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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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!
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Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.