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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
Takuya Nagasaka, Takeo Muroga, Akio Sagara, Hiroshi Yukawa, Tomonori Nambu
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1580-1583
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12736
Articles are hosted by Taylor and Francis Online.
Tensile and creep strength of pure V, Nb, Ta, and Nb-9W alloy were examined at 600 °C to assess their applicability as hydrogen permeation material for the recovery of tritium from the high temperature liquid breeder blanket of a fusion reactor. The Nb-9W alloy required a comparatively higher annealing temperature to achieve good ductility. Based on tensile strength results, it is estimated that a permeation wall thickness of 0.1 mm is achievable. According to creep rate of Nb-9W alloy, design stress maybe decreased below 1/3 of yield stress.
