ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Aug 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
October 2026
Nuclear Technology
September 2026
Fusion Science and Technology
August 2026
Latest News
Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Panle Liu, Bo Li, Xue Zheng, Xiang Chen, Qiang Li, Junzhao Zhang, Yihang Chen, Jian Zhou, Rui Ma, Zhongmin Huang
Fusion Science and Technology | Volume 81 | Number 5 | July 2025 | Pages 413-424
Research Article | doi.org/10.1080/15361055.2024.2437331
Articles are hosted by Taylor and Francis Online.
Achieving advanced divertor configurations and high-confinement operating regimes is crucial for mitigating divertor heat loads and exploring enhanced confinement physics in the HL-2M tokamak. However, these scenarios with highly elongated plasmas face severe vertical displacement events that can lead to rapid plasma termination and potential device damage. Robust active control of vertical instability is therefore essential. As HL-2M lacks internal control coils, we developed two sets of vertical stabilization (VS) control systems, each employing a pair of external poloidal field (PF) coils, PF main power supplies, and VS power supplies. This paper details the first vertical stabilization (VS1) control system’s circuit diagram, hardware architecture, and software implementation and discusses issues encountered during commissioning and their solutions. By improving the internal hardware of the VS power supply, the voltage rise time was reduced to approximately 30 μs, resolving branch current imbalances. The transmission delay of the control signals is approximately 38 μs. Preliminary plasma experiments demonstrated effective vertical displacement control with the VS1 control system, achieving a maximum plasma elongation of 1.73 and typical control accuracy of ~20 mm. This work lays the foundation for robust control under high-parameter operational scenarios and the design and implementation of the higher-power second vertical stabilization (VS2) control system.