Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components

O. Grulke*, C. Albert, J. A.Alcuson Belloso, P. Aleynikov, K. Aleynikova, A. Alonso, G. Anda, T. Andreeva, M. Arvanitou, E. Ascasibar, E. Aymerich, K. Avramidis, J. P. Bähner, S. G. Baek, M. Balden, J. Baldzuhn, S. Ballinger, M. Banduch, S. Bannmann, A. Bañón NavarroL. Baylor, S. Chen, Y. Feng, Y. Gao, X. Han, J. Huang, J. Huang, J. Jin, A. Johansson, J. Kontula, A. Kumar, T. Kurki-Suonio, B. Lee, Y. Liang, J. Liu, Y. Luo, M. Machielsen, J. Martínez, S. Nielsen, A. Pandey, L. Sanchis Sanchez, D. R. Smith, Y. Suzuki, J. Wagner, F. Wang, Y. Wei, J. Yang, D. Zhang, S. Zhou, J. Zhu, EUROfusion Consortium

*Tämän työn vastaava kirjoittaja

Tutkimustuotos: LehtiartikkeliArticleScientificvertaisarvioitu

19 Sitaatiot (Scopus)
13 Lataukset (Pure)

Abstrakti

After a long device enhancement phase, scientific operation resumed in 2022. The main new device components are the water cooling of all plasma facing components and the new water-cooled high heat flux divertor units. Water cooling allowed for the first long-pulse operation campaign. A maximum discharge length of 8 min was achieved with a total heating energy of 1.3 GJ. Safe divertor operation was demonstrated in attached and detached mode. Stable detachment is readily achieved in some magnetic configurations but requires impurity seeding in configurations with small magnetic pitch angle within the edge islands. Progress was made in the characterization of transport mechanisms across edge magnetic islands: Measurement of the potential distribution and flow pattern reveals that the islands are associated with a strong poloidal drift, which leads to rapid convection of energy and particles from the last closed flux surface into the scrape-off layer. Using the upgraded plasma heating systems, advanced heating scenarios were developed, which provide improved energy confinement comparable to the scenario, in which the record triple product for stellarators was achieved in the previous operation campaign. However, a magnetic configuration-dependent critical heating power limit of the electron cyclotron resonance heating was observed. Exceeding the respective power limit leads to a degradation of the confinement.

AlkuperäiskieliEnglanti
Artikkeli112002
Sivut1-10
Sivumäärä10
JulkaisuNuclear Fusion
Vuosikerta64
Numero11
DOI - pysyväislinkit
TilaJulkaistu - marrask. 2024
OKM-julkaisutyyppiA1 Alkuperäisartikkeli tieteellisessä aikakauslehdessä

Sormenjälki

Sukella tutkimusaiheisiin 'Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components'. Ne muodostavat yhdessä ainutlaatuisen sormenjäljen.

Siteeraa tätä