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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
NRC grants license for TRISO-X fuel manufacturing using HALEU
The Nuclear Regulatory Commission has granted X-energy subsidiary TRISO-X a special nuclear material license for high-assay low-enriched uranium fuel fabrication. The license applies to TRISO-X’s first two planned commercial facilities, known as TX-1 and TX-2, for an initial 40-year period. The facilities are set to be the first new nuclear fuel fabrication plants licensed by the NRC in more than 50 years.
E. A. Vinitskiy, D. L. Ulasevich, A. S. Prishvitsyn, N. E. Efimov, R. R. Khayrutdinov, S. A. Krat
Fusion Science and Technology | Volume 81 | Number 5 | July 2025 | Pages 485-494
Research Article | doi.org/10.1080/15361055.2024.2431782
Articles are hosted by Taylor and Francis Online.
A novel design of a continuous toroidal solenoid for the small spherical tokamak MEPhIST-0 is presented. The solenoid’s geometry is optimized in regard to stray magnetic fields perpendicular to the toroidal fields based on Maxwell’s equations and interface conditions for magnetic fields. The solutions obtained may in theory provide the level of stray fields ~10−10 of the toroidal fields. The design of the solenoid is tested by means of COMSOL modeling. The observed ratio of stray fields to the toroidal component of magnetic fields, Bp/BT is approximately ~0.4% at the plasma center. A ripple of the toroidal magnetic field at the edge of the plasma of δ ~ 0.8% is observed. The possibility of plasma breakdown with the chosen toroidal solenoid configuration was evaluated using the DINA calculation code.