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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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
A. R. Raffray, A. E. Robson, M. E. Sawan, G. Sviatoslavsky, I. N. Sviatoslavsky, X. Wang
Fusion Science and Technology | Volume 52 | Number 3 | October 2007 | Pages 603-608
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1554
Articles are hosted by Taylor and Francis Online.
A possible way to address the issue of dry wall survival in a Laser IFE chamber is to use magnetic diversion in order to steer away the ions from the chamber wall (representing ~25-30% of the yield energy). A cusp magnetic field is imposed on to the chamber; the ions from the micro-explosion are trapped within the magnetic field and are directed to more readily accessible and replaceable dump regions at the equator and poles. A large fraction of the magnetic energy can be dissipated in the chamber walls if an electrically resistive structural material is used. An advanced blanket based on a self-cooled liquid breeder (e.g.Pb-17Li or flibe) and SiCf/SiC structure has been proposed for this purpose and a scoping design study performed as part of the High Average Power Laser program effort.This paper summarizes the results of this scoping study, and highlights the advantages of such a concept as well as the key issues that need to be addressed by R&D.