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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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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Latest News
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.
C. Rotti, N. Panda, H. Patel, N. Kanoongo, A. Chakraborty, K. Balasubramanian
Fusion Science and Technology | Volume 65 | Number 2 | March-April 2014 | Pages 205-211
Technical Paper | doi.org/10.13182/FST13-669
Articles are hosted by Taylor and Francis Online.
In high heat flux components of neutral beam injector (NBI) systems, CuCrZr alloy is used as a heat sink material. In different national standards, chromium content varies from 0.4 to 1.5 wt%, and zirconium content varies from 0.03 to 0.25 wt%. Indian CuCrZr material was produced at the Non-Ferrous Materials Technology Development Centre and used for the NBI system of the Indian tokomak SST-1, which complied with these chemical composition ranges. The properties of the Indian CuCrZr material were in accordance with procurement specifications. CuCrZr ITER-grade (IG) specifications are as defined in “ITER Materials Properties Handbook” (MPH). The MPH recommends a narrower range of Cr and Zr contents. The reason for limiting the Cr content is that a high Cr content may result in the formation of coarse Cr precipitates, which affect the radiation resistance. Indian CuCrZr with ITER specifications has been produced in a large number (38) of heats and characterized for compositional, tensile, grain size, and weld properties. The properties are, in general, found to comply with those of ITER specifications. The material-processing and component-making steps have been determined, and prototypes of heat transfer elements have been made. Residual ion dump plates have been successfully deep drilled, and component welding trials are in progress. This paper discusses experiences in producing CuCrZr IG and making the elements.