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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
W. M. Stacey, Jr., K. Evans, Jr.
Nuclear Technology | Volume 32 | Number 2 | February 1977 | Pages 142-154
Technical Paper | Reactor | doi.org/10.13182/NT77-A31719
Articles are hosted by Taylor and Francis Online.
A survey has been made of the toroidal magnetic field strength requirements in a tokamak reactor as a function of size, confinement, temperature, safety factor, aspect ratio, and cross-sectional shape. The maximum field strengths consistent with reasonable limitations on the wall-loading and plasma-driving system and the minimum field strengths necessary for predicted confinement were determined along with the associated power output and an indication of the magnet cost. It was found that a maximum toroidal field at the coil of 80 kG (8 T) may be adequate for large-scale reactors. Fields in excess of 100 kG (10 T) would only be required for reactors in the intermediate-size range (major radius ∼7 m).