KTM

Intelligence Summary: Kazakhstani Material Testing Tokamak (KTM)

Node Identity: KTM (Kazakhstani Material Testing Tokamak) is a one-of-a-kind spherical tokamak with aspect ratio A=2 (R=0.9m, a=0.45m) located at the NNC in Kurchatov, Kazakhstan. It is the only spherical tokamak of its specific configuration in the world, dedicated to plasma-material interaction studies for future fusion reactors. The physical launch occurred in late 2019 through joint efforts of Kazakhstan's NNC and Russia's Kurchatov Institute and Troitsk Institute of Innovative and Thermonuclear Research (TRINITI). By end of 2022, KTM achieved 70% of nominal design parameters in ohmic heating mode (Ipl = 500 kA, natural elongation knat = 1.25).

Strategic Relevance: KTM's strategic relevance to the FRC/plasma weapons landscape is defined by its unique spherical tokamak configuration with compact toroid-relevant geometry. The aspect ratio A=2 configuration is explicitly noted as enabling "unique studies of boundary magnetic configuration of extremely compact toroids and classical Tokamaks" — directly relevant to compact toroid and FRC physics. The facility's plasma-material interaction studies, lithium divertor technology using capillary porous structures (CPS), and divertor heat load capabilities (up to 20 MW/m²) represent advanced plasma-facing component engineering with dual-use potential. The deep Russian involvement (Kurchatov Institute, TRINITI) means plasma physics knowledge flows bilaterally — any advances at KTM are effectively shared with Russia's military-relevant plasma research programs. Kazakhstan signed an ITER cooperation agreement in 2017, volunteering KTM for materials testing in support of the international fusion program.

Technical Focus / Capabilities: KTM design parameters: plasma current 750 kA (design), SND elongation k=1.7, electron density ne = 5×10¹⁹ m⁻³, discharge duration 5 s, estimated divertor heat loads up to 20 MW/m². Achieved 70% nominal parameters by 2022 (Ipl = 500 kA, knat = 1.25). Plasma instabilities characterized include unipolar plasma arcs, hot spots, MARFE, and fan-like instability. Unique features include a movable divertor device and transport sluice. A lithium divertor model using capillary porous structures (CPS) is under development. An ICR (ion cyclotron resonance) plasma heating system is being prepared for startup. The KTM operates under a CIS Intergovernmental Agreement on joint use, with research including plasma physics, plasma-wall interaction, plasma diagnostics, structural/functional material studies, and lithium technology development.

Network Linkage: KTM maintains 2 documented connections: NNC operates KTM (at Kurchatov, Kazakhstan) and Russian Cooperation supports KTM (Kurchatov Institute and TRINITI participated in physical start-up; protocol signed between NNC RK and Kurchatov Institute). KTM operates under a CIS Intergovernmental Agreement on joint tokamak use. Kazakhstan's 2017 ITER cooperation agreement volunteered KTM for international materials testing. The ICR heating system preparation connects KTM to advanced RF plasma heating capabilities.