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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.
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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.
Makoto Fukuda, Shuhei Nogami, Kiyohiro Yabuuchi, Akira Hasegawa, Takeo Muroga
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 690-693
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-998
Articles are hosted by Taylor and Francis Online.
The effects of K-bubble dispersion and 3 wt.% Re addition on the tensile properties and their anisotropy in W were investigated in this work. K-doped W and K-doped W-3%Re showed ~45 and ~65% higher tensile strengths than pure W, respectively. The ultimate tensile strength and its temperature dependence in pure W, K-doped W, and K-doped W-3%Re showed anisotropy. However, the effects of K-bubble dispersion and 3% Re addition on the anisotropic tensile strength were not clearly observed. K-doped W and K-doped W-3%Re showed better deformation abilities than pure W. K-doped W-3%Re showed better tensile properties than pure W under non-irradiation conditions used in this work. Since irradiation hardening is suppressed by adding 3% Re, K-doped W-3%Re is expected to be more advantageous as a plasma facing material in a fusion reactor than pure W and K-doped W.
