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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Xinwu Su, Yongli Xu, Yinlu Han
Nuclear Science and Engineering | Volume 195 | Number 3 | March 2021 | Pages 239-255
Technical Paper | doi.org/10.1080/00295639.2020.1808388
Articles are hosted by Taylor and Francis Online.
The medium-mass structural material titanium has been extensively applied in the nuclear reactor systems of fission or fusion, and related data are also urgently needed. In the present work, all reaction cross sections, angular distributions, energy spectra, and double-differential cross sections are consistently calculated and analyzed for the n+48Ti reaction below 200 MeV. The theoretical calculations are compared with the experimental data, together with the evaluated results in the ENDF/B-VIII.0, JENDL-4.0, and JEFF-3.3 libraries. In general, these results provide a satisfactory description of the corresponding experimental data.