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.
Marco Nassi
Fusion Science and Technology | Volume 24 | Number 1 | August 1993 | Pages 50-64
Technical Paper | Magnet System | doi.org/10.13182/FST93-A30174
Articles are hosted by Taylor and Francis Online.
The definitions and correlations existing between different terms used by physicists and engineers are clarified in order to deal with the assessment of the poloidal flux requirement in a fusion experiment. The theoretical formulation of both the Faraday and the Poynting methods, for the internal flux evaluation, is briefly reviewed. Heuristic expressions that allow estimates of internal flux consumption are reported for the specific case of an ignition experiment represented by the Ignitor configuration. The analytical and heuristic results for both internal and external poloidal flux requirements are checked against numerical evaluations carried out by using the TSC transport and magnetohydrodynamics code and the TEQ equilibrium code. A fairly good agreement between the different estimates is found. This suggests that simple heuristic expressions can be used to evaluate the poloidal flux requirement of future experiments, even if a detailed simulation of the plasma current penetration process is strongly recommended to correctly assess and optimize the resistive poloidal flux consumption. Finally, the poloidal flux requirement for different plasma scenarios in the Ignitor experiment is compared with the magnetic flux variation that can be delivered by the poloidal field system.