Wendelstein 7-X Stellarator

The Wendelstein 7-X (W7-X) is a large advanced stellarator-type nuclear fusion experiment located in Greifswald, Germany. It is operated by the Max Planck Institute for Plasma Physics (IPP).

Overview

• Type: Stellarator
• Location: Greifswald, Germany
• Operator: Max Planck Institute for Plasma Physics (IPP)
• Purpose: Research into controlled nuclear fusion as a potential source of sustainable energy
• Construction Started: Late 1990s
• First Plasma: December 2015

Design and Features

• Magnetic Configuration: W7-X is designed as a modular, optimized stellarator, with a complex arrangement of magnetic coils to confine hot plasma efficiently without the need for a strong plasma current (unlike tokamaks).
• Magnetic Coils: It has 50 non-planar superconducting magnetic coils arranged around the plasma vessel to generate a twisted magnetic field that confines the plasma.
• Plasma Volume: Approximately 30 cubic meters
• Plasma Temperature: Can reach over 100 million degrees Celsius, necessary for fusion reactions
• Plasma Duration Goals: A key aim of W7-X is to sustain plasma discharges for up to 30 minutes or longer—a timescale much longer than previous stellarators or tokamaks, helping to study steady-state operation.

Scientific Goals

• Demonstrate the stellarator as a viable design for steady-state fusion power plants.
• Improve plasma confinement and stability.
• Understand plasma behavior without large plasma currents (tokamaks rely on current to generate part of the confining magnetic field).
• Test materials and plasma-facing components for long-duration plasma operation.

Significance

Wendelstein 7-X is one of the most advanced stellarator experiments worldwide and aims to answer fundamental questions about plasma confinement in stellarators, which could provide a path to continuous fusion power.

Recent Status

• Since its first plasma in 2015, W7-X has undergone several upgrade phases, improving heating power, diagnostics, and plasma control.
• Achievements include record plasma durations and improved energy confinement.
• It serves as a complementary approach to tokamaks like ITER, focusing on continuous (steady-state) operation.

If you want more on specific aspects like technical details, recent experimental results, or comparison with other fusion devices, let me know!