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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
Hairui Guo, Yongli Xu, Yinlu Han, Qingbiao Shen, Tao Ye, Weili Sun
Nuclear Science and Engineering | Volume 186 | Number 2 | May 2017 | Pages 156-167
Technical Paper | doi.org/10.1080/00295639.2016.1273008
Articles are hosted by Taylor and Francis Online.
A set of optical model potential parameters for the n+51V reaction is obtained based on the experimental data of the total cross section, elastic scattering cross section, and elastic scattering angular distribution at incident energies up to 300 MeV. All cross sections, angular distributions, energy spectra, and double-differential cross sections for the n+51V reaction are consistently calculated and analyzed at incident neutron energies below 250 MeV. The theoretical nuclear models including the optical model, distorted wave Born approximation theory, Hauser-Feshbach theory, evaporation model, exciton model, and intranuclear cascade model are used in the analysis. The calculated results are compared with the experimental data and the evaluated results in ENDF/B-VII.1 and JENDL-4.