ASDEX Upgrade

ASDEX Upgrade
Name	ASDEX Upgrade
Type	Tokamak
Location	Garching bei München, Germany
Operator	Max-Planck-Institut für Plasmaphysik
Construction	1987
First plasma	1991
Status	Active

ASDEX Upgrade is a major tokamak research facility operated by the Max-Planck-Institut für Plasmaphysik in Garching bei München that investigates magnetic confinement fusion, plasma physics, and materials interactions. The device builds on earlier experiments and complements international projects such as JET, ITER, DIII-D, and JT-60 to address high-performance plasmas, plasma-facing components, and divertor physics. ASDEX Upgrade serves as a platform connecting European research programs like EUROfusion, national initiatives such as the Bundesministerium für Bildung und Forschung, and institutional research at universities including the Technische Universität München.

Overview

ASDEX Upgrade is a medium-sized, divertor-equipped tokamak designed to study H-mode, edge-localized modes, and impurity control with relevance to reactors like ITER and future devices explored by EUROfusion and national roadmaps such as those from the Max-Planck-Institut für Plasmaphysik and the Deutsches Zentrum für Luft- und Raumfahrt. The facility integrates diagnostics, auxiliary heating systems, and plasma control systems developed in collaboration with partners like Culham Centre for Fusion Energy, Princeton Plasma Physics Laboratory, Oak Ridge National Laboratory, and the CEA. ASDEX Upgrade coordinates experimental campaigns, technology tests, and theoretical comparisons with groups from the University of Oxford, École Polytechnique, and EPFL.

Design and Technical Specifications

The machine is a toroidal magnetic confinement device with a high-field, high-current capability influenced by design concepts tested on predecessors and contemporaries such as the original ASDEX, JET, and DIII-D. Its vessel, superconducting magnets heritage, and actively cooled plasma-facing components were developed with industrial partners including Siemens, Thyssenkrupp, and specialized suppliers from the European Commission framework. Heating and current-drive systems comprise neutral beam injection (NBI), electron cyclotron resonance heating (ECRH), and ion cyclotron resonance heating (ICRH) technologies shared in collaborations with ITER Organization contributors and manufacturers in France, United Kingdom, and United States. Diagnostics include Thomson scattering, charge-exchange recombination spectroscopy, bolometry, reflectometry, and magnetic probes developed with teams from the Max Planck Society, Lawrence Livermore National Laboratory, and Culham Centre for Fusion Energy for realtime plasma control and stability analysis.

Experimental Program and Research Areas

Research campaigns focus on confinement optimization, transport barriers, edge localized mode (ELM) mitigation, and divertor exhaust physics together with materials testing relevant to the ITER divertor and future DEMO concepts pursued by EUROfusion and national programs at the Technische Universität München. Experimental studies span impurity seeding, tungsten erosion and redeposition, pellet fueling, and advanced scenario development connected to theoretical work from Princeton University, CEA, and IPP Greifswald. Collaborations extend to model validation with simulation codes and theory groups at institutions such as MIT, University of California, San Diego, Kyoto University, and Friedrich-Alexander-Universität Erlangen-Nürnberg.

Key Results and Contributions

ASDEX Upgrade produced influential results on H-mode access, ELM control via resonant magnetic perturbations, and tungsten behavior under high heat fluxes, informing design choices for ITER, DEMO concepts championed by EUROfusion, and materials strategies discussed at forums like the IAEA meetings and conferences organized by EPS and APS. Work on impurity transport, plasma shaping, and advanced divertor configurations contributed to cross-machine scalings used by researchers at JET, DIII-D, and NSTX-U. Diagnostics and control algorithms developed at the facility influenced real-time control efforts at Princeton Plasma Physics Laboratory and hardware implementations within the ITER Organization collaborations.

Collaboration and Facility Operations

Operations rely on multinational teams and institutional partnerships spanning the Max-Planck-Institut für Plasmaphysik, European research networks like EUROfusion, project partners at Culham Centre for Fusion Energy, and academic groups from Imperial College London, University of Manchester, and Université Paris-Saclay. Funding, technical upgrades, and strategic planning involve stakeholders including the Bundesministerium für Bildung und Forschung, the European Commission, and industry partners in Germany and across Europe. The facility hosts visiting scientists from Princeton Plasma Physics Laboratory, Lawrence Berkeley National Laboratory, and CCFE for joint experiments, code benchmarking, and coordinated campaigns aligned with international roadmaps set by bodies such as the IAEA and the European Council.

History and Development

The device evolved from the original ASDEX program, reflecting advances made in the 1980s and 1990s at institutions like the Max-Planck-Institut für Plasmaphysik and parallel developments at JET and DIII-D. Major upgrades incorporated lessons from collaborations with CEA, Culham Centre for Fusion Energy, and US laboratories, leading to enhancements in plasma-facing components, heating systems, and diagnostic suites. Development milestones align with international gatherings and agreements involving EUROfusion, the ITER Agreement, and national science policy decisions by the Bundesministerium für Bildung und Forschung and academic partners such as the Technische Universität München.

Category:Tokamaks