ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
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.
L. F. Hansen, J. D. Anderson, R. J. Doyas, R. J. Howerton, T. Komoto, C. M. Logan, C. Wong, J. L. Kammerdiener
Nuclear Science and Engineering | Volume 55 | Number 3 | November 1974 | Pages 345-348
Technical Note | doi.org/10.13182/NSE74-A23461
Articles are hosted by Taylor and Francis Online.
The neutron spectra emitted from 2 and 4 mean-free-paths of concrete irradiated by 14-MeV neutrons have been measured between 14 and 2 MeV using the sphere transmission and time-of-flight techniques. The spectra have been calculated with the Monte Carlo neutron transport code TART using the ENDL Livermore neutron library and the ENDF/B-III neutron library. From the comparison between measurements and calculations, it was inferred that the nonelastic cross section for oxygen in the ENDL library was too large. A revision of the cross sections for 14- and 14.6-MeV neutrons was carried out and resulted in very good agreement between measurements and calculations.