Conveners
LPO session
- Christopher Holcomb (Lawrence Livermore National Laboratory)
LPO session
- Christopher Holcomb (Lawrence Livermore National Laboratory)
LPO session
- Stefano Coda (CRPP-EPFL)
LPO session
- Joerg Stober (IPP Garching)
LPO session
- Joerg Stober (IPP Garching)
The ITER long-pulse and steady-state operations, foreseen in the ITER Research Plan [IRP, 2018 ITER technical report, ITR-18-03], are important steps towards exploration of reactor relevant tokamak operation and research. A few key research areas, such as the operational space with heating mixes and external current drive, access to target plasma states with profile tailoring and control, and...
Significant progress has been achieved on EAST in the development of long-pulse steady-state advanced plasmas, and in the understanding of the related scientific and technical issues in support of ITER and future fusion reactors.
A thousand-second time scale (~1056s) fully non-inductive plasma has been achieved on EAST at the end of 2021 with poloidal beta ~1.5, a normalized confinement...
The Large Helical Device (LHD) started its operation in 1998. One of the main objectives of the LHD project is the comprehensive study for the steady-state operation towards fusion reactors. Since the plasma current is not essential for LHD/stellarator devices to confine plasma, it is free from intensive efforts to drive and sustain plasma current. However, any other issues necessary for...
The Wendelstein 7-X stellarator has a super-conduction coil system, to prove the steady state capabilities of optimized stellarators. After different steps with a limiter (OP1, starting December 2015) and two runs with inertially cooled divertors (OP1.2a, OP1.1b, up to December 2018) the device was completed to fulfill the steady-state capabilities:
- A High-Heat Flux Divertor (HHF) for...
The WEST tokamak has recently fully completed the installation of its ITER-like actively cooled divertor, and it is now ready to pursue integrated investigations for the qualification of the ITER divertor components (named PFU for Plasma Facing Units) as well as for operating high performance plasmas in a full tungsten environment. A comprehensive diagnostic survey tracks the evolution of the...
C. Holcomb for the DIII-D Team
Lawrence Livermore National Laboratory
DIII-D is focused on providing the scientific basis of high fusion performance, noninductively-sustained tokamak operation in ITER and pilot plants that will set the stage for commercial energy production. This presentation will highlight recent DIII-D research progress investigating core plasma scenarios ranging from...
Conventional tokamak high-confinement mode (H-mode) scenarios suffer from magnetohydrodynamic (MHD) instabilities and also depend on inductive current from the central solenoid to maintain the plasma current.
Advanced Tokamak (AT) scenarios that feature manipulated non-standard $q$-profiles not only promise to improve the stability and confinement of the discharge by eliminating some of the...
Coordinated experiments on DIII-D and EAST are developing the physics basis of fully non-inductive, high poloidal-beta (βP) plasmas for application to steady-state high performance operating scenarios in ITER and Fusion Pilot Plants (FPPs). By optimizing at low plasma current and high plasma pressure, high-βP operation reduces disruption risks and requirements on external current drive, while...
The Advanced Tokamak concept represents a virtuous approach for a fusion reactor, combining improved confinement and stability with reduced heat flux and disruption severity, and the potential for fully stationary “always on” steady state operation to ease engineering and stability challenges. Self-consistent, integrated 1.5D simulations project new paths to a compact fusion pilot plant based...
JT-60SA is a large fully superconducting new tokamak device built jointly by Europe and Japan [1]. The tokamak was fully assembled in March 2020, and the integrated commissioning of the tokamak is on-going. The mission of JT-60SA is to contribute to the early realization of fusion energy by addressing key physics issues for ITER and DEMO. Especially, development of fully non-inductive...
The UK-based STEP programme aims to develop by 2040 a prototype reactor based on the spherical tokamak (ST) concept, thereby establishing a basis for developing commercial electricity production from fusion [1]. The compact design restricts the possible inductive flux, hence the flat-top plasma current will be entirely non-inductive, enabling long-pulse operation. External current drive will...
Recently, stationary plasma with a world-record pulse length of 1056 second was obtained, where a stable internal transport barrier (ITB) is present in electron temperature channel. The core magneto-hydrodynamics (MHD) events with m/n=1/1 or m/n=3/2, m is the poloidal mode number and n is the torodial mode number, have been observed near e-ITB region. The time evolution of frequency and the...
