Published 2019 | Version v1
Report Metadata-only

Modelling of toroidal ripple field and fast ions in the COMPASS Upgrade tokamak

Creators

  • 1. IPP of the CAS, Prague (Czech Republic)
  • 2. DIFFER (Netherlands)
  • 3. University of Birmingham (United Kingdom)

Description

The COMPASS Upgrade tokamak 1 will be a tokamak of major radius R0~0.894 m with high-field (Bt~5 T) and high-current (Ip~2 MA). The machine should be completed by 2022. It will be located in Prague, Czech Republic and is currently in design phase. The main auxiliary heating system used to access H-mode will be 4 MW of Neutral Beam Injection (NBI) power with an injection energy of 80 keV. This will create a population of well-confined energetic D ions. In this contribution, the modelling studies the effects of the toroidal ripple induced by the 16 TF coils: a Biot-Savart solver is used to calculate the intensity of the perturbation (BTFR/Bt~10-3 at outermost mid-plane positions).

Part of:
16th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems - Theory of Plasma Instabilities. Report of Abstracts

Additional details

Identifiers

URL
https://conferences.iaea.org/event/185/attachments/7893/10613/BoA_EPPI_2019.pdf;

Publishing Information

Imprint Title
16th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems - Theory of Plasma Instabilities. Report of Abstracts
Imprint Pagination
84 p.
Journal Page Range
p. 53-54
Report number
INIS-XA--21M2910

Conference

Title
16. IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems - Theory of Plasma Instabilities
Dates
3-6 Sep 2019
Place
Shizuoka City (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
52116639
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AUXILIARY HEATING; BEAM INJECTION; COMPASS DETECTOR; COMPASS-D TOKAMAK; DESIGN; HEATING SYSTEMS; H-MODE PLASMA CONFINEMENT; IONS; KEV RANGE; PLASMA SIMULATION
Descriptors DEC
CHARGED PARTICLES; CLOSED PLASMA DEVICES; CONFINEMENT; ENERGY RANGE; ENERGY SYSTEMS; HEATING; MAGNETIC CONFINEMENT; MEASURING INSTRUMENTS; PLASMA CONFINEMENT; RADIATION DETECTORS; SIMULATION; SPACE HEATING; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information

Notes
5 refs.