Conveners
LPO & Control session
- Stefano Coda (CRPP-EPFL)
LPO & Control session
- Stefano Coda (CRPP-EPFL)
The control of the core-plasma kinetic state determining the overall fusion power, usually referred to as burn control, arises as one of the most fundamental problems in nuclear fusion. Feedback control of the burn condition will be necessary to avoid undesirable transient performance, to respond to changes in plasma confinement, impurity content, or operation conditions, which could...
Control developments, including porting a Proximity Controller [1] to aid in continuous disruption prevention and upgrading the existing Real-Time Feed-Forward algorithm [2] for robust and reliable shape control during long-pulse sustainment and ramp-down, have been implemented to support long-pulse scenarios on KSTAR with its new tungsten divertor. The proximity controller calculates the...
The WEST superconducting tokamak features a full tungsten environment and is equipped with an actively cooled ITER-grade divertor providing valuable input for future operation at ITER. Versatile multi-energy soft and hard X-ray pinhole cameras have been developed, calibrated, deployed and operated for long-pulse plasmas at WEST. These cutting-edge instruments, serving as novel enabling...
WEST is a tungsten tokamak designed for long pulse operation with actively cooled components. The main missions of WEST include high fluence plasma divertor exposure and the demonstration of long pulse H-mode in a full tungsten environment. Achieving long duration and high performance plasma discharges while ensuring the protection of the machine requires features such as specific controllers...
Metallic impurities induced by divertor heat load and ELM filaments are the main challenges in achieving long-pulse high-performance H-mode operations. Long-pulse (>50s) no-ELM H-mode discharges with feedback-controlled divertor detachment by nitrogen seeding from outer horizontal target plate of the lower divertor have been achieved under boronized metal wall in the EAST tokamak. Figure 1...
The DIII-D research program will close key gaps in knowledge for the design and operation of long-pulse tokamak fusion pilot plants (FPPs) by deploying increased electron cyclotron heating and current drive power to reach and study more relevant plasma regimes. The U.S. is focused on low capital cost compact FPPs on the path to commercialization. Steady-state or long-pulse inductive tokamaks...
WEST is a machine designed for attaining Long Pulse Operation [1] with Lower-hybrid Heating and Current Drive (LHCD), superconducting coils, actively-cooled components and a W wall. In 2024, a more than six-minutes-long L-mode plasma was sustained with 1.15 GJ of injected energy. In parallel, developments were undertaken on the modeling side. The High Fidelity Pulse Simulator (HFPS) [2], an...
