Russian fusion program (T-15MD, IGNITOR)

Overview

The Russian fusion program represents one of the foundational pillars of modern magnetic confinement fusion research. Originating in the Soviet Union, its most significant contribution was the invention and development of the tokamak, a toroidal device that has become the dominant design for fusion energy experiments worldwide. The program is managed under the state corporation Rosatom and is primarily executed by the National Research Center "Kurchatov Institute" in Moscow, with significant contributions from other institutions like the D.V. Efremov Scientific Research Institute of Electrophysical Apparatus in St. Petersburg and the Ioffe Institute. Historically a leader that set the pace for global research, the program now focuses on supporting the international ITER project, developing next-generation materials and components, and operating a fleet of domestic experimental devices to explore key physics and engineering challenges on the path to a fusion power plant.

Physics / Mechanism

The scientific and engineering focus of the Russian program is multifaceted, building upon its deep expertise in tokamak physics. A primary area of research is the study of plasma-wall interactions and the development of robust plasma-facing components (PFCs). This is a critical challenge for any long-pulse fusion device, as intense heat and particle fluxes can erode and damage the reactor's inner wall. The T-15MD tokamak is specifically designed to test different PFC materials and divertor configurations under reactor-relevant heat loads of up to 20 MW/m². This research is directly applicable to the design and operation of future devices, including ITER and demonstration power plants (DEMOs).

Another key area is plasma heating and control. Russian scientists have long been leaders in the development of gyrotrons, high-power microwave sources used for Electron Cyclotron Resonance Heating (ECRH). ECRH is a versatile tool for heating plasma electrons, driving non-inductive current to sustain the plasma, and suppressing magnetohydrodynamic (MHD) instabilities. The program continues to advance gyrotron technology for use on domestic machines and as part of its in-kind contributions to the ITER project.

The program also investigates alternative magnetic confinement configurations. The Globus-M2 device at the Ioffe Institute is a spherical tokamak, characterized by a more compact, apple-like plasma shape. This configuration offers the potential for higher plasma pressure for a given magnetic field strength, which could lead to more compact and economically efficient reactors. Research on Globus-M2 focuses on achieving high plasma beta and understanding energy confinement in this low-aspect-ratio geometry.

Historical development

The history of the Russian fusion program is central to the history of fusion energy itself. Soviet research began in secret in the early 1950s under the direction of Igor Kurchatov. Physicists Andrei Sakharov and Igor Tamm conceived of the tokamak concept in 1950-51 as a way to confine a hot plasma using a combination of a strong toroidal magnetic field and a weaker poloidal field generated by a current flowing through the plasma itself.

A series of experimental devices were built at the Kurchatov Institute to test the concept. While early results were promising, they were met with skepticism by the international community. The breakthrough came in 1968 with the T-3 tokamak. At the IAEA conference in Novosibirsk, Soviet teams led by Lev Artsimovich reported achieving electron temperatures of 1 keV and confinement times of tens of milliseconds, an order of magnitude better than any other device at the time. To verify these extraordinary claims, a British team from the Culham laboratory was invited to Moscow in 1969. Using their advanced laser Thomson scattering diagnostic, the "Culham Five" confirmed the Soviet results, an event that triggered a global shift towards the tokamak design.

This success led to the construction of a series of increasingly powerful machines, including the T-4, T-10 (which is still operational for materials studies), and the T-7, the world's first tokamak to use superconducting magnets. The T-15, which began operation in 1988, was a large superconducting tokamak intended to be a major step towards reactor-scale conditions. However, its operational life was hampered by the economic and political turmoil following the dissolution of the Soviet Union. The experience gained from these devices cemented the Soviet Union's, and later Russia's, expertise in tokamak operation, plasma physics, and fusion technology.

Current status

As of 2026, the Russian fusion program is centered on a few key domestic facilities and its significant role in the ITER project. The flagship domestic device is the T-15MD tokamak, a major modification of the original T-15, which was commissioned at the Kurchatov Institute in 2021. T-15MD is a conventional aspect-ratio tokamak with resistive copper coils, designed to operate with high auxiliary heating power (up to 25 MW) and a uniquely shaped D-shaped vacuum vessel. Its primary mission is to serve as a materials and components testbed, investigating PFCs, divertor concepts, and plasma heating schemes relevant to ITER and DEMO. The machine has been progressively increasing its operational parameters, including plasma current and heating power, and has demonstrated successful H-mode operation.

At the Ioffe Institute in St. Petersburg, the Globus-M2 spherical tokamak, an upgrade to Globus-M, has been operational since 2018. It features a stronger magnetic field (up to 1 T) and higher plasma current (up to 0.5 MA) than its predecessor. Recent experimental campaigns have focused on achieving high-density plasmas and exploring the limits of plasma beta in a compact configuration. Results from Globus-M2 inform the design of next-generation spherical tokamaks and contribute to the global understanding of their potential as a power plant concept.

