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.
Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Zaporizhzhia ‘extremely fragile’ relying on single off-site power line, IAEA warns
Europe’s largest nuclear power plant has just one remaining power line for essential nuclear safety and security functions, compared with its original 10 functional lines before the military conflict with Russia, warned Rafael Mariano Grossi, director general of the International Atomic Energy Agency.
Peter H. Titus, under contract from Stone & Webster Engineering Corporation)
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 383-388
Advanced Designs | doi.org/10.13182/FST01-A11963264
Articles are hosted by Taylor and Francis Online.
The toroidal field coil system of the FIRE tokamak utilizes inertially cooled, copper alloy Bitter plate type magnets which are LN2 cooled between shots. The baseline configuration is wedged. C17510 high strength, high conductivity beryllium copper alloy developed for BPX is proposed for the conductor. These design choices were made after considering a number of alternative structural concepts and a variety of conductor materials. FIRE's high elongation and double null plasma results in high overturning moments. The use of a large compression ring and the large centering forces provides adequate frictional wedging pressures to support the inner leg out-of-plane (OOP) forces. Studies of the pulse length indicate flat top time of 12 sec at peak field and nuclear heat. Non-linear friction simulations have been performed to confirm OOP load support. Structural criteria for the FIRE reactor require demonstration of adequate ductility of the conductor material. Examination of the elastic plastic behavior of the coils for overloaded conditions, 13T, and 14T, has been used to satisfy this criteria, and demonstrate margin. Discussions of primary load paths and evaluation of primary stresses are presented. The contribution of the central tie rod assembly was found to be too small in reducing the inner leg vertical tension stress, and the tie rod has been removed.