Conveners
LPO Control session
- Tomohiro Morisaki (National Institute for Fusion Science)
LPO Control session
- Hans-Stephan Bosch (Max-Planck-Institute for Plasma Physics)
Existing magnetically confined plasma devices benefit from an extensive array of diagnostics, commensurate with the R&D function of these plasma devices. While increased diagnostic coverage, and access to information relevant to the plasma, first-wall components, and plasma-material interactions is always desired, the harsh nuclear environment of future fusion reactors is more likely to...
Feedback controlled fully non-inductive plasma discharge have been sustained in EAST long-pulse operation up to 1056s with a new world record of injected–extracted energy exceeding 1.7 GJ. This steady-state real-time plasma control requires integrated accurate control of plasma equilibrium, current and loop voltage [1]. An improvement of the plasma position and shape control within a few...
WEST is a tungsten tokamak designed for long pulse operation. It is now fully equipped with actively cooled components especially, the lower divertor is made of 456 ITER like Plasma Facing Units (PFU) that are being qualified in a tokamak environment. The main missions of WEST address high fluence plasma divertor exposure and the demonstration of long pulse H-mode in a full tungsten...
A model has been developed in the transport code ASTRA, which is capable of simulating advanced tokamak discharges, using the density and actuator setup as inputs. The model uses a reduced Gyro-Bohm based core transport, which does include simplified ITG and TEM mode contributions, to achieve a run time of only a few minutes for a full discharge. Edge transport is included via the use of a...
Avoidance of radiative collapse in high-density plasma has been attempted in the Large Helical Device (LHD) with a real-time control system based on a data-driven predictor model. The predictor model has been developed based on machine-learning techniques and high-density experiment data in LHD.
In stellarator-heliotron plasma, radiative collapse is one of the most critical issues that...
Demonstration of long-pulse plasma discharge is one of the critical issues in making fusion reactors true. In the Large Helical Device (LHD), we realized the duration time of 48 min with the electron density of 1.2e19 m-3, the plasma temperature of 2 keV, and the heating power of 1.2 MW using the ICRF and ECRF waves in hydrogen minority helium plasmas He(H). Several feedback systems kept the...
In long pulse experiments on ITER and DEMO, pellet injection will need to be used to fuel the core plasma and will likely be the sole actuator available for core density control. The reason is that gas injection will be largely ineffective due to its limited penetration depth towards the core. However, considering the expected 10% lost pellet rate during injection, feedback control will be...