Russia remains a full member of the ITER project, responsible for delivering 9% of the project's components as in-kind contributions. The Efremov Institute is a key supplier of complex components, including superconducting conductors, gyrotrons for the ECRH system, and various diagnostic systems. Despite geopolitical tensions, Russia continues to fulfill its manufacturing and delivery obligations to the ITER Organization.

Notable implementations

• T-15MD (Kurchatov Institute): The program's primary domestic facility. It is a conventional tokamak focused on testing reactor technologies, particularly plasma-facing components and heating systems. Its flexible design allows for the testing of various divertor configurations and materials under high heat flux conditions, providing critical data for future reactors.

• Globus-M2 (Ioffe Institute): A leading spherical tokamak experiment. Its research program aims to explore the physics of high-beta plasmas in a compact geometry. The device is a key part of the international effort to assess the viability of the spherical tokamak as a more compact and potentially more economical path to fusion energy.

• IGNITOR Project (TRINITI / ENEA collaboration): A long-standing collaboration with Italy to build a high-field, compact tokamak designed to reach ignition, where the plasma is self-heated by fusion reactions. The Russian side, primarily the TRINITI institute, is responsible for designing and manufacturing major components. While the project has faced delays, it represents a continued interest in the high-field path to achieving a burning plasma.

• ITER Contributions (Rosatom): As a member of the ITER project, Russia is responsible for manufacturing and delivering critical high-technology components. This includes 25% of the project's advanced superconducting Strands, powerful 170 GHz gyrotrons for the plasma heating system, and several key diagnostic ports and systems. This participation ensures Russia remains at the forefront of fusion engineering.

Open challenges

The Russian fusion program, like its international counterparts, faces significant scientific and engineering hurdles. A primary challenge is developing materials that can withstand the extreme environment of a fusion reactor core. The neutron flux and high heat loads in a future power plant will degrade structural materials and PFCs over time. While T-15MD is a platform for testing these components, developing and qualifying materials for a full-scale commercial reactor requires a dedicated, high-flux neutron source, a facility which is currently in the planning stages (e.g., DEMO-FNS).

Another challenge is achieving steady-state tokamak operation. Most current tokamaks operate in pulses. A power plant must operate continuously, which requires replacing the inductive current drive with fully non-inductive methods. Research on T-15MD and other devices is exploring techniques like ECRH and neutral beam injection for current drive, but achieving high efficiency and stability for long durations remains an unsolved problem. This is directly related to the challenge of avoiding or mitigating large-scale plasma disruptions, which can damage the reactor wall and must be reliably controlled for a commercial plant to be viable.

Finally, the program faces the overarching challenge of securing sustained, long-term funding to pursue its ambitious goals, particularly in a complex geopolitical and economic climate. Maintaining a cutting-edge research program, developing next-generation facilities, and fulfilling international commitments requires significant and stable government investment.

Outlook

The credible 5-15 year trajectory for the Russian fusion program involves a three-pronged approach. First, the program will continue to ramp up the operational capabilities of T-15MD, aiming to reach its full design parameters for magnetic field, plasma current, and heating power. This will enable it to function as a world-class testbed for PFCs and divertor solutions, providing crucial data for the Lawson criterion and beyond. Second, the program will continue its research on spherical tokamaks with Globus-M2, contributing to the global assessment of this alternative concept. The design of a next-step, more powerful spherical tokamak is a likely outcome of this research.

Third, Russia will remain a key partner in the ITER project, completing its hardware contributions and preparing for the scientific exploitation phase. Russian scientists and engineers will play an active role in ITER's first plasma and subsequent operational campaigns. Looking further ahead, the program is developing concepts for a fusion-neutron source (FNS) and a DEMO reactor. The FNS is seen as a necessary intermediate step to test and qualify materials in a true fusion neutron environment. The design of a Russian DEMO will build upon the operational experience from T-15MD and the results from ITER. The program's long-term vision is to develop a hybrid fusion-fission system, where neutrons from a fusion core are used to transmute nuclear waste or breed fuel for fission reactors, though this remains a more distant goal.

References

1. Start of the T-15MD Tokamak — Journal of Fusion Energy (2022)
2. First results of the Globus-M2 tokamak operation — Nuclear Fusion (2021)
3. Russia's Rosatom completes new tokamak T-15MD physical start-up — World Nuclear News (2021)
4. The role of the Russian Federation in the ITER project — ITER Organization
5. A new twist in the tale of the tokamak — Nature (2021)
6. Forty years of magnetic confinement fusion research in the USSR/Russia — Plasma Physics and Controlled Fusion (1999)
7. Status of the IGNITOR project — Nuclear Fusion (2019)
8. Russian Federation Domestic Agency for ITER — Project Center ITER