TJ-II Stellarator
Provides key experimental data on 3D magnetic confinement and plasma transport physics.
01 Definition
A medium-sized flexible heliac stellarator operated by CIEMAT in Madrid, representing Spain's flagship magnetic confinement device.
02 Detailed_Analysis
TJ-II is an advanced flexible heliac stellarator situated at CIEMAT's Laboratorio Nacional de Fusión in Madrid, Spain. Operating with a major radius of 1.5 m and an on-axis magnetic field of 1.0 T, it features high magnetic configuration flexibility. TJ-II utilizes electron cyclotron resonance heating (ECRH) and neutral beam injection (NBI) to investigate 3D plasma confinement, transport barriers, and kinetic instabilities.
03 Key_Facts
- ▸ Located at CIEMAT's Laboratorio Nacional de Fusión in Madrid
- ▸ Features a flexible heliac magnetic geometry with R0 = 1.5 m and B0 = 1.0 T
- ▸ Heated by microwave ECRH (53 GHz) and two neutral beam injectors (1.6 MW)
04 Deep_Dive_Intelligence
Intelligence Summary: TJ-II Flexible Heliac Stellarator
Node Identity: TJ-II is a flexible, medium-size stellarator of the heliac type located at the Laboratorio Nacional de Fusión (LNF) at CIEMAT in Madrid. It is the second-largest operational stellarator in Europe after W7-X and serves as Spain's flagship magnetic confinement fusion experiment. Key parameters: major radius R₀ = 1.5 m, averaged minor radius ⟨a⟩ = 0.2-0.25 m, magnetic field B₀ = 1 T. Heating is via microwave ECRH (800 kW at 53 GHz) and neutral beam injection (1.6 MW, 30 keV). The device features 92 access windows for diagnostics and a rotational transform range of 0.96 < ι₀ < 2.5, making it unique for studying magnetic configuration effects on transport.
Strategic Relevance: TJ-II's strategic relevance to the FRC/plasma weapons landscape is defined by its 25+ years of continuous operation and its unique flexibility in magnetic configuration. The heliac design allows variation of the rotational transform, enabling systematic studies of how magnetic geometry affects plasma confinement, turbulence, and transport — knowledge directly transferable to compact toroid and FRC concepts where magnetic configuration optimization is critical. The device was designed in collaboration with Oak Ridge National Laboratory (ORNL, USA) and IPP Garching (Germany), connecting Spanish stellarator research directly to US fusion programs. The liquid metals research program (Li and alloys for power exhaust) is directly relevant to plasma-facing component technology with dual-use implications. Spain's stellarator expertise represents a genuine, long-term plasma physics capability that contributes to W7-X operations and broader stellarator optimization.
Technical Focus / Capabilities: TJ-II research focuses on: (1) turbulence and zonal flow physics; (2) isotope effect studies; (3) power exhaust physics with liquid metals (Li and alloys); (4) stellarator optimization using swarm strategy; (5) Alfvén eigenmode control and stability; (6) support for W7-X operations. The device achieved L-H transition in 2008 using NBI and lithium wall conditioning. Leading researcher Carlos Hidalgo (h-index 52, 10,209 citations) has published extensively on model validation of plasma flow asymmetries, plasma fuelling physics, Alfvén eigenmodes, neoclassical-turbulence interplay, and liquid metals. TJ-II is the third device in a series: TJ-I tokamak (1983-1995), TJ-IU torsatron (1994, later transferred to Germany as TJ-K), and TJ-II.
Network Linkage: TJ-II maintains 1 documented connection: CIEMAT operates TJ-II (at Laboratorio Nacional de Fusión, Madrid). TJ-II was designed with ORNL (USA) and IPP Garching (Germany). It is funded through EUROfusion Spain and supports W7-X operations. The device received EURATOM preferential support for Phase I (Physics) in 1986 and Phase II (Engineering) in 1990. Construction completed October 1996, with 60% of investments reverting to Spanish companies.
06 Related_Terms (1)
07 Related_Entities (12)
08 Timeline_Mentions (7)
NRL LINUS Liquid Metal Liner Concept
NRL develops the LINUS fusion reactor concept using rotationally stabilized liquid lead-lithium liner. CFS-NM's SLC concept has strong conceptual similarities.
Fusion PhysicsLASL Fast Liner Experiment
LASL Fast Liner Experiment using magnetically imploded aluminum liners. Direct precursor to FRCHX and CFS-NM SLC. Also used coaxial plasma gun for injection.
Fusion PhysicsLLNL Beta II Compact Toroid Experiment
LLNL Beta II compact toroid experiment using coaxial plasma gun with LASL features. Second link in three-lab lineage: LANL (CTX) → LLNL (Beta II) → AFRL (MARAUDER).
Fusion PhysicsLANL CTX Spheromak Experiment
LANL CTX using magnetized coaxial plasma gun to generate spheromaks. Foundational node of the three-lab compact toroid lineage.
Fusion PhysicsLLNL RACE Compact Toroid Acceleration
LLNL RACE program accelerates compact toroids in coaxial railgun. Fusion-oriented: ICF driver, x-ray generator, tokamak fueling. Inspired AFRL MARAUDER.
Fusion PhysicsPrinceton PFRC Experiment Begins
PFRC begins at PPPL by Samuel Cohen. Uses rotating magnetic fields. Enables DFD propulsion. Descends from LANL FRX.
Fusion PhysicsPRC Yingguang-I FRC Design
The People's Republic of China designs the Yingguang-I device, indicating active research into Field-Reversed Configuration (FRC) fusion physics.
fusion-physics09 FAQ
What is TJ-II Stellarator? ▾
Why does TJ-II Stellarator matter? ▾
How does TJ-II Stellarator relate to other concepts? ▾
When did TJ-II Stellarator appear in the research timeline? ▾
Which entities are associated with TJ-II Stellarator? ▾
Is there a detailed dossier for TJ-II Stellarator? ▾
Quick_Facts
- Category
- Experiments
- Aliases
- TJ-II Stellarator, tj-ii-stellarator, TJ-II, TJ-II Heliac
- Sources
- 0
- Related Terms
- 1
- Graph Entities
- 12
- Timeline Events
- 7