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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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Fusion Science and Technology
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.
Jungchung Jung, John V. Foley
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 1998-2009
Technical Paper | Blanket Comparison and Selection Study | doi.org/10.13182/FST85-A24575
Articles are hosted by Taylor and Francis Online.
Three-dimensional, tritium breeding, and energy multiplication analyses were performed for nine tandem mirror reactor (TMR) designs and seven tokamak reactor designs that had evolved as the “rank-1” concept from the latest Blanket Comparison and Selection Study. These designs include a variety of combinations of candidate breeder, coolant, and structural materials that seem most promising for the respective TMR/tokamak concept application. The analysis was performed using a single consistent computational technique, i.e., a continuous energy Monte Carlo transport method based on MCNP with the associated cross-section libraries based on the latest ENDF/B-V data. Through a comparative study of those 16 candidate blanket designs, an attempt is made to rank them from a standpoint of the neutronic blanket performance.