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Estimate of 3D power wall loads due to Neutral Beam Injection in EU DEMO ramp-up phase

  • P. Vincenzi*
  • , J. Varje
  • , P. Agostinetti
  • , J. F. Artaud
  • , T. Bolzonella
  • , T. Kurki-Suonio
  • , M. Mattei
  • , P. Sonato
  • , M. Vallar
  • *Tämän työn vastaava kirjoittaja
  • National Research Council of Italy
  • CEA, Grenoble
  • University of Campania Luigi Vanvitelli

Tutkimustuotos: Lehtiartikkeli › Article › Scientific › vertaisarvioitu

3 Sitaatiot (Scopus)
196 Lataukset (Pure)

Abstrakti

Heating and current drive systems such as high energy Neutral Beam Injection (NBI) are being considered for pulsed EU DEMO (“DEMO1”) pre-conceptual design. Their aim is to provide auxiliary power, not only during flat-top, but also during transient phases (i.e. plasma current ramp-up and ramp-down). In this work, NBI fast particle power loads on DEMO1 first wall, due to shine-through and orbit losses, are calculated for the diverted plasma ramp-up phase. Numerical simulations are performed using BBNBI and ASCOT Monte Carlo codes. The simulations have been done using a complete 3D wall geometry, and implementing the latest DEMO NBI design, which foresees NBI at 800 keV particle energy. Location and power density of NBI-related power loads at different ramp-up time steps are evaluated and compared with the maximum tolerable heat flux taken from ITER case. Since NBI shine-through losses (dominant during low density phases) depend mainly on the beam energy, plasma density and volume, DEMO has a more favourable situation than ITER, enlarging NBI operational window. Using ITER criteria, DEMO NBI at full energy and power could be switched on during ramp-up at <ne> ~ 1.3 × 1019 m-3. This increases the appeal of neutral beam injectors as auxiliary power systems for DEMO.

AlkuperäiskieliEnglanti
Sivut188-192
Sivumäärä5
JulkaisuNuclear Materials and Energy
Vuosikerta18
DOI - pysyväislinkit
TilaJulkaistu - 1 tammik. 2019
OKM-julkaisutyyppiA1 Alkuperäisartikkeli tieteellisessä aikakauslehdessä

Rahoitus

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement number 633053 . This work has been supported by a EUROfusion Engineering Grant . The views and opinions expressed herein do not necessarily reflect those of the European Commission.

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