement, but nitrogen seeding restores high pedestal temperatures and high confinement. Compared with the carbon wall, major disruptions with the new wall show a lower radiated power and a slower current quench. The higher heat loads on plasma-facing components due to lower radiation, made the routine use of massive gas injection for disruption mitigation essential.

UR - https://www.scopus.com/pages/publications/84988385351

U2 - 10.1088/0029-5515/53/10/104002

DO - 10.1088/0029-5515/53/10/104002

M3 - Article

AN - SCOPUS:84988385351

SN - 0029-5515

VL - 53

JO - Nuclear Fusion

JF - Nuclear Fusion

IS - 10

M1 - 104002

ER -

Overview of the JET results with the ITER-like wall

Abstract

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