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UKAEA Completes Heavy Enclosure Lift for Spherical Tokamak

Recently, the UK Atomic Energy Authority (UKAEA) flagship spherical tokamak experimental device (MAST Upgrade) reached an important engineering milestone with the successful lifting and installation of a 12-tonne dual-layer beam enclosure. The enclosure is specifically designed to house two additional neutral beam injectors (NBI). With the subsequent installation of related infrastructure and supporting systems, the neutral beam heating power of the MAST Upgrade device is planned to increase from the current 4.4 MW to 8.8 MW, doubling its heating capability. The core strategic objective of this upgrade is to explore plasma physics behavior under extremely high temperature and pressure conditions, and to focus on testing the ultimate capability of the core heat exhaust system (such as the Divertor) to handle the heat load of higher-performance plasmas, thereby providing key technical and physics parameter support for the UK's prototype fusion power plant (STEP) project.

2026-11-04

Startorus Fusion Completes 20 K Cryogenic Rapid Discharge Test of Central Solenoid Model Magnet (CSMC) for Spherical Tokamak Device

Startorus Fusion (HTS) recently announced that its independently developed central solenoid (CS) model magnet for a spherical tokamak device (tokamak) successfully completed a 6350 A cryogenic current-carrying and rapid discharge test under harsh cryogenic conditions. Test results showed that the magnet achieved a maximum magnetic field of 10 T and a magnetic field change rate of up to 63 T/s, setting a new record for the magnetic field change rate of known fusion superconducting magnets. This test was conducted at 20 K (-253 °C). The magnet not only successfully reached a maximum magnetic field strength of 10 T, with a central magnetic field of 7.6 T, but also smoothly completed the rapid discharge test required for tokamak ohmic discharge. As a...

2026-10-09

Princeton Plasma Physics Laboratory to Validate Spherical Tokamak Fusion Path with NSTX-U

The Princeton Plasma Physics Laboratory (PPPL) is advancing research on the National Spherical Torus Experiment-Upgrade (NSTX-U), planning to use this largest spherical tokamak in the United States to assess the potential of compact tokamak configurations for future fusion power plants. The device is designed to become one of the most powerful spherical tokamaks in the world and will be used to study key issues such as high-temperature plasma confinement, heat transport, material performance, and real-time control. The image above shows the vacuum vessel and center column of the NSTX-U at the Princeton Plasma Physics Laboratory (PPPL). This device will help scientists determine the optimal shape for future fusion power plants...

2026-08-20

StarRing Fusion Completes RMB 880 Million Series A++ Financing to Advance Fusion Device and Key Technology Engineering

StarRing Fusion recently announced the completion of a new Series A++ financing round, raising RMB 880 million. This round was jointly invested by Shenzhen Capital Group, Shendan Venture Capital, ABC Capital, BOCOM Investment, GGV Capital, Yongxin Ark, Keke Capital, Advantage Capital, and other institutions, with existing shareholder Shanghai Science and Technology Innovation Group's intellectual property fund and other institutions continuing to follow on. The company stated that the proceeds from this round, together with the previous Series A and A+ financing, will be used for the construction of the Shanghai Jiading experimental base, the construction and operation of the NTST negative-triangularity spherical tokamak, the design and construction of the CTRFR-1 "StarRing One," and the continued engineering advancement of key technologies including fusion-grade high-temperature superconducting magnets and AI-based plasma control...

2026-08-08