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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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May 2025
Latest News
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.
S. Yamaguchi, T. Nakamura
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 573-578
Fusion Nucleonics Experiment | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24805
Articles are hosted by Taylor and Francis Online.
As a part of the Phase I of JAERI/USDOE collaborative program on fusion blanket neutronics, the effect of constituents of the fusion blanket on tritium production rate distribution was examined experimentally by the Lithium-glass scintillator method. The self-shielding factor of the Lithium-glass scintillator was estimated by an experiment as well as a calculational method. The Li-glass method has shown excellent performance and reliability in the parametric measurement of the tritium production rate distribution.