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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
S. Nogami, K. Yamamoto, M. Fukuda, A. Hasegawa
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 601-606
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-927
Articles are hosted by Taylor and Francis Online.
To improve the fatigue life assessment of the relatively thin wall structure of the fusion reactor blanket, the fatigue micro-crack initiation behavior of the F82H steel at room temperature was investigated. The micro-crack initiation life was approximately 20–30 % of the fatigue life. The crack initiation was observed at the prior austenitic grain boundary, the packet boundary, the block boundary, and the inside of the block structure. The majority was the transgranular crack initiation, which exceeded 90 % of the all. The effect of the irradiation damage (irradiation hardening) was only a shortening of the micro-crack initiation life. No change of the micro-crack initiation sites and their ratio were observed.
